ML19345A437

Proposed Tech Specs 6.5,6.7 & 6.8 Re Audit & Review Committee Member Qualifications,Safety Limit Violations & Procedures

ML19345A437
Person / Time
Site:	Yankee Rowe
Issue date:	12/02/1975
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML19345A435	List: ML19345A434 ML19345A437
References
NUDOCS 8011210409
Download: ML19345A437 (5)

Text

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Re&gulatory Docket File ADMINISTRATIVE CONTROLS d.

The Committee membership and its Chairman and-Vice Chairman shall be appointed by the Yankee Atomic Electric Company Vice President or such person as he shall designate.

c.

Qualifications:

M.MM.48!.d..

p Membership to the Committee requires that an individual-meet one of the below academic and/or experience requirements:

(1)

Bachelor Degree; plus two years total experience in the below listed disciplines.

(2) Associates Degree; plus three years total experience in the below listed disciplines.

(3)

Five years total experience in the below listed disciplines:

(a)

Nuclear Power Plant Technology (b)

Reactor Operations (c) Utility Operations (d) Power Plant Design (c)

Reactor Engineering, (f) Radiation Safety-(g)

Safety Analysis (h)

Instrumentation and Control (i) Metallurgy (j) Quality Assurance ALTERNATES 6.5.2.3 a.

Alternate members shall be appointed by the Yankee -

Atomic Electric Company Vice President or such person as he shall designate, b.

No more than two alternates shall participate in NSARC activitics at any one time.

CONSULTANTS 6.5.2.4 Consultants shall-be utili::cd as determined by the NSAR Chairman to provide additional expert advice, when needed, to the NSAR Committee.

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ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.2.5 a.

The Committee shall hold a minimum of two regularly

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scheduled meetings per year.

b.

Special meetings may be held when deemed necessary by Company management or by the Chairman of the Committee, or, in the absence of the Chairman, by l

the Vice Chairman.

QUORUM 4

i 6.5.2.6 A quorum shall consist of a minimum of five members as follows:

a.

The Chairman or Vice Chairman plus four members (or two members plus two alternatas).

b.

The Chairman and Vice Chairman plus three members (or one member plus two alternates).

c.

Those personnel from the organi:ation reporting to the. Manager of Operatione cha11 always he in the minority.

l.

REVIEl?

6.5.2.7 The NSAR Committee shall review:

a.

The safety evaluation for.1) changes to equipment

.or systems and 2) special tests or experiments and their implementing procedures completed under the provision of Section 50.59, 10CFR, to verify that

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such actions did not constitut'e an unreviewed-safety question.

b.

Proposed tests or experiments _which involve an unreviewed safety question as defined.in Section-50.59, 10CFR.

I c.

. Proposed changes in-Technical' Specifications or-l.

licenses.

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d.

Violation of Technical. Specifications and license.

requirements.

Significant. operating-abnormalitics or deviations c.

l from normal and expected performance of plant l

equipment that affect nucicar safety, defined as;

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Plant Information. Reports.

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-ADMINISTRATIVE CONTROLS f.

Reportable Occurrences, as defined in Regulatory Guide 1.16.

g.

Reports and meeting minutes of the Plant Operation,

Review Committee.

h.

Perform special reviews and investigations and-render reports thereon as requested by the Assistant Vice President of Operations.

1 AUDITS 6.S.2.8 Audits of facility Quality Assurance activities that have a direct effect upon the operating plant shall be 4

performed by the Opcrational Quality Control and Audit Dept. (0QCAD) unbr the cognizance of the hSKA Committee.

The NSAR Committee may 1) audit the OQCAD audits; 2) per-form an independent audit of the same areas or; 3) impic-ment a combination of these methods.

The NSAR Committee may audit any other area of facility -

operation considered appropriate by the Committee or the Vice President.

AUT110RITY 6.S.2.9 The NEAR Committee shall report to and advise the Company Vice President on those areas of responsibility spccified in Section 6.5.2.7 and 6.5.2.8.

RECORDS l

6.5.2.10 llinutes of each NSARC meeting shall be prepared and for-warded to the Company Vice President:and each member.of the Committce for review within 20 working days following each meeting.

The meeting minutes shall' include,_where applicabic, reports of reviews encompassed by Section-6.5.2.7; and ' reports of audits included in Section 6.5.2.8.

The review of the minutes'shall be completed within 60 days of the date of their distribution.

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6-10 L

b-ADMINIST'ATIVE CONTROLS R

f 6.6 REPORTABLE' OCCURRENCE ACTION l

For reportable occurrence actions, reference Appendix A, Section E.4 to j

Facility License DPR-3.

6.7 SAFETY LIMIT VIOLATIONS 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

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i The provisions of 10 CFR 50.36 (c)(1.)(1) shall be complied a.

with immediately.

b.

The Safety Limit violation shall be reported to the Commission and Manager of Operations immediately.

t c.

A Safety Limit Violation Report shall be prepared. LThe report shall be reviewed by the Plant Operation Review Committee.

This report shall describe -(l) applicable -

circumstances preceding the violation, (2). effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limir Violation Report snali te submitted to the Commission, the Nuclear Safety Audit and Review 4

Committee and the Ibnager of' Operations within two weeks

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following the violation.

l 6.8 PROCEDURES 6.8.1 Written procedures and administrative policies shall be-established, implemented and maintained'that meet or exceed the requirements and recommendations of Section 5.1 and 5.3

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of ANSI N18.7-1972 and Appendix "A" of USNRC-Regulatory Guide 1.33 except as provided in 6.8.2 and 6.8.3 below.

6.8.2 Each procedure and administrative policy of.6.6.1 above, l

and changes thereto, shall be reviewed by'the Plant Operation Review Committee and approved by,the Plant Superintendent prior to implementation and-reviewed periodically as set forth in-each document.

V 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

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a.

The intent of the original procedure is not altered, c

b.

The change is approved by two members of! he' plant management-t l

' staff, at least one of whom holds.a senior Reactor.

Operator's License.

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c.

The change is documented, reviewed-by the Plant Operation-Reviev Committee and approved by the Plant Superintendent within 30 days.and prior to the. changed procedure being used.

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6-11

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_ NRC DISTRl!;UTION FOR PART 50 DOCKET MATERIAL (TEMPORARY FORM)

CONTROL NO:

13608 FILE:

F RO.'.*. Yankee Ato:nic Elec. Co.

DATE OF DOC DATE R EC'D LTR TWX RPT OTHER

'/estborough, Mass. 01581 t~.4s F. Feider 12-2-75 12-5-75 XX TO:

ORIG CC OTHER SENTliRC PDR XX Mw

't signed 37 SENT LOCAL PDR ___ XX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:

XXX 40 50-29 DESCRIPTION:

Ltr notarized 12-2-75 requestinENCLOSURES:

f:: Proposed Change ::o. 130, Supp1~1 to Lic. DPR-3 with attcheed revised Tech Spe c Pa;cs....

Q, fiC00W2 DOS PLANT NAME:

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