ML20065L433
| ML20065L433 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/15/1994 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065L439 | List: |
| References | |
| NUDOCS 9404210074 | |
| Download: ML20065L433 (5) | |
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' UNITED STATES
- jf iR,f j NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D.C. 20E0001
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s, NORTHERN STATES ~ POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AtjENOMENT TO FACILITY OPERATING LICENSE Amendment No. 87 a
License No. DPR-22 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States. Power Company,(the licensee). dated July 7,1993, 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 ccmpliance 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 Specifications 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:
C 9404210074 940415 PDR ADOCK 05000263 P
PDR c
f Technical Specifications The Technical Specifications contained in Appendix A, as revised through l
Amendment No.
87, 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 issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 8 ~L Ledyard B. Marsh, Director Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 15, 1994 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE NO. OPR-22 DOCKET NO. 50-263 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 vertical lines indicating the areas of change.
REMOVE INSERT 126 126 126a i
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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS D.
Coolant Leakage D.
Coolant Leakage 1.
Any time irradiated fuel is in the reactor 1.
Any time irradiated fuel is in the reactor vessel and coolant temperature is above 212 F, vessel and coolant temperature is above reactor coolant system leakage, based on sump 212 F, the following surveillance program monitoring, shall be limited to:
shall be carried out:
- a. 5 gpm Unidentified Leakage Unidentified and Identified Leakage a.
- b. 2 gpm increase in Unidentified rates shall be recorded once per shift Leakage within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period not to exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using primary
- c. 20 gpm Identified Leakage containment floor and equipment drain
- d. no pressure boundary leakage sump monitoring equipment.
2.
With reactor coolant system leakage greater than 2.
The reactor coolant system leakage 3.6.D.1.a or 3.6.D.l.c above, reduce the leakage detection systems shall be demonstrated rate to within acceptable limits within four OPERABLE by:
hours or initiate an orderly shutdown of the reactor and reduce reactor water temperature to a.
Primary containment atmosphere less than 212*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
particulate monitoring systems-performance of a sensor check at least 3.
With an increase in Unidentified Leakage in once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a channel excess of the rate specified in 3.6.D.l.b, functional test at least monthly and a identify the source of increased leakage within channel calibration at least once per four hours or initiate an orderly shutdown of
- cycle, the reactor and reduce reactor water temperature F
to less than 212 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
Primary containment sump leakage measurement system-performance of a 4.
If any Pressure Boundary Leakage is detected sensor check at least once per shift when the corrective actions outlined in 3.6.D.2 not to exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and a channel and 3.6.D.3 above are taken, initiate an orderly calibration test at least once per F
shutdown of the reactor and reduce reactor water cycle.
temperature to less than 212 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
U
}C 3.6/4.6 126
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMEhTS d
5.
Any time irradiated fuel is in the reactor vessel and reactor water temperature is above 212 F at least one of the leakage measurement instruments associated with each sump shall be operable.
If no leak rate measurement instru-ments associated with a sump are operable, then;
- a. Perform manual leak rate measurements once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and restore a measurement instrument to operable status within 30 days.
- b. Otherwise, initiate an orderly shutdown of the reactor and reduce reactor water temperature to less than 212 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
6.
Any time irradiated fuel Ls in the reactor vessel and reactor water temperature is above 212'F the drywell particulate radioactivity monitoring system shall be operable.
If the drywell particulate radioactivity monitoring system is not operable, then:
- a. Analyze grab samples of the primary containment atmosphere once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
sg
- b. Otherwise, initiate an orderly shutdown of g
the reactor and reduce reactor water r+
temperature to less than 212 F within 24 r
hours.
g 3.6/4.6 126a i
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