ML20245D226

Amend 120 to License DPR-40,changing Min Operating Requirements for Raw Water Pumps to Allow Operation W/One Inoperable Raw Water Pump When River Water Temp Below 60 F

ML20245D226
Person / Time
Site:	Fort Calhoun
Issue date:	04/14/1989
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245D208	List: ML20245D204 ML20245D226 ML20245D231
References
NUDOCS 8904280163
Download: ML20245D226 (6)

Text

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~! o NUCLEAR REGULATOR \ OMMISSION

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OMAHA.PUBLIC. POWER. DISTRICT DOCKET.HO. 50-235 FORT.CALHOUN STATION, UNIT.NO. 1 AMENDMENT T0. FACILITY OPERATING LICENSE Amendment No.120 License No. DPR-40

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by the Omaha Public Power District (the licensee) dated December 31, 1988 as supplemented March 15, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; ,

B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D. The issuance of this license amendiuent will not be inimical to the common defense and security or to tte 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.

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2. Accordingly, Facility Operating License No. DPR-40 is amended by changes i to the Technical Specifications as indicated in the attachment to this '

license amendment, and paragraph 3.B. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.120 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. The license amendment is effective as of its date of issuance with full implementation within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION x' h.(cA%

Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 14, 1989 I

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ATTACHMENT TO LICENSE AMENDMENT N0.120 FACILITY OPERATING LICENSE NO. OPR-40 DOCKET NO. 50-285 ,

I Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment nuirber and contain vertical lines indicating the area of change.

i Remove Pages Insert Pages 2-24 2-24 2-25 2-25

- 2-25a e

-_____..__________________.__.___.-._._.-____________a.._._._____. . . _ . _ _ . _ _ _ _ . _ _ _ . _ _ _ . . _ _ _ . _ _ .,_ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _- . . . _ , . _ . _ _ _ _ _ _ - _ ______.m__.-__ -

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2.0 LIMITING CONDITIONS FOR. OPERATION 2.4 _ containment Coo 11ns i

Applicability

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l Applies to the operating status of the con.tainment cooling systems. {

Objective To assure operability cf equipment required to remove heat from the containment durinq normal operating and emergency situations.

Specifications (1) Minimum Requirements

a. The reactor shall not be made critical, except for low- l temperature physics tests, unless all the folicwing are met:

1. The following equipment normally associated with I diesel-generator D1 (4.16-kV bus IA3 and associated non-automatically transferrin {3j80-Volt bus sections) is operable, except as noted: .

Raw water pump AC-10A Raw water pump AC-10C Component cooling water pump AC-3A Component cooling water pump AC-3C Containment spray pump SI-3A Containment air cooling and filtering unit VA-3A Containment air cooling unit VA-7C

11. The following equipment normally associated with I diesel-generator D2 (4.16-kV 1A4 and associated non-automaticallytransferably3j80Voltbussections) is operable, except as noted Raw water pump AC-108 Raw water pump AC-10D Component cooling water pump AC-3B Containment spray pump SI-3B Containment air cooling and filtering unit VA-3B Containment air cooling unit VA-70 Containment spray pump SI-3C 111. All heat exchangers, valves, piping and interlocks )

associated with the above components and required to function during accident conditions are operable.

III Reactor may be made critical with one inoperable raw water pump. LCO action statements shall apply.

2-24 Amendment No.120

12.0 LIMITING CONDITIONS FOR OPERATION

'2.4. Containment. Coo Mng (Continued)

b. Duringpoweroperatingoneofthecomponentslistedin(1)a.i.

and 11. may be inoperable. If the inoperable component is not restored to operability within seven. days, the reactor shall be placed in hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the '

inoperable component is.not restored to operability within an l' additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in a cold p, shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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c. - For' cases involving Raw Water pump inoperability, if the river.

water temperature is below 60 degrees Fahrenheit, one Raw Water

! pump may be inoperable indefinitely without' applying any LCO l action statement. When the river water temperature is greater l' than 60 degrees Fahrenheit, an incperable Raw. Water pump shall, be restored to operability within 7 days or the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the inoperable Raw Water pump is not restored to operability within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(2) Modification _of Minimum Requirements ,

During power operation, the rinimum-requirements may be modified to allow a total of two of the component listed in (1)a.i. and 11. to be inoperable at any one time (this does not' include one Raw Water pump which may be inoperable as described above if the river water temperature is below 60' degrees Fahrenheit). Only two raw water purps may be out of service during power operations. If the operability of one component is not restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the re..ctor 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.shall be p(lace

.LCO 2.4 1)b.inshall a hetbe shutdown applied ifcondition one of the within inoperable components is restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the operability of both components is not restored within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Any valves, interlocks and piping directly associated with one of the above components and required to function during accident conditions shall be deemed to be part of that component and shall meet the same requirements as for that component.

Any valve, interlock or piping associated with the containment cooling system which is not included in the above paragraph and which is required to function'during accident conditions 2-25 Amendment No. 6,III,120 a_--_--___-____________ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ . . _ - _ _ _ _ .__ _ _ _ _ _ _ _ _ _ _ . . _ - _ _ _ _

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2.0 LIMITING. CONDITIONS FOR OPERATION 2.4 Containment Cooling (Continued) may be irtoperable for a period of no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

If operability is not restored within 24 hoeirs, t!,e reactor l shall be placed in a het shutdown condition witnin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Basis The requirements of Section 2.3, Emergency Core Cooling System, apply to the specifications above with respect to the operability of the l

l 2-25a Amendment No.120