ML20105A698

Proposed TS Page 6.7-4 Re COLR

ML20105A698
Person / Time
Site:	Prairie Island
Issue date:	09/11/1992
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20105A695	List: ML20105A692 ML20105A696 ML20105A698
References
NUDOCS 9209170180
Download: ML20105A698 (4)

Text

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Exhibit B [

t Prairie Island Nuclear Generatin6 Plant .

[

License Amendment Request Dated September 11, 1992 l

.t Proposed Changes Marked Up i

, On Existing Technical Specification Page >

k Exhibit B consists of the existing Technical Specification page with the  ;

proposed changes highlighted on that page. The existir d page affected by this  !

License Amendment: Request is listed below:  ?

hp i

TS-6.7-4 i

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9209170180 920911 PDR ADOCK 05000282 P pop

TS 6.7-4

, RE" 93 2/11/94 6.7.A.S. Annual Summaries of Meteorolonical Data An annual summary of meteorological data shall be submitted for the previous calendar year in the form of joint frequency distributions of wind speed,-wind directior., and atmospheric stability at the request of the Commission.

6.7.A.6. Core Operatinn Limits Report

a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

R

1. Heat Flux Hot Channel Factor Limit ( F,T"P ), Nuclear Enthalpy RTP Rise Hot Channel Factor Limit (Fg ), PFDH, K(Z) and V(Z)

(Specifications 3.10.B.1, 3.10.B.2 and 3.10.B.3)

2. Axial Flux Difference Limits and Target Band (Specifications 3.10.B.4 through 3.10.B.9)

3. Shutdown and Control Bank Insertion Limits (Specification 3.10.D)

4. Reactor Coolant System Flow Limit (Specification 3.10.J)

b. The analytical methods used to determine the core operating limits shall be those previously reviewed-and approved by the NRC, specifically those described in the following documents:

NSPNAD-8101-A, " Qualification of Reactor Physics Methods for Application to P1 Units" (latest approved version)

NSPNAD 8102 A, " Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units" (latest approved version)

WCAP-9272-P-A, " Westinghouse Reload Safety Evaluation Methodology", July,1985 WCAP-10054-P A, " Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code" August, 1985 WCAP-10924-P-A, " Westinghouse Large Break LOCA Best-Estimate Methodology", December, 1988 i

WCAP-10924-P-A, Volume'1, Addendum.4, " Westinghouse Large Break LOCA Best Estimate Methodology", August, 1990~

"WnEingh60sE1XrgelEHihk WCAP;109247PiAKVolW27Addendani@ber LOCAiBestjEstimate! Methodology g Decem ,

fl992

Exhibit C

e n f le Island Nuclear Cenerating Plant Licens, .anendment Request Dated September 11, 1992 e

Revised Technical Specification Page Exhibit C consists of a revised page for the Prairie Island Nuclear Generating Plant Technical Specifications with the proposed changes incorporated. The revised page is listeu below:

ESLt TS-6,7-4'

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4 TS.6.7 4 6.7.A.S.,,Annun1 Summaries of Meteorological Data l An annual summary of neteorological data shall be submitted for the p.evious calendar year in the form of joint frequency distributions  ;

of wind speed, wind direction, and atmospheric stability at the  ;

request of the Commission, j i

6. 7. A. 6. Core Operat ing Limits Rengrl;

a. Core operating limits shall be established and documented in the l CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following: l 1_ ,

I ate I

), Nuclear Enthalpy l j 1. Heat Flux Hot Channel Factor Limit (F, 1 i RTP j Rise Hot Channel Factor Limit (F3 ), PFDH, K(Z) and V(Z) l j (Specifications 3.10.B.1, 3,10.B.2 and 3.10.B.3) i J

i 2. Axial Fic. Difference Liruits and Target Band j (Specificatinns 3.10.B.4 through 3 dO.B.9) {

3. Shutdown and Control Bank Insertion Limits j i (Specification 3.10.D)  ;

e

, 4. Reactor Coolant System Flow Limit  !

(Specification 3.10.J) f l b. The analytical methods used to determine the core operating

! limits shall be those previously reviewed a d approved by the  !

NRC, specifically those described in the following documents: }

I NSPNAD 8101 A. " Qualification of Peactor Physics Methods for  !

Application to P1 Units" (latest ar'scved

version)  !

i -

j. NSr'NAD 8102 A, " Prairie Island Nuclear Power Plant Rel'oad Safety }

j Evaluation Methods for Application to PI Units" l (latest approved version) ';

i I l WCAP 9272-P-A, " Westinghouse Reload Safety. Evaluation f

! Methodology", Jily, 1985 [

! t WCAP.10054-P A, " Westinghouse Small Break ECCS Evaluatfion Model Using the NOTRUMP Code", August. 1985 3 WCAP-10924 P-A, "Westinghous Large Break.LOCA Best-Estimate l Methodology", December, 1988 {

f  !

I- WCAP 10924 P-A, Volume 1, Addendum 4, " Westinghouse 12rge Break  !

l LOCA Best Ectimate Methodology", August, 1990 t

l WCAP-10924 P A, Volume 2, Addendum 3, " Westinghouse Ler;,e Br$ak '[

j LOCA Best. Estimate Methodology", December, 1992 j

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