ML20012B706
| ML20012B706 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 02/27/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012B707 | List: |
| References | |
| NUDOCS 9003160141 | |
| Download: ML20012B706 (5) | |
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UNITED STATES E
>82 NUCLEAR REGULATORY COMMISSION
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s NEBRASKA PUBLIC POWER DISTRICT
. DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.131 License No. DPR-46 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Nebraska Public Power District (thelicensee)datedflarch 20, 1989 as supplemented June 6, 1989, complies with the standards and requirements of the Atomic Energy-Act of -1954', as amended (the Act), and the Comission's rules and regula-tions set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended,-the provisions of the Act, and the rules _and regulations of the Comission; C.
There is-reasonable assurance:
(1)that'theactivitiesauthorized by-this amendment can be conducted without endangering the health and safety of.the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in.accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9003160141 900227 PDR ADOCK 05000298 P-PDC
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2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and 1
Paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
2.
_ Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.131, are hereby incorporated in the license'.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
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[vFrederick J. Hebdon, Director u
Project Directorate IV
-Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
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Char.ges to the Technical
. Specifications Date of Issuance:- February 27, 1990
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l ATTACHMENT TO LICENSE AMENDMENT N0_.131__
FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 1
Replace trie following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change, j
Pages 219 219a j
236 deleted l
237 deleted I.
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.6. 0 -
ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION
-6.1.1 Responsibilitv The Division Manager of Nuclear Operations shall have the over all fulltime onsite responsibility for the safe operation of the Cooper Nuclear Station.
During periods when the Division Manager of Nuclear Operations is unavailable, he may delegate his responsibility to one of the managers in the Nuclear Operations Division, i
6.1. 2 :
Offsite and Onsite Orrani-ations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.
The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
A.
Lines of authority, responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating org nization e
positions.
These relationshi'ps shall be documented and updated, as appropriate, in the form of organization charts,. functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
l These requirements shall be documented in the USAR.
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B.
The Division Manager of Nuclear Operations shall be responsible for-l.
overall unit safe operation and shall have control over those onsite 1
activities necessary for safe operatlon and maintenance of the plant'.
L C.
The Nuclear Power Group Manager shall have corporate responsibility for L
overall plant nuclear safety and shall take any measures needed to ensure i
acceptable performance of e.he staff in operating,. maintaining, and providing technical support t.
the plant to ensure nuclear safet.y.-
l D.
'The individuals who train the o,)erating staff and those who ca.rry out health physics and quality. at surance functions may report to the appropriate onsite manager; Iowever, -they shall have sufficient organizational freedom to ensure their independence from operating pressures.
i 6.1. 3..
Plant Staff - Shift Comolement The shift complement at the station shall at all times meet the following requirementti. Note: Higher grade licensed operators may take the place of.
lower grade licensed or unlicensed operators.
A.
A licensed senior reactor operator (SRO) shall be present at the station at all times when there is any fuel in the reactor.
B.
A licensed reactor operator shall be in the control room at all times when there is any fuel in the reactor.
C.
Two licensed reactor operators shall be in the control room during all startup, shutdown and other periods involving significant planned control rod manipulations. A licensed SRO shall either be in the Control Room or immediately available to the Control Room during such periods.
Amendment No. 65,82,85,99, 131
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A licensed' senior reactor operator (SRO) with no other concurrent duties c
shall be directly in charge of any refueling operation, or alteration of the reactor core.
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A licensed reactor operator (RO) with no other concurrent duties shall-be directly in charge of operations involving the handling of irradiated-fuel other than refueling or reactor core alteration operations.
E.
An individual who has been trained and qualified in health physics techniques shall be on site at all times that fuel is on site.
F.
Minimum crew size during reactor operation shall consist of four licensed reactor operators (two of whom shall be licensed SRO) and three unlicensed operators.
Minimum crew size during reactor cold shutdown conditions shall consist of two licensed reactor operators (one of whom shall be licensed SRO) and one unlicensed operator, In the event. that any member of a minimum shif t crew is absent or incapacitated due to illness or injury a qualified replacement shall be designated to report onsite within two hours.
G.
A Fire Brigade of at least 5 members shall be maintained at all times, This excludes the 3 members of the minimum shif t crew necessary for safe shutdowns,.and other personnel required for other essential functions during a. fire emergency.
Three fire Brigade members shall be from the Operations Department and 2 support members may be from other departments inclusive of Security personnel.
Fire Brigade composition may-be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the' Fire Brigade to within the minimum requirements.
H.
The. Operations Supervisor, Shif t Supervisor and Control Room Supervisor shall hold a senior. reactor operator license. The Unit Operators shall hold, at a minimum, a reactor operator license.
6.1.4 Plant Staff Oualifications The minimum qualifications, training, replacement training, and retraining of plant personnel at the time of fuel loading or appointment to the active position shall meet the requirements as described in the American National Standards. Institute N 18.1 1971, " Selection and Training'of Personnel-for t
Nuclear Power Plants". The Chemistry and Health Physics Supervisor shall meet or exceed the qualifications of Regulatory Guide 1.8, Sept 1975; personnel qualification equivalency as stated in the Regulatory Guide may be proposed in selected-cases. The minimum frequency of the retraining program shall be l
every two years.
The training program shall be under the direction of the Training Manager.
A.
A training program for the fire brigade -will be maintained under the direction of ' the Training Manager and shall meet or exceed the requirements of Section 27 of the NFPA Code 1976, except for Fire Brigade training sessions which shall be held at least quarterly.
The training program requirements will be provided by a qualified fire protection engineer.
-Amendment No. 80,82.85, 131
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