ML20070J612
| ML20070J612 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/10/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Toledo Edison Co, Cleveland Electric Illuminating Co |
| Shared Package | |
| ML20070J616 | List: |
| References | |
| NPF-03-A-051 NUDOCS 8212280071 | |
| Download: ML20070J612 (5) | |
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NUCLEAR REGULATORY COMMISSION E
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THE TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.51 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
f The application for amendment by the Toledo Edison Company)and A.
The Cleveland Electric Illuminating Company (the licensees dated November 25, 1901, 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 i-10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable. assurance (i) that the activities authorized by this amendment can be conducted without en' angering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; j
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; l
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements
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have been satisfied.
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Accordingly, Facility Operating License flo. NPF-3 is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachment to this license amendment:
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Revise paragraph 2.C.(2).t.o read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 51, 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 thc date of its issuance.
4 FOR THE NUCLEAR REGULATORY COMMISSI0tt J
F. Stolz, Chie erating Reactors ranch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 10,1932 l
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s ATTACHMENT TO LICENSE AMENDMENT NO. 51 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Ter.hnical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment nunber and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Pages 6-14 6-14a (new page)
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ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit
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a.
The facility shall be placed in at least HOT STANDBY within one hour, b.
The Safety Limit violation shall be reported to the Comission.
the Vice President. Nuclear and to the CNRB within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SRB. This report shall describe (1) applicable circumstances preceding the violation (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit V*olation Report shall be submitted to the Comission, the CNh3 and the Vice President, Nuclear within 14 days of the violation.
5.S DRCCE*"PE5 6.E.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:
a.
The applicable procedures recome..ded in Appendix "A" of Regulatory Guide 1.33, November,1972.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment, d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.'
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the SRB and approved by the Station Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures.
DAVIS-BESSE, UNIT 1 6-13 Amendment No. 9, 72,27
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6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered, b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactar Operator's License on the unit affected.
c.
The change is documented, reviewed by the SRB and approved by the Station Superintendent within 14 days of implementation.'.
6.8.4 The following programs shall be established, impiemented, and maintained:
a.
Primary Coolant Sources Outside Containment A pmgram to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include makeup, letdown, seal injection, seal return, low pressure injection, containment spray, high pressure injection, waste gas, primary sampling and reactor coolant drain systems. The program shall include the following:
(i) Preventive maintenance and/or periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less, b.
In-Plant Radiation Monitoring A program which will ensure the capability to accurately deter-mine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:
(1)
Training of personnel, (ii)
Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis eouip-ment.
DAVIS-BESSE, UtlIT 1 6-14 Amendment do.JTJC 51 y
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l ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the appropriate Regional Office unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testin shall be submitted following (1) receipt of an operating license. (2) g anendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.
6.9.1.2 The re; ort shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report.
6.9.1.3 Startup repcrts shall be submitted within (1) 90 days following completion of the startuo test program, (2) 90 days following resumption or commencement of commerical power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial O
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DAVIS-BESSE, UNIT 1 5-14a Amendment No,51 l
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