ML17338A501

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Responds to NRC Re Violations Noted in IE Insp Repts 50-250/78-29 & 50-251/78-29.Corrective Actions: Removal of Lead from Unit 4 Containment During Shutdown Period
ML17338A501
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 01/18/1979
From: Robert E. Uhrig
FLORIDA POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML17338A500 List:
References
L-79-14, NUDOCS 7902230017
Download: ML17338A501 (3)


Text

P.O. BOX 3311 MIAMI,FLORIDA 33101 I

FLORIDA POWER 4 LIGHT COMP January 18, 1979 L-79-14 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:RWZ 50-250/78-29 50-251/78-29 lorida Power

& Light Company has reviewed the subject inspection eport and a response is attached.

There is no proprietary information in the report.

Very truly yours,

') E(c'(

'j!:...C':~

Robe'rrt E. Uhrig Vice President Advanced Systems and Technology REU/MAS/cpc Attachment cc:

Robert Lowenstein, Esquire 790 22300t l

73( u t: C.QS

ATTACHMENT Re:

RII:RNZ 50-250/78-29 50-251/78-29

~Findin 10 CFR 50.59(b)

requires, in part, a written safety evaluation which provides the bases for the determination that a change to the facility does not involve an unreviewed safety question.

Contrary to the above, as of November 30,

1978, a written safety evaluation was not performed for the installation of lead shielding on the regeneration heat exchanger and residual heat removal "C"

loop piping inside the Unit 4 containment.

he corrective action was to remove the lead from the Unit 4

ontainment during a December 3 to December 12, 1978 shutdown period.

By the December 12 startup, compliance had been achieved.

To help prevent recurrence, a quality control inspection holdpoint has been added to Operating Procedure 0202.1 (Reactor Startup, Cold Conditions to Hot Shutdown Conditions).

The holdpoint requires that all temporary lead shielding be removed from containment prior to heating the reactor coolant system above 200'F.

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