ML17265A183
| ML17265A183 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/03/1998 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-89-10, GL-96-05, GL-96-5, NUDOCS 9803120352 | |
| Download: ML17265A183 (7) | |
Text
CATEGORY l REGULA'i RY INFORMATION DISTRIBUTIO SYSTEM (RIDS) i ACCESSION NBR:9803120352 DOC.DATE: 98/03/03 NOTARIZED: YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION
. MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
SUBJECT:
Responds to GL 96-05, "Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves."
C DISTRIBUTION CODE:
A073D COPIES RECEIVED: LTR )
ENCL 3 SIZE:
A TITLE: GL-96-05 Periodic Verif. of Design Basis Capability of Safety-Related
- T NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 E
RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD/SOD/RAB NRR/DE/EMEB RES/DET/EIB/B RES/DST/PRAB EXTERNAL: NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME VISSING,G.
FILE CENTE "R/flu RES/DST NRC PDR COPIES LTTR ENCL 1,
1 1
1 1
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0 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 11
,ENCL 11
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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, Robert C. Mecredy Vice President Nuclear Operating Group March 3, 1998 Hfw IOils~
ROCHESTER, N.K 14649-0001 TELEPHONE APE* COOE T<e 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555-0001
Subject:
Response
to NRC Generic Letter 96-05 (Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves)
R.E.
Ginna Nuclear Power Plant Docket No. 50/244
References:
A.
NRC Generic Letter 96-05, dated September 18, 1996 B.,
RG&E 60 Day Response to NRC Generic Letter 96-05, letter from R.C.
Mecredy (RG&E) to G.
Vissing (NRC), dated November 18, 1996 C.
D ~
RG&E Notification of Closure of NRC Generic Letter 89-10, letter from R.C.
Mecredy (RG&E) to G. Vissing (NRC), dated March 3, 1998 Program Topical Report MPR-1807, Revision 2,
"Joint BWR and Westinghouse Owners Group Program on Motor-Operated Valve (MOV) Periodic Verification," in response to NRC Generic Letter 96-05, dated July, 1997
Dear Mr. Vissing:
On September 18,
- 1996, the NRC issued Generic Letter (GL) 96-05, "Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves" (Reference A).
The generic letter requested that each addressee establish a
- program, or ensure the effectiveness of its current program, to verify on a periodic basis that safety-related motor-operated valves (MOVs) continue to be capable of performing their safety-related function within the current licensing basis.
9803i20352 980303 t PDR ADQCK 05000244 P
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By letter dated November 18, 1996 (Reference B), Rochester Gas and'lectric (RG&E) documented its intentions to implement such a
program.
In that letter, RG&E committed to incorporate information developed as a result of a self-assessment of the GL 89-10 program and the efforts of the Westinghouse Owner's Group into RG&E's periodic verification program.
RG&E also committed to provide this summary description upon notification to the NRC of the completion of the GL 89-10 program for Ginna Station.
By letter dated March 3,
1998 (Reference C),
RG&E is providing such notification concerning GL 89-10.
Therefore, attached to this letter is a
summary description of RG&E's GL 96-05 program.
We consider all actions requested in Generic Letter 96-05 to be addressed for Ginna Station.
Ver truly yours, Robert C.
Mec y
Subscribed and sworn to before me on this 3rd day of March, 1998.
Notary Pu lic DEBORAH A.PIPERNI Notary Public m the State of New York ONTARlO COUNTY Commiss~ Expires Nov. 23, 19..,.I., l Attachment xct Mr. Guy S. Vissing (Mail Stop 14B2)
Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D AC. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S.
NRC Ginna Senior Resident Inspector
Periodic Verification Program Summary In response to NRC Generic Letter (GL) 96-05, "Periodic Verification of Design Basis Capability of Safety Related Motor-Operated Valves," the following summary description of the Ginna Station Program for periodic verification of motor-operated valves (MOVs) is provided.
The purpose of the Ginna Station Periodic Verification Program is to confirm on an established interval that safety related MOVs are capable of performing their safety functions consistent with the current licensing basis.
The Ginna Station Periodic Verification Program is based on the program developed by the Joint Owners Group (JOG).
The program is designed to monitor for potential valve degradation which could result in higher than anticipated thrust and torque requirements.
Revisions to the program will be based on recommended JOG changes, plant specific data or future guidance from the NRC.
The Ginna Station Periodic Verification Program consists of three basic elements:
static testing, dynamic testing and feedback data evaluation, which includes tracking and trending.
Although the current MOV program (established per the criteria of NRC GL 89-10) contains these three basic
- elements, there are slight differences in test intervals, selection and importance as compared to the JOG method.
The test program as developed under the GL 89-10 criteria will be maintained as the transition to the JOG test matrix is completed; Static Testing The objective of periodic static testing is to ensure that MOVs continue to be capable of performing their safety functions within the current licensing basis of Ginna Station.
Periodic static testing monitors for stem lubrication degradation, torque switch repeatability and overall valve/actuator performance.
Static testing is performed with no process fluid flow or differential pressure.
Test intervals are based on valve margin and its risk importance.
The current planned frequency of valve static testing, based on the combination of safety significance (risk) and valve margin, is shown in the following table:
MOV Static Test Frequency Risk Category Low Margin MOVs
((
5 :)
Medium Margin MOVs
() 5 'o'o 10 High Margin MOVs
(> 10.)
High Medium Low 1 cycle 2 cycles 3 cycles 2 cycles 4 cycles 6 cycles*
3 cycles 6 cycles*
6 cycles*
- Not to exceed 10 years Dynamic Testing The second element of the Periodic Verification Program is dynamic testing.
Dynamic testing is the most accurate method for determining final torque switch settings that ensure that each MOV continues to be capable of performing its safety functions within the current licensing basis.
In
- addition, dynamic testing helps to monitor important factors such as rate of loading, safety margins, valve factor and overall valve degradation.
For the JOG effort, each member is assigned MOVs that are to be differential pressure (D/P) tested at a minimum of three times over a five year period.
Each test must be performed at a minimum of 1 year intervals.
After each test, a report will be generated and submitted to the JOG periodic verification '.coordinator.
This data will be shared by all JOG members and reviewed at periodic intervals during a five year span.
The following two valves have been assigned to Ginna:
~ 857B RHR Pump Discharge to Safety Injection Pump Suction Motor-Operated Valve, 6" x 4" x 6" Anchor Darling Double Disk Gate Valve 9629A Service Water Inlet Isolation Valve to Standby Auxiliary Feedwater Pump C MOV, 4"
Borg Warner Flexible Wedge Gate Valve The initial baseline dynamic tests have been completed.
A minimum of two more dynamic tests will be conducted over the next two refueling outages
~
In addition, dynamic testing will be performed for selected valves to verify their design inputs and to improve the basis for selected valve factors.
Feedback Data Evaluation The last element of the Periodic Verification Program is the analysis and evaluation of the data.
All test data will be shared with the JOG.
Degradation will be documented in the Ginna Station Corrective Action process, and will require prompt evaluation for operability, cause analysis, and corrective action.
For shared
- data, degradations and/or, anomalies will be compared and analyzed against similar in-house valves.
Action plans for the shared data will be evaluated on a case-by-case basis.
If margins for valves decrease below established criteria, an enhancement plan will be established for such valves.
Following the nominal five year JOG program plan, the JOG committee will propose the final criteria for the Periodic Verification Program.
All implementing procedures and program documents will be
- revised, as needed, to reflect the final criteria at the end of this nominal five year period.
Continued MOV Performance Enhancement The three elements, combined,.will ensure that changes in required performance resulting from degradation (such as those caused by age) can be properly identified and accounted for.