ML20077E433

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Proposed Tech Specs 6.0,revising Station Review Board Composition & Reflecting Organizational Changes
ML20077E433
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 05/10/1991
From:
CENTERIOR ENERGY
To:
Shared Package
ML20077E423 List:
References
NUDOCS 9106100195
Download: ML20077E433 (3)


Text

4 Doci:et.11 umber 50-346 License Number NPF-3 S!?ial.Wmber 1840 Attachment 1 Page 5 l ADMINISTRATIVE CONTROLS ___

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! COMPOSITION ~

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,;6 % 1.2 The Station Re@i'ew Board shall be composed of the:/-

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Station Review Board Chairmt..e U

N ChaYrman:

Member: N anager 4 Plant Operations ,/

H Member: Ahlstant Plant Manager Maintenance t' Member: Techn'ical Support Manaaer/

Member: Radiologica kContro.lsd uperintendent Member: Operations Eng'indring Supervisor (Plant)

Member: An Engineer-ifig Director Member: Quality' Assurance Superi/isor Member: Opefations Superintendent (Plant {

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  • Desig~ fnated in writing by the Plant Manager. YfiKhainnan will be

, / drawn from SRB members. \

. ALTERNATES l 6. 5.1. 3 All alternate members shall be appointed in writing by the SRB I

Chairman; nowever, no more than two alternates '

shall participate as voting -

members in SRB activities at any one time.

MEETING FRE00ENCY 6.5.1.4 The SRB shall meet at least once per calendar month and as cenvened by the SRB Chairman or his dc;ignated altcrnate.

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-QUORUM dD" 6.5.1.5 A quorti.n of the SRB shall consist of the Chairman or his designated altcrnacc and four members including alternates. db p RESPONSIBILITIES 6.5.1.6 The Station Review Board shall be responsible for:

a. Review of plant administrative procedures and changes thereto.
b. Review of the safety evaluatior, for 1) p ocedures, 2) changes to procedures, ecaipment or systems, and 3) tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions do not constitute an unreviewed safety question.
c. Review of proposed procedures and changes to procedures and equipment determined to involve an unrt r.M safety question as defined in 10 Cf 50.59.

DAVIS-BESSE, UNIT 1 f. 6 Amendment No. JZ,76,yE,J07,J22,,149, 142 9106100195 910510 PDR ADOCK 05000346 P PDR

I Dockot Numb 2r 50-346 Licensa Numb 2r NPF-3 Serial Number 1840 Attachment 1 Page 6 INSERT A 6.5.1.2 The Station Review Board shall be composed of at least six members of the Davis-Desse onsite management organization at the supervisor level ot above. Each of the following disciplines shall be represented: plant operations, maintenance, planning, radiological controls, engineering, and quality assurance.

The SRB Chairman shall be drawn from the SRB members and designated in writing by the Plant Manager.

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7 Gocket Number 50-346 Licenae Number NPF-3 Ser'ial Number 1840 Attachment 1

.{ADMINIST:.ATIVE CONTROLS s.3 nctuTy sTArr ouAttr1CATtoNS p mangec -aa dio/oy/ca/ C ohho/

l6.3.' Eacn rr.encer of tnt f acility staf Vshall meet or excee0 tne minimum loua lifies t1nns cf ANSI N18.1-1971 for/cmoaracle positions. except /or l

'(1) tne ': r r': w " *: - '- :_ _ . ....__... wno snall meet or exceto the oualifications of Regulatory Guice 1.8. Septemoer 1975 (2) the Shif t Tecnnical Advisor wno snall have a bacnelor's degree or ecu1 valent in a I 'scient1fic or engineering discipline with spac1fic training in plant design, ana response and analysis of the plant for transients ano acc1 cents, ano l

(3) the fianager - Plant Operations wnose relutrement for a senior reactor operator license is as stated in Specification 6.2.2.g.

' ,6. 4 TRAINING #ddd 7

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.6.4.1 A retraining anc replacement training program forf the f acility statf 3 isnall be maintaineo unoer tne atrect1on of the .. . _. --

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l lana snall meet or exceed the reovirements anc reco::vnenaattons of Section

, {5.5 of ANSI N18.1-1971 ano of 10 CFR 55.59.

6.4.2 A training prcgram for the Fire Brigaae anall be maintaineo unoer the direct 1on of the ......_. - -: -- Ei xx:-

Plan.1ger- twuear &Jnlng-

6. 5 JEVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD (SRB)

FUNCTION

!6.5.1.1 The Station Review Boarc (SRB) snall funct1on to aavise tne Plant P.anager on all matters relatea to nuclear safety.

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l -DAV15-BE55E. UNIT 1 6-5 Anenement No. 9.27.27.98.105.125.228, 142 t _-