ML20010A228

Revised Tech Spec Pages 6-19 & 6-20 Re Prompt Notification & Written Followup of LERs

ML20010A228
Person / Time
Site:	Turkey Point
Issue date:	11/26/1975
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML20010A217	List: ML20010A223 ML20010A228 ML20010A230
References
NUDOCS 8108110199
Download: ML20010A228 (2)

Text

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, c. Prompt Notification 1ith tiritten' Followup. The typts cf .

events listed 'clow shall be reported as expeditiously cs o

• possibic, but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirped by' "',

- telegraph, mailgram, or facsimile transmission to the.

Director of the approprinto Regional Office, or his designate -

no later than the first working day following the event, with  !

a written followup report within two weeks. The written followup report shall include, as a mininum, a completed copy -

of a licensee event report form. Information provided on ,

the licensee event report form shall be supplemented, ,

as needed, by additional narratiye material to prcvide com - '

plcte explanation of the circumstances surrounding the event, .

(1) Failu:e of the reactor protection system or other

• a systems subject to limiting. safety Ly tem settings'to , ,

initinte the required protective function by the time a monitored parameter reaches the setpoint specified '

as the limiting safety system setting in the technical . ,

specifications or failure to complete the requirsd ,- ,n

.protective function.

Note: Instrument drift discovered as a result of ' testing .~

need not be reported under this item but may be ,

e -

reportabic under items.2.a(5), 2.a(6), or 2.b(1) -

25 below.

(2) Operation of 'the unit or affected sys.tems when any; , .

parameter or operation subject to a limiting condition I is Icss conservative than the Icast conservative aspect of the liniting' condition for operat, ion established

• in the technical specifications. -

Note: If specified action is taken when a system is found to be operating between the most conservative and the least conservative aspects of a limitin; condition for operation listed in the technical specifications, the limiting condition for operation is not considered to have been violated and need not be reported under i

this item, but it may be reportable under item 2.b(2)  %

below.

j (3) Abnormal degradation discovered in fuel cladding,_rea'etor coolant pressure boundary, iir primary containment.'

Note: Leakage of valve packing or gaskets within the limits

• for identified leakage set forth in technical spec-ifications need not be reported under this , item.

6-19

-- 810811o199 810807 *

.C '

DR ADOCK 05000 NOV 2 61975 t

C .

, (4) Reactivity anomatics, involving disagreement with the predicted value r,f reactivity lial.:nce under eteady r. tate conditions during pr.zer operation, greater than or equal to It ak/k; a calculated reactivity balance indicating a shut-down margin less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than S seconds or, if sub-critical, an unplanned reactivity insertion of more than 0.5% ak/k or occurrence of any unplanned criticality.

(5) Failure or malfunction of o$c or core components which prevents or could prevent, by itself, the fulfillment of the functional requirerents of system (s) used to cope with accidents analy:cd in the SAR.

(6) Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with eccidents analy:cd in the SAR.

Note: For items 2.a(5) and 2.a(6) reduced redundancy that

. does not result in a loss of system function need not be reported under this section but may be 25 reportable under items 2.b(2) and 2.b(3) below.

(7) Conditions arising from natural or man-made events that, as a direct result of the event require plant shutdown, operation of safety systems, or other protective measures

( required by tc:hnical specifications.

(8) Errors discovered in the transient or accident analyses or in the methods used for such analyses as described ,

in the safety analysis report or in the bases for the technical specifications tFat have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.

(9) Performance of structurcs, systems, or components that requires remedial action or corrective measures to -

prevent operation in a canner less consersati;c than assumed in the accident analyses in the sr.fety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically con-sidered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition. '

6-20 -

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NOV 2 61975

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