ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION 6.5.1 · and Appendix A of 10 CFR Part 55 and ti.e...

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Transcript of ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION 6.5.1 · and Appendix A of 10 CFR Part 55 and ti.e...

Page 1: ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION 6.5.1 · and Appendix A of 10 CFR Part 55 and ti.e supplemental requirements specified in Sections A and C of Enclosure 1 of the March

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ATTACHMENT 2

PROPOSED TECHNICAL SPECIFICATION 6.5.1.2,

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Attachment 2' , ._

S L 3216,

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14 1 RAINING''

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6.4.1 A-retraining and replacement-training program for the unit staff shall ;

be maintained under the direction of the Training Manager and shall meet.or,,

- exceed the requirements and recommendations of Section 5.5 of_ ANSI N18.1-1971and Appendix A of 10 CFR Part 55 and ti.e supplemental requirements specified inSections A and C of Enclosure 1 of the March 28. 1980 NRC letter to all- licensees,and shall include familiarization with relevant industry operational experience. ~

6.5 REVIEW AND AUDli_

6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC).

FUNCTION3

6.5.1.1 The P0FC shall function to advise' the Plant Manager on all matters'related to nuclegsafetg 4g ,4 p g a ,, g

Svea sa,< ope.Jh a rresw.sg nes,#,Mio<os4c.skr / fs weinc o wu rE s

euf <we<<<'9 cmbrow,Lm,As am,,ee taCOMPOSITION oR e v svr g o

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l' 6.5.1.2 The PORC shall be composed of thr:g5*4hassw.:.ee4/p <j va p% 4( 7E ed<f assve-ca /g/ ), ' e ,, '

L ember: nt Superintendent repres@Js y x d,g y 4 .e,M mber: Tec a1 Services Manager cpp ,.4,f. J u gc,He er: Plant op tions Manager- 4 *'-,

j 4., Me er: Plant Engine ng Manager *

Mem er: Maintenance ManMem r: Quality Engineer ng ager

The PORC Chairman shall be appointed in writing from anone these members bythe Plant Managegl=ri er re i=2m. Easta;;rine "crerJ -!! iS 4-Teeimics 'arvie:f .".eneger dx; r.etweet ti.e ;n".'ic th ; :T : PM! tf en --Pret::tien Nr.e ., e; &fk:d b 0;pkte , GuiA 1.6 (Ter;;;;;l 'al dien er.dv ,

?? h; 0;; hie., i 0, tr.:: tre TenC waaiden wiii indva U 6.lttc j ;

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ALTERNATES "'3

h 6.5.1.3 All alternate members shall be appointed in writing by the PlantL . Manager to serve on a tesporary basis; however, no sore than two alternates

shall participate as voting members in PORC activities at any one time.

MEETING FREQUENCY

6.5.1.4 The PORC shall meet at least once per calendar month and as convenedby the- PORC Chairman or his designated alternate.

. QUORUM-

6.5.1.5 The quorum of the PORC necessary for the performance of the PORCresponsibility and authority provisions of these Technical Specificationsshall consist of the Chairman or his designated alternate and three othermembers including alternates.

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SOUTH TEXA5 - UNITS 1 & 2 6-7 Unit 1 - Amer dment .10. 4

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ATTACHMENT 3',

SICNIFICANT HAZARDS EVALUATIONFOR A PROPOSED CHANGE IN.THE

NUCLEAR. SAFETY REVIEW BOARD COMPOSITION AND ALTERNATESo .-

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ATTACHMENT 3

'SIGNIFICANT HAZARDS EVAI,UATION

FOR A PROPOSED CHANGE IN THE -<

NUCLEAR SAFETY REVIEW BOARD COMPOSITION AND ALTERNATES

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Backcround

Technical Specification 6.5.2.2 requires that the Nuclear Safety ReviewBoard (NSRB) composition consist of managers by specific title. The specifictitles include the General Manager NSRB, General Manager S<.uth Texas ProjectManagoment, Vice President Nuclear Plant Operations, General Manager NuclearAssurance and General Manager South-Texas Project Operations Support. .Severalof the management titles listed are no longer in use at STPEGS.

Proposed Chance-

Delete specific management titles from Technical Specifications and add '

a description which ensures top level functional area managers compose theNSRB (Attachment 6). .

Safety Evaluation

In an effort to avoid future administrative Technical Specificationchanges when organization evolutions occur, specific etanagement titles for thecomposition of the NSRB should be avoided. The proposed changes ensure thelevel and range of expertise is maintained in the composition of the NSRB.This is accomplished by requiring a full time NSRB chairman and four seniortop-level functional area managers as members of the NSRB. These proposedchanges vill allow HL&P and NRC resourcos to be better utilized on moreimportant safety issues instead of utilizing resourcer on administrativeTechnical Specification changes. This proposed change will allow organizationevolutions to occur without requiring Technical Specification changes.

Members of the NSRB will be qualified in accordance with ANSI 3,1-1981and Regulatory Guide 1.8.

Determination of Sienificant Hazards

Pursuant to 10CFR50.91 this analysis provides a determinntion that theproposed changes to Technical Specifications does not involve any significanthazards consideration as defined in 10CFR50.92.

1. The proposed changes do not involve a significant increaser

in the probability or consequences of an accidentpreviously evaluated. Because no aspects of the STPECSorganization that are important to safety are removed ordiminished, the proposed amendment, will not involve asignificant increase in the probability or consequences ofany accident previously evaluated.

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2 .- The proposed changes do not create the possibility of anew or different kind of accident from-any previouslyovaluated. The~ proposed amendment is administrative innature and does not involve any changes to plant design or ,

configuration. Therefore, the proposed changes will not j

create the possibility of a new or different kind of'

accident. ,,

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3. The proposed changes do not involve a significant ireduction in the margin of safety. The proposed changes l

'do not remove or diminish any elements of the nuclearorganization that are essential:to the safe operation of 1

!STPEGS. The proposed changes do not involve any changesto plant operating systems or associated' safety analyses.Therefore, the proposed changes do not involve a

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significant reduction in the margin of safety.

Conclusi2D

The commission has provided guidance concerning the application of thestandards for determining whether a significant hazards consideration exists.This guidance includes examples (51FR7750) of the type of amendments that areconsidered not likely to involve significant hazards considerations.- The i

changes proposed are cimilar to the examples of administrative changesidentified in $1FR7750.

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ATTACHMENT 4- .

PROPOSED TECHNICAL SPECIFICATION 6.5.2.2..

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ADMINISTRATIVE C01010L5b * 4 d I| h nm Ckogtetawa. V mcf %t l ece.st Seh Rp COMPOSIT10N_ 3.p pggg

6.5.2.2 The NSRB shall be composed of@th; fcilwing, e~f ather :::b:r; si.11,-be appointed in writing by the Group _Vice President, Nuclear

.Chai ~er Gen re! ".; rieger, NSES".; be r: Cer.:r:1 ".:n:g:r, Seeth Texn Prej=t ":=;;:nr.t-"dc r; Vice Pre 3ideni, Huclear Fioni Oper;ti = - '

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";...Le i . C;r.crei "ei..wer, huciear assurance"::b:r- ceneral u.a nger, South Texn Drej=t Op;retier,s %pp;rt-

ALTERNATES

6.5 2.3 All alternate _ members shall be appointed in writing by the Group,Vice President-Huclear to sevve on a temporary basis;, however, no more thantwo alternates shall participate as voting rrembers in NSRB activities at anyone time.

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CONSULTANTS

6.5.2.4 Consultants shall be utilized as determined by the NSRB Chairmanto provide expert advice to the NSRB.

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MEETING FREQUENCY!

6.5.2.5 The NSRB shall meet at least once per calendar quarter during theinitial year of unit operation following fuel loading and at least once per 6

, months thereafter.l

| QUORUM

L- 6.5.2.6 The quorum of the NSRB necessary for the performance of the NSRB| review and audit functions of these Technical Specifications shall consist of

the Chairman or his designated alternate and at least a majority of NSRB members |'

! including alternates. No more than a minority of the quorum shall have lineresponsibility for_ operation of the unit.

L REVIEW

6.5.2.7 The NSRB shall be responsible for the review of:

L a. The safety evaluations for: (1) changes to procedures, equipment,| or systems; and (2) tests or experiments completed under the provision| of 10 CFR 50,59, to verify that such actions did not' constitute an

unreviewed safety question;

b. Propcsed changes to procedures, equipment, or systems which involvean unreviewed safety question as defined in 10 CFR 50.59; 1

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SOUTH TEXAS - UNITS 1 & 2 6-10 Uni.t 1 - Amendment No. 4

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