ML20210P019

Summary of 870113 Meeting W/Util Re Completion of Equipment Qualification Program & Program & Approvals Required for Plant Restart

ML20210P019
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/05/1987
From:	Heitner K Office of Nuclear Reactor Regulation
To:	Berkow H Office of Nuclear Reactor Regulation
References
TAC-63576, NUDOCS 8702130277
Download: ML20210P019 (5)

Text

m i *4 WE%q'o f- ~g UNITED STATES i jI '

,, g NUCLEAR REGULATORY COMMISSION

-i  ; j- WASHINGTON, D. C. 20555

• % ,,,.* February 5, 1987 Docket No. 50-267 MEMORANDUM FOR: Herbert N. Berkow, Director 4 Standardization and Special Projects Directorate Division of PWR Licensing-B, NRR THRU: Oliver D. T. Lynch, Jr., Section Lead Standardization and Decommissioning S on Standardization and Special Projects Directorate Division of PWR Licensing-B, NRR

, FROM: Kenneth L. Heitner, Project Manager Standardization and Decommissioning Section Standardization and Special Projects Directorate Division of PWR Licensing-B, NRR

SUBJECT:

SUPWARY OF MEETING WITH PUBLIC SERVICE COMPANY OF COLORADO (PSC) ON THE FORT ST. VRAIN (FSV)

EQUIPMENT QUALIFICATION (EQ) PROGRAM AND APPROVALS REQUIRED FOR PLANT RESTART A meeting was held with PSC on January 13, 1987 to discuss FSV's status with regard to completion of the EQ program. At this meeting, the status of other approvals required for plant restart was also discussed.

Attendees at this meeting are given in the enclosure.

Status of the EQ Program PSC reviewed the status of the FSV EQ program and its relationship to the upcoming EQ inspection. Discussions between NRC and PSC focused on the status of EQ documentation (including procedures and qualification binders), the EQ Master List, plant EQ modification and maintenance activities, and logistics for the inspection. During the meeting PSC stated that they planned to have all EQ efforts (including any necessary corrective action resulting from the EQ inspection) completed by the middle of February 1987. PSC plans to certify that FSV conforms with the requirements of 10 CFR 50.49 at that time. Based on the information provided in the meeting, the NRC confirmed the EQ inspection for the week of January 26, 1987.

8702130277 870205 PDR ADOCK 05000267 P PDR

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Approvals Required for Plant Restart The staff and licensee reviewed the approvals required for plant restart.

The specific focus of this discussion .was the proposals by PSC to initially operate the plant based on the analyses that supported continued use of the steam generator reheaters up to 39% of full power. The staff noted that continued use of the reheaters for safe shutdown cooling posed additional technical problems. Specifically, the licensee's analyses and tests had shown that only 2 or 3 of the 6 reheater modules would receive cooling water. The " dry" modules would be subject to high temperatures which could lead to failure of the tubes or supporting structures. Thus, justification of this mode of operation would be largely based on the materials analyses and posed potentially complex issues.

By contrast, an alternative basis for plant operation was available at 35%

of full power, based on using the liner cooling system. In view of the small additional power level gained by the new analyses, it was mutually agreed by the staff and PSC that further consideration of this approach offered little safety or economic benefit. Hence,it was agreed that PSC would request that initial operation of the plant be based on the liner cooling system with a power level limit at 35%. PSC would review their prior bases for operating in this mode, and the NRC's prior approval for any potential changes and inform the staff of their review. PSC would commit to this interim power limit (35%) until the staff had reviewed and approved the changes associated with the proposed high power limit (P2),

estimated to be 82% of full power. -

At this time, the Region IV staff also noted that they would request a

" hold" on FSV at 10% of full power, to evaluate operational performance.

~

PSC said they would agree to a " hold" at that power level so that the NRC could evaluate PSC's operational performance before proceeding to higher power levels.

l Kenneth L. Heitner, Project Manager Standardization and Decommissioning Section Standardization and Special t

Projects Directorate Division of PWR Licensing-B, NRR l

Enclosure:

l As stated cc w/ enclosure:

j See next page

, *4

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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 80220 Denver, Colorado 80201 Mr. David Alberstein, 14/159A Mr. J. W. Gahm, 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 Mr. P. F. Tomlinson, Manager Public Service Company of Colorado Ouality Assurance Division P. O. Box 840 Public Service Company of Colorado Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. R. F. Walker P. 0. Box 840 -

Public Service Company of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 80201-0840 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. Suite 100-D Denver, Colorado 80211 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 1

I Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 i Denver, Colorado 80202-2413 l

l l

.j.e.

'f . Enclosure NRC-PSC MEETING JANUARY 13, 1987 Name Organization Ken Heitner NRC/NRR/DPWRL-B

.C. H. Fuller Public Service Company of Colorado Don Waremboung Public Service Company of Colorado Mike Niehoff .Public Service Company of Colorado John Waage Public Service. Company of Colorado Tim Prenger Public Service Company of Colorado D. J. Brown Public Service Company of Colorado H. L. Brey Public Service Company of Colorado G. T. Hubbard NRC/IE/VPB D. E. Norman NRC/RIV H. N. Berkow NRC/NRR/DPWRL-B J. P. Jaudon CH/PSA/RIV/NRC J. E. Gagliardo NRC/RIV, Proj. Branch Ch.

R. E. Ireland NRC/RIV, Ch. E.S.

A. R. Johnson NRC/RIV/RSB/ES R. E. Hall NRC/DRSP R. O. Williams VP/NUC/PSC i

i

' February 5, 1987 Approvals Required for Plant Restart The staff and licensee reviewed the approvals required for plant restart.

The specific focus of this discussion was the proposals by PSC to initially operate the plant based on the analyses that supported continued use of the steam generator reheaters up to 39% of full power. The staff noted that continued use of.the reheaters for safe shutdown cooling posed additional technical problems. Specifically, the licensee's analyses and tests had shown that only 2 or 3 of the 6 reheater modules would receive cooling water. The " dry" modules would be subject to high temperatures which could lead to failure of the tubes or supporting structures. Thus, justification of this made of operation would be largely based on the materials analyses and posed potentially complex issues.

By contrast, an alternative basis for plant operation was available at 35%

of full power, based on using the liner cooling system. In view of the small additional power level gained by the new analyses, it was mutually agreed by the staff and PSC that further consideration of this approach offered little safety or economic benefit. Hence,it was agreed that PSC would request that initial operation of the plant be based on the liner cooling system with a power level limit at 35%. PSC would review their prior bases for operating in this mode, and the NRC's prior approval for any potential changes and inform the staff of their review. PSC would commit to this interim power limit (35%) until the staff had reviewed and approved the changes associated with the proposed high power limit (P2),

estimated to be 82% of full power.

At this time, the Region IV staff also noted that they would request a

" hold" on FSV at 10% of full power, to evaluate operational performance.

PSC said they would agree to a " hold" at that power level so that the NRC could evaluate PSC's operational performance before proceeding to higher power levels.

Original signed by Kenneth L. Heitner, Project Manager Standardization and Decommissioning.Section Standardization and Special Projects Directorate Division of PWR Licensing-B, NRR

Enclosure:

As stated cc w/ enclosure:

See next page DISTRIBUTION: -

! Docket File " NRC PDR ACRS (10)

PBSS Reading Local PDR NRC Participants PNoonan OGC-Beth Licensee and Plant Service Lists XHeitner EJordan Olynch BGrimes

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onan PBSS 'XH KHeitner:ac r

Olyngh 02/4//87 02/+/87 02/g/87 I

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