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 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

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/llllCHl&AN~S 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 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

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 OC1189-0022-NL02

ENCLOSURE 1 UNRESOLVED SAFETY ISSUES FOR WHJCH A FINAL TECHNICAL RESOLUTJON HAS BEEN ACHIEVED USl/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-1 Water HaD1Tier SECY.84-119 All C/11/88 Closed per NRC NUREG-09?7, Rev. 1 IR 89-09 dated NUREG-0993, Rev. 1 4/21/89.

NUREG-0737 Item t.A.2.3 SRP revisions A-2/ AsYflllletric Rlowdown NUREG-0609 PWR C/Oct 89 MPA D-10 Loads on Reactor Primary f.L 84-04, GDC-4 Coolant Systems A-3 West.inghouse Steam NUREG-0844 W-PWR NA Generator Tube Integrity SECY 86-97 SECY 88=-?72 GL 85-02 .

(No requirements)

A-4 CE Steam Generator Tube NUREG-0844, SECY 86-97 CE-PWR C/Mar 88 Revised Technical Integrity SECY 88-272 Specifications issued GL 85-02 by the NRC.

!No requirements}

A-5 B&W Steam Generator NURE6-0844, SECY 86-97 8&W-PWP NA Tube Integrity SECY 88-272 GL 85-02 (No Requirements)

E

~-6 Mark I Containment NUREG-0408 Mark I-BWR NA Short-Tenn Program

• C - COMPLETE NC - NO CHANGES NECESSARY NA - NOT APPLICABLE I - INCOMPLETE f - fVALUATING ACTIONS REQUIRED

- ?. -

USl/MPA NUMB Ell TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-7/ Mark I Long-Tenn NUREG-0661 Mark 1-BWR NA D-01 Program NUREG-0661 Suppl. 1 Gl 79-57 A-8 Mark II Containment NUREG-0808 MarJ: I I -BWR NA Pool Dynamfc Loads NUREG-0487, Suppl. 1/2 NUREG-0802 SPP 6.2.l.lC GDC 16 A-9

• Anticipated Transients NUREG-0460, Vol. 4 All I/90 REFOUT Hardware Without Scram .10 CFR 50.62 Installation A~lO/ BWR Feedwater Nozzle NUREG-0619 8WP NA HPA 8-25 Cracking Letter from DG Eisenhut dated 11/13/80 GL 81-11 A-11 Reactor Vessel Material NUREG-0744, Rev. 1 All I Additional Informa-Toughness IO CFR 50.60/ tion will be sub-82-26 mitted.

A-12 Fracture Toughness of NUREG-0577, Rev. l PWP NA Steam Generator and SAP . Revision Reactor Coolant Pump .s.3.4 Supports A-17 Systems Interactions Ltr: - DeYoung to All NC licensees - 917?.

NUREG-1174, NUREG-1229, NUREG/CR-3922, NUREG/CR-4?.61, NUPEG/

CR-4470, Gl 89-18 (No requirements)

A-24/ ~valificat1on of Class NIJREG-0588 Rev. l 1 All C/Nov 85 MPA B-60 iE Safety-Related SRP 3.11

• Equipment 10 CFP 50.49 GL 82-09, Gt R4-24 GL 85-15

.;. 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 A-36/

c-10.

Residual Heat Removal Shutdown Requirements Control of Heavy Loads Near Spent Fuel NUREG-0606 RG 1.113 RG 1.139 SRP 5.4.7 NUREG-0612 SRP. 9.1.5 1

All Ols After 01/79.

A.ll NA C/Nov 83 C-15 GL 81-07 GL 83-42 1 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 0783 0802 1 1 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 NUREG/CR-0054 1 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 Rev. 1 1 BWR NA MPA 8-05 Water Reactors NUREG-0313, Rev. 2 GL 81-03, GL 88-01

.. f I I USl/MPA APPL ICAB IL ITY STATUS/DATE* REMARKS NUMBER TITLE REF. DOCUMENT Containment Emergency NUREG-0510, All NC A-43 .

Sump Perfonnance NUREG-0869, Rev. l NUREG-0897, R.G.1.8?

(Rev. 0), SRP 6.2.2 GL 85-22 No Requirements RG 1.155 All I/90 REFOUT Hardware A-44 Station Blackout Installtion

• NUREG-1032 NUREG-1109 10 CFR 50.63 Shutdown Decay Heat . SECY 88-260 All NC A-45 NUREG.;.1289 Removal Requirements NUREG/CR-5230 SECY 88-260 (No requirements)

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

Operating Plants Gl 87-0?., GL 87-03 NUREG-1217, NUREG- All E 180 day response, A-47 Safety Implication to 9/20/89 letter ~

of Control Systems 1218 GL 89-19 due March.1990.

r Hydrogen Control 10 CFR 50.44 All, except A-48 PWRs with Measures and Effects SECY 89-1?2 of Hydrogen Burns large dry on Safetv Equipment containments RGs 1.154, 1. 99 PWR I/May 90 A-49 Pressurized Thennal

~hock SECY 82-465 SECY P.3-288 SECY 81-687 10 CFR 50.61/

.GL 88-11