U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/19/97 - 11/20/97 ** EVENT NUMBERS ** 33285 33286 33287 33288 33289 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33285 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 11/19/97 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 09:02 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 11/19/97 | +------------------------------------------------+EVENT TIME: 08:10[EST]| |NRC NOTIFIED BY: DAVID CROOK |LAST UPDATE DATE: 11/19/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT SECURITY EVENT. | | | | SAFEGUARDS SYSTEM DEGRADATION RELATED TO COMPUTER FAILURE. IMMEDIATE | | COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33286 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 11/19/97 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 11:53 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/18/97 | +------------------------------------------------+EVENT TIME: 16:30[EST]| |NRC NOTIFIED BY: BILL WEBSTER |LAST UPDATE DATE: 11/19/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - FITNESS FOR DUTY EVENT - | | | | A CONTRACTOR SUPERVISOR TESTED POSITIVE FOR ILLEGAL DRUGS. HIS ACCESS | | AUTHORIZATION TO THE PLANT HAS BEEN TERMINATED. THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33287 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 11/19/97 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 12:58 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/18/97 | +------------------------------------------------+EVENT TIME: 16:55[EST]| |NRC NOTIFIED BY: FRANK GORLEY |LAST UPDATE DATE: 11/19/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DRYWELL PNEUMATIC NITROGEN SUPPLY ISOLATION. | | | | DURING A PLANT SHUTDOWN ON 11/18/97, THE 'B' MAIN STEAM LINE INBOARD | | ISOLATION VALVE (#1B21F022B) DEVELOPED A NITROGEN LEAK FROM ITS PNEUMATIC | | ACTUATOR AFTER VALVE CLOSURE. AN AUTOMATIC DRYWELL PNEUMATIC NITROGEN | | SUPPLY ISOLATION OCCURRED (SETPOINT - 30 SCFM FLOW FOR 10 MINUTES), | | CAUSING THE DRYWELL NITROGEN SUPPLY VALVE (#1P70F004) TO CLOSE. THIS | | ISOLATION IS AN ENGINEERED SAFETY FEATURE ACTUATION. NO OTHER VALVES | | INSIDE THE DRYWELL REPOSITIONED AS A RESULT OF THIS ISOLATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33288 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 11/19/97 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 13:55 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/19/97 | +------------------------------------------------+EVENT TIME: 12:05[CST]| |NRC NOTIFIED BY: DOUG SMITH |LAST UPDATE DATE: 11/19/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS |STU RICHARDS, NRR EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -RCP LUBE OIL COLLECTION SYSTEM NOT IN COMPLIANCE WITH 10CFR50, APPENDIX R- | | | | DURING A UNIT 1 REFUELING OUTAGE, THE LICENSEE DISCOVERED THAT A POTENTIAL | | PRESSURIZED LEAK FROM THE OIL LIFT PUMP AND ASSOCIATED PIPING FOR UNIT 1 | | WESTINGHOUSE REACTOR COOLANT PUMPS #RCP-11 AND #RCP-12 WOULD NOT BE | | CAPTURED BY THE COLLECTION PANS OF THE INSTALLED RCP LUBE OIL COLLECTION | | SYSTEM. THUS, THE UNIT 1 RCP LUBE OIL COLLECTION SYSTEM IS NOT IN LITERAL | | COMPLIANCE WITH THE REQUIREMENTS OF 10CFR50, APPENDIX R, SECTION III.0 | | IN THAT PRESSURIZED LEAKS DURING OPERATION OF THE RCP OIL LIFT PUMP MAY | | NOT BE COLLECTED. UNIT 2 HAS THE SAME CONFIGURATION. | | | | THE LICENSEE HAS NOT DECLARED ANY EQUIPMENT OR SYSTEMS INOPERABLE AS A | | RESULT OF THIS CONDITION. THE LICENSEE IS PREPARING GUIDANCE TO MONITOR | | FOR LEAKS DURING RCP STARTUP AND ALARM CONDITIONS AND IS REVIEWING THE RCP | | LUBE OIL COLLECTION SYSTEM FOR POSSIBLE MODIFICATION AND WILL REVISE PLANT | | PROCEDURES, AS NECESSARY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33289 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/19/97 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 19:44 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/19/97 | +------------------------------------------------+EVENT TIME: 19:20[EST]| |NRC NOTIFIED BY: MIKE GWIRTZ |LAST UPDATE DATE: 11/19/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK MCFADDEN RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP |STU RICHARDS, NRR EO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -S/G BLOWDOWN & SAMPLE ISOLATION VALVES NOT BEING TESTED PER NRC GL 96-01- | | | | THIS REPORT APPLIES TO UNIT 2 WHICH IS OPERATING IN MODE 1 AT 100% POWER. | | | | WHILE PERFORMING A REVIEW OF APPLICABLE AS-BUILT DRAWINGS AND TEST | | PROCEDURES IN ACCORDANCE WITH THE GUIDELINES OF NRC GENERIC LETTER 96-01, | | THE LICENSEE IDENTIFIED THAT THE UNIT 2 STEAM GENERATOR (S/G) BLOWDOWN | | ISOLATION VALVES (21GB4, 22GB4, 23GB4, 24GB4) AND THE S/G BLOWDOWN SAMPLE | | ISOLATION VALVES (21SS94, 22SS94, 23SS94, 24SS94) ARE NOT BEING | | FUNCTIONALLY TESTED TO VERIFY THAT THEY CLOSE ON AN AUTOMATIC START OF | | THE AUXILIARY FEEDWATER (AFW) PUMPS. | | | | MOST PORTIONS OF THE AFW PUMP START CONTROL CIRCUIT ARE VERIFIED TO BE | | OPERATIONAL IN ACCORDANCE WITH THE AFW SURVEILLANCE PROCEDURES, AND THERE | | ARE SEVERAL SURVEILLANCE TASKS ASSOCIATED WITH THE S/G BLOWDOWN AND SAMPLE | | ISOLATION VALVES. HOWEVER, THERE ARE NO TESTS BEING PERFORMED TO VERIFY | | THE CLOSURE OF THESE VALVES WHEN THE AFW PUMP IS STARTED AUTOMATICALLY. | | AN AUTOMATIC START OF THE AFW PUMP WILL INITIATE THE CLOSURE OF THE S/G | | BLOWDOWN AND SAMPLE ISOLATION VALVES. BUT THERE IS NO SPECIFIC REQUIREMENT | | IN THE PLANT TECHNICAL SPECIFICATIONS TO TEST THIS INTERCONNECTED FUNCTION. | | | | THE UNIT 2 UFSAR SECTION 10.4.7.2.2 STATES IN PART THAT WHEN EITHER OF THE | | AFW PUMPS ARE STARTED AUTOMATICALLY, A SIGNAL IS SENT TO CLOSE S/G BLOWDOWN | | AND SAMPLING SYSTEMS' ISOLATION VALVES. TO FULLY DEMONSTRATE THE DESIGN | | CAPABILITY OF THE AFW PUMP START CONTROL CIRCUIT, AS DESCRIBED IN THE | | UFSAR, IT MAY BE NECESSARY TO VERIFY THE S/G BLOWDOWN AND SAMPLE ISOLATION | | VALVES CLOSE ON AN AUTOMATIC START OF THE AFW PUMP, AS INTENDED. | | | | FOR THE LOSS-OF-NORMAL-FEEDWATER ACCIDENT ANALYZED IN THE UFSAR, | | THE CURRENT ANALYSIS ASSUMES THAT UPON THE START OF THE AFW PUMPS, | | THE S/G BLOWDOWN VALVES WILL CLOSE. WITH THE VALVES NOT BEING TESTED | | TO CLOSE ON THE START OF THE AFW PUMPS, CREDIT CAN NOT BE ASSUMED FOR | | THE COMPLETION OF THIS FUNCTION. | | | | IF S/G BLOWDOWN IS ASSUMED TO BE OPERATING AT MAXIMUM FLOW, THE AMOUNT | | OF INVENTORY REMOVED FROM THE S/G BY THE BLOWDOWN FLOWPATH IS ESSENTIALLY | | THE SAME AS THE INVENTORY BEING ADDED BY THE AFW PUMPS. THEREFORE, | | UNIT 2 MAY MAY HAVE OPERATED IN THE PAST IN AN UNANALYZED CONDITION THAT | | MAY HAVE SIGNIFICANTLY COMPROMISED PLANT SAFETY. | | | | BASED ON LICENSEE ENGINEERING JUDGMENT AND REVIEW OF THE ACCIDENT ANALYSIS, | | IF S/G BLOWDOWN FLOW IS RESTRICTED TO 40,000 LBM/HR, THERE WOULD BE | | SUFFICIENT INVENTORY MAINTAINED IN THE S/G TO ENSURE ADEQUATE HEAT REMOVAL. | | CURRENTLY, S/G BLOWDOWN IS BEING LIMITED TO 40,000 LBM/HR. | | | | THE LICENSEE PLANS TO EVALUATE THE ADEQUACY OF PRESENT SURVEILLANCE TESTING | | AND THE POTENTIAL INCLUSION OF THIS FUNCTION IN THE PLANT TECHNICAL | | SPECIFICATIONS. | | | | THIS CONDITION IS BEING REPORTED ON UNIT 2 AS AN UNANALYZED CONDITION THAT | | COULD COMPROMISE PLANT SAFETY IN ACCORDANCE WITH 10CFR50.72(b)(1)(ii)(A). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2037 ON 11/19/97 BY MIKE GWIRTZ ENTERED BY JOLLIFFE * * * | | | | UNIT 1 IS DEFUELED IN MODE 6 IN A REFUELING OUTAGE. | | | | THE LICENSEE HAS DETERMINED THAT THE ABOVE CONDITION ALSO APPLIES TO | | UNIT 1. THE UNIT 1 S/G BLOWDOWN ISOLATION VALVES ARE 11GB4, 12GB4, 13GB4, | | AND 14GB4 AND THE S/G BLOWDOWN SAMPLE ISOLATION VALVES ARE 11SS94, 12SS94, | | 13SS94, AND 14SS94. | | | | THIS EVENT IS BEING REPORTED ON UNIT 1 AS A DEGRADED CONDITION WHILE UNIT 1 | | IS SHUTDOWN IN ACCORDANCE WITH 10CFR50(b)(2)(i). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED R1DO JACK McFADDEN. | +------------------------------------------------------------------------------+