ML18153C284
| ML18153C284 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/09/1990 |
| From: | Buckley B Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9007130071 | |
| Download: ML18153C284 (11) | |
Text
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g Docket Nos. 50-280 and 50-281 LICENSEE:
FACILITIES:
SUBJECT:
UNITED STATES 1)C5e~l. 1 /CIU e*
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 July 9, 1990 Virginia Electric and Power Company Surry Power Station, Units 1 & 2 MEETING
SUMMARY
OF JUNE 28, 1990 A meeting was held with representatives of Virginia Electric and Power Company (VEPCO) in Rockville, Maryland on June 28, 1990.
The purpose of the meeting was to discuss planned modifications to the component cooling water (CCW) piping to mitigate the consequences of a reactor coolant pump thermal barrier tube leak.
The meeting handout and a list of attendees are enclosed.
VEPCO representatives discussed various design options they had evaluated, and concluded that, based on long-term maintenance, ALARA, and cost considerations the modifications as shown on Figure 2 of the meeting handout was the most practical approach to resolve this concern.
The current CCW piping configuration is shown on Figure 1 of the handout.
The section of piping of interest consists of two high pressure check valves to prevent backflow, a safety valve set at 2500 psig located upstream of the reactor coolant pump and an isolation valve that will automatically close should the normal CCW flowrate of 40 gallons per minute (gpm) increase to 50 gpm.
Other means are available in the CCW System, such as CCW temperature and radiation monitors to alert plant personnel of thermal barrier leakage.
The proposed changes as shown on Figure 2 consist of replacing the existing containment isolation valve located outside containment with a 1500 lb. valve and installing another 1500 lb. containment isolation valve and a local, manually operated 1500 lb. block valve inside containment.
In addition to the two aforementioned automatic containment isolation valves closing on containment hi-hi pressure, they will also close on a high CCW flowrate signal. The emergency operating procedures will be revised to address this accident scenario.
In response to NRC staff questions the licensee will inform the NRC how they will address post-LOCA thermal expansion between the two new automatic contain-ment isolation valves which has the potential to result in unacceptably high pressures between these two closed valves.
VEPCO was also asked to advise the NRC staff if the two new containment isolation valves and associated new piping are being designed to current regulatory requirements or to the original plant licensing basis. Because of long lead times associated with the procurement of the new valves and instrumentation, these modifications will not be completed until the Cycle 11 refueling outage, currently scheduled for the first quarter of 1992.
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e e The NRC staff agreed that VEPCO's design approach and implementation schedule appeared reasonable.
Enclosures:
- 1. List of Attendees
- 2. Meeting Handout cc w/enclosures:
See next page D~
. DISTRIBUTION.
Docket F.i le. **:.
NRG & Local PDRs PD22 Reading F. Miraglia 12/6/18 J. Partlow 12/6/18 S. Varga
- 6. Lainas H. Berkow B. Buckley
- 6. Belisle RII J. Pulsipher 8/D/l B. LeFave 8/D/l 06C E. Jordan MNBB-3302 ACRS (10)
R. Borchardt 17621 D. Miller Original signed by Bart C. Buckley, Project Manager Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
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DATE
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e Virginia Electric and Power Company cc:
Michael W. Maupin, Esq.
Hunton and Williams Post Office Box 1535 Richmond, Virginia 23212 Mr. Michael R. Kansler, Manager Surry Power Station Post Office Box 315 Surry, Virginia 23883 Senior Resident Inspector Surry Power Station U.S. Nuclear Regulatory Conunission Post Office Box 166, Route 1 Surry, Virginia 23883 Mr. Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Mr. W. T. Lough Virginia Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23209 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 C. M. G. Buttery, M.D., M.P.H.
Department of Health 109 Governor Street Richmond, Virginia 23219 Mr. W. L. Stewart Senior Vice President - Nuclear Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060
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Surry Power Station Attorney General Supreme Court Building 101 North 8th Street Richmond, Virginia 23219 Mr. E. Wayne Harrell Vice President - Nuclear Operations Virginia Electric and Power Company 5000 Old Dominion Blvd.
Glen Allen, Virginia 23060 Mr. J. P. O'Hanlon Vice President - Nuclear Services Virginia Electric and Power Company 5000 Old Dominion Blvd.
Glen Allen, Virginia 23060 Mr. Re F. Saunders Manager - Nuclear Licensing Virginia Electric and Power Company 5000 Old Dominion Blvd.
Glen Allen, Virginia 23060
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MEETING WITH SURRY AND NRC STAFF REGARDING COMPONENT COOLING WATER (CCW)
June 28, 1990 NRC VEPCO B. Buckley D. Sommers G. Belisle (RII)
B. Benthall J. Pulsipher E. Grecheck B. LeFave G. Nash T. Shaub
VIRGINIA POWER COMPONENT COOLING THERMAL BARRIER MEETING JUNE 28, 1990 I
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PROPOSED MODIFICATION AND BASIS SIX OPTIONS INVESTIGATED MITIGATION OF EVENT MAINTAIN REACTOR COOLANT WITHIN CONFINES OF CONTAINMENT
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ALARA CONSIDERATIONS - INSTALLATION/MAINTENANCE COSTS
PROPOSED MODIFICATION AND BASIS SELECTED OPTION NONSAFETV TRIP VAL VE ANAL VZED PIPING REDUNDANT SAFETY-RELATED TRIP VALVES AT CONTAINMENT PENETRATION BASIS FOR SELECTED OPTION CONTAINMENT ISOLATION ARRANGEMENT INSTRUMENT LOOP DESIGN PIPING DESIGN J
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CURRENT SYSTEM CONFIGURATION RCP THERMAL BARRIER UPSTREAM CC SYSTEM DESIGN RCP THERMAL BARRIER DOWNSTREAM CC SYSTEM DESIGN ADMINISTRATIVE PERIODIC TESTING
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IMPLEMENTATION SCHEDULES DESIGN CHANGE PACKAGES
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