ML20210P998
| ML20210P998 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/25/1997 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210Q002 | List: |
| References | |
| NUDOCS 9708280046 | |
| Download: ML20210P998 (10) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION t.
WASHINGTON, D.C. seseH001
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.177 License No. DPR 24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated April 14,1997, as supplemented on August 11,1997, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commiss;on; 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 (ii) that such activities will be conducted in compliance 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 issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have bean satisfed.
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9708280046 970025 PUR ADOCK 05000266 P
2 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR 24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.177, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION d
M 1/ G Linda L. Gundrum, Project Manager Project Directorate lil-1 Division of Reactor Projects - Illny Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
August 25, 1997
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NUCLEAR REGULATORY COMMISSION
\\,...../g WASHINGTON, D.C. 30006-0001 WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 6MENDMENT TO FACILITY OPERATING LICENSE Amendment No.181 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated April 14,1997, as supplemented on August 11,1997, 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; 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 (ii) that such activities will be conducted in compliance 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 issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
3 2
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-27 is hereby amended to read as follows:
B.
Itchnical Soecifications
^
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.181 are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION O
Mv Linda L. Gundrum, Project Manager Project Directorate Ill-1 Division of Reactor Projects. Ill/lV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
August 25, 1997 i
i
ATTACHMENT TO LICENSE AMENDMENT NOS.177AND 181 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR 27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identifed below and inserting the enclosed pages, The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
BEMQVE INSERT 15.6.2 2 15.6.2-2 15.6.5 3a 15.6.5-3a 15.6.6-1 15.6.6-1 15.6.7 1 15.6.7-1 15.7.8-1 15.7.8-1 I
f 15.6 ADMINISTRATIVE CONTROLS (Continued) 15.6.2 ORGANIZATION (Continued) 15.6.2.1 (Continued) c.
The Chief Nuclear Officer shall be an officer of the Company and l
I shall have corporate responsibility for overall p; ant nuclear safety and shall take any measures needed to ensure acceptable 4
performance of the staff in operating, maintaining, and providing i
technical support to the plant to ensure nuclear safety, d.
The individuals who carry out health physics and quality assurance functions may report to the appropriate onsite manager, however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
FACILITY STAFF 1
15.6.2.2 Facility staffing shall be subject to the following requirements:
a.
Each on duty shift shall normally be composed of at least the minimum shift crew composition (for all modes except with a unit defueled) as follows:**
1.
Shlft Superintendent (SRO)* - one per shift 2.
Duty Technical Advisor - one per shift l
3.
Operating Supervisor (SRO)* - one per shift 4.
Operator (RO)* - two per shift for one unit operation
- three per shift for two unit operation 5.
Operator - two per shift for one unit operation
- three per shift for two unit operation i
6.
The Duty Technical Advisor is located on-site on 10 minute call to the control room.
b.
At least one licensed Operator shall be in the control room when fuel -
is in either reactor.
Unit 1 - Amendment No. 438,177 Unit 2 - Amendment No. 433,181 15.6.2-2
15.6.5 REVIEW AND AUDIT (Continued) 15.6.5.1 Manamer's Suoervisory Stat [(Continued) c.
Make recommendations as to whether or not proposals considered by the Staff involve unreviewed safety questions.
d.
Review and approve the contents of a report for each reportable event. Copies of a!! such reports shall be submitted to the Chief Nuclear ONicer and the Chairman l
of the ON4tte Review Committee, e.
Written minutes of each meeting shall be reviewed by staN members and copies shall be provided to the Chief Nuclear Officer and Chairman of the On Site Review Committee.
Unit 1 - Amendment No. 444, 177 Unit 2 - Amendment No. 450, 181 15.6.5-3a
o 15.6.6 REPORTABLE EVENT ACTION SJ2fMJGali9D The following action shall be taken for Reportable Events:
A.
The Commission shall be notified and a report submitted pursuant to the requirements
' of Section 50.73 to 10 CFR Part 50, and B.
Each Reportable Event shall be reviewed by the Manager's Supervisory Staff (MSS) and submitted to the ON Site Review Committee (OSRC) and the Chief Nuclear
- Officer, i
i Unit 1 - Amendment No. 86,177 Unit 2 - Amendment No. 80,181 15.6.6-1
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15.6.7 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED Soecification A.
If a safety limit is exceeded, the affected reactor shall be shut down and reactor operation shall not be resumed until approval is received from the NRC.
B.
An immediate report shall be made to the Chief Nuclear Officer and the Chairman of l
the Off-She Review Committee.
C.
The Chief Nuclear Officer shall report the circumstances to the NRC.
l D.
A Safety Limit Violation Report including a complete analysis of the circumstances leading to and resulting from the occurrence, effects upon facility components, systems or structures, together with recommendations to prevent a recurrence, shall be prepared. This report shall be submitted tJ the Chief Nuclear Officer and the l
Chairman of the Off-Site Review Committee. A Safety Limit Violation Report shall be submitted to the NRC by the Chief Nuclear Officer within 10 days of the occurrence.
l Unit 1 - Amendment No. 94,177 Unit 2 - Amendment No. 96,181 15.6.7-1
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15.7.8 ADMINISTRATIVE CONTROLS 15.7.8.1 Duties of the Manaaers Supervisory Staff N duties of the Manager's Supervisory Staff with respect to these radidgical emuent technical specifications are listed in Spec.fication 15.6.5.1.8 at items J. and k.-
15.7.8.2 Augg A.
An audit of the activities encompassed by the Offsite Dose Calculation Manual and the Process Control Program and its implementing procedures shall be performed utilizing either offsite licensee personnel or a consulting firm.
B.
An audit of the radiological environmental monitoring program and the results thereof shall be performed utilizing either offsite licensee personnel or a qualified consulting firm.
C.
The results of the audits in A and B above shall be transmitted to the Chief Nuclear Officer and the Chairman of the Offsite Review.
l Committee.
15.7.8.3 Plant Ooeratina Procedures The ODCM and the PCP shall be established and maintained in accordance with the provisions of specification 15.6.8. Effluent and environmental monitoring shall be addressed in the Quality Assurance Program.
15.7.8.4 RETS Reoortina Recuirements The following written reports shall be submitted to the Administrator, U. S.
Nuclear Regulatory Commission Region ill with a copy to the Director, Office of Inspection and Enforcement, USNRC, Washington, D.C. 20555 within the time periods specified.
A.
ADDMal.MSDiledQE.BAGQ!!
A report covering the operation of P8NP for the previous twelve (12) month period, or fraction thereof, ending on December 31, shall be submitted by May 1 of each year containingi 1.
Information relative to the quantities of liquid, gaseous and solid radioactive effluents released from the facility, and effluent volumes used in maintaining the releases
- Unit 1 - Amendment No. 443,177 Unit 2 - Amendment No. 446,181 15.7.8-1
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