ML20056D089
| ML20056D089 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/12/1993 |
| From: | Bill Dean Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056D090 | List: |
| References | |
| NUDOCS 9308030343 | |
| Download: ML20056D089 (4) | |
Text
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S UNITED STATES
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i NUCLEAR REGULATORY COMMISSION l
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WASHINGTON D.C. 20555-0001 I
NORTHERN STATES POWER COMPANY l
DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86-j License No. DPR-22 l.
The Nuclear Regulatory Commission (the Commission) has found that-A.
The application for amendment by Northern States Power Company.(the
)
licensee) dated December 31, 1992, complies with the standards and i
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.
ThefacilitywilloperateinconformitywiththeappliEation,the provisions of the Act, and the rules and-regulations of the Commission; C.
There is reasonable assurance (1) 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 amendme'it is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
I 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 1
amended to read as follows:
a 930B030343 930712 PDR ADOCK 0500 3
. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 86, 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.
f FOR THE NUCLEAR REGULATORY COMMISSION
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a db-WilliamM. Dean,ActingDirector l
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Project Directorate 111-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 12, 1993 b
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ATTACHMENT TO LICENSE AMENDMENT NO. 86 FACILITY OPERATING LICENSE NO. DPR-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 77 77 e
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.3.0 1.IMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIR.tMENTS 2.' Reactivity margin - stuck control rods.
2.
Reactivity margin - stuck control rods.
(a)
Control rod drives which cannot be (a)
Each fully or partially withdrawn moved with control rod drive pressure operable control rod shall be exercised shall be considered inoperable. The at least one notch each week, directional control valves for inoperable control rods shall be (b)
IE power operation is continuing with one disarmed electrically and the rods fully or partially withdrawn control rod shall be in such positions that that is inoperable because it is stuck Specification 3.3.A.1 is met.
(i.e., cannot be moved by drive or_ scram pressure), each' fully or partially (b)
If a partially or fully withdrawn withdrawn operable control rod shall be control rod is stuck (i.e.,-cannot be exercised at least one notch every 24 moved with control rod drive or scram hour period. His surveillance is not pressure) the reactor shall be required if it has been confirmed that brought to a het shutdown condition control rod drive collet housing fatture within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Shutdown is not is not the cause of the immovable control required if it-is confirmed that rod.
control rod drive collet housing failur, is not the cause of the (c)
If power operation is continuing with two i m vable control rod.
or more non-fully inserted control rode that are inoperable, each operable fully (c)
If more than six non-fully inserted or partially withdrawn control rod shall control rods are inoperable during be exercised ac least one notch overy 24 power operation, the reactor shall be hour period.
brought to a hot shutdown condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
8.
Control Red withdrawal 1.
'Each centrol rod shall be coupled to its drive or completely inserted and the e
' directional control valves dtsarmed 5
electrically. H is requirement does not "g.
-apply when removing a control rod drive g
for inspection as long as the reactor is o
in the refueling mode.
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