ML20154S648

Proposed Tech Specs,Allowing Independent Review & Audit Functions to Be Accomplished by Independent Organizational Unit Rather than Standing Committee

ML20154S648
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	09/22/1988
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20154S641	List: ML20154S637 ML20154S648
References
NUDOCS 8810050118
Download: ML20154S648 (8)

Text

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a ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155 PROPOSED TECHNICAL SPECIFICATION PAGE ClfANGES September 22, 1988 i

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PDR ADOCK 05000155 P PDC .

TSB0888-0086-NLO4

ADMINISTRATIVE CONTROLS 6.2.3 (DELETED) /

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ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 Alternate members of the PRC shall be ar ointed in writing by the PRC Chairman to serve on a temporary basis. However, no l more than two alternates shall participate as voting members at any one time in PRC activities.

MEETING FREQUENCY l

6.5.1.4 The PRC shall neet at least once per calendar month, with l

special meetfogs as required.

l l QUORU4 6.5.1.5 A quorum for PRC shall consist of the Chairman and four (4) voting members.

RESPONSIBILITIES 6.3.1.6 The PRC shall be responsible for:

a. Review oft (1) all procedures required by Technical Specification 6.8 and changes thereto and (2) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety. //

b. Review of all proposed tests a.id experiments that affect nuclear safety.

c. Review of all proposed changes to the Operating License and Technical Specifications.

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d. Review of all proposed changes or modifications to plant systems or equipment that affect .'uclear safety,

e. Investigation of all violations of the Technical Specifications. (A report shall be prepared covering evaluation and recommendations to prevent recurrence ,

and forwarded to the Vice President Nuclear Operations '

and to the Nuclear Safety Services Department.) /

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f. Revies of plant operations to detect potential j nuclear safety hazards. l 1

g. Review of reportable events as defined in Section 1.2.14.

h. Performance of special reviews and investigations and  ;

reports thereof as requested by the Plant Manager or //

l Nuclear Safety Services Department. / l

1. Review of the Site Emergency Plan and implementing i procedures. '

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ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

j. Review of any accidental, unplanned or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding o:f these reports to the Plant Manager and to the Nuclear Safety Services //

Department. /

PRC review may be performed through a routing of the item subjoet to the requirements of Specification 6.5.1.7.

AUTHORITY 6.5.1.7 The PRC shall:

a. Recommend in writing to the Plant Manager approval or //

disapproval of items considered under Specifications 6.5.1.6.a through d. above,

b. Render determinations in writint with regard to whether or not each item considered under Specifications 6.5.1.6.a through e. above constitutes an unreviewed safety question.

c. 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 Vice President - Nuclear Operations and to the Nuclear Safety /

Services Department of aay disagreement between the PRC /

and the Plant Manager; however, the Plant Manager shall //

have responsibility for the resolution of such disagreements pursuant to Specification 6.1.1 above.

The PRC Chairman may recommend to the Plant Manager approval of //

those items identified in Specifications 6.5.1.6 a, through d.

and i above based on a routing review provided the following ///

conditions are met (1) at least five PRC members, including the Chairman and no more than 2 alternates, shall review the item, concur with determination as to whether or not the item constitutes an unreviewed safety question, and provide written comments on the item; (2) all comments shall be resolved to the

, satisfaction of the reviewers providing the comments; and (3) if the PRC Chairman determines that the comments are significant, the item (including comments and resolutions) shall be recirculated to all reviewers for additional comments.

The item shall be reviewed at a PRC meeting in the event that (1) comments are not resolved; or (2) the Plant Manager overrides //

the recocnendations of the PRC; or (3) a proposed change to the Technical Specifications involves a safety limit, a limiting safety system setting or a limiting condition for operation; or (4) the item was a REPORTABLE EVENT as defined in 10 CFR 50.73. ///

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// Proposed by CR of 7/23/87 TSB0888-0086-NLO4

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e ADMINISTRATIVE CONTROLS RECORDS 6.5.1.8 The PRC shall maintain written minutes of each PRC meeting and shall provide copies to the NSSD. /

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6.5.2 NUCLEAR SAFETY SERVICES DEPARTMENT (NSSD) /

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FVNCTION /

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6.5.2.1 The Nuclear Safety Services Department shall function to / j provide independent review of activities in the areas oft /

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a. Nuclear Power Plant Operation /

b. Nuclear Engineering / !

c. Chemistry and Radiochemistry /

d. Metallurgy /

e. Nondestructive Testing /

f. Instrumentation and Control /

g. Radiological Safety /

h. Mechanical and Electrical Engineering /

i. Administrative Controls and Quality Assurance Practices /

j. Emergency Planning /

k. Training /

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C0hPOSITION /

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6.5.2.2 The NSSD shall consist of a full-time staff reporting to the /

Vice President - Nuclear Operations. NSSD staff shall have no /

direct responsibility for activitice subject to their review. /

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The NSSD staff shall meet or exceed the qualifications described /

in Section 4.7 of ANSI /ANS 3.1 - 1987. /

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CONSULTANTS /

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6.5.2.3 If sufficient expertise is not available wichin NSSD for review /

of particular issues, the NSSD shall have the authority to / .

utilize consultants or other qualified organizations for expert / I advice. / i

/ l 6.5.2.4 RESPONSIBILITIES /

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REVIEW / '

/ i 6.5.2.4.1 NSSD shall review: /

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a. The safety evaluations fort 1) changes to procedures. / I equipment or systems, and 2) tests or experiments / l completed under the provisions of 10 CFR 50.59 to /  :

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ADMINISTRATIVE CONTROLS 6.5.2.4 RESPONSIBILITIES- (Continued) /

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REVIEW 6.5.2.4.1 (Continued) /

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verify that such actions did not constitute an /

unreviewed safety question. Review of safety /

evaluationo may be accomplished through sampling. / -

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b. Proposed changes to procedures, equipment or systems /

which involve an unreviewed safety question as defined /

in 10 CFR 50.59. /

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c. Proposed tests or experiments which involve an /

unreviewed safety question as defined in 10 CFR $0.59. /

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d. Proposed changes to Technical Specifications or the /

Operating License. /

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e. Violations of codes, regulations, orders, Technical /

Specifications, license requirements or internal /

procedures or instructions having nuclear safety /

significance. /

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f. Significant operating abnormalities or deviations from /

normal and expected performance of plant equipment that /

affect nuclear safety. /

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g. All REPORTABLE EVENTS having nuclear safety significance. /

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h. All recognized indications of an unanticipated deficiency /

in rome aspect of design or operation of structures. /  !

systems or components that could affect nuclear safety. / .

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i. Reports and meeting minutes of the Plant Review /

I Committee. /

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i AUDITS /

l / l 6.5.2.4.2 Audits of operational nuclear safety-related facility activities / I a

shall be performed under the cognizance of NSSD. These audits /

shall encompass: / ,

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l a. The conformance of plant operation to provisions /

l contained within the Technical Specifications and /

applicable license conditions at least once per 12 months. /

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b. The performance, training and qualifications of the /

entire facility staff at least once per 12 months. /

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ADMINISTRATIVE CONTROLS AUDITS 6.5.2.4.2 (continued) /

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c. The performance of activities required by the /

Operational Quality Assurance Program Description for /

Operational Nuclear Power Plants (CPC-2A) to meet the /

criteria of 10 CFR 50 Appendix B, at least once per /

24 months. /

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d. The Site Emergency Plan and implementing procedures at /

least once per 12 months. /

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e. The Site Security Plan and implementing procedures (as /

required by the Site Security Plan) at least once per /

12 months. /

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f. Any other area of plant operation considered appropriate /

by NSSD or the Vice President - Nuclear Operations. /

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g. The plant Fire Protection Program and implementing /

procedures at least once per 24 months. /

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h. An independent fire protection and loss prevention / l inspection and audit shall be performed annually /

utilizing either qualified offsite licensee personnel /

or an outside fire protection firm. /

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1. An inspection and audit of the fire protection and loss /

prevention program shall be performed by an outside /

qualified fire consultant at intervals no greater than /

3 years. / '

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j. The Radiological Environmental Monitoring Program and / o the results thereof at least once per 12 months. / )

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k. The Off:ite Dose Calculation Manual and implementing /

procedures at least once per 26 months. /

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1. The Process control Program and implementing procedures /

for processing and packaging of radioactive wastas at /

least once per 24 months. /

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Audit reports encompassed by 6.5.2.4.2 above shall be /

forwarded to the NSSD, and management positions responsible /

for the iceas audited within thirty (30) days after /

completion of the audit. /

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AUTHORITY /

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6.5.2.5 The NSSD shal. . port to and advise the Vice President - /

Nuclear Operatiena of significant findings associated with /

those areas of responsibility specified in Section 6.5.2.4.1 /

and Section 6.5.2.4.2. /

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. o ADMINISTRATIVE CONTROLS RECORDS /

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6.5.2.6 Records of NSSD activities shall be maintained. Reports shall /

be prepared and distributed as indicated below /

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a. The results of reviews performed pursuant to Section /

6.5.2.4.1 and Section 6.5.2.4.2 shall be reported to the /

Vice President - Nuclear Operations at least mone.hly. /

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b. A report assessing the overall nuclear safety performance /

of the Big Rock Point Plant shall be provided to senior /

Consumers Power Company management annually. /

6.6 (DELETED) 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated

a. The reactor shall be shut down immediately and not restarted until the Commission authorizes resumption of operation (10 CFR 50.36(c)(1)(1)(.\)).

b. The safety limit violation shall be reported within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to the Commission in accordance with 10 CFR 50.36, as well as to the Vice President - Nuclear Operations and to the NSSD. /

c. A report shall be prepared in accordance with 10 CIR 50.36 and 6.9 of this specification. (The safety limit violation and the report shall be reviewed by the PRC.)

d. The report shall be submitted withie 14 days to the Commission (in accordance with the requirements of 10 CFR 50.36), to the Vice President - Nuclear Operations and to the NSSD. /

6.8 PROCEDURES 6.8.1 Written precedures shall be established, implemented and maintained for all structures, systems, components and safety actions defined in the Big Rock Point Quality List. These procedures shall meet or exceed the requirements of ANSI N18.7, as endorsed by CPC-2A, 6.8.2 PRC is responsible for the review of each procedure of 6.8.1 above, and changes thereto (except for Security Implementing Procedures which are reviewed and approved in accordance with the Site Security Plan). The Plant Manager shall approve //

such procedures and changes prior to implementation.

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