ML17309A497
| ML17309A497 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/25/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| GL-89-10, NUDOCS 9210080230 | |
| Download: ML17309A497 (6) | |
Text
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INFORMATION DISTRIBUTION STEM (RIDE)
ACCESSION NBR:9210080230 DOC.DATE: 92/09/25 NOTARIZED: NO DOCKET FA6IL:50-'244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Responds to Phase I insp of MOV qualification program,per GL 89-10,documented in Insp Rept 50-244/92-80.Current plans re use of prototypical flow 6 differential pressure testing clarified.
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TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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r Sl Arm Ililzil/A's@(ztztz ROCHESTER GAS AND ELECTRIC CORPORATION 14Er Oar@A cs 89 EAST AVENUE, ROCHESTER N.K 14649.0001 ROBERTC MECREDY Vice President Clnna Nuclear Producdon September 25, 1992 TELEPHONE AREACODE 716 54B 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Generic Letter 89-10:
Parallel Tfain Motor-Operated Valve (MOV) Testing R.
E. Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a):
NRC Inspection Report No. 50-244/92-80, "Motor-Operated Valve Inspection at R.
E. Ginna Nuclear Power Plant".
Ref. (b): Letter from R.
C. Mecredy (RG&E) to A. R. Johnson (NRC),
"Generic Letter 89-10:
Clarification to Program to Satisfy GL 89-10 Requirements",
dated March 27, 1991.
Ref. (c): Letter from A. R. Johnson (NRC) to R.
C. Mecredy (RG&E),
"Closeout of Generic Letter 89-10", dated March 6, 1992.
Dear Mr. Johnson:
This letter is in response to the NRC Phase I inspection of the Ginna Station MOV Qualification Program as documented in Reference (a).
Specifically, this letter is intended to clarify the current plans of Rochester Gas
& Electric Corporation (RG&E) regarding the use of prototypical flow and differential pressure (DP) testing.
-In Reference (b),
RG&E stated that the Generic Letter 89-10 MOV Program at Ginna Station requires design-basis DP testing to be performed on a minimum of one MOV in a parallel train of identical MOVs provided adequate margin above the thrust required to overcome DP is demonstrated.
This would occur on a case-by-case
- basis, and require justification.
If DP test results are satisfactory but adequate margin does not exist, the other MOVs would be DP tested.
Nevertheless, it is the intention of RG&E to perform baseline design-basis DP testing on all program MOVs, whenever feasible.
As practicable, this DP testing will be scheduled for completion within the time frame of Generic Letter 89-10, i.e. prior to the end of our 1994 refueling outage.
RG&E is in the process of evaluating the feasibility for DP testing each program MOV and has instituted an aggressive DP test program in order to obtain baseline data on all program MOVs possible.
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RG&E does not rely solely on any one method to ensure the operability of an MOV.
DP testing is an integral part of an overall program which provides assurance of MOV performance.
RG&E attempts to duplicate design-basis DP conditions; however, in most cases some limited amount of extrapolation to higher DP conditions than actually tested will be reguired.
Typically, RG&E attempts to limit such extrapolation to less than 20% beyond tested conditions.
For MOVs where 80% of the design-basis DP cannot be achieved, MOV setup will be accomplished using the best data and methods available, and then validated when results of the two-stage approach become available, as recommended in Generic Letter 89-10.
Temperature and flow are considered
- and, as with DP, in-situ test conditions prototypical of design-basis conditions are attempted to be established.
As previously indicated in reference (c),
RG&E is implementing a
two-stage approach toward verification of MOV operability and reliability. All MOV setup and in-situ verification results will be evaluated considering the design-basis testing and predictive modeling of MOV behavior currently being developed as part of the second stage of this program. It is expected that present methods used for MOV setup and DP testing will be validated by this effort.
Very truly yours, KAM/243 Robert C. Mecredy xc:
Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 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
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