ML17331A814

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Suppls 810814 Request for License Amend Granting Relief from Tech Spec Requirements.Rope Tie Downs Installed to Satisfy Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys, Pending Permanent Mod
ML17331A814
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 08/17/1981
From: Jurgensen R
AMERICAN ELECTRIC POWER SERVICE CORP.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML17331A811 List:
References
GL-81-14, NUDOCS 8109290477
Download: ML17331A814 (2)


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AMKR1CAN:-L=-C7RJC POWER Service Co'ryoration 2 Broadway, Vno York,X Y. l0004.

, (212) 440-9000 August 17, 1981 Donald C. Cook Nuclear Plant Unit Nos.

1 arid 2 Docket Nos. 50-315 and 50-316 License Nos.

DPR-58 and DPR-74 REQUEST FOR RELIEF FROM TECHNICAL SPECIFICATION NO'. 3.0.3 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Cormission Washington, D. C.

20555

Dear Mr. Denton:

This letter supplements our letter of August 14, 1981 concerning our r equest for a license amendment granting relief from the requirements of Technical Specification No; 3.0.3.

As reported to you earlier, during the investigation conducted to satisfy the requirements of Generic Letter 81-14 entitled "Seismic gualification of Auxiliary Feedtiater Systems,"

the installation=of certain safety-related 4 kV switchgear bus cabinets and 600V motor control centers was found to be inadequate

'to prevent this safety-related equipment from overturning during the Design Basis Earthquake (DBE) event.

Overturning of this equipment might conceivably result in damage which may prevent fold ig f

Our continued investigation of the matter has now shown that certain of the safety-related 600V switchgear bus cabinets are also inadequately anchored to prevent overturning during the DBE.

This investigation is beyond the scope of NRC Generic Letter 81-14 covering safety-relat.d equipment not part of the Auxiliary Feedwater System.

To ensure that this equipment will withstand the overturning moment due to the

OBE, we are installing the temporary modifications consisting of rope tiedowns similar in purpose to those done to the 4 kV switchgear bus cabinets.

At the same

time, we have designed, and are expeditiously proceeding to implement, a

permanent modification.

':le believe that this oermanent modification vari ll be completed within the time period specified in cur letter of August 14, 1981.

8109290477 810924 PDR ADOCK 05000315 P

PDR

Mr. H. R. Denton, Director August 17, 1981 The following is a list of all safety-related equipment requiring modification:

A) 600Y Motor Control Centers - Unit 2 only i)

MCC AM - A ii)

MCC - 2AM-D B) 4 kY Switchgear Buses/Cabinets i)

Unit 1 - TllA, TllB, TllC, T11D ii) Unit 2 - T21A, T21B, T21C, T21D C) 600V Switchgear Buses/Cabinets i)

Unit 1 - 11A, 11B,

11C, 11D ii) Unit 2 - 21A, 21B, 21C, 21D The plant equipment served by the 4 kV and 600V switchgear buses is shown on FSAR Figure 8-1.

Our letter of December 20, 1979 (AEP:NRC:00300A) contains diagram numbers 1-1200A-19, 1-1200G-32, 2-1200A-4 and 2-1200G-20 which also show which equipment is served by each bus or MCC.

We have agreed with your Staff to decrease reactor power until such time at which we either complete the temporary bracing of one train of the 600V switchgear equipment or until we reach 6GX reactor power, whichever occurs first.

Should we reach 60% reactor power first, we will hold at that power level until one train of equipment has been temporarily braced, but in no case for more than eight hours without further approval from your Staff.

Your Staff has further agreed to allow the Units to return to full reactor power as soon as one train of equipment has been braced in each

.unit.

In addition, we have agreed to brace the second train not later than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the completion of the temporary bracing of the first train of equipment.

Very truly yours, RWJ:clb W. Jurg en Assistan ce P esident Nuclear ginee ing Division

-cc.

John E. Dolan, R. S. Hunter G. P.

Fi eld H. L. Alexander D. V. Shaller - Bridgman H. L. Sobel/J. I. Castresana/J.

G. Del Percio/G.

M. Garner Resident Inspector at Cook Plant - Bridgman AEP:NRC:0486A ZC-N-6015.1