ML19351A565

Application for Amend to License NPF-12,removing cycle-specific Limits from Tech Specs & Placing Limits in Core Operating Limits Rept

ML19351A565
Person / Time
Site:	Summer
Issue date:	12/11/1989
From:	Bradham O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19351A566	List: ML19351A565 ML19351A570 ML19351A674
References
NUDOCS 8912190339
Download: ML19351A565 (9)

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' So th CarOhn2 DecidC & G1s Company e S. B m y socie r opor.1 on.

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December 11, 1989 5 i

Document Control Desk U. S. Nuclear Regulatory Commission .

Washington, DC 20555  :

Subject:

Virgil C. Summer Nuclear Station  !

Docket No. 50/395 Operating License No. NPF-12

Technical Specifications Change Core Operating Limits Report Gentlemen:

SouthCarolinaElectric&GasCompany(SCE&G)herebyrequestsanamendmentto the Technical Specifications involving cycle specific parameter limits. The proposed amendment resolves the unnecessary burden of processing Technical Specifications changes to update such limits for each core reload. ,

The Technical Specifications for which changes are requested involve limits associated with reactor physics parameters that change for each fuel cycle.

This amendment will remove such cycle specific limits from the Technical Specifications and place them in a separate Core Operating Limits Report which will be defined in the Technical Specifications. This altarnative to modifying the individual Technical Specifications for each core reload is >

responsive to industry and NRC efforts to improve Technical Specifications.

The individual Technical Specifications which are affected are contained in Attachment I accompanied by the change description and basis. Attachment 11 provides the marked up pages for the proposed amendment. Attachment III is a sample Core Operating Limits Report based on data for the current fuel cycle.

Attachment IV contains the plant specific safety evaluation covering the request and the basis for its acceptability. The no significant hazards considerationpursuantto10CFR50.91(a)(1)ispresentedinAttachmentV.

This request has been reviewed and approved by the Plant Safety Review -

Committee and the Nuclear Safety Review Committee.

This submittal is a reformatted version of the Core Operating Limits Report Technical Specifications change request submitted on September 19, 1989.  !

SCE&G requests the NRC to review this proposed Technical Specifications amendment expeditiously so that, if approved. Virgil C. Summer Nuclear Station will be able to utilize the Core Operating Limits Report for Cycle 6.

In order to support the outage planning activities necessary for this, SCE&G requests that the NRC review and approve this amendment request by Feoruary 1, 1990, i <

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v: Document Control Desk-December 11, 1989 Page 2 of 2 I' declare that the statements and matters set forth herein are true and i correct to the best of my knowledge, information, and belief.

Should you have any questions, please call at your convenience, s

Very truly yours, We, l ,

0. S. Bradham EWR/OSB: led  :

. Attachments c: D. A. Nauman/0. W. Dixon, Jr./T. C. Nichols, Jr.

E. C. Roberts  :

W. A. Williams, Jr.  ;

S. D. Ebneter i J. J. Hayes, Jr. '

General Managers C. A. Price p .R. B.~Clary K. E. Nodland J. C.-Snelson L R. L. Prevatte ,

J. B. Knotts, Jr.

H. G. Shea1y  ;

NSRC 3 RTS (TSP;880021) l- NPCF l- File (813.20)  ;

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Attachment 1 i

, Technical Specifications Affected and Description of Change t

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9~ ' Attachment 113 Document C":ntrcl Desk lett:r b 4~ December 11,1989  ;

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e TECHNICAL SPECIFICATION AFFECTED BY PROPOSED  ;

AMENDNENT AND BRIEP DESCRIPTION OF CHANGE .

PAGE TECHNICAL SPECIFICATION CHANGE DESCRIPTION I Definitions Updates index to show the addition of a  !

l 1.9a Core Operating Limits COLR definition ,

Report

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i XIX 6.B.1 Routine Reports : Core Updates index to change name of the Peaking ,

Operating Limits Report Factor Limit Report to the COLR r

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1-2 1.9a Definitions Adds definition of COLR -

3/4 1-4 3.1.1.3 Moderator Temperature Relocates MTC Limits to the COLR  !

Coefficient 3/4 1-5 4.1.1.3 MTC Surveillance i Requirement B3/4" 1-2 3/4.1.1,3 Moderator Temperature i Coefficient Bases i

s 3/4 1-14 3.1.3.1 Moveable Control Replaces reference to Figures 3.1-1 and ,

Assemblies 3.1-2 (which are relocated to the COLR) with Specification 3.1.3.6 i

3/4 1-20 3.1.3.5 Shutdown Rod' Insertion Replaces the fully withdrawn limit with n Limit more general insertion limits which are to 4.1.3.5 Surveillance Requirement be provided in the COLR. This is done to allow RCCA repositioning to minimize wear h 3/4.1-21 3.1.3.6 Control Rod Insertion Relocates the control bank rod insertion l: Limits limits to the COLR l

-3/4 1-22 Fig._3.1-1 Pod Group Insertion Limits VS. Thermal Power Three Loop Operation

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. Attachment 1 to Docum:nt Centr l Desk LGtter N* Dec mber 11,1989 I

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TECHNICAL SPECIFICATION AFFECTED BY PROPOSED AMENDNENT AND BRIEF DESCRIPTION OF CHANGE PAGE TECHNICAL SPECIFICATION CHANGE DESCRIPTION

.3/4 1-23 Fig.3.1-2 ELANK Relocates the control bank rod insertion ,

limits to the COLR '

h 3/4 2-1 3.2.1 Axial Flux Difference Reflects the change from the Peaking Factor l

-Limit Report to the COLR as the source of i AFD limits ,,

33/4 2-1 3/4.2.1 Aulal Flux Difference Bases ,

B3/4 2-2 3/4.2.1 Axial Flux Difference Bases 3/4 2-4 3.2.2 Heat Flux Hot Channel Relocates the F0, K(E),and W(E) functions Factor to the COLR. The numerical FO limit is replaced with a function FQR TP which is to be specified in the COLR.

3/4 2-5 4.2.2.2.c Heat Flux Hot Channel

• Factor Surveillance Requirements 3/4 2-6 4.2.2.2.f Heat Fl*Jx Hot Channel Factor Surveillance Requirements 3/4 2~6a 4.2.2.3 Heat Flux Hot Channel Factor Surveillance Requirements 3/4 2-64 4.2.2.tc Heat Flux Hot Channel

• Factor Jurveillance Requirements 3/4 2-6c 4.2.2.4f h0at Flux Hot Channel Factor Survelllance Requirements 3/4 2-7 Fig. 3.2-1 K(E) VS. Core Height ,

3/4 2-8 3.2.3 RCS Flow Rate and Nuclear Relocates the F-delta H and RCS flow limits Enthalpy Rise Hot Channel Factor to the COLR. The numerical values for the F-delta H limit and part power multiplier are replaced with parameter FAHRTP and PFAH which are to be defined in the COLR.

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Attachment 1 to Docum:nt Centr:l Desk Lett:r  !

1. Decen1ber 11,1989 l Page 3 of 5 l 1

TECHNICAL SPECIFICATION AFFECTED BY PROPOSED AMENDNENT AND BRIEF DESCRIPTION OF CHANGE l PAGE TECHNICAL SPECIFICATION CHANGE DESCRIPTION 3/4 2-9 4.2.3.2 Surveillance Requirements for RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor ,

3/4'2-10 Fig. 3.2-2 RCS Total Flow Rate Relocate the F-delta H and RCS flow limits i VS. R Three Loop Operation to the ',OLR. The numerical values for the F-delta 1 limit and part power multiplier are rspla ed with parameter FAHRTP and PFAH whica are to be defined in the COLR.

53/4 2-3 3/4.2.2.2 and 3/4.2.3 Heat Flum Hot Channel Factor and RCS l Flowrate and Nuclear Enthalpy Rise Hot Channel Factor-Bases 33/4 2-4 3/4.2.2.2 and 3/4.2.3 Heat Flux

-Hot Channel Factor and RCS i

.Flowrate and Nuclear Enthalpy .

Rise Hot Channel Factor-Bases l

B3/4 2-5 3/4.2.5 DNB Parameters Bases Replaces the W-3 correlation DNBR design limit (1.30) with a general statement.

Three Correlations are in use on Summer Station and the use of " design limit" as opposed to a numerical value is appropriate. These changes are an oversite in the Vantage 5 tech spec change request (Amd 75) and are purely administrative.

I B3/4 4-1 3/4.4.1 Reactor Coolant Loops and Coolant Circulation l

B3/4 2-6 3/4.2.5 DNB Parameters-Bases Deletes a section of writeup that is on the previous page. This change is editorial only.

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I Ittachment 113 Docum:nt Contr;l Desk Letter

• " December 11,1989 Page 4 of 5 l

TECHNICAL SPECIFICATION A?FECTED BY PROPOSED AMENDNENT AND BRIEF DESLRIPTION OF CHANGE PAGE TECHNICAL SPECIFICATION CHANGE DESCRIPTION 6-18 Administrative Controls 6.9.1.11 In the Administrative Controls Section the Radial Peaking Factor Limit description of the Peaking Factor Limit Report Report is replaced with the description of the COLR.- The COLR will be provided, upon issuance for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

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Attachment 113 Docum;nt Ccntr l Desk lett;r December 11,1989

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LEGEND FOR ATTACHMENT 1 AFD- Axial Flux Difference FAHRTP. F deltaH limit at rated thermal power FQRTP- FQ limit at Rated Thermal Power COLR- Core Operating Limits Report DNB- Departure From Nucleate Boiling

- DNBR Departure from Nucleate Boiling Ratio

, F deltaH- Nuclear Enthalpy Rise Hot Channel Factor FQ- Heat Flux Hot Channel Factor K(Z) Normalized FQ as a function of core height MTC- Moderator Temperature Coefficient PFall. Power Factor Multiplier for F deltaH RCS- Reactor Coolant System l W(Z) Cycle dependent function that accounts for power distribution transients i

encounted during normal operation i

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e-Attachment 2 Marked-Up Technical Specification Pages i

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