ML17251A415
| ML17251A415 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/23/1989 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Stahle C NRC, NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8903310156 | |
| Download: ML17251A415 (7) | |
Text
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DR1BUTI OY DEMO%ST.TIOY SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8903310156 DOC.DATE: 89/03/23 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 STAHLE,C.
NRC No Detailed AffiliationGiven
SUBJECT:
Provides documentation of 890315 telcon w/NRC answering IST questions.
DISTRIBUTION CODE A001D COPIES RECEIVED LTR ENCL SIZE:
TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DOCKET 05000244 05000244 ~
RECIPIENT ID CODE/NAME PD1-3 LA STAHLE,C INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/ICSB NRR/DEST/RSB 8E
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1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MTB 9H NRR/DOEA/.TSB 11 OGC/HDS2 RES/DSIR/EIB NRC PDR COPIES LTTR ENCL 1
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TOTAL NUMBER OF COPIES REQUIRED:
LTTR 22 ENCL 20
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/Ã ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 March 23, 1989 TELEPHONE ARE* COOK 710 546-2700 I
U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Carl Stahle PWR Project Directorate No.
1 Washington, D.C.
20555
Subject:
Documentation of Telecon with NRC Answering IST Questions R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Stahle:
The following is a summary of the telecon held on March 15, 1989 between RG&E and the NRC concerning the 12/20/88 IST submittal.
RG&E Re resentatives Charlie Anderson (Manager, QA)
Steve Piccolo (ACT Associates, Inc.)
NRC Re resentatives Clair Wranson (EG&G)
Renee Li (NRC)
Pat Sears (NRC)
The telecon was initiated at the request of Mr. George Wrobel in order to facilitate the rapid resolution of comments on the 12/20/88 IST submittal.
The NRC had telecopied 6
questions to RG&E, which are attached.
They are labeled. A.16, D.1, E.1, K.3, L.1 and P.9.
The responses discussed are as follows:
A.16 Allactive air operated valves which cannot be exercised during plant operation are identified in the upgraded IST program.
There are no air operated valves in this program which are practical to part stroke exercise.
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D.1 The modification which allows individual testing of 743 will be complete prior to restart after the 1989 outage.
Disassembly of 842 A and B as well as 867 A and B is scheduled for this outage.
Since it has been numerous years since the last disassembly, this preventive maintenance activity will allow us to establish the baseline condition of all 4 valves.
If no deviations in condition of the 4
valves are
- found, we will reconsider the grouping for sample disassembly to 1
group of 4 rather than 2 groups of 2 for the next 10 year interval.
K.3 We are scheduled to disassemble valve 4023 this outage.
In the future this valve will be exercised by circulating pump minimum flow requirements through this valve.
~L.l Reverse flow closure of 3992 and 3993 can only be adequately confirmed when transferring from main feedwater to auxiliary feedwater during normal plant shutdown.
If shutdown is due to plant trip this opportunity is missed.
Therefore, relief is requested (VR-28) so that testing can be performed at the next routine shutdown.
P.9 Valves 1813 A
and B
are classified as passive and receive an Appendix J test and a position indication test.
Valve 822A was inadvertently grouped with 1813 A and B and has since been deleted from the response to this question.
Agreement was obtained from all parties that these answers satisfactorily resolved. all NRC comments.
They will transmit approval for the interim program based on the submittal and this copy of telecon.
obert C. Mecr General Manager Nuclear Production GJWK030 Attachment xc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
REViEM CO%FATS DN THf DECdIBKR 20, 1S88 SUNITTAL FOR THE ROBERT E.
QINHA NUCLEAR POQKR PLANT PNP AHG VAlVE INSERYICK TESTING PROGRAM A.
The response to quostfon A.16 does not clearly indfcate that the afr A.)6 the re oparated valves whfch can not be practically full-stroke exercised quarterly durfng poww operations are part-stroke exercised at that frequency when possible,
~hfs point should bi clarfffed.
6.1 Qhen requesting temporary relfef from the Code requframents to fndivfdually verify the reverse flow closure of valves 743 and 743A, the lfcensee should fdantffy the spectffc time when the system modifications wfll be completed to allow individual testing (f.e.,
prior to startup from the next refueling outage scheduled for June 1991).
K,)
Valves 842A and B should not be grouped wfth valves BOTA and 8 for samp'le dfsassambly and fnspectfon since they da not meet the staff's posftfon for sfmt'tar service conditions.
Valves 867A and S are part. stroke exercised during cold shutdowns while valves 84RA and 8 are not exsrcfsed at that frequency.
Also these valve pairs are sub)ected to dffferent temperatures and pressures which could affect valve wear and corrosion rates, K.3 The response to questfon K.S fndfcatad that plant engfneerfng was valfdat!ng the minimum flow recirculation acceptance cr1terfa for the turbine driven auxflfary feedwater pump.
The licensee should provide the resolution from thfs svaluatfon.
l.,l Durfng the November 1 and 2, 1088 <<orkfng eeetfng the lfcensee agreed to test valves 3992 and 3993 at a cold shutdown frequency, The response to question l. 1 in the December 20, 1988 submittal fndfcatas that these valves w111 be verified fn the closed position durfng refuelfng outages and that a reliei'equest will be submitted.
In their relief request the 3fcensea should provide a detafled techn1cal
)ustfffcatfon for not testing these valves during cold shutdowns.
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P.S The ) )censee's response to qt est)on P,9 does not clearly <ndicate what test)Jig wil'I be pe@'oned on valves 1B13A and 8.
The response
)nd)cates that these valves why> be categor)red "A" and be 1eak rata tasted per Append1x 4 requirements,
- however, they have not )nd)cated whether these valval era to te exercised or class)fled as pass)ve
- valves, Th)s should be clarified )n the IST program.
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