ML20082G477

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Proposed Tech Specs 6.5.1 & 6.5.3 Revising Facility Review Committee & Nuclear Review Board Composition
ML20082G477
Person / Time
Site: River Bend Entergy icon.png
Issue date: 08/09/1991
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20082G470 List:
References
NUDOCS 9108190143
Download: ML20082G477 (4)
v • d • e


Text

.

ADMINISTRATIVE CONTROLS

6. 3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI /ANS 3.1-1978 for comparable positions, except for the Director-Radiological Programs who shall meet or exceed the cualifications of Regulatory Guic'e 1.8, September 1975.

The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter

-to all licenseis.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Director - Nuclear Training and shall m*it or excud the rerpirements end rscorrmandations of Seiction 5.5 of ANSI /

ANS 3.1-1978 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28.-1980 NRC letter to all licensees, an6 shall include familiarization with relevant industry 4

operational experience.

6.5 REVIEW AND AUDIT 6.5.1 FACILITY REVIEW COMMITTEE (FRC)

FUNCTION 6.5.1.1 The FRC i. hall function to advise the Plant Manager on all matters related to nuclear safety.

COMPOSITION g,ER The T"C ; hell E; ;;p;T '

INS

6. 5.1. 2
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i MEETING FREQUENCY r"

Chairperson ~

6.5.1.4 The FRC shall meet at-least once per calendar month and as convened l,

by the FRC Ch;ichu or M+-designated alternate.

RIVER BEND - UNIT 1 6-7 Amendment No. F 9 t os190142: 910809 PDR-ADOCK 05000458 p

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RESPONSIBILITIES i

6.5.1.6 The FRC shall be responsible for:

i Review of all plant general administrative procedures and changes a.

thereto; b.

Review of all proposed tests and experiments that affect nuclear safety; Rtview of all propnned ch'.nDes to Appundix A Technical Specifications; c.

d.

Review of all proposed changes or modifications to structures, compo-nents, systems or equipment that affect nuclear safety; Investigation of all violations of the Technical Specifications, I

e.

including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence, to the Senior Vice President - RBNG and the Nuclear Review Board;

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f.

Review of all REPORTABLE EVENTS; Review of unit operations to detect potential hazards to nuclear safety; !

g.

items that may be included in this review are NRC inspection reports that require written response, QA audits / surveillance findings of l

operating and maintenance activities, NRB audit results, and Ameri-can Nuclear Insurer (AN!) inspection results; i

h.

Performance of special reviews, investigations, or analyses end reports thereon as requested by the Plant Manager or the Nuclear Review Board; i.

Review of initial start-up testing phase start-up procedures and revisions; and

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j.

Review of the Emergency Plan and implementation procedures at least i

i once per 12 months and all proposed changes thereto.

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6. 5.1. 7 The FRC shall:

Recommend in writing to the Plant Manager approval or disapproval of a.

items considered under Specification 6.5.1.6.a. through d. prior to their implementation.

i b.

Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6.a. through e. constitutes

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an unreviewed safety question.

t Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Senior Vice i

c.

[

President - RBNG and the Nuclear Review Board of disagreement between l

the FRC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Speci-j fication 6.1.1, f

RIVER BEND - UNIT 1 6-8 A.mendment No. N l

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l ADMINISTRATIVE CONTROLS FUNCTION (Continued) a.

Nuclear power plant operations, b.

Nuclear engineering, Chemistry and radiochemistry, c.

d.

Metallurgy, Instrumentation and control, e.

f.

Radiological safety, g.

Mechanical and electrical engineering, h.

Quality assurance practices, i.

Licensing and regulatory affairs, j.

Training.

The NRB shall report to ar.d idvi:1 the Swnior Vice Prusibent - RBNG on those areas of responsibi'ity in Specifications 6.5.3.7 and 6.5.3.8.

COMPOSITION

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A.s s4 s tant-#4 ant-)(anage c=0pe r a ti o n s-a nd-R a dwa s t e Mambar:

Director-Design-Engineering

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Director-Mue4 ear-04 censing

. Member:

Outage-Manager

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"::t:rt Ofrector-P4ent-0versight ALTERNATES

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litSERT '

6. 5. 3. 3 -AM-alternate ::riers-sham 4e-appointed-la-witing4y-the-NRB shiir;;r to serec cr. ; t;g rary-bethg t:r^ 4r, ne er4-than-two-alternates

!M11 peatie! pats --as yeting-member 4-tr 'R! ::tiv4 tie 5-at any e ti m CONSUt.TANTS

( Chairperson 6.5.3.4 Consultants shall be utilized as deter 1 mined by the NRB-Chairmam to provide expert advice to the NRB.

RIVER BEND - UNIT 1 6-10 Amendeent No. )7

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ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.3.5 The NRB shall meet At-4 east ^nce per-4434nda* quarter #4a; ne 4ait4 1 deer ef Unk-tpeest4en-fe44ewf*g-49e4-4eadkg-enf at least once per 6 months

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QUORW jINSERT+)

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z 6.5.3.6 Th: qu:eue-et-thf,'PRB necessary for the-peeformance-4f-the-#RS-r494ew

nd sudit funetien: ef th::c Technieel--Spee4f44at44n6-+hal4-sen54et-of-the Chairman er the Vice Cheiraan end at-4eest-th-#RB :: Sees-4nstuding-no-more than-two-alternate:.

"O mece-than-e-abeMty-of-the-querum-sha14-bave-44ee responsibi'ity for Operation of the-unit /

U?.12 6.5.3.7 The NRB shall be responsible for the review of:

The safety evaluations for (1) changes to procedures, equipment, or a.

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; t

b.

Proposed changes to procedures, equipment, or systems which involve an unreviewed safety que'stion as defined in 10 CFR 50.59; Proposed tests or experiments which involve an unreviewed safety c.

quection as defined in 10 CFR 50.59; J.

Proposed changes to Technical Specifications or this Operating License; Violations of codes, regulations, orders, Technical Specifications, e.

license requirements, or of internal procedures or instructions having nuclear safety significance; f.

Significant coerating abnormalities or deviations from normal and 3xpt:ted,sar/.mr.nce of unit equipma7t that affect nuclear safety; g.

All REPORTABLE EVENTS:

h.

All recognized indications of an unanticipated deficiency in some aspect of design or coeration of structures, systems, or component.s that could affect nuclear safety; and i.

Reports and meeting minutes of the FRC.

AUDITS 6.5.3.8 Audits of unit activities shall be performed under the cognizance of the NRB.

These audits shall encompass:

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3 RIVER BEND - UNIT 1 6-11

-. -

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