ML17321A392

Responds to NRC 841214 Ltr Re Violations Noted in Insp Repts 50-315/84-19 & 50-316/84-21.Corrective Actions:Fire Damper to Cable Vault Supply Fan Repaired.Administrative Changes Implemented

ML17321A392
Person / Time
Site:	Cook
Issue date:	01/11/1985
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
AEP:NRC:0915, AEP:NRC:915, NUDOCS 8501290118
Download: ML17321A392 (6)

Text

INDIANA & MICHIGAN ELECTRIC COMPANY P.O. BOX I6631 COLUMBUS, OHIO 43216 January 11, 1985 AEP:NRC:0915 Donald C. Cook Nuclear Plant Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 INSPECTION REPORT 50-315/84-19 (DRP) -- RESPONSE TO NOTICE (DRP)'0-316/84-21 IE FILE COPY OF VIOLATION Mr. James G. Keppler U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, ILL 60137

Dear Mr. Keppler:

This letter responds to Mr. M. D. Shafer's letter dated December 14, 1984, whioh forwarded the sub)cot Inspeotion Report of the routine safety inspeotion oonduoted by your staff at the Donald C. Cook Nuclear Plant on September 1, 1984 through October 26, 1984. The Notice of Violation attached to Mr. Shafer's letter identified two items as violations of Technical Specification requirements. The following are our responses to these items:

Teohnical Specification 1. 10 states: "A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.

This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter."

Teohnical Specification 3.3. 1. 1 requires reactor trip instrumentation to be operable.. Technioal Specification 4.3.1.1.1 states: "Each reactor trip system instrumentation ohannel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. . . at the frequencies shown in Table 4 3 1 ft Surveillance Test Procedure OHP 4030 STP.030 "Operations Daily and Shift Surveillance Checks" Step 8.5 states: "Mhere redundant instrumentation on a panel is checked, there are maximum deviations between channel limits."

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Mr. James G. Keppler AEP:NRC:0915 Contrary to the above Data/Signoff sheets of OHP 4030 STP.030 do not include acoeptance criteria for the channel oheok of:

Source Range Nuolear Instruments T.S.3.9.2, 3.3.1.1 Power Range Excore Detectors T.S.3.3. 1. 1 Intermediate Range Excore Detectors T.S.3.3.1.1 Reactor Coolant Overpower Delta T T.S.3.3.1.1 Reactor Coolant Overtemperature Delta T T.S.3.3. 1. 1 Reactor Coolant T(AVG) T.S.3.3.2.1 Similarly, Data/Signoff Sheet 6.2 to OHP 4030 STP.031 does not include acceptance criteria for channel checks of:

Hot Shutdown Panel instrumentation T.S.4.3.3.5 Post Aocident Monitoring instrumentation T.S.4.3.3.8 ES 0 SE 0 TE

1. re ie ci T e eu s hee Procedures OHP 4030.STP.030 and 031 have been or will be revised to inolude acceptance or iter ia for performing CHANNEL CHECKS (i.e., a qualitative assessment of ohannel behavior). Some of the'ited instruments (e.g., Source Range Nuclear Instruments) do not lend themselves to a quantitative number for acceptance criteria.

Therefore, for these instruments, the procedures have been revised to require verification that the instrument behavior is proper and operating (i.e., responding to a qualitative change in the monitored process.)

The development of quantitative acceptance criteria in procedure OHP 4030.STP.031, for use between channels in instruments such as the Subcooling Margin Monitor, are in the final stages of development.

2. C r e e io ke he o Applicable procedures are being or have been revised.

3. D te e F C be d Full compliance will be achieved when Unit 1 and 2's OHP 4030.STP.031's are revised, approved, and implemented. This is expected to be completed prior to February 28, 1985.

TEM 2 Technical Specification 3.7. 10 requires fire dampers to be operable at all times.

Technical Specification 3.7.9.3 requires the CO system for the Control Room Cable Vault to be operable since the primary Halon Suppression system was found to be inoperable on April 5, 1983. This CO suppression system is designed to be a "total flooding>> type system, which requires integrity of the proteoted volume.

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Mr. James G. Keppler AEP:NRC:0915 Contrary to the above, the Control Room Cable Vault Ventilation Supply fire damper was found propped open on August 22, 1984 and had been in this condition since the last known maintenance inspection on May 21, 1984.

RESPONSE TO ITEM - 2

1. Crr ie ci d Result hie On August 22, 1984 the fire damper to the Cable Vault Supply Fan was found propped open with a pieoe of conduit. Upon the discovery of the obstructed damper, the CO system was considered inoperable believing that the required C concentration could not be maintained. Therefore, a fire2watch was maintained until the damper, and consequently, the CO system were declared operable.

The obstruction was removed from the fire damper track. The damper was reset, tested and declared operable.

2. C rrecti e Take erN cm a e To prevent recurrence, administrative ohanges have been implemented to ensure fire dampers are procedurally restored to operable and unobstructed status following activities such as testing, maintenance, or actuations which,'disturb a damper's,operational readiness.

30 te e e e We have been in full compliance since August 22, 1984, when the fire damper was declared 'operable.'his document has been prepared following Corporate procedures which inoorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours M. P. lexich ~A i

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Vice President <i cm cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector << Bridgman

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