ML20205S238

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Amend 116 to License DPR-40,modifying Tech Specs to Provide Addition of Table of Contents for Tables & Figures & Correct Error to Location Ref in Section 2.19
ML20205S238
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 11/03/1988
From: Calvo J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20205S235 List:
References
NUDOCS 8811100299
Download: ML20205S238 (9)
v • d • e


Text

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,,{ p aae:t,g % , UNITE 3 8TATES y a NUCLEAR REGULATORY COMMISSION O l wAsMihoTow, o. c. meses

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,0MAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMEN 0 MENT 10 FACILITY OPERATING LICENSE Amendment No.116 License No. DPR-40

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

A. The application for atendment by the Cir.aha Public Power District (the licensee) dated July 19, 1988, cocplies 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; E. The facility will operate in conformity with the application, as arended, the prcvisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i)thattheactivitiesauthorized by this arendrent can be conducted without endangering the health arid safety of the public, and (ii) that such activities will be

conducted in compliance with the Cornission's regulations; D. The issuance of this license amendnent will net be inimical to the

< corron defense and security or to the health and safety of the public; arid E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Coesnission's regulations and all applicable requirements have been satisfied.

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i 8911100299 891103 .

DR ADOCK 0500 3

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2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.

OPP-40 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.116 , are hereby incorporated in the license. The licensee shal's operate the facility in accordance with the Technical Specifications.

3. The license anendment is effective as of its date of issuance.

FOR THE hUCLEAR FEGULATORY C0!FIS!!ON

,%e. ' 6 (<; v. Q Jese A. Calvo, Director Freject Directorate - IV Division cf Reactor Projects - !!!,

IV, Y and Special Projects Office of Nuclear Reactor Fetulatien Attachrent:

Charges to the TecFr. ital Specifications Date of Issuance: November 3,1988 i

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Q ATT A C FF E NT, ,T O, l. I C,Ep 5,E, R EJpp,E,fg, tip,. ,1 16 FACILITY OPERATIfiG LICENSE tiO. DPR-40 00CKET li0. 50-28,5 Revise Appendix "A" Technical Specifications as iridicated below. The revised pages are identified by amendment nurber and contain vertical lines indicating the area of change.

Remove Paf g Insert Paget iv

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V Vi vii viii 2-91 2-91 F

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TECHMICAL SPECIFICAT10h5 - TABLES l

T ABL.E, p,F, Cpp]Ep]S TABLE DESCRIPTION PAGE 1-1 RPS LSSS. . . . . . . . . . . . . . . . . . . . . . . . . . . 1-10 (

1-10e  !

2-1 ESFS Initiation Instrumentation Setting Limits. . . . . . . . 2-64 2 64 2-2 Instrument Operating Requirerents for RPS . . . . . . . . . . 2-67 i 2-67a 2-3 Instrument Courating Requirements for Engineered Safety Features . . . . . . . . . . . . . . . . . . . . . . .  ?-68 P-68a  ;

2-68b i i

2-4 Instrurer,t Operating Canditions fer Isolation Functions . . .  ?-60 ,

2-69a 1 2-5 Instrurentation Crerating Pequirements for Other Safety '

Feature Functions . . . . . . . . . . . . . . . . . . . . . .  ?-70 ,

2-7 Fire Detection Zones. . . . . . . . . . . . . . . . . . . . . 2-90  ;

)!a l e n A re a F i ro Z e n c s . . . . . . . . . . . . . . . . . . . .  ?-90s ,

t 2-8 Fire Hose Station Locations . . . . . . . . . . . . . . . . .  ?-94 j 2-95 r 2-9 RCS Pressure Isolation Yalves . . . . . . . . . . . . . . . . 2-2d 2-10 Post-Accider.t Monitoring Instrueentation Crerating Lie,1ts . .  ?-9F ,

?-98a 2-9Bb i

2-11 Toxic Gas Monitors Operating Limits . . . . . . . . . . . . .  ?-100 l

3-1 Minimum Frequencies for Checks. Calibrations,  !

and Testing of RPS. . . . . . . . . . . . . . . . . . . . . . 3-3 l 34 ,

3-5 t 3-6 }

t 3-7 Minimum Frequencies for Checks, Calibr tions and Testing of I Engineered Safety Features, Instrumentation ar.d Controls. . . 3-7  !

3-8  !

3-9 l 3-10  ;

3 11 3-12 3-12a iv Arendrent No.116 '

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TECHNICAL SPECIFICATIONS - TABLES t TABLE OF CONTENTS TACLE DESCRIPTION PAGE I t

3-3 Minimum Frequenci s for Checks, Calibrations, and Testing of Miscellaneous Instrumentation and Controls . . . . . . . . 3-13 3-14 l 3-15  ;

3-16  !

' 3-16a 3-1fb '

3-1(c {

3-4 Minimum Frequencies for Sampling Tests. . . . . . . . . . . . 3 18 3 19 35 Mininun Frec;uencies for Equipment Tests . . . . . . . . . . . 3-20 i 3-20a i 3-20b i J

3-20c j 3-20d ;

i 3-6 Rear, tor Coolant Purp Surveillance . . . . . . . . . . . . . . 3 27 3-7 Capsule Removal Schedule. . . . . . . . . . . . . . . . . . . 3-27 (

i 3-9 Radiological Ervironeent Penitoring Progren . . . . . . . . . 3-66  ;

i 3 67 ,

I 3 11 Radioactive Liquid Waste Sarpling and Analysis. . . . . . . . 3-72 r 3-73

\ i 3-12 Radicactive Gasecus Waste Sampling and Analysis . . . . . . . 3-74  !

3-75 l 3-13 Stear.Ger.erator Tube Inspection . . . . . . . . . . . . . . . 3-90 i l

5.2-1 Minimum Shif t Crew Composition. . . . . . . . . . . . . . . . 5-2 l

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, v Arendment No.116 l

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. TECHNICAL SPECIFICATIONS - TABLES TABLEOFCONTENTSJALPHABETICALORDER)

TABLE DESCRIPTION ,PA,G,E 3-7 Capsule Receval Schedule. . . . . . . . . . . . . . . . . . . 3-27 2-1 ESFS Initiation Instruinentation Setting Limits. . . . . . . . 2-64

?-64a 2-7 Fire Detection Zones. . . . . . . . . . . . . . . . . . . . .  ? 90 2-8 Fire Hose Station Locations . . . . . . . . . . . . . . . . .  ?-94 l ,

2-95 i

2-7 Halon Area Fire Zones . . . . . . . . . . . . . . . . . . . . 2 90a ,

2-4 Instrument Opert 'r.g Conditions fer Isolation Functions . . .  ?-69 l

2-698 i t-2 Instrurent Operating Requireinents for RPS . . . . . . . . . . 2-67 l

?-67a .l l-23 Instrutent Operating Requirements for Ergineered S a f e ty F e a t u r e s . . . . . . . . . . . . . . . . . . . . . . .  ?-68  ;

2-680 2-f8b l l

2-5 Instrurentation Operating Requirerents for Other Satety Features Functions. . . . . . . . . . . . . . . . . . . . . .  ?-70 3-2 Pinicun Frequencies for Checks, Calibratiens ard Testing of Engineered Safety Features, Instrurentation ard Controls. . . 37 38 l 3-9 3-10 3 !!

3-1?

3 12a 33 Finissa Frequencies for Checks, Calibrations, and Testing of Miscellaneous Instrueientation ar.d Controls . . . . . . . . 3 13 3-14 3 '. 5 3.;c 3-It' 3-16b 3-16e 3-1 P,inimun Frequencies for Checks, Calibrations, and Testing of RPS. . . . . . . . . . . . . . . . . . . . . . 33 -

3-4 l 3-5  :

3-6  :

vi Anendrent No. 116 i Y .

. i TECHNICAL _ SPECIFICATIONS - TABLE,5 l

TABLE OF CCNTENTS (Al.ff:AP.ET ,Tigt,0RDER)

C'oid'iriceT .

TABLE ,0ESCRIPTION PAGE 3-5 Minimum Frequencies for Equipment Tests . . . . . . . . . . . 3-20 <

3 ?0a 3-?0b l; 3-20c t 3 20d l l 3-4 Miniewm Frequencies for Sampling Tests. . . . . . . . . . . . 3-18 3-19 5.2 1 Minituni Shif t Crew Corrposition. . . . . . . . . . . . . . . . 5-2 ,

2-10 Post Accident l'onitoring Ir.strunentation Cperating Limits . . 2-98 2-98a 2-9Eb 3 12 Radioactive Gas 6eus Waste Saepling and Analysis . . . . . . . 3 74 3-75 ,

3-11 Radioactive Lic.uid Waste Sar.pling and Analysis. . . . . . . . 3-72 3-73 30 Radiological Environr.eni Pcnitcring Program . . . . . . . . . 3 E6 3 67 P9 RCS Pressure Isolation Yalves . . . . . . . . . . . . . . . . P-?c 3 ?7 '

36 Reactor Coolant Purp Surveillarce . . . . . . . . . . . . . .

1-1 RPS LSSS. . . . . . . . . . . . . . . . . . . . . . . . . . . 1-10 1-1Ca 3 13 Steac. Generator Tube Inspection . . . . . . . . . . . . . . . 3-90 2-11 Tonic Gas Monitoring Operating Limits . . . . . . . . . . . . 2-100 I

i vii Arendment No.Ilt j

y TECHNICAL $PECIFICAT10k$ - FIGURES f

t TABLE OF CONTENTS  !

PACE Ph!CH TABLE DESCRIPTION TABLE F0llDWS i t

1-1 THLP Safety Limits 4 Pump Operations. . . . . . . . . . . . . 1-3 l 1 !

1-2 Axial Power Distribution LSSS for 4 Purp Operation. . . . . . 1-3  ! t 13 TMLP LSSS 4 Pump Operation. . . . . . . . . . . . . . .. . . .  ?-6  !

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l 2-1A RCS Press-Terp Limits Heatup. . . . . . . . . . . . . . . . . 2-74  ;

2-1B RCS Press-Terp Lie.its Cooldown. . . . . . . . . . . . . . . .  ?-7a 23 Predicted Patietion Induced NDTT Shift. . . . . . . . . . . . 2-74 l 2 10 Spent Fuv1 Pool Region 2 Storage Criteria . . . . . . . . . .  ?-38a h

1 2-4 PDIL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-57e i 25 Allewable Peak Linear Feat Rate vs Burnup . . . . . . . . . .  ?-57e 1 <

?-6 LC0 for Execre ronitoring of LHP. . . . . . . . . . . . . . .  ?-57e [

2-7 LCO fer DI:B Monitcring. . . . . . . . . . . . . . . . . . . .  ?-57e (

2-8 Flux Feaking Augrentation Factors . . . . . . . . . . . . . .  ?-57e e <

T P9 F A, pxY and Core Power Linitetions. . . . . . . . . . . . .  ?-57e  !

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2.0 LIMITING CONDIT!0hs FOR OPEP.A110N  !

2.19 Fire Protection SysteriTCoMTn'uId) i (3) The provisions set forth in Section 2.19(2) do not apply to tire periods during which Containment Integrated Leak Rate Tests are  !

beir' performed.

l (4) Fire suppressions water system shall be operable, except during {

system testing, jockey purp maintenance or training (not to exceed 7 l consecutive days) with both fire pus.ps, each with a minimuni capacity r of 1800 spm, with their discharge aligned to the fire suppression L header and autenatic initiation logic for each fire put.p.

a. With less than the above required equiprent:  !

(i) restore the inoperable equiprent to operable status  !

within 7 days, [

(ii) if equiptrent is not restored to operable status  !

within 7 days, prepare and submit a report to the i Nuclear Regul6 tory Corrission, pursuant to i Section 5.9.3.1 of the Technical Specifications, I within the next 30 days, outlining the plans and '

l procedures to be used to provide for the loss of the i syste and the cause of the ralfunction. J

b. )!ith no fire suppression water system operable:

(1) establish a backup fire suppression water syster  !

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, j

(ii) rctify the Nuclear Regulatory Comission, pursuant to .

Section 5.9.2 of the Technical Specifications, t !

outlining the cause of the malfunction, the actions [

taken, and the plans and schedule for restoring the l system to operable status.  !

i (iii) If(I)abovecar.notbefulfilled,placereactorin Pot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following thirty (30) hours, f (5) The sprinkler system in the Diesel Generator Rooms, the sprinklers above the steam driven auxiliary feedwater pump, the sprinkler / spray norrie system in the compressor roce, and the deluge systen in the personnel corridor between fire areas 6 and 20 shall be operable except during system testing. If inoperable:

a. Within one hour establish a continucus fire watch with backup fire extinguishing equiprent for those areas in which redundant systems or corponents could be damaged; for other aers, establish an heurly fire watch patrol.

2 91 Amendrent flo if.f3,95,110

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