ML20128H815

Amend 76 to License DPR-6,approving Administrative Control Tech Spec Changes Re Offsite Corporate Reorganizations of Util QA & Nuclear Activities Plant Organizations

ML20128H815
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	07/01/1985
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20128H811	List: ML20128H806 ML20128H815 ML20128H818
References
NUDOCS 8507100255
Download: ML20128H815 (9)

Text

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~ UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION

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July 1,1985 CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT PLANT AMENPMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. DPR-6

1. The Nuclear Regulgtory Commission (the Commission) has found that:

A. The application for amendment by Consumers Power Company (the licensee) dated January 30, 1985, as revised February 1, 1985 and June 7, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the "

Commission's rules and regulations set forth in 10 CFR Chapter I;

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B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (11) that such activities will be conducted in compli-ance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The inuance of this amendment is in accordance with 10 T'R Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

8507100255 850701 DR ADOCK0500g5

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraphs 2.C.(2) of Facility Operating License flo. DPR-6 are hereby amended to read as follows: ..

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendnent No.76 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY OMMISSI0ff J \.

John A. Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: July 1,1985

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ATTACHMENT TO LICENSE AMEf!DMENT NO. 76 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing the pages identified belev and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain narginal lines indicating the area of change.

REMOVE INSERT 10-3 10-3 10-4 10-4 10-5 10-5 10-8 10-8 10-10 10-10 10-11 10-11

ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP 6.2.3.1 The ISEG may function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources which may indicate areas for improving plant safety. The organization shall report to the Director Nuclear Safety. With the concurrence of the Director, ISEG may function as staff to the onsite and offsite review organizations and provide technical support for problem resolution and General Office interface.

COMPOSITION 6.2.3.2 The ISEG shall be composed of members located at other Consumers Power Company Nuclear Power facilities. Any ISEG member may be drawn upon to perform ISEG duties on a temporary basis at Big Rock Point.

REPORTS 6.2.3.3 Reports of ISEG activities shall be submitted regularly to the NSB with copies to PRC.

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10-3 Amendment No. ,fI , 76

.- Y CONSUMERS POWER COMPANY OFFSITE ORGANIZATION PRESIDENT i

EXECUTIVE EAECUTIVE VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT NUCLEAR SAFETY GENERAL SERVICES NUCLEAR OPERATIONS BOARD I

DIRECTOR OF PROPERTY PROTECTION *"

, o U E 1 OTHER DIRE PAllSADES PLANT SERVICES GENERAL SUPERINTENDENT NUCLEAR ASSURANCE. MANAGER BIG ROCK POINT I

n PALISADES OA DIRECTOR IUPE TE ENT DIRECTOR QA DIRECTOR NUCLEAR SAFETY **

BG K N QA SUPPORT k

a W -

a -

o t

' NSB CHAIRMAN

" NSB VICE CHAIRMAN AND SECRETARY

"' RESPONSIBLE FOR OVERALL FIRE PROTECTION PROGRAM FIGURE 6.2-1 m

CONSUMERS POWER COMPANY i '

PLAN! ORGANIZATION Plant L Superintendent (a) l Nuclear Assurance loff-Site i

QA ____ _ _ _ _ Plant Review Superintendent Comnittee QC Supervisor Chem /HP Operations and Technical Superintendent Maintenance Superintendent Superintendent i

I I Operations Maintenance Superintendent Superintendent or Supervisor - SR0(b) or Engineer I

Shift Supervisors - SRO A. To support the above Plant organization, personnel knowledgeable in the following areas identified in ANSI N18.7-1976/ ANS 3.2 will-report at the discretion of the Plant Superintendent:

1. Nuclear Power Plant Mechanical, Electrical and Electronic Systems

2. Nuclear Engineering

3. Chemistry and Radiochemistry

4. Radiation Protection (Reports to Chem /HP Superintendent)

A single individual may be qualified and perform in more than one discipline.

B. The Security Force will be supervised as described in the Plant Security Plan.

C. Quality Assurance / Control activities will be in accordance with Consumers Power Company's Quality Assurance Program Description for Operational Nuclear Power Plants (CPC-2A, as revised).

(n) Responsible for the Plant Fire Protection Program implementation.

f (b)Either the Operations Superintendent or the Operations Supervisor will hold an SRO and meet the other requirements of 6.3.1 of these Technical Specifications i

(as applicable to Operations Manager in ANSI N18.1). The individual holding an SRO shall be responsible for directing the activities of licensed operators.

(SRO - Senior Reactor Operator License)

Figure 6.2-2 Amendment No. pd pd, 76 10-5

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

MEETING FREQUENCY ._

6.5.1.4 The PRC shall meet at least once per calendar month, with special meetings as required.

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

RESPONSIBILITIES a

6.5.1.6 The PRC shall be responsible for:

a. Review of: (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 -i Plant Superintendent to affect nuclear safety.

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

c. Review of all proposed changes to Appendix "A" Technical Specifications.

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

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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 Director - Nuclear Safety.)

f. Review of plant operations to detect potential nuclear safety hazards.

g. Review of events requiring 24-hour written notification to the Commission.

h. Performance of special reviews and investigations and reports thereof as requested by the Plant Superintendent or Chairman of NSB.

i. Review of the Site Emergency Plan and implementinF l procedures. '

10-8 Amendment No. pd, pdI, 76 1

ADMINISTRATIVE CONTROLS FUNCTION 6.5.2.2 The NSB shall function to provide review of designated activities in the areas specified in Specification 6.5.2.3.

COMPOSITION 6.5.2.3 The NSB shall consist of members appointed by the Vice President -

Nuclear Operations. NSB shall be chaired by the Executive-Director of Nuclear Assurance, the Vice Chairman, or a duly appointed alternate.

The Director - Nuclear Safety, shall be the Vice Chairman and Secretary.

Collectively, the personnel appointed to NSB shall be competent to conduct reviews in the following areas:

a. Nuclear Power Plant Operations

b. Nuclear Engineering

c. Chemistry and Radiochemistry

d. Metallurgy

e. Instrumentation and Control

f. Radiological Safety

g. Mechanical and Electrical Engineering

h. Quality Assurance Practices An individual appointed to NSB may possess expertise in more than one of the above specialties. These individuals should, in general, have had professional experience in their specialty at or above the Senior Engineer level.

ALTERNATE MINEERS l

6.5.2.4 Alternate members may be appointed in writing by the Vice President -

Nuclear Operations to act in place of members during any legitimate and unavoidable absences. The qualifications of alternate members shall be similar to those of members.

! CONSULTANTS 6.5.2.5 Consultants shall be utilized as determined by the NSB Chairman or Vice Chairman to provide expert advice to the NSB. NSB members are not

( rastricted as to sources of technical input and may call for separate investigation from any competent source.

( 10-10 AmendmentNo.jkI,J',76 d l

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ADMINISTRATIVE CONTROLS Eb MEETING FREQUENCY 6.5.2.6 NSB shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once every six months thereafter.

QUORUM 6.5.2.7 A quorum of NSB shall consist of the Chairman and four (4) members.

(The Vice Chairman may be a voting member when not acting in the capacity of Chairman.) No more than a minority of the quorum shall have line responsibility for operation of the facility. It is the responsibility of the Chairman to ensure that the quorum convened for a meeting contains appropriately qualified members or has at its disposal consultants sufficient to carry out the review functions required by the meeting agenda.

6.5.2.8 RESPONSIBILITIES REVIEW 6.5.2.8.1 NSB shall be responsible for the review of:

a. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

b. All events which are required by regulations or Technical Specifications to be reported to NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and other violations (of applicable statues, codes, regulations, orders, Technical Specifications, license requirements or of internal procedures or instructions) having nuclear safety significance.

c. Issues of safety significance identified by the Plant Superintendent, the NSB Chairman, Director - Nuclear Safety or the PRC.

d. Proposed changes in the operating license or Appendix "A" Technical Specifications.

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e. The results of actions taken to correct deficiencies identified by the audit program specified in Specification 6.5.2.8.2 at least once every six months.

f. Safety evaluations for changes to procedures, equipment or I systems and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question.

! g. Maintain cognizance of PRC activities through ISEG attendance l at scheduled and special PRC meetings or through review of PRC meeting minutes.

10-11 y AmendmentNo.jd,jd,76 i

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