ML20246D235
| ML20246D235 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/16/1989 |
| From: | Yandell L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246D222 | List: |
| References | |
| NUDOCS 8908250299 | |
| Download: ML20246D235 (10) | |
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CONSUMEP.S POWER COMPANY BIG ROCK POINT PLANT DOCQTNO.50-M5 AMENDMENT TO FACILIY OPERATING LICENSE
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Amendment No.100 i License Ho. DFR-E l
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Consumers Power Coinpany (the licensee) dated September 22, 1988 and supplemented on January 17, and April 12, 1989, complies with the standerds 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; B. The facility will operate in conformity with the application, the provisions of the At;t, and the rules and regulations of the
. Comm ssion; C. There is reasonable assurance (1) that the activities authorized f by tnis amendment can be condected without ender.pering the ' health and safety of the public; ar.d (ii) that such activities will be conducted in compliance with the Commission's' regulations; D. The issuarce of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; er d E. The issuance of this amendment is in accnrdance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have
'ceen satisfied.
- 2. Accordingly, the license is emended by changes to the Technical Specifications as indicated in the attachnent to this licrnse amendment and Paregraph 2.C.(2) of Facility Operating License No. OPR-6 is hereby amended to read as follows:
Technical Specifications
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The Technicel Specifications vntained in Appendir. A, as revised
) through Amendment No.100 , are hereby incorporated in the license. l The lice vee shall operate the facility in accordance with the Te:hnical Specifications.
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,, ' 3. . This-license amendment is effective as of. the' date of its issuance.
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, i ulLLlG [(tky$l-Lawrence A. Yandell, Acting Director D- Project Directorate III Division of Reactor Projects - III, IV,.V-
& Special: Projects Office of Nuclear Reactor Regulation
Attachment:
' Changes to the Technical i._ Specification?-
Date of Issuance: ~ August 16; 1989 .
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Li ATTACHMENT TO LICENSE AMENDMENT N0.'100 FACILITYOPERATINGLICPSENO._DPR-6 DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 10-3 10-3 10-8 10-8 10-9 10-9 10-10 10-10 10-11 10-11 10-12 10-12 10-13 10-13 L
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P , ADMINISTRATIVE CONTROLS-l -
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10-3 Amendment No. 63, Eh,100
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ADMINISTRATIVE CONTROLS !
' ALTERNATES -;
l 6.5.1.3 Alternate members of the PRC shall be appointed in writing by the PRC l Chairman to serve on a temporary basis. However, no more than two alternates shall participate as voting inembers at any ora time in PRC sctivities. l l
MEETING FRLOUENCY 6.5.1.4 The PRC shall ineet at least once per calendar rsonth 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 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 I thereto as determined by the Plant Superintendent to affect nuclear safety.
l l b. Peview of all proposed tests and experiments thct effect nuclear safety.
- c. Review of all proposed changes to Appendix "A" Technical Specifications
! d. Review of all preposed changes or modifications to plant systems er ecuipment that affect nuclear safety.
- e. investigation of all violations of the Technical Specifications.
(A report shall be prepared covering evaluation and recom;tendations to prevent recurrence and forwarded to the Vice President Nuclear Operations and to the Nuclear Safety Services Department.)
- f. Review of plant operations to detect potential nuclear safety hazards. {
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- g. Review of reportable events as defined in Section 1.2.14.
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- h. Performance of special reviews and investigations and reports thereof as requested by the Plant Superintendent or Nuclear Safety Services Department.
- 1. Review of the Site Emergency Plari and implementing procedures.
10-8 Amer.dment No. (5. O , 7li, if,100 E - - - _ -- - - - - - - - - a
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 of these reports to the Plant Superintendent and to the Nuclear Safety Services Department.
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PRC review may be performed through a routing of the item subject to the requirements of Specification 6.5.1.7.
AUTHORITY
- 6. 5.1.' 7 The PRC shall:
- a. Recommend in writing to the Plant Superintendent approval or disap-proval of items considered under Specifications 6.5.1.6.a. through
- d. above,
- b. Render Terminations in writing 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 j-any disagreement between the PRC and the Plant Superintendent; however, the Plant Superintendent shall have responsibility for the resolution of such disagreements pursuant to Specification 6.1.1 above.
The PRC Chairman may recommend to the Plant Superintendent approval of those items identified in Specifications 6.5.1.6.a. through d. above based on a routing review provided the following conditions are met: (1) at lea:,t 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 comrents; and (3) if the PRC Chairman determines-that the comments are significant, the item (including comments and resolu-tions) 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 Superintendent overrides the recommenda-tions of the PRC; or (3) a proposed change to the Technical Specifications involves a safety limit, a limiting safety system setting or a limiting conW tion for operati?n; or (4) the item was a reportable event as defined in 10 CFR 50.73.
RECORDS
- 6. 5.1. 8 The PRC shall n,aintain written minutes of each PRC meeting and shall g provide copies to the NSSit 20-9 Amendment No. 46, 63, 71 , 77,100 i
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6.5.2. NUCLEAR' SAFETY SERVICES' DEPARTMENT (NSSD) l-FUNCTION i- 6.5.2.-1 The Nuclear Safety Services Department shall function to provide independent review of activities in the areas of:
-a. Nuclear Power Plant Operation
- b. Nuclear. Engineering
- c. Chemistry and Radiochemistry {
- d. -Metallurgy
- e. Nondestructive-Testing
- f. Instrumentation and Control 1
- g. -Radiological _ Safety
- h. Mechanical and Electrical Engineering
- i. Administrative Controls and Quality Assurance. Practices
- j. Emergency Planning
- k. Training COMPOSITION 6.5.2.2 The NSSD shall consist of a full-time staff. appointed by and reporting to the Vice President - Nuclear Operations. NSSD staff shall have no direct responsibility for activities subject to their review.
The NSSD staff,shall meet or exceed the qualifications described-in Section 4.7 of ANSI /ANS 3.1'-:1987.
CONSULTANTS 6.5.2.3 If sufficient expertise is not available within NSSD'for. review of particular issues, tue NSSD shall have the authority to utilize consultants or other qualified organizations for expert advice.
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6.5.2.4' RESPONSIBILITIES REVIEd 6.5.2.4.1 NSSD shall review:
- a. The safety evaluations for: 1) changes to procedures, equipment or systems, and 2) tests or experiments completed under the provisions of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.
10-10 Amendment No. 53, 7Z , 76, 7/// ,
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ADMINISTRATIVE CONTROLS _ q 6.5.2.4 RESPONSIBILITIES (Continued)
REVIEW 6.5.2.4.1 (Continued)
- b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
- c. Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
- d. Proposed changes to Technical Specifications or the Operating License.
- e. Violations of codes, regulations, orders Technical Specifications, license requirements or internal procedures or instructions having nuclear safety significance,
- f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
- g. All REPORTABLE EVENTS having nuclear safety significance.
- h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems or components that could affect nuclear safety.
l i. Reports and meeting minutes of the Plant Review Committee.
AUDITS l ti . 5. 2. 4. 2 Audits of operational nuclear safety-related facility activities shall be performed under the cognizance of NSSD. These audits shall encompass: <
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- a. The conformance of plant operation to provisions 4 contained within the Technical Specifications and i applicable license conditions at least once per 1 12 months.
- b. The performance, training and qualifications of the I i entire facility staff at least once per 12 months.
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1 10-11 Amendment No. #E. 63, 76, 25,100 L --_ - - - .
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- c ADMINISTRATIVE CONTROLS AUDITS 6.5.P.4.2 (Continued)-
- c. The performance of activities required by the Quality Assurance u 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.
- d. .The Site.fmergency Plan and implementing procedures at-least once
.per'12 months.' '
L e. The. Site' Emergency Plan and implementing procedures (as required by the Site Security Plan) at least once per 12 months.
- f. Any other area'of plant operation considered appropriate by NSSD or the. Vice President - Nuclear Operations.
- g. 'The Plant' Fire Protection Program and implementing procedures at least once per 24 months.
- h. An independent fire protection and loss prevention inspection and audit shall t,e cerformed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
- i. 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.
j .- The Radiological Environmental Monitoring Program and the results thereof.at least once per 12 months.
- k. The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.
L 1. The Process Control Program and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.
Audit reports encompassed by 6.5.2.4.2 above shall be forwarded to the NSSD, and management positions responsible for the areas audited within thirty (30) days after completion of the audit.
6.5.2.4.3 NSSD review of the subjects in Specifications 6.5.2.4.1 and 6.5.2.4.2 shall be carried out by an assigned lead reviewer selected on the basic of his technical expertise relative to the subject being reviewed. A second level review shall also be performed. If the lead reviewer or second-level reviewer determines the need for interdisciplinary review, additional reviewers shall be assigned. ,
10-12 Amendment No. 58, 63, //,100
ADMINISTRATIVE CONTROLS-6.5.2.5 The NSSD shall report to and advise the Vice President - Nuclear Operations of significant findings associated with those areas of responsibility specified in Section 6.5.2.4.1 and Section 6.5.2.4.2 RECORDS 6.5.2.6 Records of NSSD activities shall be maintained. Reports shall be prepared and distributed as indicated below:
- 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 monthly.
- 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.
4 6.6 (Deleted) 6.7 SAFETY LIM.IT 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)(i)(A).
- b. lhe safety lim'it violation shall be reported within I hour to the Commission in accordance with 20 CFR 50.36, as well as to the Vice President - Nuclear Operations and to the NSSD. l
- c. A report shall be prepared in accordance with 10 CFR 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 sebmitted within 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. l j
- 6. 8 PROCEDURES l
6.8.1 Written procedures shall be established, implemented and maintained for 1 all structures, systems, components and safety actions defined in the Big Rock Point Quality List. These procedures shall meet or exceed the requirements of ANSJ N18.7, as endorsed by 09C-2A. ,
3.8.2 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
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J 10-13 Amendment No. 46, 63,100 I
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