ML20236W420
| ML20236W420 | |
| Person / Time | |
|---|---|
| Issue date: | 07/31/1998 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML20236W422 | List: |
| References | |
| TAC-M92782, NUDOCS 9808050265 | |
| Download: ML20236W420 (5) | |
Text
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. p *, UNITED STATES
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t NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20046 0001
\ . . . . . p# July 31, 1998 Dr. Robert C. Meeredy Vice President, Nuclear Operations I Rochester Gas and Electric Corporation {
89 East Avenue Rochester, NY 14649 ,
SUBJECT:
REVIEW OF WESTINGHOUSE OWNERS GROUP TOPICAL REPORTS WCAP-14333P AND WCAP-14334NP, DATED MAY 1995,"PROBABILISTIC RISK ANALYSIS OF THE RPS AND ESFAS TEST TIMES AND COMPLETION TIMES" (TAC NO. M92782)
Dear Dr. Meeredy:
i By letter dated June 20,1995, you submitted proposed changes to the improved Technical Specifications (ITS) Instrumentation Chapter (i.e., LCO 3.3.1, " Reactor Trip System (RTS)
Instrumentation" and limiting condition for operation (LCO) 3.3.2, " Engineered Safety Feature Actuation System (ESFAS) Instrumentation." These proposed changes effectively increase the j allowed tast and completion times for various instrumentation functions. The basis for these proposed changes is the Westinghouse prepared evaluation (WCAP-14333P and WCAP.
14333NP, "Probabilistic Risk Analysis of RPS and ESFAS Test Times and Completion Times,"
May 1995) of these functions using Probabilistic techniques. At the same time, the Westinghouse Owners Group (WOG) submitted the subject reports for staff review. The NRC staff has completed its review of the subject topical reports prepared by Westinghouse Electric Corporation for the WOG. The enclosure provides the staff's safety evaluation (SE) approving the topical reports. The topical reports describe the Westinghouse Owners Gronp's program, which was completed as an industry effort to demonstrate the acceptability of the increase in the test bypass times and the allowed outage times for the reactor protection system (RPS) and engineered safety feature actuation system (ESFAS). The enclosed SE was prepared by the NRC staff and accepts topical report WCAP-14333P 'or referencing in plant-specific license amendment applications.
In WCAP-14333P, the WOG proposed relaxations in the technical specification required test bypass times and allowed outage times (AOTs) for the RPS and ESFAS. The staff used a three-tiered approach to evaluate risk associated with the proposed changes. The approach is consistent with the guidance in Draft Regulatory Guide DG-1065, "An Approach for Plant-Specific, Risk-Informed Decision Making: Technical Specifications." The first tier evaluates the licensee's probabilistic risk analysis (PRA) model and the impact of the change on plant operational risk. The second tier addresses the need to preclude potentially high risk configurations, shoulo additional equipment outages occur during the AOT period. The third tier !
evaluates the licensee's configuration risk management program (CRMP), to ensure that f I equipment removed from service immediately prior to or during the proposed AOT will be q appropriately assessed from a risk perspective. 1 j0 Based on the t/ tree-tiered approach, the staff finds that implementation of the proposed changes in RPS and ESFAS instrumentation AOTs should result in only a very small quantitative impact on plant risk. The PRA insights generally support the proposed changes; however, the generic applicability of the PRA analysis in the topical report to all Westinghouse plants introduces a 8 b 2 W5I A r1 H 4 $ _ 3_ b 24 D% l 98080'50265 980731 '>
- DR TOPRP EMV
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July 31, 1998 R. C. Mecredy larger degree of uncertainty. Therefore, the staff expects licensees that use this topical report to justifj the extended test times and AOTs by submitting a license amendment request that includes the following p! ant-specific information:
- 1. Confirm the applicability of the WCAP-14333P, analyses for their plant.
- 2. Address the Tier 2 and 3 analyses including the CRMP insights which confirm that these insights are incorporated into their decision making process before taking equipment out of service.
You may now submit a license amendment reque4 incorporating the proposed changes as requested in your June 20,1995, letter. The essences of this letter and the enclosed SE was sent to Mr. Louis F. Liberatori Jr., Chairman of the WOG. Should you have any questions or wish further clarification, please call me on (301) 415-1441.
Sincerely, Original Signed by:
Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - 1/Il Office of Nuclear Reccior Regulation
Enclosure:
Safety Evaluation cc w/ encl: See next page DISTRIBUTION:
' Docket FHe
- PUBLIC PDL 1 R/F J. Zwolinski (A)
S. Bajwa S. Little G. Vissing
' H. Garg T. Harris (E-mail SE only, TLH3)
OGC ACRS C. Hehl, Region i DOCUMENT NAME: G:\GINNA\M92782.COM l ' To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" j = Copy with attachment / enclosure "N" = No copy f 0FFICE PM:PDI 1 ;lE LA: POI +1 lC D:PDI 1 , , ,
l l l NAME Gvissirig: Leg /f/7 SLtttle T/t, /c 7 SBejwa RO x' V
D_ ATE 07/ft/98 07/ N /98 07/ 31/98 TC( 07/ /98 07/ /98
Ouly 31, 1998 A
R. C. Mectedy larger degree of uncertainty. Therefore, the staff expects licensees that use this topical report to justify the extended test times and AOTs by submitting a license amendment request that includes the following plant-specific information:
- 1. Confirm the applicability of the WCAP-14333P, analyses for their plant.
- 2. Address the Tier 2 and 3 analyses including the CRMP insights which confirm that these insights are incorporated into their decision making process before taking equipment out of service.
You may now submit a license amendment request incorporating the proposed changes as I requested in your June 20,1995, letter. The essences of this letter and the enclosed SE was sent to Mr. Louis F. Liberatori Jr., Chairman of the WOG. Should you have any questions or wish further clarification, please call me on (301) 415-1441.
Sincerely, Original Signed by:
Guy S. Viss!ng, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - t/ll Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ encl: See next page DISTRIBUTION:
Docket Fila PUBLIC PDI-1 R/F J. Zwolinski (A)
S. Bajwa S. Littie G. Vissing H. Garg T. Harris (E-mail SE only, TLH3)
OGC ACRS C. Hehl, Region i DOCUMENT NAME: G:\GINNA\M92782.COM l To re:eive a copy of this document, indicate in the box: "C" = Capy without attachment / enclosure "E" l = Copy with attachment / enclosure "N" = No copy 0FFICE PM:PDI 1 ,lE LA:PDI 1 lC D:PDI 1 l l l NAME GVissing:lce,ef/7 SLittle ~7/r ,/r-, SBajwa ROC DATE 07/f r /98 ' FC(
07/ 3 / /96 07/ 3 t /98 07/ /98 07/ /98
R. C. " redy larger degree of uncertainty. Therefore, the staff expects licensees that use this topical report to justify the extended test times and AOTs by submitting a license amendment request that includes the following plant-specific information:
- 1. Confirm the applicability of the WCAP-14333P, analyses for their plant.
- 2. Address the Tier 2 and 3 analyses including the CRMP insights which confirm that these insights are incorporated into their decision making process before taking equipment out of service.
You may now submit a license amendment request incorporating the proposed changes as requested in your June 20,1995, letter. The essences of this letter and the enclosed SE was sent to Mr. Louis F. Liberatori Jr., Chairman of the WOG. Should you have any questions or wish further clarification, please call me on (301) 415-1441.
Sincerely, Guy S. Vissing, Senior Project ' anager Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ encl: See next page l
l
Dr. Robert C. Mecredy Rochester Gas and Electric Company R.E. Ginna Nuclear Power Plant cc:
Peter D. Drysdale, Sr. Resident inspector R.E. Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road Ontario, NY 14519 .
i Regional Administrator, Region i U.S. Nuclear Regulatory Commission
'475 Allendale Road King of Prussia, PA 19406 Mr. F. William Valentino, President I New York State Energy, Research, and Development Authority i
Corporate Plaza West 286 Washington Avenue Extension l Albany, NY 12203-6399 {
I Charles Donaldson, Esquire Assistant Attomey General New York Department of Lalw 120 Broadway New York, NY 10271 Nicholas S. Reynolds Winston & Strawn
.1400 S Street N.W.
Washington, DC 20005-3502 Ms. Thelma Wideman, Director
- Wayne County Emergency Management Office Wayne County Emergency Operations Center )
i 7326 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Falls Road, Room 11 Rochester, NY 14620 l Mr. Paul Eddy !
New York Ctate Department of l Public Service 3 Empire State Plaza,10th Floor
)
i Albany, NY 12223 4
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