ML17318A271

Supplements Response to IE Bulletin 79-14 Re Field Insps of Component Cooling Water & Safety Injection Sys.Requests Extension of 120 Days for Field Insp of Inaccessible Portions of safety-related Sys

ML17318A271
Person / Time
Site:	Cook
Issue date:	08/23/1979
From:	Dolan J INDIANA MICHIGAN POWER CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
AEP:NRC:00238A, AEP:NRC:238A, NUDOCS 7909240254
Download: ML17318A271 (5)

Text

INDIANAl MICHIGAN POWER COMPANY P. 0. BOX 18 BOWLING GREEN STATION NEW YORK, N, Y. 10004 August 23, 1979 AEP:NRC:00238A Donald C.Cook Nuclear Plant Unit Nos.

1 and 2

Docket Nos.

50-315 and 50-316 License Nos.

DPR-58 and DPR-74 Hr. James G. Keppler, Regional Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Glen Ellyn, Illinois 60137

Dear Mr.,

Keppler:

This letter informs you of our most recent actions concerning IE Bulletin No. 79-14.

In our response to the Bulletin, submittal No. AEP:NRC:00238, dated August 3, 1979, we stated that should our inspection of the Component Cooling Water (CCW) and Safety

. Injection (SI) systems reveal significant discrepancies between the actual piping configurations and the "as-built" documentation

packets, we would perform field inspections of all systems listed in Attachment 1 to the said submittal.

We have completed the inspection of Cook Plant Unit I CCW and SI systems.

Although our inspection has revealed a close agreement between actual piping geometry and the "as-built" drawings in the documentation packages, it has also revealed several discrepancies which we consider sufficient reason to initiate inspection of the remaining accessible Unit I safety-related piping systems.

We have chosen to correct the non-conformances discovered so far where that is the practical route to follow.

In those cases where hard-ware fixes are not immediately indicated we have performed a preliminary analysis which insures that the operability of the systems under the design basis earthquake loads is not impaired.

Final seismic reanalysis will be performed when circumstances dictate it.

This reanalysis will be done within the 30 day period mentioned in the supplement to the Bulletin dated August 15, 1979 which we received on August 21, 1979.

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Nr. James G. Keppler, Regional Director AEP NRC:00238A The inspection of the Unit 2 CCW and SI systems has begun but has not yet progressed to the point that we can make a meaningful evaluation.

We will keep you updated of our progress and of any significant developments arising as a result of the activities per-formed to comply with the Bulletin.

We also request an extension to the 120 day period for field inspection of the inaccessible portions of safety-related systems until the end of November 1979, a relief of approximately one month beyond the bulletin date.

We base our request on the fact that the number and nature of the non-conformances found so far do not give us reason to doubt the safety of the plant in the unlikely event of a design basis earthquake.

We are making every possible effort to expedite the inspection of the accessible parts of the Unit 1 safety-related systems.

The re-quested relief will allow us to make use of scheduled outages for the inspection and not force us to bring a Unit down on an unplanned

basis, without significant benefit to the safety of the public.

Very truly yours, JED:em ohn E. Dolan Vice President cc:

R.

C. Callen R.

S.

Hunter R.

W. Jurgensen G. Charnoff V. Stello D.

G. Eisenhut D. V. Shaller-Bridgman

INDIANA R MICHIGAN POWER COMPANY P. 0. BOX 18 BO WLI H G 0 R E EH STAT ION HEW YORK, H. Y. 10004 August 23, 1979 AEP:NRC:00238A Donal d C. Cook Nucl ear P 1 ant Unit Nos.

1 and 2

Docket Nos.

50-315 and 50-316 License Nos.

DPR-58 and DPR-74 Mr. James G. Keppler, Regional Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Glen Ellyn, Illinois 60137

Dear Mr. Keppler:

This letter informs you of our most recent actions concerning IE Bulletin No. 79-14.

In our response to the Bulletin, submittal No. AEP:NRC:00238, dated August 3,

1979, we stated that should our inspection of the Component Cooling Mater (CCM) and Safety. Injection (SI) systems reveal significant discrepancies between the actual piping configurations and the "as-built" documentation

packets, we would pe1form field inspections of all systems listed in Attachment 1 to the said submittal.

We have completed the inspection of Cook Plant Unit I CCH and SI systems.

Although our inspection has revealed a close agreement between actual piping geometry and the "as-built" drawings in the documentation packages, it has also revealed several discrepancies which we consider sufficient reason to initiate inspection of the remaining accessible Unit I safety-related piping systems.

We have chosen to correct the non-conformances discovered so far where that is the practical route to follow.

In those cases where hard-ware fixes are not immediately indicated we have performed a preliminary analysis which insures that the operability of the systems under the design basis earthquake loads is not impaired.

Final seismic reanalysis will be performed when circumstances dictate it.

This reanalysis will be done within the 30 day period mentioned in the supplement to the Bulletin dated August 15, 1979 which we received on August 21, 1979.

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