ML17261A838

Responds to Generic Ltr 88-14, Instrument Air Supply Problems Affecting Safety-Related Equipment. Actions Taken to Implement Four Listed Specific Actions & Proposed Schedule for Implementation Not Yet Complete

ML17261A838
Person / Time
Site:	Ginna
Issue date:	02/03/1989
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-NUREG-1275 GL-88-14, NUDOCS 8902080166
Download: ML17261A838 (13)

Text

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ACCESSION NBR:8902080166 DOC.DATE: 89/02/03 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 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION STAHLE,C. Project Directorate I-1

SUBJECT:

Responds to Generic Ltr 88-14, "Instrument Air Supply Problems Affecting Safety-Related Equipment."

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). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 0 PD1-3 PD 2 2 STAHLE,C 1 1 INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SICB 1 1 NRR/DOEA/TSB 11 1 1 NUDOCS~BSTRACT 1 1 OGC/HDS2 1 0 IL 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR NSIC 1 1 R

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NOTE TO ALL "RIDS" RECIPIENIS'IZASE S

HELP US TO RE2XJCE HASTE! CXNI'ACI'IHE DOCUNEMI'ONTROL DESK, ROON Pl-37 (EXT. 20079) TO ELXMXNATE KSR NME FRQH DXSTIGBVTXON LXSTS POR DOCUKBCIS KRJ DON'T NEZDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 16

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// /////////L urij II SZ(rZZZZ ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 0001 TELEPHONE ARE* CODE 7>e 546.2700 February 3, 1989 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Carl Stahle PWR Project Directorate No. 1 Washington, D.C. 20555

Subject:

Instrument Air Supply Problems Affecting Safety-Related. Equipment (Generic Letter 88-14)

R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Stahle:

Generic Letter 88-14 requested confirmation of actions taken to implement four specific actions and a proposed schedule for implementation of those actions not yet complete.

Based on a review of NUREG-1275 Volume 2 and Generic Letter 88-14, the four actions are as follows:

1) Verification by test that actual instrument air quality is co'nsistent with the manufacturer's recommendation for individual components served..

2) Verification that maintenance practices, emergency procedures, and. training are adequate to ensure that safety-related equipment will function as intended on a loss of instrument'ir.

3) Verification that the design of the instrument air system is in accordance with its intended. function.

This includes verification by test that air operated safety components will perform as expected.

4) A discussion of the program for maintaining proper instrument air quality.

Rochester Gas and Electric Corporation has prepared an action plan detailing the documentation and testing as specified in Generic Letter 88-14. A review of recommendations of INPO Significant Operating Experience Report (SOER) 88-1 was factored into this action plan. The safety-related valve testing verification is being integrated with the Inservice Test Program for air operated valves.

eS02 ~0>~6 PDR R 89020m AQGCK 05000244 PDC

Because of the extensive scope and. detail of the action plan, it is necessary to obtain contract support. Highlights of Action Plan activities are as follows:

~ Evaluate INPO SOER 88-01 recommendations

~ Review instrument air design bases

~ Define component air quality requirements

~ Identify and perform air quality testing

~ Complete, current P&ID upgrade,

~ Complete Instrument Air System valve database

~ Field verify (new test or history) valve failure positions

~ Prepare system description/design description

~ Review operations/training/maintenance practices Perform any potential follow-up hardware/procedure/training/testing if necessary

~

This contract effort will. be underway in the upcoming refueling outage scheduled to begin March 17, 1989 to prepare a design description/system description document. This effort includes a review of the maintenance and emergency procedures, as well as operational practices. Any recommended changes to procedures affecting maintenance or operational practices identified by this review will be reported to management by August 31, 1989. Those changes required by RGGE management will be accomplished, including appropriate training by December 1989. If this review identifies potential hardware modifications, we will review the scope, necessity, and priority of the changes. Any necessary modification(s) will then be appropriately factored into the work schedule for both engineering and'nstallation/testing.

Air operated valve fail safe testing on loss of air for AOVs that assure safe operation and. shutdown has been reviewed and incorporated. into the current Inservice Test Program. is a list of such valves that either have been tested. or will be tested during the upcoming refueling outage.

Integrated plant response, including controller functional response, due to degrading air supply or loss of air will be evaluated for feasibility and, necessity of testing during the 1989 outage.

Any physical testing associated with validation of the design description/system description document will be deferred until the 1990 refueling outage. This is necessary based on the current schedule for performance of the system design verification. This verification requires walkdowns of areas that. are inaccessible during operation.

Air dryer performance has not been an operational or maintenance problem to date. Automatic receiver blowdown functions have also not been a concern. Dryer desiccant breakdown was a concern at one time. This resulted in an annual inspection of dryer operation and desiccant. Dew point testing was performed and indicated significant temperature margin was available before moisture problems would occur.

i A filter element used to detect particulate and oil will be used to gather a test sample on the instrument air system so that interim acceptable operation is assured.

The requirements for maintaining the air quality in the instrument air system will be addressed during 1989 refueling outage with any necessary procedure upgrades to follow.

Very truly yours, Robert C. M credy General Manager Nuclear Production Subscribed and sworn to before me on this 3rd day of February 1989.

SAMUEL R SAOWNB NTAAYPUSUC,@Coat tArpYgh NL C1704$

+cendmha BPmQag@f SFPN020 Attachments xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

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ATTACHMENT 1 VALVE TESTING PROGRAM P LAN I

AOV FAX L SAFE TESTE D VALVES PAGE 1 pf 7 Va1 ve,'oo r. TTTe 'Safety Number'w Si ze 'ctuator 'lass 110B J-7 GTV AOV 2 1266 2 1 12B F-2 BFV AOV 1265 112C D-2 BFV AOV 1265 142 B-7 GLV AOV 1265 200A B-11 GLV AOV 1264 2 200B B-10 GLV AOV 1264 2 202 B-9 GLV AOV 1264 371 A-6 GLV AOV 1264 386 C-9 GTV AOV 1265 430 B-7 GLV AOV 1258 431 C C-7 GLV AOV 1258

VA LVE TESTING PROGRAM P LAN AOV FAI L SAFE TESTE D VA LVES PAGE Val Number 508

'w ve,'oor.

H-6

~Te Size GTV AOV

'Safety

'ctuator 'lass 2

1258 2 539 G-6 GLV AOV 1258 .375 745 8=10 GLV AOV 1246 2 836A H-3 GLV AOV 1261 8368 H-3 GLV AOV 1261 846 A-3 GLV AOV 1262 897 C-6 GTV AOV 1261 898 C-7 GTV AOV 1261 951 E-2 GLV AOV 1278 .375 953 C-2 GLV AOV 1278 .375 955 8-2 GLV AOV 1278 .25

VA LVE TESTXNG PROGRAM P LAN AOV FAIL SAFE TESTE D VA LVES PAGE of 7 Va1 Number 966A

'wr.

ye,'oo E-3

~Te Si ze GLV

'ctuator AOV

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'Safety ass 2

1278 ~ 375 966B C-3 GLV AOV 1278 .375 966C B-3 GTV AOV 1278 .375 1003A E-7 DIV AOV 2 1272 10038 G-7 DIV AOV 1272 1597 G-10 DIV AOV 1866 1598 F-10 DIV AOV 1866 1599 F-10 DIV AOV 1866 1721 F-6 AOV AOV 1272 1723 H-9 DIV AOV 2 1272 1728 H-5 DIV AOV 1272

VA LVE TESTING PROGRAM P LAN AOV FAIL SAFE TESTE D VA LVES PAGE 4 of 7 Va 1 Number 'w ve,'oo r . ~Te,',

Si ze 'ctuator

'Safety

'1ass 1 786 B-7 DIV AOV 2 1272 1 1787 B-6 DIV AOV 1272 1789 D-8 DIV AOV 1272 .375 3410 I-4 GTV AOV 1231 3411 C-4 GTV AOV 1231 3516 G-1 1 CV AOV 1231 30 3517 A-11 CV AOV 1231 30 4269 D-7 GTV AOV NC 1236 12 4270 G-7 GTV AOV NC 1236 12 4271 D-8 GTV AOV NC 1236 4272 H-8 GTV AOV NC 1236

VA LVE TESTING PROGRAM P LAN AOV FAIL SAFE TESTED VALVES PAGE 5 of 7

'Coor.

'ctuator ,'afety Va1ve , TTTe Number'w Size 'C1ass 4291 H-5 GTV AOV 3 1237 2 4297 I-10 GTV AOV 1237 4298 J-8 GTV AOV 1237 4304 C-6 GTV AOV 1237 4310 E-6 GTV AOV 1237 4480 B-6 GTV AOV 1237 1.5 4481 F-6 GTV AOV 1237 1.5 4561 F-10 BFV AOV 1250 14 4562 F-11 BFV AOV 1250 14 5392 A-9 GTV AOV 1893 5735 A-5 GTV AOV 1277 .375

VA LVE TESTING PROGRAM P LAN AOV FAIL SAFE TESTED VALVES PAGE 6 of 7 Val ve 'Coor. ~Te 'Safety Number'w Size 'ctuator 'Class 5736 B-5 GTV AOV 2 1277 .375 5737 C-5 GTV AOV 1277 .375 5738 D-5 GTV AOV 1277 .375 5869 BFV AOV 1865 48 5879 I-2 BFV AOV 1866 48 7445 H-9 BFV AOV 1865 7478 H-10 BFV AOV 1865 7970 F-3 BFV AOV 1870 7971 BFV AOV 1870 9227 GTV AOV 1241 9632A D-11 GTV AOV 1250 0.5

VA LVE TESTING PROGRAM P LAN AOV FAIL SAFE TESTED VALVES PAGE 7 of 7 Val ve'Coo Number '

9632B Dw r.

C-11 I

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'ctuator AOV

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'Safety ass 3

1250 0.5 9710A C-7 GLV AOV 1238 9710B H-7 GLV AOV 1238 1.5 RCV01 7 A-3 GLV AOV 1245