ML20011D435

Proposed Tech Specs,Revising Administrative Controls for Plant Operations Review Committee & Nuclear Safety Review Board Composition & Alternatives

ML20011D435
Person / Time
Site:	South Texas
Issue date:	12/18/1989
From:	HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20011D434	List: ML20011D433 ML20011D435
References
NUDOCS 8912270212
Download: ML20011D435 (7)

Text

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ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION 6.5.1.2 T

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Attachment 2 ,

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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 N18.1-1971 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 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) 3 FUNCTION 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 COMPOSITION Svea oR e v svrsa,<s ope.Jh weinc o wu rE s io<os4c.skr a rresw.sg nes,#,Mg

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L euf <we<<<'9 cmbrow,Lm,As ek ar , opi am,,ee p,g ,jta l' 6.5.1.2 The PORC shall be composed of thr:g5*4hassw.:.ee4/p <j va p% 4

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L ember: 7E ed<frepres@Js nt Superintendent assve-ca y/g/x ,g y d4 .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 Man Mem r: Quality Engineer ng ager The PORC Chairman shall be appointed in writing from anone these members by the 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 -

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??,eie* knovs' . hove kf k ppmj,,g sw& yge ,.asy[yQ ALTERNATES MMQ[j "' 'M'O '

3 h 6.5.1.3 All alternate members shall be appointed in writing by the Plant L . 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 convened by the- PORC Chairman or his designated alternate.

. QUORUM 6.5.1.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and three other members including alternates.

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

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u ATTACHMENT 3 ,

SICNIFICANT HAZARDS EVALUATION FOR A PROPOSED CHANGE IN.THE o .- NUCLEAR. SAFETY REVIEW BOARD COMPOSITION AND ALTERNATES a ,

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ST-HL-AE-3216 .

ff. Page 1 of 2 ATTACHMENT 3 SIGNIFICANT HAZARDS EVAI,UATION FOR A PROPOSED CHANGE IN THE -

NUCLEAR SAFETY REVIEW BOARD COMPOSITION AND ALTERNATES Backcround Technical Specification 6.5.2.2 requires that the Nuclear Safety Review Board (NSRB) composition consist of managers by specific title. The specific titles include the General Manager NSRB, General Manager S<.uth Texas Project Managoment, Vice President Nuclear Plant Operations, General Manager Nuclear Assurance and General Manager South-Texas Project Operations Support. .Several of 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 the NSRB (Attachment 6). .

Safety Evaluation In an effort to avoid future administrative Technical Specification changes when organization evolutions occur, specific etanagement titles for the composition of the NSRB should be avoided. The proposed changes ensure the level and range of expertise is maintained in the composition of the NSRB.

This is accomplished by requiring a full time NSRB chairman and four senior top-level functional area managers as members of the NSRB. These proposed changes vill allow HL&P and NRC resourcos to be better utilized on more important safety issues instead of utilizing resourcer on administrative Technical Specification changes. This proposed change will allow organization evolutions to occur without requiring Technical Specification changes.

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

Determination of Sienificant Hazards Pursuant to 10CFR50.91 this analysis provides a determinntion that the proposed changes to Technical Specifications does not involve any significant hazards consideration as defined in 10CFR50.92.

r 1. The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. Because no aspects of the STPECS organization that are important to safety are removed or diminished, the proposed amendment, will not involve a significant increase in the probability or consequences of any accident previously evaluated.

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. Attachment 3 Page 2 of 2 ST-HL-AE-3216 2 .- The proposed changes do not create the possibility of a new or different kind of accident from-any previously ovaluated. The~ proposed amendment is administrative in nature 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 i reduction in the margin of safety. The proposed changes l do not remove or diminish any elements of the nuclear organization that are essential:to the safe operation of 1 STPEGS. The proposed changes do not involve any changes  !

to plant operating systems or associated' safety analyses.

Therefore, the proposed changes do not involve a significant reduction in the margin of safety.

Conclusi2D The commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists.

This guidance includes examples (51FR7750) of the type of amendments that are considered not likely to involve significant hazards considerations.- The i changes proposed are cimilar to the examples of administrative changes identified in $1FR7750.

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ATTACHMENT 4 .

PROPOSED TECHNICAL SPECIFICATION 6.5.2.2 1 '

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ADMINISTRATIVE C01010L5 b

• 4 d Il h nm Ckogtetawa. V mcf %t l ece.st Seh R p 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 = - '

";...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 than two alternates shall participate as voting rrembers in NSRB activities at any one time.

i CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRB Chairman to provide expert advice to the NSRB.

MEETING FREQUENCY 6.5.2.5 The NSRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter.

l l QUORUM L- 6.5.2.6 The quorum of the NSRB necessary for the performance of the NSRB l 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 l

! including alternates. No more than a minority of the quorum shall have line responsibility 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, l or systems; and (2) tests or experiments completed under the provision l 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 involve an unreviewed safety question as defined in 10 CFR 50.59; 1 l

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

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