ML20080M973

Concurs W/Nrc Conclusion That Tech Spec SR 5.1.1 Sufficient to Demonstrate Control Rod Operability & NRC Recommendation to Revise Second Paragraph Re Control Rod Drop Max Temp Monitoring.Future License Amend Rev Provided

ML20080M973
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/21/1983
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
P-83319, NUDOCS 8310040325
Download: ML20080M973 (2)

Text

A Public wivice coniipiiiiy cecccaturdo 16805 WCR 19 1/2, Platteville, Colorado 80651 p q d j),,

p-6 G83 Septembf(\\1,N8 Fort St-A M ~'

Unit #1

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P-83319 Mr. John T. Collins, Regional Administrator Region IV Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011

SUBJECT:

Basis to Specification SR 5.1.1 Change Incorporating Description of CRDM Temperature Monitoring

REFERENCE:

NRC Letter, Madsen to Lee, dated August 3, 1983 (G-83283)

Dear Mr. Collins:

Public Service Company of Colorado (PSC) has reviewed the referenced letter and concurs with the Nuclear Regulatory Commission's conclusion that the Fort St. Vrain Technical Specification, SR 5.1.1, is sufficient to demonstrate control rod operability.

PSC also concurs with the Commission's recommendation to revise the second paragraph in the Basis for SR 5.1.1 and proposes the following revision to be included in a future License Amendment as suggested:

"All control rods which are withdrawn during power operation are periodically exercised by the performance of a

' rod drop' test to provide assurance of scram capability. These tests are nominally performed on a biweekly basis and involve deenergizing the brake assembly, thereby allowing the control rod pair to drop for approximately six inches. The time and distance are measured and the data extrapolated to ensure the maximum scram time can be met.

In addition, the temperatures, of those mechanisms already equipped with operable temperature measuring

devices, will be recorded periodically in conjunction with the drop test to ensure that the maximum operating temperatures are not exceeded."

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. Other than the insertion of the word " periodically" in the last sentence, this revision is essentially the same as that recommended by the Commission.

The insertion is necessary to clarify the fact that temperature measurements are normally taken only during plant operations when reactor power is greater than fifty percent of rated and the core pressure drop is greater than 3 PSID. High control rod drive motor temperatures are not expected at the lower reactor power and core pressure drop conditions.

If you have any questions, please contact me at (303) 785-2224.

Very truly yours, b 7)Ludr%

Don Warembourg Manager, Nuclear Production DWW/djm

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