ML18054B136

Forwards Status of Implementation of USI for Which Final Technical Resolution Has Been Achieved,Per Generic Ltr 89-21, Status of USI Requirements.

ML18054B136
Person / Time
Site:	Palisades
Issue date:	11/28/1989
From:	JOHNSON B D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR GL-89-21, NUDOCS 8912050309
Download: ML18054B136 (6)

Text

.. consumers Power l'OWERIN&

l'RO&RESS General Offices: 1945 West Parnell Road, Jackson,'

Ml 49201 * (517) 788-0550 November 28, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -RESPONSE TO GENERIC LETTER 89-21 STATUS OF UNRESOLVED ISSUE (USI) REQUIREMENTS This letter provides Consumers Power Company's response to Generic Letter 89-21 for the Palisades Plant. Consumers Power Company has reviewed and reported on, the status of implementation of Unresolved Safety Issues for which a final technical resolution has been achieved and which are applicable to Palisades.

Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector

-Palisades Attachment OC1189-0022-NL02 OC1189-0022-NL02 ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 ENCLOSURE 1 FROM GENERIC LETTER 89-21 AND REMARKS ON UNRESOLVED SAFETY ISSUE RESOLUTION November 28, 1989 4 Pages ENCLOSURE 1 UNRESOLVED SAFETY ISSUES FOR WHJCH A FINAL TECHNICAL RESOLUTJON HAS BEEN ACHIEVED USl/MPA NUMBER TITLE A-1 Water HaD1Tier A-2/ AsYflllletric Rlowdown MPA D-10 Loads on Reactor Primary Coolant Systems A-3 West.inghouse Steam Generator Tube Integrity A-4 CE Steam Generator Tube Integrity A-5 B&W Steam Generator Tube Integrity E Mark I Containment Short-Tenn Program

• C -COMPLETE NC -NO CHANGES NECESSARY NA -NOT APPLICABLE I -INCOMPLETE f -fVALUATING ACTIONS REQUIRED REF. DOCUMENT APPLICABILITY STATUS/DATE*

SECY.84-119 All C/11/88 NUREG-09?7, Rev. 1 NUREG-0993, Rev. 1 NUREG-0737 Item t.A.2.3 SRP revisions NUREG-0609 PWR C/Oct 89 f.L 84-04, GDC-4 NUREG-0844 W-PWR NA SECY 86-97 SECY 88=-?72 GL 85-02 . (No requirements)

NUREG-0844, SECY 86-97 CE-PWR C/Mar 88 SECY 88-272 GL 85-02 !No requirements}

NURE6-0844, SECY 86-97 8&W-PWP NA SECY 88-272 GL 85-02 (No Requirements)

NUREG-0408 Mark I-BWR NA * !' REMARKS Closed per NRC IR 89-09 dated 4/21/89. Revised Technical Specifications issued by the NRC.

USl/MPA NUMB Ell A-7/ D-01 A-8 A-9 TITLE Mark I Long-Tenn Program Mark II Containment Pool Dynamfc Loads

• Anticipated Transients Without Scram BWR Feedwater Nozzle HPA 8-25 Cracking A-11 A-12 A-17 Reactor Vessel Material Toughness Fracture Toughness of Steam Generator and Reactor Coolant Pump Supports Systems Interactions A-24/

of Class MPA B-60 iE Safety-Related

• Equipment

-?. -REF. DOCUMENT NUREG-0661 NUREG-0661 Suppl. 1 Gl 79-57 APPLICABILITY Mark 1-BWR NUREG-0808 MarJ: I I -BWR NUREG-0487, Suppl. 1/2 NUREG-0802 SPP 6.2.l.lC GDC 16 NUREG-0460, Vol. 4 .10 CFR 50.62 All NUREG-0619 8WP Letter from DG Eisenhut dated 11/13/80 GL 81-11 NUREG-0744, Rev. 1 IO CFR 50.60/ 82-26 NUREG-0577, Rev. l SAP .. Revision .s.3.4 Ltr: -DeYoung to licensees

-917?. NUREG-1174, NUREG-1229, NUREG/CR-3922, NUREG/CR-4?.61, NUPEG/ CR-4470, Gl 89-18 (No requirements)

NIJREG-0588 1 Rev. l SRP 3.11 10 CFP 50.49 GL 82-09, Gt R4-24 GL 85-15 All PWP All All STATUS/DATE*

NA NA I/90 REFOUT NA I NA NC C/Nov 85 REMARKS Hardware Installation . *' ' ' Additional tion will be mitted.

. . . .;.. 3 -.; t USl/MPA , I NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE*

REMARKS A-26/ Reactor Vessel Pressure DflP. Letters to PWR I/ Submit Additional MPA B-04 Transient Protection Licensees 8/76 Analysis by 5/1/90 NUREG-0224 per CPCo letter NUREG-0371 dated 7/28/89. SRP 5.?. GL 88-11 A-31 Residual Heat Removal NUREG-0606 All Ols After NA -Shutdown Requirements RG 1.113 1 01/79. RG 1.139 SRP 5.4.7 A-36/ Control of Heavy Loads NUREG-0612 A.ll C/Nov 83 c-10. Near Spent Fuel SRP. 9.1.5 C-15 GL 81-07 1 GL 83-42 1 GL. 85-11 Letter from DG Eisenhut dated 12/22/80 A-39 Determination of SRV NUREG-080?.

BWR NA Pool Dynamic Loads NUREGs-0763 1 0783 1 0802 and Pressure Transients NUREG-0661 SRP 6. 2. 1.1. C A-40 Seismic Design SRP Revisions, NUREG/ All I/ Resolution in " Criteria CR-4776 1 NUREG/CR-0054 1 conjunction wi . NUREG/CR-3480, NUREG/ SQUG activities.

CR-1582, NUREG/CR-1161, . ) NUREG-1233 1 NUREG-4776 NUREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509 A-42/ Pipe Cracks in Boiling NUREG-0313 1 Rev. 1 BWR NA MPA 8-05 Water Reactors NUREG-0313, Rev. 2 GL 81-03, GL 88-01

,. .. f I I ' USl/MPA NUMBER TITLE REF. DOCUMENT APPL I CAB IL ITY STATUS/DATE*

REMARKS A-43 . Containment Emergency NUREG-0510, All NC Sump Perfonnance NUREG-0869, Rev. l NUREG-0897, R.G.1.8? (Rev. 0), SRP 6.2.2 GL 85-22 No Requirements A-44 Station Blackout RG 1.155 All I/90 REFOUT Hardware NUREG-1032 Installtion

• NUREG-1109 10 CFR 50.63 A-45 Shutdown Decay Heat . SECY 88-260 All NC Removal Requirements NUREG.;.1289 NUREG/CR-5230 SECY 88-260 (No requirements)

A;,,46 Seismic Qualification NUREG-1030 All I/90 REFOUT of Equipment in NUREG-1211/

Operating Plants Gl 87-0?., GL 87-03 180 day response, A-47 Safety Implication NUREG-1217, NUREG-All E of Control Systems 1218 to 9/20/89 letter GL 89-19 due March.1990.

r A-48 Hydrogen Control 10 CFR 50.44 All, except Measures and Effects SECY 89-1?2 PWRs with of Hydrogen Burns large dry on Safetv Equipment containments A-49 Pressurized Thennal RGs 1.154, 1. 99 PWR I/May 90 SECY 82-465 SECY P.3-288 SECY 81-687 10 CFR 50.61/ .GL 88-11