ML20206B459

Forwards Summary of Equipment Qualification (EQ) Insp Conducted by NRR & IE on 870126-30.EQ Program Approved. Detailed Results of Insp Will Be Provided

ML20206B459
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/03/1987
From:	Harold Denton, Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), Office of Nuclear Reactor Regulation
To:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
References
TAC-42527, TAC-63576, NUDOCS 8704090158
Download: ML20206B459 (7)

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UNITED STATES i

NUCLEAR REGULATORY COMMISSION o

I WAsMINGTON, D. C. 20008 f

\\ **... j April 3. IS87 l

l Docket No. 50-267 l

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Mr. R. O. Williams, Jr.

j Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 I

Denver, Colorado 80201-0840 i

Dear Mr. Williams:

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SUBJECT:

APPROVAL OF FORT ST. VRAIN EQUIPMENT QUALIFICATION (EQ)

PROGRAM i

On November 25, 1985, the Commission granted Public Service Company of Colorado (PSC) an extension until May 30, 1986, for environmental qualifica-tion of electrical equipment at the Fort St. Vrain Nuclear Generating Station (FSV). The Memorandum and Order granting the extension also stated that-

" operation above thirty-five percent power is conditional upon completion of j'

the EQ program and its approval by the Director, NRR and the Director, IE."

By letter dated September 10, 1986, we found your EQ program in compliance 3

j with the requirements of 10 CFR 50.49.

However, we noted that the reviews l

of the FSV ter,perature and pressure profiles and the proposed Steam Line i

Rupture Detection and Isolation System (SLRDIS) were not complete.

l By letter dated February 26, 1987, we issued to PSC Amendment No. 50 for j

FSV, approving the SLRDIS Technical Specifications.

This action completed our review and approval of the SLRDIS system.

1 By letter dated March 13, 1987, we approved FSV's temperature and pressure i

profiles, and by letter dated March 31, 1987 (P-87127), PSC certified that FSV is in compliance with 10 CFR Part 50.49 including completion of all E.Q. related field work.

During the week of January ?6, 1987, an inspection of your program was con-i ducted by representatives of the Office of, Inspection and Enforcement and the Office of Nuclear Reactor Regulation. contains a summary of j

that inspection.

The detailed results of this inspection will be provided 1

to you separately, t'

i 8704090158 B70403 l

PDR ADOCK 05000267 G

PDR i

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s Mr. R. O. Williams, Jr.,

Based on the above we conclude that your E.Q. program has been completed as specified in the Commission's Memorandum and Order and is approved.

Sincerely, 4

/

A Harold R. Denton, Director Office of Nuclear Reactor Regulation Yf j

es M.

aylor, Di~ rector Office Inspection and Enforcement

Enclosures:

As stated cc w/ enclosures:

1 See next page i

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Mr. R. O. Williams Public Service Company of Colorado Fort St. Vrain cc:

Mr. D. W. Warembourg, Manager Albert J. Hazle, 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 80223 Denver, Colorado 80r.01 Mr. David Alberstein, 14/159A Mr. R. O. Williams, Acting Manager GA Technologies, Inc.

Nuclear Production Division 3

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 Mr. P. F. Tomlinson, Manager Public Service Company of Colorado Quality Assurance Division P. O. Box 640 Public Service Company of Colorado Denver, Colorado 80201 16805 Weld County Road 19-1/2 l

Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. R. F. Walker P. 0. Box 840 Public Service Comoany of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 80201-0340 Kelley, Stansfield & 0'Donnell Public Service Company Building Commitment Control Program Room 900 Coordinator 550 15th Street Public Service Company of Colorado Denver, Colorado 80202 2420 W. 26th Ave. i'uite 100-D Denver, Colorado 80211 l

Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 4

1 Denver Place 999 18th Street, Suite 1300

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Denver, Colorado 80202-2413

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EQUIPMENT QUALIFICATION INSPECTION AT FORT ST. VRAIN NUCLEAR GENERATING STATION An equipment qualification (EQ) inspection at Fort St. Vrain Nuclear Generating

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Station (FSV) was conducted by IE and NRR on January 26-30, 1987.

The inspec-tion reviewed the licensee's implementation of a program for establishing and maintaining the qualification of electric equipment within the scope of 10 CFR 50.49.

The inspection consisted of examination of selected procedures and records, l

interviews with personnel, and observations by the inspectors.

A total of 39 qualification files out of 81 were reviewed and samples of equipment from t

approximately 25 different equipment types were inspected during the plant walkdown.

The inspection determined that FSV had implemented a program to meet the requirements of 10 CFR 50.49, except for.certain deficiencies identified during the inspection and described below.

Additionally, during the inspection i

entrance meeting, FSV identified some program activities which had not been completed.

These incomplete items were scheduled to be accomplished prior to l

FSV certification of compliance with 10 CFR 50.49.

t Two deficiencies were identified as Potential Enforcement / Unresolved Items since qualification was not supported in the respective qualification files and the files were submitted to the NRC inspectors as being complete.

One deficiency i

dealt with the qualification of the installed configurations of certain Raychem f

splices.

FSV had completed a qualification test program at Wyle Laboratories i

in Huntsville, Alabama, for the questioned splice configurations; however, the test report had not been included in the qualification file.

Results of the testing were provided to the NRC inspector during the inspection and qualifi-l cation of the splice configurations was supported.

The other deficiency pertained to qualification of first generation Rockbestos coaxial cable.

FSV had established qualification of second and third generation i

Rockbestos coaxial cable, but did not have data to support qualification of the first generation coaxial cable in the respective qualification file. When i

ques,tioned by the NRC inspectors FSV was able to provide additional test data toadequatelysupportqualificatIonofthefirstgenerationcoaxialcable.

Five Open Items were identified during the inspection; however, only three pertained to actions required of FSV.

The three items pertained to qualifi-cation file revisions for five cable files, the ASCO solenoid valve file, and the Limitorque motor valve operator file. While qualification was considered 1

supported, the revisions were considered necessary to clarify the basis of i

qualification in the files.

a e

The other two Open Items pertained to NRC review of FSV's implementation of their procurement and maintenance programs.

The inspectors reviewed the FSV program procedures in these areas; however, the effectiveness of the procedure implementation was not reviewed during this inspection.

Region IV is scheduled to perform an implementation review of these areas prior to FSV exceeding 35%

power level.

Based on the results of the inspection, the inspection team determined that FSV was in the process of completing an EQ program that would meet the requirements of 10 CFR 50.49.

When FSV completes:

(1) the actions associated with the deficiencies identified during the inspection; (2) the outstanding items identified during the entrance meeting and on the FSV open item lists; and (3) certifies that FSV is in compliance with 10 CFR 50.49, there is reasonable assurance that FSV will be in compliance with the requirements of 10 CFR 50.49.

(The PSC certification letter of March 31, 1987 adequately addresses these points.)

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April 3, 1987 Mr. R. O. Williams, Jr. Based on the above we conclude that your E.Q. program has been completed as specified in the Commission's Memorandum and Order and is approved.

Sincerely, Ortlad stad t3

~ ti.n.cer. tog -

Harold R. Denton, Director Office of Nuclear Reactor Regulation original signed by E. J. Jordan for James M. Taylor, Director Office of Inspection and Enforcement

Enclosures:

As stated cc w/ enclosures:

See next page

[ISTRLBUTLON:

l ectai.. File /

OGC-Beth NRC PDR EJordan Local PDR BGrimes PBSS Reading JPartlow PNoonan HThom

, N"pson KHeitner

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Olynch HBerkow FMiraglia WShields JTaylor

• SEE PREVIOUS CONCURRENCES

• PBSS

• PBS$

• PBSS

• PBSS

• DPWRL-B:DIR

• 0GC-BETH IR PNoonan KHeitner:ac Olynch HBerkow FMiraglia TDorian ylor 03/13/87 03/16/87 03/18/87 03/18/87 04/1/87 03/18/87 04/2/87 1

o 01(;/87

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0 Mr. R. O. Williams, Jr. During the week of January 26,1987,'an inspection of your program was con-ducted by the Office of Inspection and Enforcement (IE). Enclosure I contains a sumary of that inspection. The detailed results of this inspection will be provided to you separately. However, the sumary findings are that your program was implemented in accordance with the regulations and is considered to be approved by the Director of IE.

Sincerely, l

Harold R. Denton, Director Office of Nuclear Reactor Regulation

(

James M. Taylor, Director Office of Inspection and Enforcement

Enclosures:

As stated cc w/ enclosures:

See next page l

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DISTRIBUTION:

Docket File OGC-Beth NRC POR EJordan Local PDR BGrimes l

PBSS Reading JPartlow PNoonan HThompson KHeitner ACRS(10) 0 Lynch IIBerkow FMiraglia WShields JTaylor

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PP PBSS M PBd5/

P DPk B DIR 0

H gf o' n' Kileitnerrac P '/(b/87 OLy/g/87 y/'ylory87 l

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FMi ia an JTa 03 03/fg/87 Of///87

/87 03 03/16/87 NRR:0IR HDenton s

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