ML20133H499

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Informs That Safety Aspects of 850501 & 0614 Requests Re Tech Spec Changes Covering Engineered Safeguards Equipment Tests Reviewed.No Safety Significance or Enforcement Action Will Be Taken If Remaining Surveillances Completed
ML20133H499
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 06/19/1985
From: Walker R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Wilgus W
FLORIDA POWER CORP.
References
NUDOCS 8508090368
Download: ML20133H499 (2)


Text

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JUN 191985 C

Florida Power Corporation ATTN: Mr. W. S. Wilgus Vice President Nuclear Operations P. O. Box 14042, M.A.C. H-2 St. Petersburg, FL 33733 Gentlemen:

SUBJECT:

CRYSTAL RIVER 3 TECHNICAL SPECIFICATION CHANGE REQUEST N0. 128 -

ENGINEEREDSAFEGUARDS(ES)EQUIPMENTTESTS By letters dated May 1, 1985 and June 14, 1985, Florida Power Corporation (FPC) requested Technical Specification (TS) changes covering certain ES equipment tests to resolve conflicts with commitments made to provide increased protection against possible low temperature overpressurization during such tests.

Included in these requests is a one-time waiver of the 18-month frequency requirement for TS Sections 4.8.1.1.2.c.3 and c.5 until Mode 3 during the startup for Cycle 6.

Also included is authorization to perform tests covered by those sections in Mode 3.

We have reviewed the safety aspects of this request and conclude the following:

1.

There is no reason to believe that the reliability of the diesel generators will be significantly affected during the period of time until the plant reaches Mode 3 and the testing can be completed.

Other required diesel generator tests will have been successfully completed.

2.

Core decay heat is very low considering that fuel heat has been decaying for at least 3 months.

In view of the above, we believe that the requirement for TS Sections 4.8.1.1.2.c.3 and c.5 has no safety significance and no enforcement action will be taken provided that:

1.

The remaining surveillance testing specified in TS 4.8.1.1.2 will be ccm-pleted for one emergency diesel generator prior to movement of fuel.

Therefore, aside from the testing specified in TS 4.8.1.1.2.c.3 and c.5, the diesel generator will be fully operable.

2.

Surveillances required by TS 4.8.1.1.2.c.3 and c.5 will be completed in Mode 3 prior to entering Mode 2.

Sincerely.

Original signed D. Verrelli Roger D. Walker, Director Division of Reactor Projects cc:

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JUN 191985 e

Florida Power Corporation 2

cc:

E. M. Howard, Director Site Nuclear Operations P. F. McKee, Nuclear Plant Manager G. R. Westafer, Manager Nuclear Operations Licensing and Fuel Management bec: G. Lainas J. Stolz H. Silver R. Walker V. Brownlee V. Panciera NRC Resident Inspector Document Control Desk State of Florida RI)

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