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

'-~j~gp~~TED DISTURBl.'TIOA DEMONSTRX+)4 SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8902080166 DOC.DATE: 89/02/03 NOTARIZED:

YES FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 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).

DOCKET 05000244 05000244 RECIPIENT ID CODE/NAME PD1-3 LA STAHLE,C INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DEST/SICB NUDOCS~BSTRACT IL 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 0 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/DOEA/TSB 11 OGC/HDS2 RES/DSIR/EIB NRC PDR COPIES LTTR ENCL 2 2 1 1 1 1 1 1 1 1 1 0 1 1 R I NOTE TO ALL"RIDS" RECIPIENIS'IZASE 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 A D D S TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 16

///////////L

//II///////

L1iI 01/JA urij II SZ(rZZZZ ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y.14649 0001 February 3, 1989 TELEPHONE ARE*CODE 7>e 546.2700 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 PDR~0>~6 89020m R 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.Attachment 1 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 NTAAY PUSUC,@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

~~SNY6AQ A JSUMAS tg'AN b NaS~NATN MYlQAN~~ey5fl~ecxMHLCh6 ATTACHMENT 1 I VALVE TESTING PROGRAM P LAN AOV FAX L SAFE TESTE D VALVES PAGE 1 pf 7 Va1 ve,'oo r.Number'w TTTe ,'Safety Si ze'ctuator'lass 110B J-7 GTV AOV 2 1266 2 1 12B F-2 1265 BFV AOV 112C D-2 1265 BFV AOV 142 B-7 1265 GLV AOV 200A B-11 GLV 1264 2 AOV 200B B-10 GLV 1264 2 AOV 202 B-9 1264 GLV AOV 371 A-6 1264 GLV AOV 386 C-9 1265 GTV AOV 430 B-7 1258 GLV AOV 431 C C-7 1258 GLV AOV VA LVE TESTING PROGRAM P LAN AOV FAI L SAFE TESTE D VA LVES PAGE Val ve,'oor.Number'w~Te ,'Safety Size'ctuator'lass 508 H-6 GTV AOV 2 1258 2 539 G-6 GLV 1258.375 AOV 745 8=10 GLV 1246 2 AOV 836A H-3 1261 GLV AOV 8368 H-3 1261 GLV AOV 846 A-3 1262 GLV AOV 897 C-6 1261 GTV AOV 898 C-7 1261 GTV AOV 951 E-2 GLV 1278.375 AOV 953 C-2 GLV 1278.375 AOV 955 8-2 1278 GLV.25 AOV VA LVE TESTXNG PROGRAM P LAN AOV FAIL SAFE TESTE D VA LVES PAGE of 7 Va1 ye,'oo r.Number'w~Te ,'Safety Si ze'ctuator'l ass 966A E-3 GLV AOV 2 1278~375 966B C-3 GLV 1278.375 AOV 966C B-3 GTV 1278.375 AOV 1003A E-7 1272 DIV AOV 2 10038 G-7 1272 DIV AOV 1597 G-10 DIV 1866 AOV 1598 F-10 DIV 1866 AOV 1599 F-10 DIV 1866 AOV 1721 F-6 1272 AOV AOV 1723 H-9 1272 DIV AOV 2 1728 H-5 1272 DIV AOV VA LVE TESTING PROGRAM P LAN AOV FAIL SAFE TESTE D VA LVES PAGE 4 of 7 Va 1 ve,'oo r.Number'w~Te,', ,'Safety Si ze'ctuator'1ass 1 786 B-7 DI V AOV 2 1272 1 1787 B-6 1272 DIV AOV 1789 D-8 1272 DIV.375 AOV 3410 I-4 1231 GTV AOV 3411 C-4 1231 GTV AOV 3516 G-1 1 1231 CV 30 AOV 3517 A-11 1231 CV 30 AOV 4269 D-7 1236 GTV 12 AOV NC 4270 G-7 1236 GTV 12 AOV NC 4271 D-8 1236 GTV AOV NC 4272 H-8 1236 GTV AOV NC VA LVE TESTING PROGRAM P LAN AOV FAIL SAFE TESTED VALVES PAGE 5 of 7 Va1ve ,'Coor.Number'w TTTe ,'afety Size'ctuator'C1ass 4291 H-5 GTV AOV 3 1237 2 4297 I-10 GTV 1237 AOV 4298 J-8 1237 GTV AOV 4304 C-6 1237 GTV AOV 4310 E-6 1237 GTV AOV 4480 B-6 1237 GTV 1.5 AOV 4481 F-6 1237 GTV 1.5 AOV 4561 F-10 1250 BFV 14 AOV 4562 F-11 1250 BFV 14 AOV 5392 A-9 1893 GTV AOV 5735 A-5 1277 GTV.375 AOV VA LVE TESTING PROGRAM P LAN AOV FAIL SAFE TESTED VALVES PAGE 6 of 7 Val ve ,'Coor.Number'w~Te'Safety Size'ctuator'Class 5736 B-5 GTV AOV 2 1277.375 5737 C-5 GTV 1277.375 AOV 5738 D-5 GTV 1277.375 AOV 5869 1865 BFV 48 AOV 5879 I-2 1866 BFV 48 AOV 7445 H-9 1865 BFV AOV 7478 H-10 BFV 1865 AOV 7970 F-3 1870 BFV AOV 7971 1870 BFV AOV 9227 1241 GTV AOV 9632A D-11 GTV 1250 0.5 AOV VA LVE TESTING PROGRAM P LAN AOV FAIL SAFE TESTED VALVES PAGE 7 of 7 Val ve'Coo r.Number'Dw I~Te I ,'Safety Si ze'ctuator'l ass 9632B C-11 GTV AOV 3 1250 0.5 9710A C-7 1238 GLV AOV 9710B H-7 1238 GLV 1.5 AOV RCV01 7 A-3 1245 GLV AOV