Headquarters Daily Report MARCH 28, 1997 *************************************************************************** REPORT NEGATIVE NO INPUT ATTACHED INPUT RECEIVED RECEIVED HEADQUARTERS û REGION I û REGION II û REGION III û REGION IV û PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS MARCH 28, 1997 MR Number: H-97-0030 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS NRC Information Notice 97-14, "Assessment of Spent Fuel Pool Cooling," dated March 28, 1997. The NRC is issuing this information notice to alert addressees to results of an assessment performed by the Office for Analysis and Evaluation of Operational Data on operating experience involving spent fuel pool cooling and inventory control. Technical contacts: Jose G. Ibarra, AEOD (301) 415-6345 Stephen Koenick, NRR (301) 415-2841 _ REGION II MORNING REPORT PAGE 2 MARCH 28, 1997 Licensee/Facility: Notification: Tennessee Valley Authority MR Number: 2-97-0019 Browns Ferry 1 2 3 Date: 03/28/97 Decatur,Alabama Dockets: 50-259,50-260,50-296 BWR/GE-4,BWR/GE-4,BWR/GE-4 Subject: MEDIA INTEREST REGARDING AN INJURED WORKER Discussion: On March 27, 1997, a contract worker was injured at the Browns Ferry site. While cleaning a water softener/purification tank sightglass, a portion of the sightglass was ejected due to excess tank pressure. The worker was struck by a piece of the sightglass assembly, causing facial cuts to the individual. The tank is located outside the protected area of the plant but on site property. The worker was transported offsite to a local hospital for treatment, where he was released shortly thereafter. The individual was not contaminated. No vital plant equipment was involved. There was local television media interest due to misinformation about an explosion at the site (there was no explosion), causing the injury. TVA is continuing to review the incident. TVA has concluded that this issue is not reportable under 50.72 requirements. Regional Action: The resident inspectors were informed of the injury, and discussed the details with plant management. Additional review will be conducted by the residents, as necessary. Contact: Len D. Wert (205)729-6196 Scott S. Sparks (404)331-5619 _ REGION II MORNING REPORT PAGE 3 MARCH 28, 1997 Licensee/Facility: Notification: Carolina Power & Light Co. MR Number: 2-97-0020 Harris 1 Date: 03/28/97 Raleigh,North Carolina Dockets: 50-400 PWR/W-3-LP Subject: MOVEMENT OF IF-300 SPENT FUEL SHIPPING CASK WITH DETENSIONED HEAD Discussion: On February 11, 1997, during a review of NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, the licensee identified an Unreviewed Safety Question (USQ) related to movement of a Vectra IF-300 spent fuel shipping cask with the cask lid in a less than a fully secured configuration. The licensee found that the Cask Safety Analysis Report (CSAR) supported moving the cask with all but four head nuts removed. The Cask Operating Manual also had steps that describe this configuration for movement. The licensee assumed from the CSAR that full cask integrity was maintained even when only four head nuts were used. The licensee found that the vendor had not performed an analysis to support movement of a loaded cask with only four nuts. The licensee stopped any further cask movements. The vendor performed an analysis and determined that following a cask drop the head would not be dislodged with only four nuts installed. However, the cask would not be gas tight. The radiological analyses considered that all the gas in the fuel would be released. The release would be less than a small fraction of the 10 CFR 100 exposure guideline values. FSAR, Section 15.7.5, Spent Fuel Cask Drop Accidents, considered a potential drop of a spent fuel cask with full integrity. In NUREG-1038, November 1993, Safety Evaluation Report for Shearon Harris Nuclear Plant, Section 15.7.5, the NRC concluded that since no loss of cask integrity was postulated, that no significant radiation release to the environment would occur. Due to the cask being moved with ony four nuts on the head the licensee determined that a USQ existed. Regional Action: Resident Inspectors verified that cask movement was stopped and placed on hold. The issue was taken to enforcement prepanel in Region II on March 26, 1997. Contact: Milton Shymlock (403)331-5535 _ REGION IV MORNING REPORT PAGE 4 MARCH 28, 1997 Licensee/Facility: Notification: Washington Public Power Supply System MR Number: 4-97-0030 Washington Nuclear 2 Date: 03/28/97 Richland,Washington Call from Resident Inspector Dockets: 50-397 BWR/GE-5 Subject: REACTOR SCRAM DURING TESTING OF REACTOR FEEDWATER AND REACTOR RECIRCULATION CONTROL SYSTEMS Reportable Event Number: 32031 Discussion: On March 27, 1997, at 9:06 a.m. (PST), with the reactor at 96 percent power, control room operators manually tripped a reactor feedwater (RFW) pump to test the capability of the reactor recirculation control (RRC) and RFW systems. The systems were designed so that, in the event of the trip of one reactor feedwater pump, a reactor scram would not occur. The licensee had installed new digital control systems for the RRC and RFW systems during the last refueling outage (R11) and this test was to demonstrate the scram avoidance capability as described in the FSAR. After RFW Pump B was manually tripped, the RRC pumps ran back from 60 Hertz to 27 Hertz, as designed. Shortly thereafter, the RRC pumps unexpectedly ran back to 15 Hertz, apparently on a "low differential temperature between the steam dome and pump suction" signal (cavitation protection trip). The runback to 15 Hz resulted in the entry to Region A (instability region) of the power-to-flow map. At 9:09 a.m., on recognition of entering Region A, operators manually scrammed the reactor, as required by Technical Specifications, and entered the Emergency Operating Procedures. As expected, in response to the scram, reactor water level decreased to below 13 inches. In response to the low level condition, RFW flow increased and level was recovered to above 13 inches. Although the RFW level control system appeared to be working properly in attempting to control level at 18 inches, RFW Pump A failed to decrease speed in response to the control signal. Subsequently, reactor water level reached level 8 (54.5 inches) and RFW Pump A automatically tripped on high level. Operators quickly restored both RFW pumps to service. Reactor vessel level was maintained within an acceptable range. The licensee reported apparent indication problems with three control rods which had computer displays which changed from full-in to an unknown position. However, verification with the full core display showed the rods with full-in indication. The licensee suspects a reed switch problem. The resident inspector was in the control room at the time of the test and the event and observed that operators appropriately followed plant procedures and Technical Specifications. The licensee's intent is to remain shut down and begin preparations for a refueling outage due to begin on April 15, 1997. REGION IV MORNING REPORT PAGE 5 MARCH 28, 1997 MR Number: 4-97-0030 (cont.) Regional Action: A conference call with the licensee, NRR, AEDO, and Regional personnel was held to review the event on March 27, 1997. A followup call is planned to further discuss the event after additional evaluations have been performed. Regional personnel are closely monitoring the licensee's evaluation of the event. The need for a special inspection of this event will be evaluated early next week. Contact: H. Wong (510)975-0296 G. Johnston (510)975-0304 _