ML20205C145

Amend 105 to License DPR-22,revising TSs for CST Low Level Suction Transfer Setpoint for HPCI & RCIC Sys to Allow Removing 1 CST from Svc for Maint

ML20205C145
Person / Time
Site:	Monticello
Issue date:	03/19/1999
From:	Lyon C NRC (Affiliation Not Assigned)
To:
Shared Package
ML20205C150	List: ML20205C145 ML20205C165
References
NUDOCS 9904010085
Download: ML20205C145 (6)

Text

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[a rai gk UNITED STATES g

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NUCLEAR REGULATORY COMMISSION WASMINGTON, D.C. 3086Ho01

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NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 105 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 November 25,1997, as supplemented September 25 and November 11,1998, and January 28,1999, 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; P.

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; i

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 i

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.

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 Fac;.ity Operating License No. DPR-22 is hereby amended to read as follows:

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9904010005 990319 PDR ADOCK 05000263 F

PDR _

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' Technical Soecifications The Technical Specifications contained in Appendix A, as revis,ed through Amendment No.

105, 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, with full implementation within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Co hF.

s Carl F. Lyon, Project Manager Project Directorate 111-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical 4

Specifications Date of issuance: March 19,1999 i

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I ATTACHMENT TO LICENSE AMENDMENT NO.105 i

FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 l

l Revise Appendix A Technical Lpecifications by removing the pages identified below and Inserting the attached pages. The revised pages are identified by amendment number and contain verticallines indicating the areas of change.

f3fMOVE INSERT l

Sb Sb 60d 60d 71a 71a l

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m AQ. Core Ooeratina Limits Reged The Core Operating Umits Report is the unit specific document that provides core operating limits for the current operating reload cycle. These cycle-specific operating limits shall be determined for each reload cycle in accordance with Specification 6.7.A.7. Plant operation within these operating !imits is addressed in individual specifications.

AR. Allowable Value - The Allowable Valese is the limiting value of the sensed process variable at which the trip setpoint may be found during instrument surveillance.

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1.0 Sb Amendment No. 70, 105

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o Table 3.2.8 Other Instrumentation Minimum No. of Minimum No. of Operable or Oper-Total No. of instru-Ope,T-Oe or Operating ating ment Channels Per Instrument Channels Required Function Trip Setting Trip System (1) (2)

Trip System PerTrip System (1) (2)

Condshons*

A.

RGIG Initiation 1.

Low-Low Reactor Level 2 6'6" & s 6'10" 1

4

-4 B

above top of active fuel B.

HPCl/RCIC Turbins Shutde.

a.

High Reactor Level s 14' 6" above 1

2 2

A top of active fuel G.

HPGl/RGIG Turtune Suction l

Transfer a.

Condensate Storage 22' 3" above tank 1

2 2

C Tank Low Level bottom (Two Tank Alle,wable Values Operation) 26' 9" above tank 1

2 2

C I

bottom (One Tank

. Operation)

N U I1::

1.

Upon discovery that minimum requirements for the number of operable or operating trip systems or irstrument channels are not t

satisfied, action shall be initiated as follows:

a.

With one required instrument channel inoperable per trip funct%, piace the inoperable channel or trip system in the tripped f

condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or b.

With more than one instrument channel per trip system inoperable, immediately satisfy the requirements by placing the appropnate channels or systems in the tripped condition, or c.

Flace the plant under the specified required condition usmg normal operating procedures.

2.

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tnpped condition provided that at least one other operable channel in the same trip system is monitoring that parameter.

Required conditions when mViimum conditicro for operation are not satisfied:

A.

Comoly with Specification 3.5.A.

4 B.

Comply with Specification 3.5.D.

C. Abgn HPCI and RCIC suction to the suppress;On pool.

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3. M.2 Amendment No. 37,93,403,105

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Bases 3.2 (Continued):

Trip Function Deviation l

instrumentation for Safety / Relief Valve Reactor Coolant System

• 20 psig Low Low Set Logic Pressure for Operiing/ Closing Opening-Closing Pressure 260 psi I

Discharge Pipe Pressure inhibit t10 psid Timer inhibit

-3 sec

+10 sec I

Other Instrumentation

• High Reactor Water Level

+6 inches f

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• Low-Low Reactor Water Level

-3 inches i

• This indication is reactor coolant temperature sensitive. The calibration is thus made for j

rated conditions. The level err:,r at low pressures and temperatures is bounded by the j

safety analysis wh ch reflects the weight-of-coolant above the lower tap, and not the indicated level.

A violation of this specification is assumed to occur only when a device is knowingly set outside of the limiting trip settings, or, when a sufficient number of devices have been affected by any means such that the automatic function is incapable of operating within the allowable deviation while in a reactor mode in which the specified function must be operable or when actions specified are not initiated as specified.

6, 3.2 BASES 71a Amendment No. 30,37,66,400a, 105

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