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| | issue date = 02/03/1989 | | | issue date = 02/03/1989 |
| | title = 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 | | | title = 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 |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:'-~j~gp~~TED DISTURBl.'TIOA DEMONSTRX+)4 SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8902080166 DOC.DATE: 89/02/03 NOTARIZED: | | {{#Wiki_filter:'-~j~gp~~TED DISTURBl.'TIOA DEMONSTRX+)4 SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| YES FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. | | 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. |
| Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION STAHLE,C.Project Directorate I-1' | | RECIP.NAME RECIPIENT AFFILIATION STAHLE,C. Project Directorate I-1 |
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| ==SUBJECT:== | | ==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: | | Responds to Generic Ltr 88-14, "Instrument Air Supply Problems Affecting Safety-Related Equipment." |
| General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). | | DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: |
| 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
| | 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 |
| ///////////L | | I A |
| //II/////// | | D D |
| 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
| | 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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| | //II/////// L1iI 01/JA |
| | // /////////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 |
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| ==Subject:== | | ==Subject:== |
| Instrument Air Supply Problems Affecting Safety-Related. | | Instrument Air Supply Problems Affecting Safety-Related. Equipment (Generic Letter 88-14) |
| Equipment (Generic Letter 88-14)R.E.Ginna Nuclear Power Plant Docket No.50-244 | | 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. |
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| | 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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| | ~ ~ |
| | SNY6AQ A JSUMAS MYlQAN ~~ |
| | tg'AN b NaS~NATN ey5fl~ecxMHLCh6 |
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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 |
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| | 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 |
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| | 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 |
| | 'l |
| | '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 |
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| | 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 |
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| | 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 |
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| | 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 |
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| ==Dear Mr.Stahle:==
| | VA LVE TESTING PROGRAM P LAN AOV FAIL SAFE TESTED VALVES PAGE 7 of 7 Val ve'Coo Number ' |
| 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.
| | 9632B Dw r. |
| 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
| | C-11 I |
| ~Review instrument air design bases~Define component air quality requirements
| | ~Te Si ze GTV I |
| ~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
| | 'ctuator AOV |
| ~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.
| | 'l |
| 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.
| | 'Safety ass 3 |
| Air operated valve fail safe testing on loss of air for AOVs that assure safe operation and.shutdown has been reviewed and incorporated.
| | 1250 0.5 9710A C-7 GLV AOV 1238 9710B H-7 GLV AOV 1238 1.5 RCV01 7 A-3 GLV AOV 1245}} |
| 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
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| ~~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}}
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Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L4481990-09-18018 September 1990 Forwards Responses to Rer 900709-13 Team Visit Findings, Per .Responses Withheld (Ref 10CFR73.21) ML17309A4491990-09-13013 September 1990 Forwards Slides Presented by Facility & Westinghouse to NRC in 900724 Meeting.Encl Withheld ML17262A1331990-09-11011 September 1990 Responds to Violations & Several Unresolved Items Noted in SSFI Rept 50-244/89-81.Update of Appropriate Unresolved Items Encl.Specific Actions Re All NRC Unresolved Items Being Tracked to Completion ML17261B1511990-08-29029 August 1990 Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Rev 3 to Process Control Program for Ginna Station, Per Tech Specs 6.9.1.4 & 6.16,respectively ML17261B1481990-08-28028 August 1990 Lists Understanding of Issues Util Planning to Address Re Containment Integrity,Per 900718 Telcon.Any Concerns or Action Items Different from Listed Submittal Should Be Provided to Util Prior to NRC 900905 & 06 Visit to Plant IR 05000244/19880261990-08-20020 August 1990 Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented ML17261B1501990-08-20020 August 1990 Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented ML17261B1371990-08-17017 August 1990 Forwards Rev 0 to, Inservice Insp Rept for Third Interval (1990-1999),First Period,First Outage (1990) at Re Ginna Nuclear Power Plant. ML17309A4481990-08-16016 August 1990 Responds to NRC 900717 Ltr Re Violations Noted in Insp Rept 50-244/90-80.Corrective Actions:Westinghouse Drawing E-2508 Approved & Issued to Central Records ML17261B1351990-08-15015 August 1990 Provides Info & Assessment on Integrity of Connection of Containment Bldg to Foundation,Per 900808 Telcon.Util Believes That Existing Condition Not Safety Concern & No Reason Exists to Suspect Joint Will Not Perform Function ML17261B1361990-08-14014 August 1990 Responds to Commitment Tracking Concerns Noted in Insp Rept 50-244/90-09 & Planned Corrective Actions.Util Confirms Commitments Dates for Implementation of Effective Shelf Life Program & Comprehensive Preventive Maint Program for Parts ML17261B1331990-08-13013 August 1990 Recommits to Performing Enhanced primary-to-secondary Leak Rate Monitoring,Per NRC Bulletin 88-002 ML17261B1261990-07-30030 July 1990 Clarifies Commitment Made in 900316 RO Re Restoring Inoperable Fire Damper I-411-21-P.Util Plans to Design Removable Track Which Will Allow Charcoal Drawer to Be Manipulated.Definitive Schedule Will Be Provided in 60 Days ML20055H9291990-07-23023 July 1990 Forwards Revised Page 6:4 of Plant Security Plan.Page Withheld Per 10CFR73.21 ML17261B1091990-07-20020 July 1990 Advises That Structural Evaluations of Containment Sys Being Performed in Response to Containment Integrity Insp ML17309A4471990-07-17017 July 1990 Forwards Decommissioning Rept, for Plant,Per 10CFR50.33(k) & 50.75(b) ML17261B0881990-07-13013 July 1990 Provides Update to Util 860616 Ltr Re Implementation of NUREG-0737,Item 6.2,Suppl 1, Emergency Response Capability. ML17261B0921990-07-11011 July 1990 Responds to 900709 Request for Addl Info Re Containment Integrity Insp.Util Will Provide Preliminary Results by 900716 Re Where Groundwater Entering Annular Access Area. Meeting Proposed for Wk of 900723 ML20044B0481990-07-10010 July 1990 Discusses Review of Station Blackout Documentation,Per 10CFR50.63.Licensee Will Complete Enhancements to Station Blackout Documentation Identified in Attachment 1 as Indicated & Other Items Will Be Completed within 2 Yrs ML17309A4461990-07-0909 July 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions ML17261B0931990-07-0909 July 1990 Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Util Completed All Actions Requested in Generic Ltr & Will Retain Documentation Verification for Min of 2 Yrs ML17261B0901990-07-0909 July 1990 Advises That Licensee Will Install Containment Isolation Signal Going to Valve AOV 745 by End of 1992 Refueling Outage,Per Util 900608 Ltr Notifying of Condition Outside Design Basis of Plant Under 10CFR50.72 Criterion ML17250B2151990-06-29029 June 1990 Forwards Application for Amend to License DPR-18, Reformatting Auxiliary Electrical Sys Tech Specs & Action Statements for Offsite & Onsite Power Sources Available for Plant Auxiliaries ML17261B0851990-06-28028 June 1990 Forwards LER 89-016-02 Re 891117 Failure of Safety Injection Block/Unblock Switch Which Could Render Both Trains of Safety Injection Sys Inoperable.Also Reported Per Part 21 ML17250B1991990-06-0808 June 1990 Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-244/89-81.Corrective Actions:Improved Battery Load Profile Developed Incorporating Calculational Improvements Contained in Current Industry Std IEEE 485-1983 ML17250B1951990-06-0505 June 1990 Responds to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning. Util Developed Erosion/Corrosion Program for Single & Two Phase Sys Consistent W/Requirements of NUREG-1344 & NUMARC 870611 Rept ML17250B1851990-06-0101 June 1990 Forwards Application for Amend to License DPR-18,providing Guidance for Action Statements Associated W/Power Distribution Limit Specs ML17261B0691990-06-0101 June 1990 Discusses Testing Frequency for Insp of Incore Neutron Monitoring Sys Thimble Tubes,Per NRC Bulletin 88-009.Thimble Tube Indicating Greatest Wear Recently Repositioned in Effort to Minimize Future Wear ML17250B1811990-05-31031 May 1990 Forwards Addl Info Re Response to Notice of Violation from Insp Rept 50-244/90-04.Info Withheld (Ref 10CFR73.21) ML17250B1801990-05-29029 May 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Util Does Not Need to Develop Enhanced Surveillance Program to Monitor Currently Installed Transmitter Based Upon Limited Installed Quantity ML17250B1841990-05-29029 May 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel (SS) Internal Pre-Load Bolting.... Valves Disassembled & 410 SS Studs Removed & Visually & Liquid Penetrant Examined ML17261B0961990-05-29029 May 1990 Responds to NRC 900427 Ltr Re Violations Noted in Insp Rept 50-244/90-07.Corrective Actions:Worker Records Immediately Corrected Indicating That Worker Received No Significant Exposure for Time While Error Occurred ML17250B1721990-05-18018 May 1990 Forwards Rev 1 to Summary Exam Rept for 1990 Steam Generator Eddy Current Insp. Rept Summarizes Observations & Corrective Actions Resulting from Insps Performed During 1990 Outage ML20042G8931990-05-0808 May 1990 Forwards Revised Emergency Operating Procedures,Including Rev 3 to AP-RHR.2,Rev 1 to ES-0.3 & Rev 11 to ES-1.3 ML17261B0611990-04-26026 April 1990 Advises of Changes to 890201 Commitments Made Under Programmed Enhancement Response to Generic Ltr 88-17.Changes Will Not Reduce Capability to Operate Safely in Reduced Inventory Condition or Scope of Programmed Enhancements ML17261B0591990-04-17017 April 1990 Advises That No Interlocks Required for RHR motor-operated Valves 701 & 720 Based on Present Arrangement.Listed Failures Would Have to Occur in Order for Potential Overpressurization of RHR Sys to Occur ML17261B0461990-04-12012 April 1990 Responds to Issues Discussed During 900323 Telcon Re Inservice Testing Program Status & Relief Request.Current Test Methodology for Seat Leakage Acceptable Based on Application of Direct Measurement Sys ML17262A1431990-04-12012 April 1990 Responds to NRC 900202 Ltr Re Weaknesses Noted in Insp Rept 50-244/89-80.Corrective Actions:Procedure ES-0.3 Modified to Provide Guidance for Rapid Cooldown & Depressurization W/ & W/O Reactor & Vessel Instrumentation Sys ML17250B1451990-04-0606 April 1990 Discusses Impact of SER Issuance for Inservice Insp & Inservice Testing Programs & Advises That Timing Will Not Affect Util Implementation Plans for Programs,Except as Listed ML17250B1441990-04-0505 April 1990 Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-244/90-02.Corrective Actions:Positive Indicator Will Be Installed for All Check Valves to Enhance Visible Positive Position Verification Ability & to Avoid Confusion ML17261B0401990-03-30030 March 1990 Advises That Final Results of Station Blackout Documentation Review Will Be Submitted to NRC on or About 900501 ML17261B0321990-03-28028 March 1990 Forwards Annual Rept of ECCS Model Revs as Applicable to Facility,Per 10CFR50.46.Mods to Model for Small Break LOCA Do Not Affect Calculated Peak Clad Temp ML17261B0331990-03-28028 March 1990 Forwards Info Re Reactor Vessel Issues,Per 900305 Telcon Concerning Change of License Expiration Date ML17261B0231990-03-26026 March 1990 Responds to NRC 890222 Ltr Re Violations Noted in Insp Rept 50-244/89-17.Corrective Actions:Personnel Verified Safety Injection Block/Unblock Switch in Proper Position & Operator Procedure 0-1.1 Changed as Indicated ML17261B0281990-03-23023 March 1990 Forwards Addl Info Re Proposed Tech Spec Amend Concerning Use of Reconstituted Fuel,Per 900315 Telcon.During Fuel Assembly Reconstitution,Failed Fuel Rods Will Be Placed W/ Filler Rods ML17261B0221990-03-22022 March 1990 Provides Revised Test Schedule for motor-operated Valve Diagnostic Test Program,Per IE Bulletin 85-003.NRC Notification of Changes to Valve Operability Program Required by Generic Ltr 89-10,dtd 890828 ML17261B0411990-03-20020 March 1990 Forwards Summary of Onsite Property Damage Coverage Currently in Force at Plant,Per 10CFR50.54(w)(4) ML17261B0151990-03-19019 March 1990 Responds to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Plants (USI A-47). Overfill Protection Provided Through Trip Bistables in Reactor Protection Racks Powered from 120-volt Instrument Buses ML17261B0101990-03-15015 March 1990 Forwards Application for Amend to License DPR-18,allowing Use of Reconstituted Fuel Assemblies ML20012D2831990-03-14014 March 1990 Responds to Issues Discussed During 900307 Telcon W/Util & Eg&G Re Inservice Testing Program Status & Relief Request. Valves 5960A & 5960B Will Be Disassembled to Verify Forward Flow.Relief Requests PR-8 & VR-25 Encl 1990-09-18
[Table view] |
Text
'-~j~gp~~TED DISTURBl.'TIOA DEMONSTRX+)4 SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
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:
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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.
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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
'l
'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.
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~Te Si ze GTV I
'ctuator AOV
'l
'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