ML20151R911
| ML20151R911 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/18/1988 |
| From: | Virgilio M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151R916 | List: |
| References | |
| NUDOCS 8804280129 | |
| Download: ML20151R911 (8) | |
Text
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E(fa aro vy jo UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
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W AsHINGTON, D. C. 20655 NORTHERNSTATESPOWERCOM1ANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING l'LANT, UNIT NO.1 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. OPR-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated August 14, 1987, as supplemented August 27, 1987, January 4 and February 10, 1988, 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. DPR-42 is hereby amended to read as follows:
8804280129 880418 ADOCK0500g2 DR
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2-Technical Specifications The Technical Specifications contained in Appendix A, as revised i
through Amendment No. 82, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
4 3.
This license amendment is effective as of the date of its issuance, i
FOR THE NUCLEAR REGULATORY COMISSION i
t/ %
Martin J. Virgilio, Director Project Directorate III-1 i
Division of Reactor Projects - III, IV, V
& Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: April 18, 1988 i
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NUCLEAR REGULATORY COMMISSION 3
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,o NORTHERN STATES POWER COMPANY DOCKET NO. 50-306, PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NO. 2 KIEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No. DPR-60 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated August 14, 1987, as supplemented August 27, 1987, January 4 and February 10, 1988, 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 Comission; 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,ecurity or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part $1 of the Commission's regulations and all applicable requirements have i
been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-l tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
r 2-t Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 75, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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.i~ Martin J. Virgilio, Director Project Directorate III-1 Division of Reactor Projects - III, IV, V
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& Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: April 18, 1988 l
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l ATTACHMENT TO LICENSE AMENCFENTS NOS. 82 AND 75 l
FACILITY OPERATING LICENSES NOS. OPR-42 AND DPR-60 1
DOCKETS NOS. 50-282 AND 50-306 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
i REMOVE INSERT TS.6.1-2 TS.6.1-2 Figure TS.6.1-2 Figure TS.6.1-2 TS.6.5-4 TS 6.5-4 I
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TS.6.%-3 D. Each member of the plant staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positions, except for (1) the Superintendent Radiation Protection who shall meet or exceed the qualifi-cations of Regulatory Guide 1.8, September 1975, (2) the Shift Technical i
Advisor who shall have a bachelors degree or equivalent in a scientific or l
engineering discipline with specific training in plant design, and re-sponso and analysis of M.a plant for en.nsion*:s and accidener, and (3) the General Superintendent Plant Operations who shall meet the requirements of ANSI N18.1 1971, except that NRC license requirement. are as specified in FIGURE TS.6.1-2.
The training program shall be under the direction of a designated member of Northern States Powar management.
~
E. A training program far the fire brigade shall be maintained under the direction of a designaced member of Northern States Powbr' management.
This program shall meet the requirements of Section 27 of the NFPA Code -
1976 with the exception of training scheduling. Fire brigade training shall be scheduled as set forth in the training program, F. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions; e.g.,
senior reactor operators, reactor operators, health physicists, auxiliary,
operators, and key maintenance personnel.
Procedures shall include the following provisions:
- 1. Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day, 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> week while the plant is operating.
- However, in the event that unforeseen problems require. substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followe'd:
a.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time, b.
Overtime should be limited for all nuclear plant staff personnel so that total work time does not exceed 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> in any seven day period, all excluding shift turnover time.
Individuals should not be required to work more than 15 consecutive days without two consecutive days off.
1 c.
A break of at least eight hours including shift turnover time should be allowed between work periods.
d.
Except during extended shutdown pa.iods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
1 e.
Shift Technical Advisor (STA) and Shift Emergency Coordinator (SEC) on site rest time periods shall not be considered as hours worked when determining the total work time for which the above limitations anply.
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P ^airie Island Unit 1 Amendment No. Id, M. H, 82 Prairie Island Unit 2 Amendment No. E E 38, 75 1
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TS.6.5 4 E. Offsite Dose Calculation Manual (ODCM)
The ODCM shall be approved by the Commission prior to initial i=plementation. Changes to the ODCM shall satisfy the following requirements:
- 1. Shall be submitted to the Commission with the Semi Annual Radio.
active Effluent Report for the period in which the change (s) were made effective.
This submittal shall contain:
- a. sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.
Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with a revision date, together with appropriate analyses or evaluations justifying the change (s),
- b. a determination that the change will not reduce the accuracy 1
or reliability of dose calculations or setpoint determinations; and documentation of the fact that the change has been reviewed c.
and found acceptable by the Operations Committee.
- 2. Shall become effective upon review and acceptance by the Operations Committee.
F. Security Procedures shall be developed to implement the requirements of the Security Plan and the Security Contingency Plan.. These implement-in procedures, with'the exception of'those non-safety related procedures which govern work activities exclusively appucable to or performed by security personnel, shall be reviewed by the Opera.
tions Committee and approved by a member of plant management designated by the Plant Manager.
Security procedures not rev12wed by the Operations Committee shall be reviewed and approved by the l
Supervisor, Security and Services, G. Temporary Changes to Procedures Temporary changes to Operations Committee reviewed procedures described in A. 5 C, D, E, and F above, which do not change the intent of the original procedure may be made with the concurrence i
of two members of the unit' management staff, at least one of whom holds a Senior Reactor Operator License. Such changes shall be i
documented, reviewed by the Operations Committee, and approved by a j
member of plant management designated by the Plant Manager within
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one month.
1 i
l Temporary changes to security procedures not reviewed by the 1
Operations Committee shall be reviewed by two (2) individuals knowledgeable in the area affected by the procedure, j
i Prairie Island Unit 1 Amendment No. 37, 80, 82 Prairie Island Unit 2 Amendment No. 33, 73,75
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