Headquarters Daily report MAY 03, 1994 *************************************************************************** REPORT NEGATIVE NO INPUT ATTACHED INPUT RECEIVED RECEIVED HEADQUARTERS X REGION I X REGION II X REGION III X REGION IV X *************************************************************************** PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS MAY 3, 1994 MR Number: H-94-0046 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS BRANCH/EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT OFFICE OF NUCLEAR REACTOR REGULATION Subject: N/A NRC Administrative Letter 94-07, "Distribution of Site-Specific and State Emergency Planning Information," will be issued May 6, 1994. The NRC is issuing this administrative letter to inform addressees that the NRC would welcome receipt of copies of the information brochures that are disseminated annually to the public pursuant to 10 CFR Part 50, Appendix E, and also updated State and/or local emergency plan information. This information will be used to augment the information contained in the site emergency plan. Contacts: Rosemary T. Hogan, AEOD (301) 492-7053 Karla K. Bristow, AEOD (301) 492-9004 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I MAY 3, 1994 Licensee/Facility: Notification: Long Island Lighting Co MR Number: 1-94-0053 Shoreham 1 Date: 05/03/94 Wading River,New York Dockets: 50-322 BWR/GE-4 Subject: STATUS OF SHOREHAM DECOMMISSIONING Reportable Event Number: N/A Discussion: The Shoreham Nuclear Power Station (SNPS) is nearing completion of removal of systems, components and structures known to exhibit contamination or radiation levels in excess of NRC decommissioning criteria. Major steps yet to be completed and the expected completion dates are: completion of the shipment of the fuel to the Limerick Generating Nuclear Station (late May); draindown and discharge of the spent fuel storage pool water (late May); removal of contaminated fuel storage racks and limited portions of the fuel pool clean-up system piping (early to mid-June); completion of characterization and termination surveys in the drained spent fuel storage pool (July); and final cutting of the biological shield wall (early May). The licensee has completed 26 of 33 planned shipments of fuel to Limerick as of May 2, 1994. Shipping activities have been monitored by NRC Region I staff, both at Shoreham, at an intermediate transfer point, and at Limerick. The draindown of the pool will involve discharge of about 325,000 gallons of water over about a 110-hour period. In preparation for draindown of the pool, Region I has initiated reviews of the licensee's design changes, procedures, pool water sampling protocol, and calibration of in-line liquid effluent monitors that will be used to monitor the discharge. Preliminary samples of the pool water were collected by Region I and sent to Idaho National Engineering Laboratory's Radiological Environmental Services Laboratory for detailed analysis. Region I plans additional sampling of the pool water and in-depth review of release documentation and authorizations prior to actual discharge of the pool water. In addition, use of the Region I independent measurements van is being considered to perform analysis of each batch of water prior to release. However, thus far, analyses performed by the licensee have found radioactivity levels in the pool water much less than NRC release criteria. Efforts are being made by the licensee to remove all contamination and radioactive materials from the Shoreham Station prior to the expected closure of the Barnwell, South Carolina disposal facility on June 30, 1994. Region I is monitoring the licensee's progress on cutting out the activated portions of the biological shield wall and will perform independent analysis of the portions of the biological shield wall that are expected to be left on site. The State of New York is being kept advised relative to the decommissioning inspection activities. On April 29, Region I was informed of the resignation of the New York Power Authority (NYPA) representative (Jack Brons) on the Board of Directors of the Long Island Power Authority. The First Executive VP NYPA (Robert Schoenberger) has been appointed to the vacant position. Contact: RONALD NIMITZ (215)337-5267 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV MAY 3, 1994 Licensee/Facility: Notification: Pacific Gas & Electric Co. MR Number: 4-94-0040 Diablo Canyon 1 Date: 05/02/94 San Luis Obispo County,California Resident Inspector Telecon Dockets: 50-275 PWR/W-4-LP Subject: OVERPRESSURIZATION OF RHR SYSTEM PIPING Reportable Event Number: N/A Discussion: On May 1, 1994, with Unit 1 in Mode 5 (350 psig), with solid pressurizer, the RHR Train 1-2 design pressure of 600 psig was exceeded briefly. Operators performing a routine charging injection system vent procedure mistakenly left a valve open, which caused inventory to inject into the RCS. RCS pressure increased rapidly due to the added inventory and solid pressurizer. PCV 135, the letdown regulator valve, opened to reduce RCS pressure, transmitting increased pressure to the RHR system. Since the core had been shut down for 2 months, RHR flow was throttled to approximately 1300 gpm, resulting in RHR pump differential pressure across the pump of approximately 180 pounds. As RCS pressure increased, the added RHR pump differential pressure resulted in pressure downstream of the pump discharge increasing to a maximum of about 605 psig in RHR Train 1-2, and approximately 600 psig in Train 1-1. RHR system design pressure is 600 psig. Upon receipt of an alarm for RHR pressure over 600 psig, operators took action to reduce RCS and RHR system pressures and isolate the charging system injection pathway. The portion of the RHR system which was pressurized included the piping from the discharge of the pump, through the RHR heat exchanger, and up to Throttle Valve FCV 637. The RHR relief valve is located downstream of the throttle valve to protect the RHR system from backleakage through injection system containment isolation valve. The RCS Low Temperature Over Pressure Protection (LTOP) system, set to relieve at 450 psig, was not challenged during this event. Regional Action: The resident staff and Regional office will be following the licensee's evaluation actions for this incident. Contact: D. Kirsch (510)975-0290 M. Miller (805)595-2354 D. Corporandy (510)975-0319 PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION IV MAY 3, 1994 Licensee/Facility: Notification: Washington Public Power Supply System MR Number: 4-94-0041 Washington Nuclear 2 Date: 05/02/94 Richland,Washington Resident Inspector Telecon Dockets: 50-397 BWR/GE-5 Subject: BENT REFUELING MAST AT WNP-2 Reportable Event Number: N/A Discussion: On May 2, 1994, at approximately 8 a.m. (PDT), with the reactor in Mode 5, refueling, the licensee bent the WNP-2 refueling mast. The mast, which was extended with no load attached, had been recently positioned for load and interlock testing in the cask storage area of the spent fuel pool. The testing had been suspended when craftsmen requested the Refueling Floor Coordinator (RFC), the backup system engineer for the refueling system, to reposition the refueling bridge so that the fuel shield blocks could be moved. The RFC manually (using the handcrank) repositioned the bridge, because the bridge was not powered-up and because the RFC had no experience in powering-up the bridge. The RFC failed to assess the position of the mast or consult operations personnel prior to moving the bridge. The refueling bridge was moved approximately 5 feet and the mast contacted the side wall of the cask storage area. The mast was sprung approximately 3 - 5 feet. When restored to its original position, the mast was permanently bent approximately 3 inches and could not be fully retracted. The licensee convened an Incident Review Board (IRB) to evaluate this event. The licensee has procured a replacement mast from General Electric. The mast is expected to arrive at 12 p.m., on May 3, 1994. The licensee anticipates that installation and testing of the replacement mast will take approximately 36 - 48 hours. Regional Action: The resident staff and Regional office will be following the licensee's evaluation actions for this incident. Contact: D. Kirsch (510)975-0290 R. Barr (509)377-2627 D. Corporandy (510)975-0319