ML19270H088

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Responds to NRC 790404 Ltr Re Violations Noted in IE Insp Rept 50-335/79-06.Corrective Actions:Safety Evaluation Conducted & Procedure Reviewed & Determined Satisfactory
ML19270H088
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 05/01/1979
From: Robert E. Uhrig
FLORIDA POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19270H083 List:
References
L-79-108, NUDOCS 7906230006
Download: ML19270H088 (3)


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  • ' ' b b P C f /. mftt1T FLORID A POWER & LIGHT COVPANY 19 IUY 3 a 9: gN May 1, 1979 L-79-108 Mr. James P. O'Reilly, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

Re: RII:EHW 50-335/79-06 Florida Power & Light Company has reviewed the subject inspection report and a response is attached. There is no proprietary infonnation in the report.

Very tr ours, Robert E. Uhrig .

Vice Presicent Advanced Systems & Technology REU/ PAS /paf cc: Harold F. Reis, Esquire 2247 050 t t 490Mo 7906230&of

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ATTACHiiENT Re: RII:EHW 50-335/79-06 Finding A As required by 10 CFR 50.59, item (b) requires ir. part that the licensee maintain records of changes to systems as described in the safety analysis report including "a written safety evaluation which provides the basis for the determination that the change...does not involve an unreviewed safety question."

Contrary to the above, plant change / modification 446-78, a change to the therr.al margin / low pressure pretrip setpoint, described in FSAR part 7.2.1.2(g), was completed on November 2,1978, without any safety evalua-tion on the control element assembly withdrawal prohibit function modified by the change, to determine that the change did not involve an unreviewed safety question.

Response A The subject safety evaluation has been conducted and the change has been found to be acceptable, i.e., there was no unreviewed safety question.

The need for complete evaluations has been re-emphasized to the responsible individuals. Compliance has been achieved and no further action is planned at this time.

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Finding B As required by Technical Specifications 6.8.2 and 6.8,la, procedures recommended in Appendix A to Regulatory Guide 1.33-1972 shall be reviewed by the FRG and approved by the plant manager. Regulatory Guide 1.33-1972 Appendix A, paragraph I.l., lists procedures for maintenance which can affect the performance of safety-related equipment.

Contrary to the above, plant change / modification 359-78, a change to the control element assembly block circuit completed November 8,1978, included a step-by-step retest procedure to test the modified circuit, which can affect the performance of safaty-related equipment, which was not reviewed by the FRG or approved by the plant manager.

Response B The subject procedure has been reviewed by the FRG and determined to be s a tis fa ctory. The responsible individual has been instructed to obtain proper review and approval of procedures. Compliance has been achieved and no further action is planned at this time.

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