ML20062G661

Amend 134 to License DPR-40,addressing Two Administrative Changes

ML20062G661
Person / Time
Site:	Fort Calhoun
Issue date:	11/19/1990
From:	Quay T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20062G657	List: ML20062G656 ML20062G661 ML20062G662
References
NUDOCS 9011290377
Download: ML20062G661 (5)

Text

._ .__ _._ _ . _ _ . _ _ _ . - . _ - _ _ ____ _._- . _ _ .__ ._. ___.- _ . . _ . _ _ . _ _

ps Lae v

. *  ?, UNITED STATES ,

s

[i 'fa f

NUCLEAR REGULATORY COMMISS;0N wassisotow. o. c. nosss

\,.....f i l

)

l OMAHA PUBLIC POWER DISTRICT 1 DOCKET NO. 50-285 FORT CALHOUN STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.134 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 (thelicensee)datedSeptember6,1990,assupplementedSeptember17, 1990, complies with the standards and re EnergyActof1954,asamended(theAct)quirementsoftheAtomic , and the Comission'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: (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 amendment will not be inimical to the common defense and security or to the health and s:'a+y of-the publ 4c; and ,

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Cons.ission's regulations and all applicable reouirements have been satisfied.

i t

Ohch g!j r v pgp

- . _._. _ m _ _ _ _ _ _ _ . _ . _ _ . _ _ _ __

l a 2.

Accordingly,ical to the Techn Specifications as indicated in the attachment to thisFacility Oper license amendment, and paragraph 3.B. of Facility Operating License No.

DPR-40 is hereby amended to read as follows: l B. Technical specifications ,

i The Technical Specifications contained in Appendix A, as 1 revised through Amendment No.134 are heresy incorporated l in the license. Thelicenseeshalloperatethefacilityin accordance with the Technical Specifications.

3. The license amendment is effective as of its date of issuance. 1 FOR THE NUCLEAR REGULATORY COMMIS$10N

. , thG .$ . og Theodore R. Quay, Acting Director Project Directorate IV-1 Division of Reactor Projects - Ill, IV, V and Special Projects

, Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date o'f Issuance: November 19, 1990

,' ATTACHMENT TO LICENSE AMENDMENT NO. 134 FACILITYOPERATINGLICENSENO.DPR-g QOCKETNO.50285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

REMOVE PAGES, INSERT PAGES 3-62a 3-62a 5-3 5-3 i

l

~

, 3.0 SURVEILLANCE REOUIR @ mil 3.9 Auxiliary Feedwater System (Continued)

BAL11 The valve position verifications performed monthly and following auxiliary feedwater system maintenance will confirm the availability of an auxiliary feedwater flow path to the steam generators.

The testing of the auxiliary feedwater pumps every month and after cold shutdowns will verify their operability by recirculating water to the emergency feedwater storage tank.

Operating the regulating valves (HCV 1107A, HCV-1107B, HCV-1108A and HCV 11088) one at a time every three months and after cold shutdowns will confirm a flow path to the steam generators and operability of the valves.

Proper functioning of the steam turbine admission valve and starting of the feedwater pump will demonstrate the integrity of the steam driven pump. Verification of correct operation will be made both from .

instrumentation within the main control room and direct visual observation of the pumps.

The operability of the auxiliary feedwater system ensures that the reactor coolant system can be cooled down to less than 300'F from normal operating conditions at which time the shutdown cooling system may be placed into operation in the event of a total loss of off site power.

References (1) USAR, Section 9.4 l (2) Technical Specification 2.5 3-62a Amendment No. f),J/,pp 134

. 5.0 ADMINISTRATIVE CON 1PQl1

. 5.4 Trainino 5.4.1 A retraining and replacement training program for the plant staff shall be maintained under the direction of the Manager - Training and shall meet or exceed the requirements of Section 5.5 of ANSI N18.1 1971 and 10 CFR Part 55.

5.4.2 A training program for the fire brigade shall be maintained under the Manager Training and shall meet or exceed the requirements of Section 27 of NFPA Code 1975, except that the meeting frequently may be quarterly.

5.5 Review and Audit 5.5.1 Elant Review Committee (PRC)

Function 5.5.1.1 The Plant Review Committee shall function to advise the Manager -

Fort Calhoun Station on all matters related to nuclear safety.

Composition 5.5.1.2 The official Plant Review Committee shall be composed of the:

Chairman: Manager Fort Calhoun Station Member: Supervisor - Operations Member: Manager - Training Member: Supervisor - Maintenance Member: Supervisor - System Engineering Member: Reactor Engineer l Member: Supervisor Radiation Protection Member: Supervisor - Chemistry

, Member: Assistant Plant Manager l Alternates 5.5.1.3 Alternate members shall be appointed in writing by the Plant Review Committee Chairman to serve on a temporary basis; however, no more than two alternates shall participate in Plant Review Committee activities at any one time.

Meetine Frecuency 5.5.1.4 The Plant Review Committee shall meet at least once per calendar month and as convened by the Plant Review Committee Chairman.

Ouorum 5.5.1.5 A quorum of the Plant Review Committee shall consist of the Chairman and four members including alternates.

53 Amendment No. ),J),JE Ef,JJE,134 t

i I

_ . . _____._________ _ _ _ ________ _