ML20042D211
| ML20042D211 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/27/1989 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20042D212 | List: |
| References | |
| NUDOCS 9001080023 | |
| Download: ML20042D211 (6) | |
Text
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04 NUCLEAR REGULATORY COMMISSION a-o 5
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i TOLEDO. EDISON COMPANY ME THE.CLEVELAWD ELECTRIC.1LLUMINATING. COMPANY DOCKET.N0. 50 346 DAVIS-BESSE. NUCLEAR. POWER. STATION.. UNIT.NO. 1 AMENDMENT.TO. FACILITY.0PERATING. LICENSE Amendment No.
142 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the T dado Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated October 9, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as-amended.(the Act), and the Comission'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 Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized 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 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes te the Technical Specifications as indicated in the attachment tt: this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
9001080023 891227 PDR ADOCK 05000346 P
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-2 (a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.142, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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3h w/f pa John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V, & Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 27, 1989
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1 ATTACHMENT TO LICENSE AMENDMENT NO. 142
< FACILIT,V OPERATING 11.1 CENSE ~ NO. NPF-3 c.
DOCKET NO. 50-346
- Replace the following pages of the Appendix "A" Technical. Specifications with the= attached pages. The revised pages are identified by amendment number and contain' vertical lines indicating the area of change. The corresponding overleaf pages are also provided to raintain document completeness.
Remove Insert m
6-la 6-la 6-5 6-5 6-6 6-6
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6.0 ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF a.
Each on duty shift shall be composed of at least the minimum shif t crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall b'e in the control panel area when fuel is in the reactor, c.
At least two licensed Operators, one of which has a Senior-1 Reactor Operator license, shall be present in the control room while in MODES 1, 2, 3, or 4.
d.
An -individual qualified in radiation protection procedures shall-be on site when fuel is in the reactor #.
e.
.All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respor.si-bilities during this operation.
f.
A site Fire Brigade of at least 5 members shall be maintained onsite at all times #.
The Fire Brigade shall not include 3 merbers of the minimum shif t crew necessary for safe shutdown.
of the unit and any personnel required for other essential functions during a fire emergency.
9 The Manager-Plant Operations shall either hold or have held a senior reactor operator's license on a pressurized water reactor.
The Operations Superintendent shall hold a senior reactor operator license for-the Davis-Besse Nuclear Power Station.
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- The individual qualified in radiation protection procedures and the 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, provided immediate action is taken to fill the required positions.
DAVIS-BESSE, UNIT 1 6-la Amendment No. 9,JB,9E,JJE,J35,J37 (next page is 6-2) 142
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUAllFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Radiological Controls Superintendent who shall meet or exceed the qualification; of Regulatory Guide 1.8, September 1975, (2) the Shift j
Technici.1 Advisor who shall have a bachelor's degree or. equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents, and (3) the Manager - Plant Operations whose requirement for a senior reactor operator license is as stated in Specification 6.2.2.g.
- 6. 4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Training Director and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and of 10 CFR 55.59.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Nuclear Training Director.
6' 5 REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD (SRB)
FUNCTION' 6.5.1.1 The Station Review Board (SRB) shall function to advise the
! Plant Manager on all matters related to nuclear safety.
1 DAVIS-BESSE, UNIT 1 6-5 Amendment No. 9,37,ES,9E,JpE,J3E,J3E, 142
(
r ADMINISTRATIVE CONTROLS COMPOSITION
- 6. 5.1. 2 The Station Review Board shall be composed of the:
Chairman:
Station Review Board Chairman
- Member:
Manager - Plant Operations l
N Member:
Assistant Plant Manager, Maintenance Member:
Technical Support Manager Member:
Radiological Controls Superintendent Member:
Operations Engineering Supervisor (Plant)
Member:
An Engineering Director Member:
Quality Assurance Supervisor Member:
OperationsSuperintendent(Plant)
- Designated in writing by the Plant Manager.
The Chairman will be drawn from SRB members.
ALTERNATES C.5.1.3 All alternate members shall be appointed in writing by the SRB Chairman; however, no more than two alternates shall participate as voting members in SRB activities at any one time.
i MEETING FREQUENCY 6.5.1.4 The SRB shall meet at least once per calendar month and as convened by the SRB Chairman or his designated alternate.
QUORUM i
6.5.1.5 A quorum of the SRB shall consist of the Chairman or his designated alternate and four members including alternates.
RESPONSIBILITIES 6.3.1.6 The Station Review Board shall be responsible for:
Review of plant administrative procedures and changes theretc.
a.
b.
Review of the safety avaluation for 1) procedures, 2) changes to procedures, equipment or systems, and 3) tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions do not constitute an unreviewed safety question.
Review of proposed procedures and changes tc pracedures and c.
-equipment determined to involve an unreviewed safety question as defined in 10 CFR 50.59.
DAVIS-BESSE, UNIT 1 6-6 Amendment No. J2,76,9E,J09,J3E, 433, 142
j ADMINISTRATIVE CO{4TROLS 1
f COMPOSITION 6.5. l'.2- -The Stat S.~ Review Board shall be ' compos.rd of the:
Chai rman:
Station Review Board Chairman
- Member:
Manager - Plant Operations l~
Member:
Assistant Plant Manager, Maintenance-Member:
Technical Support Manager Member:
Radiological Controls Superintendent Member:
Operations Engineering Supervisor (Plant)
Member:
An Engineering Director
. Member:
Quality Assurance Supervisor Member:
Operations Superintendent (Plant)
- Designated in writing by the Plant Nnager. The Chairman :4111 be' drawn from SRB members.
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SRB Chairman;;however, no more than two alternates shall participate as voting members in SRB activities at any one time.
MEETING FREQUENCY 6.5.1.4 The SRB shall meet at least once per calendar month and es-convened-by the SRB Chairman or his designated alternate.
QUORUM p
- 6. 5.1. 5 A quorum of the SRB shall consist of the Chairman or his designated alternate and four members including alternates.
RESPONSIBILITIES 6.5 1.6 The Station Review Board shall be responsible for:
a.
Review of. plant administrative procedures and changes thereto.
b.
Review of the safety evaluation for 1) procedures, 2) changes to procedures, equipment or systems, and 3) tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions do not constitute er. unreviewed safety question, c.
Review of proposed procedures and changes to procedures and equipment determined to involve an unreviewed safety question as defined in 10 CFR 50.59.
DAVIS-BESSE, UNIT 1 6-6 Amendment No. U,75,,95,W,W, gg, 142
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