ML17325B049

Submits Plan of Action for Resolving Concerns Associated w/Copes-Vulcan Valves Installed at Plant.Description of Actions Taken Also Provided

ML17325B049
Person / Time
Site:	Cook
Issue date:	12/09/1988
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Davis A NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17325B050	List: ML17325B049 ML17325B051
References
AEP:NRC:1084, NUDOCS 8812130032
Download: ML17325B049 (7)

Text

REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8812130032 DOC.DATE: 88/12/09 NOTARIZED- NO DOCKET lI Donald C. Cook Nuclear Power Plant, Unit 1, Indiana 6 05000315 ~

i'ACIL:50-315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana 6 05000316 AUTH. NAME AUTHOR AFFILIATXON ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R DAVIS,A.B. Document Control Branch (Document Control Desk)

I"

SUBJECT:

Provides plan of action for resolving concerns associated w/

Copes-Vulcan valves installed at plant. D DISTRIBUTION CODE: 'AOOID COPIES RECEIVED:LTR ( ENCL ( SIZE:

TXTLE: OR Submittal: General Distribution NOTES:

RECIPXENT COPIES RECIPIENT COPIES h XD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 0 PD3-1 PD 2 2 D SCOTT,W 1 1 D

INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 8

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.EG. F 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 h

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'IO ALL "RIDS" RIKXPIENZS: 'S PLEASE HELP US K) REIXKE MSTE! CGIlZACZ 'QiE DOCUMENT CONTROL DESK ROCM P1-37 (EXT. 20079) TO XZiQkIINATE KKR NAME HNH DISTEKBUTIGN LISTS POR DOHIMEPZS Y0U DGNiT NEEDf TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 16

~ Indiana Michigan Power Company P.O. Box 1663$

Columbus, OH 43216 R

AEP:NRC:1084.

Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 SCHEDULE AND PLAN OF ACTION FOR ADDRESSING COPES-VULCAN VALVE CONCERNS U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn. A. B. Davis December 9, l988

Dear Mr. Davis:

As requested by your staff, this letter provides our plan of action for resolving concerns associated with Copes-Vulcan valves installed at the Donald C. Cook Nuclear Plant. The problem involves inaccurate or missing design input information, specifically, the weight and location of the center of gravity of the valve, for valves supplied by the Copes-Vulcan Company.

Also included in this letter is a description of the actions that we have already taken.

Com leted Actions The following describes actions that have been completed in evaluating the Copes-Vulcan valve concerns:

1. We have identified air-operated Copes-Vulcan valves installed in safety-related systems at the Cook Nuclear Plant. Of the identified valves, preliminary estimates indicate that a total of sixty-six valves at the Cook Nuclear Plant fit the category of being 3/4-inch, l-inch, or 2-inch valves with a pressure rating of 600 psi or 1500 psi.

2. We have contacted Mr. Tim Kunkle, the engineering manager of Copes-Vulcan, regarding the inaccurate design information.

During our discussion with Mr. Kunkle, we were given the valve weights and centers of gravity for the 1-inch/600 psi, 1-inch/1500 psi, and 3/4-inch/1500 psi (nominal diameter/ANSI pressure rating) valves.

SSi2130032 SS1209 PDR ADOCK 05000315,.- '

P PDC

t Mr. A. B. Davis AEP:NRC:1084

3. We reviewed photographs of valves an'd determined that some of the valves have a U-bolt support at the interface between the valve body and the actuator that may compensate for or reduce the effect of the higher center of gravity.

4. We have requested verification of weights and centers of gravity for Copes-Vulcan valves of sizes and pressure classes other than those listed in Item 2, which are also installed in safety-related systems.

On oin or Planned Actions The following describes our plan of action associated with the Copes-Vulcan valve concerns.

1. The licensing design basis (FSAR, response to IE Bulletin 79-14, etc.) for small-bore piping will be reviewed.

2. Field walkdowns of the accessible applicable valves are in progress.

3. Confirmation of design information for the applicable valves will be obtained from Copes-Vulcan.

4. We have developed an interim acceptance criteria for evaluating these valves. These interim acceptance criteria are included as an attachment to this letter. An evaluation of the as-built piping systems will be conducted and compared to the design basis as defined in the FSAR. Piping systems exceeding the FSAR allowables will be reviewed against the interim acceptance criteria.

5. If the stresses fall within the bounds of the interim acceptance criteria, corrective actions will be implemented during the next refueling outage for each unit, and immediate action will not be necessary. If the stresses fall outside the interim acceptance criteria, safety reviews will be conducted within the time frame dictated by the Technical Specifications. Once all corrective actions are completed, the piping systems will fall within the bounds of our design basis.

Schedule:

To address the Copes-Vulcan valve concerns, we have initiated a problem report that requires, by January 3, 1989, an investigation of the problem, a determination of root cause, the extent of the deficiencies, and preventive action to preclude recurrence.

Corrective action schedules called for in our problem report investigation will be consistent with Item 5.

I Mr. A. B. Davis AEP:NRC:1084 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. Alexich Vice President MPA/eh Attachment cc: D. H. Williams, Jr.

W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff G. Bruchmann NRC Resident Inspector - Bridgman

ATTACHMENT TO AEP:NRC:1084 INTERIM ACCEPTANCE CRITERIA