ML20154A542

Requests Addl Info Re Rev 7 to Schedule Commitment Items on Pcrv Tendon Surveillance Involving Provision of Schedule for Conducting Evaluation within 45 Days for Pcrv Tendon Degradation

ML20154A542
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/30/1988
From:	Heitner K Office of Nuclear Reactor Regulation
To:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
References
TAC-54639, NUDOCS 8809130004
Download: ML20154A542 (7)

Text

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' k UNITED STATES NUCLEAR REGULATORY COMMISSION

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. rs W ASHING TON, D. C. 20655 k August 30, 1988 Docket No. 50-267 Mr. R. O. Williams, Jr.

Vice President, Nuclear Operations Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201-0840

SUBJECT:

FORT ST. VRAIN SCHEDULE COMMITMENT ITEMS PCRV TENDON SURVEILLANCE - REVISION 7 AND REQUEST FOR ADDITIONAL INFORPATION(TACH 0.54639)

Reference:

1. PSC letter dated January 8, 19o.8 (P-88002); Transmittal of fifth six month PCRV tendon irterim surveillance report.

2. PSC letter dated July 20, 1987 (P-87234); Transmittal of fourth six month PCRV tendon interim surveillance report.

3 The staff has reviewed your submittals, References I and 2, concerning changes i you have requested to comittrents for the Fort St. Vrain Nuclear Generating

Station (FSV). These changes involve an alternative PCRV Tendon Surveillance Program. The key features of this alternative program are that the surveillance intervals are extended fron 6 to I? months. The cycle for new

, tendons selected for liftoff testing is extended from 18 to 24 months.

4 In considering this extension, the staff notes that over 80% of the tendons have been examined, so the data sample is fairly corplete. Repeated testing of the control group tendons by liftoff shows no obvious degradation over

< three years. No new non effective tendon wires have been observed in the control group tendons since June 1985. The five worst case tendons are currently stable, and still acceptable by the end-of-life criteria in the FSAR. Based on the above considerations, the staff finds your revised PCRV tendon surveillance program is acceptable. A sumary of your revised comitments is enclosed.

However, in order to continue adequately monitoring the PCRV tendon status, and evaluate potential future concerns, the staff is requesting certain additional

, information. The purpose of this request is to clarify the current and future d ability of the PCRV to perfom its design function. The staff believes that this is a opportune tire to perform such an evaluation, since considerably more surveillance data is now available than was several years ago. A properly conducted evaluation could be the basis for further reductions in the surveillance intervals.

The staff's request for additional infors.ation is Enclosure 2. The staff requests that you provide a schedule for conducting your evaluation within 45 days of the date of this letter. If you wish to discuss an request, including rethodology, please contact we at 492-1333.

(301) y aspects I will of this arrange for a meeting with the staff on this issue.

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Mr. R. 0. Williams, Jr. -2 August 30, 1988 The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely,

) .

Kenneth L. Heitner, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated cc y/ enclosure:

See next pago

O Mr. R. O. Williams, Jr.

Public Service Company of Colorado Fort St. Vrain cC*

Mr. D. H. Warerbourg, Manager Albert J. Harle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201-0840 Mr. David Alberstein, 14/159A Mr. R. O. Williams, Jr., Acting Manager GA Technologies, Inc. Nuclear Production Division Post Office Box 85608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Pr. P. F. Tomlinson, Manager Public Service Corpany of Colorado Quality Assurance Division P. O. Box 840 Public Service Ccepany of Colorado Denver, Coloradn 80201-0840 16805 Weld County Read 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Comission Pr. R. F. Walker P. O. Box 640 Public Service Company of Colorado Platteville, Colorado 8C651 Post Office Box S40 Denver, Colorado 80201-0840 Kelley, Stansfield & 0'Donnell Public Service Company Building Comitment Control Program Room 900 Coordinator 550 15th Street Public Service Company of Colorado Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-D Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Comission 611 Ryan Plaza Drive, Suite 10C0 Arlington, Texas 76011 Chaiman, Board of County Comissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colorado 80202-2413

Enclosure 1 Revision 6 PUBLIC SFRVICE COMPANY OF COLORADO COM ITMENTS RELATED TO THE OPERATION OF THE FORT ST. VRAIh NUCLEAR GENERATING STATION Iten Consnitment Description / Requirement Schedele (Reference)

1. Provide status reports on the Nuclear Approximately Perfomance Enhancement Program on an annually annual basis. (P-88031)

2. Implenent the Technical S UpgradeProgram(P-85098)pecifications(TS)

a. Provide a revised final draft proposal Complete of the U graded TS for NRC coment.

(P-87063

b. Submit a license amendrent to 90 days after incorporate the Upgraded TS, (P-85243) NRC comentf on Iten 2a

c. Implement the Upgraded TS (P-85243) Approximately 4th refueling outage (License amendment will define)

3. Improve control rod and reserve shutdown (See Item 2) reliability. Incorporate the interim Technical Specifications in the Upgrade Program.

4. Develop a plan to implement approved Annually modifications to control moisture ingress and submit annual re orts on progress.

(P-85022 and P-85082

5. Evaluate control of moisture in CRDM purge 4th refueling system.(P-85021) outage

6. PCRV Tendon Surveillance Requirements:

a. Incorporate the revised Tendon Surveillance (SeeItemt)

Program into the Technical Surveillance (P-85199),

b. Provide the results of the revised Approximately program to the NRC. every six months

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, Revision 6 Page 2

7. Provide an improved CRDM surveillance Five months program which includes consideration of after the start CRDM operational testing. (P-88012) of 4th refueling outage

8. Fire Protection Modifications:

a. Perform emergency lighting Complete by 3/1/88 modifications (P-88030)

b. Perfom modifications involving Startup following ACM backfeed, permanent turbine 4th refueling water removal purop, and valve outage operability (P-87013).

I Enclosure 2 i

REQUEST FOR ADDITIONAL INFORMATION r

PCRV TENDON DEGRADATION

1. Evaluate current structural integrity and design safety margin of PCRV based on current tendon surveillance data. This evaluation should be based on actual data from the approximately 80% percent of the tendons examined to date. This includes data from tendon liftoff tests, visual examinations, and load cells. The data should be reduced to a consnon  !

basis, such as remaining preload force. Reasonable and conservative l assumptions should be used to calculate the preload forces for tendons L where there is no data. The evaluation should compare the current f condition of the PCRV in terms of the structural integrity and design ,

margins with those originally assumed and accepted as the plant's  !

licensing basis in the FSAR. i

2. Evaluate the projected-end-of-life structural integrity and design safety ,

margins of the PCRV based on current tendon surveillance data. The  !

evaluation would be based on the same data as used in item 1 above.

Reasonable and conservative assumptions about future degradation of the .

remaining preload force should be us,ed to calculate end-of-life conditions.  :

The basis for predicting the end-of-life condition of tendons already

• severely degraded should be given special attention. The evaluation i should compare the projected end-of-life condition (in terms of structural integrity and design margins of the PCRV with the FSAR comitments.  !

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s Mr. R. O. Williams, Jr. ~2- August 30, 1988 The reporting &nd/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not recuired under P.L.96-511.

Sincerely,

/s/

Kenneth L. Heitner, Project !!anacer Project Directorate - IV Division of Reactor Projects - III.

IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated ec w/ enclosure:

See next page DISTRIBUTION Docket File NRC PDR Local Pl1R PD4 Reading DR4A/J. Collins J. Calvo P. Noonan Project Manager 0GC E. Jordan J. Partlow ACRS (10)

PD4 Plant file R. Lipinski D. Jeng G. Bagchi n

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PNeonan KHeitrer:kb v lyo R. Lipinski D. Jeig G, Bapchi 06/h,/68 Of/iy/88 c/ /EE C6/3. /88 GP/J./8.8 g/0'88 3

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