ML17328A214

Responds to Generic Ltr 89-21 Re Request for Addl Info Concerning Status of Implementation of USI Requirements. Plant Walkdown Per Guidelines of Generic Implementation Procedures Planned During 1992 Refueling Outages

ML17328A214
Person / Time
Site:	Cook
Issue date:	11/29/1989
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-OR AEP:NRC:1108, GL-89-21, NUDOCS 8912070397
Download: ML17328A214 (10)

Text

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Indiana Michigan Power Company P.O. Box 16631 Columbus. OH 43216 Z

INDIANA MICHIGiAN POWER AEP: NRC: 1108 Donald C. Cook Nuclear Plants Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NRC GENERIC LETTER 89-21: REQUEST FOR INFORMATION CONCERNING STATUS OF IMPLEMENTATION OF UNRESOLVED SAFETY ISSUE (USI) REQUIREMENTS U. S, Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley November 29, 1989

Dear Dr. Murley:

This letter and its attachment are in response to NRC Generic Letter No. 89-21 entitled "Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI)

Requirements," dated October 19, 1989. The status of unresolved safety issues for Cook Nuclear Plant is given in the attached table. Several issues require discussion, which is given below.

1) USI A-17: S stem Interactions Generic Letter (GL) 89-18 dated September 6, 1989 was sent to all power reactor licensees and constitutes the resolution of USI A-17. The GL did not require any response/action on the part of the licensees. However, GL 89-18 is currently under review within AEPSC. It is acknowledged that the Individual Plant Examinations (IPE) will include some consideration of system interaction during plant walkdowns. Our submittal AEP:NRC:1082 dated October 24, 1989, "Individual Plant Examination Program Plan, Response to GL No. 88-20, Supplement No. 1," documents the IPE program for the Donald C. Cook Nuclear Plant. During the proposed walkdown in support of the IPE program, issues such as flooding from the internal sources will be considered.

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T. E. Hurley AEP: NRC: 1108

2) USI A-26: Reactor Vessel Pressure Transient Protection Generic Letter 88-11 dated July 12, 1988 was sent to all power reactor licensees for review and response. We responded to the GL in our submittal AEP:NRC:0894K dated December 5, 1988. Plant-specific evaluation and the associated technical specification change request for Cook Nuclear Plant Unit 2 were submitted to the NRC for approval in our submittal AEP:NRC:0894L dated October 25, 1989, For Unit 1, the latest surveillance capsule is currently under evaluation. We anticipate submitting the Unit 1 capsule analysis report by June 30, 1990 and the associated technical specification change request by October 31, 1990.

3) USI A-36 Control of Hea Loads Near S ent Fuel Generic Letter 81-07 and NUREG-0612 were issued to all power reactor licensees for. implementation of methods for controlling heavy loads at nuclear power plants. All

'utilities were requested to evaluate their plants against the guidance of NUREG-0612 and to provide their responses in two phases. Our submittals AEP:NRC:0514 and 0514 Series A through W constitute our two-phase response and document the handling procedures for heavy loads at the Cook Nuclear Plant.

The NRC Safety Evaluation Report (SER) for Phase 1 was issued on September 20, 1983, and by issuing GL 85-11, "Completion of Phase II of Control of Heavy Loads at Nuclear Power Plants

- NUREG-0612," dated June 28, 1985, the NRC concluded that a

. detailed review of Phase II was not required and Phase II was considered completed. Further, while not a requirement, the NRC encouraged the implementation of any actions identified in Phase II, as appropriate.

4) USI A-40 Seismic Desi n Criteria USI A-40, involved evaluation of NUREG-CR-3805, CR-5347, and CR-3509, which concluded that further action on the part of the utilities was not required. However, further evaluations of the seismic structural stability of certain items such as above ground tanks are required. As a result, evaluation of these items has been included in the USI A-46 program.

American Electric Power is a member of the Seismic Qualification Utility Group (SQUG), which was formed to systematically implement USI A-46 requirements. Therefore, USI A-40 is considered closed for Cook Nuclear Plant.

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i Dr. T. E. Murley AEP: NRC: 1108

5) USI A-46: Seismic ualification of E ui ment in 0 eratin Plants The NRC issued GL 87-02 dated February 19, 1987, "Seismic Qualification of Electrical and Mechanical Equipment in Operating Plants," to all power plant licensees. The Seismic Qualification Utility Group (SQUG) is developing the criteria and procedures to implement the requirements of GL 87-02.

The SQUG methods and approach have been approved by the NRC.

Our submittal AEP:NRC;1040, dated October 1, 1988, documents the seismic qualification reevaluation program as it is applicable to Cook Nuclear Plant.

It is expected that the final Safety Evaluation Reports for the generic implementation procedures (GIPs) and relay evaluation and screening procedures will be issued by the NRC by April-May 1990, Assuming all other commitments between SQUG and the NRC will be on schedule, we are planning to perform the plant walkdown under the guidelines of the GIP during the 1992 refueling outages for both units.

This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Sincerely, M. P. A xich Vice President MPA/eh Attachment cc: D. H. Williams, Jr.

A. A. Blind - Bridgman R. C. Callen G. Charnoff NFEM Section Chief A. B. Davis - Region III NRC Resident Inspector - Bridgman

ENCLOSURE 1 UNRESOLVED SAFFTY ISSUES FOR WHICH A FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED USI/MPA RlNBER TITLE REF. DOCUMENT APPL I CAB IL ITY STATUS DATE* RERRRKS A-1 Water Hammer SECY 84-119 A11 NA Based on enclosure 2 to GL 89-21 NUREG-09?7, Rev. 1 AEP:NRC:0398 and NUREG-0993, Rev. I 0678 Series of NUREG-0737 Item letters I.A.2.3 SRP revisions C

A-2/ Asymnetri c 81owdown NUREG-0609 AEP:NRC:0137D NRC SER dated Nov. 22, 1985 MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 Dated: Sept. 10, Amendment No. 76 to Operating Coo1ant Systems 1984 License No. DPR-74.

A-3 Westinghouse Steam NUREG-0844 W-PWR C Cook Unit 2 steam generators Generator Tube Integrity SECY 86-97 AEP:NRC:0936 were replaced; for Unit 1 additional SECY 88-272 dt. June 21, 1985 information is being provided to NRC GL 85-02 (No requirements) under IE Bulletin 88-02 A-4 CE Steam Generator Tube NUREG-0844, SECY 86-97 CE-PWR -NA- . ~

None Integrity SECY 88-272 GL 85-02 (No requirements)

A-5 BN Steam Generator NUREG-0844, SECY 86-97 88W-PWR -NA- None Tube Integrity SFCY 88-272 GL 85-02 (No Requirements)

E i-6 Mark I Containment NUREG-0408 Nark I-BWR -NA- None Short-Term Program

• C - COMPLETE NC - NO CHANGES NECESSARY NA - NOT APPLICABLE I- INCOMPLETE E - EVALUATING ACTIONS REQUIRED

US I/MPA RURBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* RERARKS A-7/ Mark I Long-Term NUREG-0661 Mark I-BWR None D-ol Program NUREG-0661 . uppl. 1 GL 79-57 A-8 Hark II Containment NUREG-0808 Hark I I-BMR -NA- None Pool Dynamic Loads NUREG-0487K Suppl. 1/2 NUREG-0802 SPP 6.2.J. 1C GDC 16 A-9 Anticipated Transients NUREG-0460, Vol. 4 All I lRIithout Scram 10 CFR 50.62 AEP:NRC:0838 Waiting for NRC reviev and SER Series of letters on several items A-10/ BMR Feedwater Nozzle NUREG-0619 BNR -NA- None HPA B-25 Cracking Letter from DG Eisenhut dated 11/13/80 GL 81-11 A-11 Reactor Vessel Materia 1 NUREG-0744, Rev. 1 All -NC-Touohness 10 CFR 50.60/

82-26 A-12 Fracture Toughness of NUREG-0577, Rev. 1 PHP -NC-Steam Generator and SRP Revis>on Reactor Coolant Pump 5.3.4 Supports A-17 Systems Interactions Ltr: DeYoung to A>1 See note in cover letter, litem l licensees - 9/7P NUREG-1174, NUREG-1229, NUREI'/CR-3922, HUREG/CR-4261, NUPEG/

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

Our letters:

E A-24/ IEE ~ -> 'ication of Class NUREG-0588, Rev. 1 Al 1 HPA B-< ..ty-Related SRP 3.11 AEP:NRC:0356 Series cquspment 10 CFR 50.49 AEP:NRC:0578 Series GL 8.-09, GL 84-24 AEP:NRC:0775 Series GL 85-15

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US I/MPA RINRER TITLE REF. DOCUMENT APPL I CAB IL I TY STATUS/DATE~ RBNRKS A-26/ Reactor Vessel Pressure DOP. Letters to PKR I See cover letter, Item 2 MPA 8-04 Transient Protection Licensees 8/76 AEP:NRC:0894K NUREG-0224 dt. Dec. 5, 1988 NUREG-0371 AEP:NRC:0894L SRP 5.2 GL 88-11 dt. Oct. 25, 1989 A-31 Pesidual Heat Removal NUREG-0606 All OLs After Shutdown Requirements RG 1.113, Ol/79. -NA-RG 1.139 SRP 5.4.7 C

A-36/ Control of Heavy Loads NUREG-Q612 All AEP:NRC:0514 See cover letter, Item 3 C-10, Near Spent Fuel SRP 9.1.5 Series of letters C-15 GL 81-07, GL 83-42, NRC SER (Phase I)

GL 85-11 dt. Sept. 20, 1983 Letter from DG Eisenhut dated 12/22/80 A-39 Determination o< SRV NUREG-0802 BHR -NA- None Pool Dynamic Loads NUREGs-0763,0783,0802 and Pressure Transients NUREG-066]

SPP 6.2.1.1.C A-40 Seismic Design SRP Revisions, NUREG/ All -NC- See cover letter, Item 4 Criteria CR-4776, NUREG/CR-0054, NUREG/CR-3480, NUREG/

CR-1582, NUREG/CR-1161, NUREG-1233, NUREG-4776 NUREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509

-NA- None A-42/ Pipe Cracks in Boiling NUREG-0313, Rev. 1 BiCR MPA B-05 inter Reactors NUREG-0313, Rev. 2 GL 81-03, GL 88-01

US I/HPA RIRIBER TITLE REF. nnCUHENT APPLICABILITY STATUS/DATE* RERARKS A-43 Coniainment Emergency NUREG-0510, No NRC submittal is required Sump Performance NUREG-0869, Rev. I NUREG-0897, R.G.I.B?

tRev. 0), SRP 6.2.2 GL 85-22 No Requirements A-44 Station Blackout RG 1.155 All C, our letter Awaiting NRC review NUREG-1032 AEP:NRC:05370 NURE0-1109 dt. April 14, 1989 IO CFR 50.63 A-45 Shutdown Decay Heat SECY 88-260 Al 1 C, AEP:NRC:1082 This has been incorporated Removal Requirements NUREG-1289 dt. Oct. 24, 1989 into . IPE program under NUREG/CR-5230 GL 88-20 .

SECY 88-260 (No requirements)

A-46 Seismic qualification NUREG-In3C All AEP:NRC:1040 See cover letter K of Equipment in NUREG-1211/ I Operating Plants GL 87-02, GL 8>-03 A-47 Safety Implication NUREG-I?17, NUPEG- AI 1 Under review and evaluation o~ Control Svstems 1218 by AEPSC GL 89-19 I Remaining open items will be A-48 Hydrogen Control 10 CFP 50.44 All, except addressed in the IPE program measures and Effects SECY 89-1?2 PXRs with AEP:NRC:0476 and o< Hydrogen Burns large dry AEP:NRC:0500 Series by AEPSC on Safetv Equipment containments Pressurized Thermal RGs 1.154, 1.99 PNR C, AEP:NRC:0561A NRC SER dated March 27, 1987 Shock SFCY 82-465 dt. January 22, 1986 SECY 83-288 SECY 81-687 10 CFR 50.61/

GL 88-11