ML20206P200

Ack Receipt of Transmitting Rept Entitled, Parameter Trending Test Program. Data from Rept Will Be Incorporated Into Listed Ongoing Licensing Actions

ML20206P200
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/22/1986
From:	Heitner K Office of Nuclear Reactor Regulation
To:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
References
TAC-56565, TAC-61066, TAC-61601, NUDOCS 8608270122
Download: ML20206P200 (3)

Text

..

August 22, 1986 Docket No. 50-267 Mr. R. O. Williams, Jr.

Vice President, Nuclear Operations Public Service Company of Coloradt P. O. Box 840 Denver, Color >

80201-0840

SUBJECT:

CONTROL R0D DRIVE AND ORIFICE ASSEMBLY PARAMETER TRENDING TEST PROGRAM We acknowledge receipt of your letter dated July 31, 1986 (P-86494),

transmitting the report entitled, " Parameter Trending Test Program". The data from this report will potentially be incorporated in the following ongoing licensing actions:

Technical Specification Upgrade Program (TAC No. 56565),

i Control Rod Drive Mechanism Preventive Maintenance (TAC No. 61066),

and

- Control Rod Drive Mechanism Temperature Requalification (TAC No.

61601).

We note that temperatures of 200 F and above were reached by certain control rod drive and orifice assembly shim motors during operation at 35 percent of full power. This parameter has the potential of limiting reactor power until the control rod drive mechanism temperature requalification program noted above has been completed.

Sincerely, 4

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Denver, Colorado 80201-0840

Dear Mr. Williams:

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SUBJECT:

CONTROL R0D DRIVE AND ORIFICE ASSEMBLY PARAMETER TRENDING TEST PROGRAM We acknowledge receipt of your letter dated July 31, 1986 (P-86494),

transmitting the report entitled, " Parameter Trending Test Program". The data from this report will potentially be incorporated in the following ongoing licensing actions:

Technical Specification Upgrade Program (TAC No. 56565),

Control Rod Drive Mechanism Preventive Maintenance (TAC No. 61066),

and Control Rod Drive Mechanism Temperature Requalification (TAC No.

61601).

We note that temperatures of 200 F and above were reached by certain control rod drive and orifice assembly shim motors during operation at 35 percent of full power. This parameter has the potential of limiting reactor power until the control rod drive mechanism temper 6ture requalification program noted above has been completed.

Sincerely,

~

n Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation cc:

See next page

t Mr. R. O. Williams Public Service Company of Colcrado 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. L. W. Singleton, Manager Public Service Company of Colorado Quality Assurance Division P. O. Box 840 Fort St. Vrain Nuclear Station Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. 0. Box 640 Platteville, Colorado 80651 Kelley, Stansfield & 0'Donnell Public Service Company Building Room 900 550 15th Street Denver, Colorado 80202 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 1800 Lincoln Street Denver, Colorado 80203 i

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