ML20067C227
| ML20067C227 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 11/30/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Northern States Power Co |
| Shared Package | |
| ML20067C231 | List: |
| References | |
| DPR-22-A-012 NUDOCS 8212090010 | |
| Download: ML20067C227 (4) | |
Text
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UNITED STATES
'g NUCLEAR REGULATORY COMMISSION
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.12 License No. DPR-22 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company.(the licensee) dateo September 24, 1982 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 Comission's regulations; D.
The issuance o'f this amendment will not be inimical to the comon 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 to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No. DPR-22 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No.12 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
r212090010 821130 PDR ADOCK 05000263 P
2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY Com ISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 30, 1982 8
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1 ATTACHMENT TO LICENSE AMENDMENT NO.12 FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Revise the Appendix A Technical Specifications by removing page 27 and inserting revised page 27.
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3.0 1.IMITING CONDITIONS FOR OPERATION 4.0 SURVEII.1ANCE REQUIREMENTS g.
Upon discovery that the requirements for the g.
Once per day durlag power operation the number of operable or operating trip systema HELPD (Masimum Fract ion'of Lietting or inst rument channels are not satistled, Fower Denalty) shall be checked and the aci ton shall be initiated tot scree setting given by the equation in Specification 2.3.A shall be adjusted if I.
Satisfy the minimum requirements by necessary, placing appropriate devices, channels, or trip systems in the tripped condition, or 2.
Place and maint ain the plant under the '
3 specified required conditions using normal operating procedures C. RPS Power Monitoring System C.
RPS Power Honitoring System
- 1. Except as specified below, both channeta
- 1. Instrument Functional Tests of of the power monitoring system for the each RPS power monitoring channel HG set or alternate source supplying shall be performed at least once each reactor protection system bus every six months.
shall be operable with the following setpoints:
- 2. At least once each Operating Cycle Time Delay an Instrument Calibration of each
- a. Over-voltage
$128 VAC 4100 milliseconds RFS power monitocing channel shall
- b. Un, der-voltage 2104 VAC K100 milliseconds be performed to verify over-voltage,
- c. Under-frequency 257 HZ
$100 milliseconds under-voltage, and under-frequency setpoints.
- 2. With one RPS electric power monitoring channels for the HG set or alternate source supplying each reactor protection system bus inoperable, restore the inoperable channel to Operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS HG set or alternate power supply from service.
- 3. With both RPS electric power monitoring channels for the MG set or alternate source supplying each reactor protection system bus inoperable, restore at least'one to Operable status within 30 minutes or remove the associated RPS HG set or alternate power supply fram service.
3.1/4.1 27 Admendment 12
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