PY-CEI-NRR-1193, Responds to Generic Ltr 90-04 Re Implementation Status of Generic Safety Issues

Responds to Generic Ltr 90-04 Re Implementation Status of Generic Safety Issues

ML20055D392
Person / Time
Site:	Perry
Issue date:	06/29/1990
From:	Lyster M CENTERIOR ENERGY
To:	NRC
References
TASK-***, TASK-OR GL-90-04, GL-90-4, PY-CEI-NRR-1193, NUDOCS 9007060263
Download: ML20055D392 (6)

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6200 Dok1ree Boulevoro Mail Acaress I Independence Cil PO Box 94661 )

216 4473100 Clevelond,0H 441004661 L

June 29, 1990 PY-CEI/NRR-1193 L  :

F U.S. Nuclear Pegulatory Commission Document Control Desk

- Washington, D.C. 20555.

Perry Nuclear Power Plant (PNPP)

Docket No. 50-440 Generic Safety Issue Implementation Status Generic Letter 90-04 Gentlemen l The subject Generic Letter requests PNPP implementation status of Generic Safety Issues according to format and content guidelines provided. This l'

letter's attachment shows that status with supporting references.

We conclude that no new commitments are required. Please feel free to call if you have further questions.

Sincere y, .,

s! +

Michael D. Lyster Vice President, Nuclear - Perry l-MDL: nj c-'

Attachment ec: NRC Region III T. Colburn l P. Hiland

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9007060263 900629 40 DR ADOCK 0500 i

O A1 ('dperating Companies.

eveiana tiectnc murninoring Toledo Edison '>

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a Perry Nuclear Power Plant tatit 1 FT-<EI/IES- -*

Docket No. 50-C40 Atta w The Cleveland Moctric Illuminating Co. Page 1 of 5- .

G8243 TIC SAFETT ISSUE IPEUPENDtTICK ,

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GSI/(N A No.) TITIE APPLICABILITY ST3trt3S CDr8ENFS/ REFERENCES 40 (9065) Safety Concerns Associated with All Bugts (sic *) N/A GL 86-01 states N/A to Pterk III's.

Pipe Brooks in the met Scram ?ysten 41 (8058) seat Scram Discharge volume Systems All BIEts C !stter Devidson to Schwencer, 10/25/82 43 (B107) Reliability of Air Systems All Plants C FT-CEI/IEEN)971b 2/22/89 FT-GI/lWWl-1080b 20/23/89 51 (L913) Improving the soliability of All Plants I-(1) FT-GI;. Jut-1121b 1/26/90 W ie Service unter Systems 67.3.3 (A017) Improved Accident Monitoring All Plants I, E-( 2 ) tatter Youngblood to Edelman, 12/11/84 i

PT-CEI/IES-0179b 2/6/95 PT-CEI/IWWHP9694 3/3/89

!atter Colburn to Esplan, 7/14/89 Letter Miraglia to Westos,1/29/90 75** (9076) Item 1.1 - Post-Trip Review All Plants C FT-GI/1551-0100L 4/6/94 (Prograar Description and FT-CEI/Igut-03094 8/28/85 Procedtare) FT 6 3544 9/23/85 75 (8085) Item 1.2 - Post-Trip Deview - All Plants C FT-GI/155t-01004 4/6/84 Data and Information capability FT-GI/14st-0397L,11/15/85 75 (8077) Item 2.1 - Equipment Classification All Plants C FT-GI/IWWt-01004 4/6/84 and vendor Interface (Boector Trip FT-GI/IES-43094 8/28/85 System Congenents) l l (1) Implement water treatment - 8/90, performance testing / inspection of boet on " , e 0/90, resolve SSFI findings - 6/91, final confirmation of performece test / inspection schednales - 12/93.

(2) (t35AR Appendix 15 License comunitsamt too. 7) Define a schedale for neutran monitoring system asdification by 7/90, subject to ERWIDG/Inc resolution of licensing basis. (License htment Iso.16) Pesesure post-accident sample line loss pending inc direction.

As identified in Generic Letter 90-04.

Perry maclear Power Plant tktit 1 PT-CEIMWWD-

• Docket sio. 50-440 Atta W The Cleveland Electric Illumnating Co. Page 2 of 5 o awmTC SAFETT ISSUE IEW12MirtkTIGE .

GSI/(PFA ND.) TITIE APPLICABII.ITY ST3STIS G5WENTSMIEPERIEWGK 75 (8086) Item 2.2.1 - Equipment Classification All P1 mets C PT-CEI/lWEE-01SO4 4/6/84 for Safety-Related Compoesnts 75 (IA03) Item 2.2.2 - Tendor Interface for All Plants E PT-CEIAEWi-01004 4/6/84 Safety-melated Components GL 90-03 Under Revice 75 (9078) Items 3.1.1 s 3.1.2 - Post-+tmintentanew All Plants C PT-CEIAest-01004 4/6/98 Testing (Reactor Trip System WM) 75 (9079) Item 3.1.3 - Post-Nmintenance Testing- All Plants C PT-CEI/3rst-4775b 2/23/98 Onanges to Test moquirements (Reactor Trip System couponents) 75 (8087) Items 3.2.1 s 3.2.2 - Post-Maintenanaco All Plants C PT-CEI/IWet-01004 4/6/84 Testing (All Other Safety-melated Components)

, 75 (Boe8) Item 3.2.3 - Post-Maintenance Testing- All Plants C PT-CEIAula-0775b 2/23/98 Ganges to Test moqutirements (All Other safety-melated Components) 75 (5080) Item 4.1 - meector Trip System All Plants (sic) M/A All Ptet's per GL 83-28 Reliability (vendor-melated Modifications) 75 (8031) Items 4.2.1 s 4.2.2 - meector Trip All Fests N/A System me11 ability - Penintenance and Testing (Preventative Maintenance and Surveillance Program for moector Trip Brookerst 75 (s082) Item 4.3 - noector Trip System All w and aser tyA i

Reliability - Design fbdifications Plants (Automatic Actistion of Shunt Trip Attactment for IAes* E , __ and BsAr Plants) 75 (8090) Item 4.3 - meector Trip System All w and asAr w/A me11 ability - Tech Spec diseges Plap*.s (Automatic Accustion of Shurt Trip Attachuset for inestinghouse and Batt Plants) i l

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Perry 9meloor Power Plant trait 1 PE-GIMER- 4 Dodet 33. 50-440 Jtttadmuset 7he Cleveland Electr',c Illuminating Co. Page 3 of 9 .

GDERIC SAFETT IS$tFE IPEP{g gyJgyIG[ ,

GSI/(MPA 150.) TIT 12 APPLI N LITY STJtTt!S CtNW4NFS/IEFE5WpCES 75 (8091) Item 4.4 - poector Trip system All Bser Plants IVA me11 ability (Improvements in femintenance and Test Procedures for sser Plants) 75 (8092) Item 4.5.1 - moector Trip system All Fleets C FT 6 100L, 4/6/94 meliability-Dinese Trip Features (system Functional Test 2ng) 75 (8093) Items 4.5.2 s 4.5.3 - meector Trip All Plants C FT-GI/15tn-3100L, 4/6/f 4 system meliability - Test Alternati w s (3) and Intervals (System Ftunctional Testing) 86 (8084) long Range Flan for Dealing with All stets C PuPP SER (stWEG 0857) S 2.4, SSER 5/5.2.5.2, Stress Carrosien Crock 2ng in SSER 7/5.2.5.2 Beatt Piping PT-CEI/155t-09944 7/29/88 FT-GI/15m-1027L, 6/15/99 FT-GI/15 tit-1944b 7/31/89 93 (8098) Steen Sinding of Auxiliary Feeduster All PIERS N/A Pumpe 4

99 (L817) RCS/RItt Suction Line valve All Posts N/A Interlock on Poets 124 Anaxiliary Foodwater Sy1 stem ABIO-1&2, mancho IVA Beliability Seco, Prairie Island 1s2, Crystal River-1 Ft. Calhoen A-13 (8017) Sud ber operability Assurance - All Plants C PT- G IAWWi-6449L, 4/15/96 Hydraulic Sudbers Techstical Specifications 3/4.7.4 1

(3) IEEDC 30844, "BIEt Ouner's Grg hosponse to Geooric Estter 83-28, Item 4.5.3, January 1985.

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Ferry sanclear Power Plant trait 1 FT-GI/15m- i~

Docket Wo. 50-440 Jtt* ==*===t

• S o Cleveland Electric Ill e anting Co. Page 4 of 5 ,

conee'C SAFETT ISSUE I!W'tJPE3FEREIst .

GSI/ W A No.) TITTE AFFLICtBILTFT STRTUS N/REFEBENCES

A-13 (8022) me operability Jhssurance - All Plants C FT4 xr/imm-0449L 4/15/96 Mechaniemi 9mdibers Todutical Specifications 3/4.7.4 A-16 (D012) Steen Effects on wet Core oyster Crook R/A Spray Distribution & ISEP-1 A-35 (3023) Adequecy of offsite Feuer All Flants Intter Davidu n to Schoencer, 8/26/92 systems USAR 3.3.1.1.2.9 responds to Branch Tod Positica FSB-1 SSER 2/S.2.4 5-10 Behavior of DEt Mark III All EBE Mark III C (4)

Containments Flaets j B-36 Develop Design, Testing and All Plants with C (5)

Maintestance Criteria for Atmosphere oL M 11 cations Cleanup System Air Filtration and After 4/1/90 Adsorption tknits for magineered Safety Features Systems (Regulatory l Guide 1.52) and for storumi l Ventilation Systems (megulatory Guide 1.140)

! IMi3 (9045) Isolation of Ice Pressure Systems All Plants (sict Er/A Connected to the Beector Coolant System Pressure Soundary i

I (4) Jgspendia R to SSER S provides the references supportinT the MIS Staff conclusicus in SSER 4/6.2 that the 66 Busyhrey contai===et system desi1pt concerns beve been addressed and resolved for FMFF. FNIPP sumApittals material to that resolutice include letters dated Septeudper 9,1982 j (D.R. Davidson to A. Schuomrer; FY422/IEEb-007L Jemanary 26,1983 (M.R. Edelman to B.J. Yoemsgblood); FT-GI/IEE-OSSL Jesumery 5, FT-GI/teist-0123L July 11, and FT-GI/15m-4151L 1Bovendsor 1,1964 (M.R. Edelsen to S.J. Youngblood); FT-GI/imm-0235L sesy 16 FT-GI/15tp-0281L Jemte 24, FT-GI/1EE-0336L September 13, FT-GI/IEst-4351L September 23, FT-GI/15m-8363L SeptemAper 24, FT-GI/ Ism-4371L i

Octoty,c 8, FT-GI/WW-4399L Bovember 12, FY6392L Bovember 11,1985 (M.R. Edelsman to 3.J. Youungblood).

(S) The PUFF licensing basis for sidsject hogulatory Omido compliance ses established in the original FSAR dated 9/12/90 in Table 1.0-1. Se

, apptopriate revision uns deterudmod by reforeseeing the sec mogulatory Boquirement Devies httee (ERAC) categorizatica. Segulatory Guide 1.52 was Category 2 - evaluated for beckfitting mood sund mogulatory Guide 1.140 uns Catagory 1 - forumed fit enly. SER 6.5.1.4 accepts as 1.52 -

movision J conforumece, and SER 9.4.1 & 9.4.3 accept 3G 1.140 - Devision 6 confotwunce.

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• I PY-CEI/NRR- )

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i GL 90-04 Guidance For Completing States Column l J

(1) Provide a separate entry for each licensed reactor unit. If the l

information is identical for multiple units, so state.

(2) If a GSI is not applicable to a unit (s), enter "NA".

(3) If a GSI is applicable but no changes were necessary to implement the ,

resolution, enter "NC". If the GSI implementation was completed prior to issuance of the operating license, enter "NC", .s no post-licensing '

changes were necessary.

(4) If a GSI is applicable, submittal of inform tfon and/or changes were necessary and such submittals were made or changes are complete, enter l- "C". Aleo identify the licensee's document (s) to the NRC which certified completion, and the document date(s).

(5) If a GSI is applicable and changes are necessary but such changes are not  ;

yet fully implemented, enter "I" and the projected month and year of completion. Provide a brief explanation of the outstanding work in the

" Comments" column.

(6) If implementition guidance for a resolved GSI was issued recently and the

'lleensee is still evaluating the appropriate response, enter "E" and the projected response date.

(7) The "Craments" column may be used to explain any entry in the " Status" column.

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