ML17264A199
| ML17264A199 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/17/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-95-07, GL-95-7, NUDOCS 9510260319 | |
| Download: ML17264A199 (5) | |
Text
PRXGRXTY 1 (ACCELERATED RZDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) r ACCESSION NBR:9510260319 DOC ~ DATE: 95/10/17 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
DOCKET g
05000244 P
SUBJECT:
Responds to GL 95-07, "Pressure Locking
& Thermal Binding of Safety-Related Power-Operated Gate Valves."
0 DISTRIBUTION CODE:
A056D COPIES RECEIVED:LTR Q ENCL 5 SIZE:
TITLE: Generic Ltr 95-07 Pressure Locking
& Thermal Banding of afety Rela NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 I RECIPIENT ID CODE/NAME NRR/DRPE/PD1-1 JOHNSON INTERN
. FILE CEN R
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AND ROCSTER GASANDElECTRIC CORPORATION ~ 89 EASTAYENUE, ROCHESTER, N. Y Idbf9 000I AREA CODE7IS 546-2700 ROBERT C. MECREDY Vice President Nudeor operations October 17, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-1 Washington, D.C.
20555
Subject:
60 Day Response per NRC Generic Letter 95-07 Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves R.
E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):
Ginna Motor-Operated Valve Inspection 95-06, dated June 16, 1995
Dear Mr. Johnson:
On August 17, 1995, the Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 95-07, "Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves".
GL 95-07 confirms the NRC staff position on this issue as presented in Supplement 6 to NRC GL 89-10, "Safety-Related Motor-Operated Valve Testing and Surveillance".
The staff position stated that licensees are
- expected, under existing regulations, to take actions as necessary to ensure that safety-related, power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their required safety functions.
As a result, the staff has requested that licensees
- perform, or confirm previous performance of, the following:
Within 90 days:
1.
A screening evaluation to identify power-operated valves which are potentially susceptible to pressure locking and/or thermal binding.
2.
The documentation of a basis for operability of potentially susceptible power-operated
- valves, or take actions in accordance with Technical Specifications.
Within 180 days:
Evaluations of operational configurations of safety-related, power-operated (including
- motor, air and hydraulically operated) gate valves for susceptibility to pressure locking and/or thermal binding.
9510260319 951017 PDR g ADOCK05000244 P
--- '"'i..":x PDR 8ik~ S8 ~ I~ioQ
0 I
h $ c Further analysis, and any needed corrective actions, to ensure that identified potentially susceptible valves are capable of performing their current licensing basis safety functions.
RG&E plans to perform all of the requested actions discussed within the GL 95-07.
- However, RG&E proposes an exception to the schedule for completion of the 90-day requested action for screening evaluation and basis documentation of identified potentially susceptible valves.
RG&E proposes to meet an alternative schedule for the 90-day requested actions.
RG&E is participating in a Westinghouse Owners Group (WOG) project designed to address the recommendations of GL 95-07.
In part, this project will establish a
common set of criteria which can be applied in the screening and evaluation of the pressure locking and thermal binding phenomena.
Most of the NSSS systems, as well as many of the valves in those
- systems, are common among the various Westinghouse plants.
Thus, it is beneficial and cost effective, to both WOG members and the NRC, to utilize the expertise of the member utilities and Westinghouse to develop a consistent, effective and comprehensive set of screening and evaluation criteria that can be used by all WOG plants.
Criteria and methodology will also be developed for use in the evaluations of those valves determined to be
. susceptible to pressure locking and/or thermal binding.,
These evaluations will determine the need for additional analysis and/or valve modifications.
In addition, an end product of the project is the development of operability justifications for those valves identified as potentially susceptible.
If operability justifications cannot be demonstrated, the.applicable Technical Specifications action will be followed.
RG&E has previously completed susceptibility screening evaluations for 259 gate valves, both power operated and manually operated, partly due to Supplement 6 to GL 89-10 and partly in anticipation of GL 95-07.
The results of this effort were reviewed by an NRC inspection team in April,.1995 (Reference (a)).
Reference (a) concluded that RG&E had satisfactorily evaluated for operability all GL 89-10 MOVs susceptible to PLTB.
However, the PLTB issue was left unresolved pending the issuance of generic guidance by the NRC.
RG&E is employing the guidance provided by GL 95-07 and the WOG to complete the tasks requested by GL 95-07.
This will enable us to utilize the screening established by the WOG project to augment our previously performed screening.
RG&E believes that the detailed evaluations to be performed as part of the WOG effort are key factors in resolving the concerns associated with GL 95-07, and that resources can be more appropriately and productively focused on meeting the actions requested under the 180-day generic letter schedule.
Consequently, there are no safety implications in delaying completion of the 90-day requested actions to 180 days.
RG&E is confident that any significant pressure locking/thermal binding concerns will not be identified as a result of future evaluations.
The valve groups receiving the most industry scrutiny (RHR containment sump isolation, pressurizer PORV block, and RHR core deluge) have either been previously modified or analytically evaluated to confirm operability at Ginna Station.
Therefore, RG&E plans to comply with all GL 95-07 actions and responses requested within 180 days.
This will allow for further analyses in conjunction with the WOG project toward the determination of potentially susceptible valves.
Very truly yours, KAM)396 Robert C. Mecr dy xc:
Mr. Allen R. Johnson (Mail Stop 14B2)
Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 US NRC Ginna Senior Resident Inspector