ML20247L718
| ML20247L718 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/19/1989 |
| From: | Bradham O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20247L721 | List: |
| References | |
| NUDOCS 8909250047 | |
| Download: ML20247L718 (8) | |
Text
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South Ccrolina Dectric & Gts CornpIny i S.
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Jenkinsville. SC 29065 Nucleas Operations a
(803) 345-4040-5i SCE&G September 19, 1989 Document Control Desk U. S. Nuclear Regulatory Commission-Washington, DC 20555
Subject:
' Virgil C.. Summer Nuclear Station Docket No. 50/395 r
Operating License No. NPF-12 Technical Specifications Change Core Operating Limits Report Gentlemen:
South Carolina Electric & Gas Company (SCE&G) hereby requests an amendment to 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 Peport I
which will be defined in the Technical Specifications. This alternative to modifying the individual Technical Specifications for each core reload is responsive to industry and NRC efforts to-improve Technical Specifications.
g, The individual Technical Specifications which are affected are contained in Attachment I accompanied by the change description and basis. Attachment II provides the marked up pages for the proposed amendment. Attachu:ent III is a sample Core Operating Limits Report based on data for the current fuel cycle.
The no..significant hazards corsiderat*on pursuant to 10CFR50.91(a)(1) is presented in Attachment IV. This request his been reviewed and approved by i
l the Plant Safety Review Comittee and the Nuclear Safety Review Committee.
I declare that the statements and matters set forth herein are true and correct to the best of my knowledge, information, and belief.
Should you have any questions, please call at your convenience.
Very truly yours,
- 0. S. Bradham EWR/OSB: led Attachments I I c: See Page 2
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,au Document Control Desk September 19, 1989 Page 2 of 2 c:
D. A. Nauman/0. W. Dixon, Jr./T. C. Nichols, Jr.
l E. C. Roberts W. A. Williams, Jr.
S. D. Ebneter J. J. Hayes, Jr.
General Managers C. A. Price R. B. Clary i-K. E. Nodland J. C. Snelson l'
R. L. Prevatte J. B..Knotts, Jr.
H. G. Shealy NSRC RTS (TSP. 880021)
NPCF File (813.20)
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Technical Specifications Affected and Description of Change 3
1 1
. Attachm:nt 113 Docum:nt Control D:sk Lotter
, Sept:mber 19,1989 Pcge 1 of 5 TECHNICAL SPECIFICATION AFFECTED BY PROPOSED AMENDMENT AND BF.IEF DESCRIPTION OF CHANGE PAGE TECHNICAL SPECIFICATION CHANGE DESCRIPTION I
Definitions Updatec index to show the addition of a 1.9a Core Operating Limits COLR definition Report XIX 6.9.1 Routine Reports : Core Updates index to change name of the Peaking Operating Limits Report Factor Limit Report to the COLR 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 Requirement B3/4 1-2 3/4.1.1.3 Moderator Temperature Coefficient nases 3/4 1-14 3 1.3.1 Moveable Control Replaces reference to Figures ?.1-1 ar,d Assemblites 3.1-2 (which are relocated tc the COLR) f with Specification 3.1.3.6 3/4 1-20 3.1.3.5 Shutdown Rod Insertion Replaces the fully withdrawn limit with 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 3/4 1-21 3.1.3.6 Control Rod Insertion Relocates the control bank rod insertion Limits limits to the COLR 3/4 1-22 Fig. 3.1-1 Rod Group Insertion Limits VS. Thermal Power Three Loop Operation
..,; Attachmsnt 1 to Docum:nt Control Desk Letter
'[ Sept.:mber 19; 1989.
P;ge 2 of 51
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TECHNICAL SPECIFICATION AFFECTED BY PROPOSED
'h AMENDMENT AND BRIEF DESCRIPTION OF CHANGE 1PAGE TECHNICAL SPECIFICATION CHANGE DESCRIPTION 3/4'l-23L ' Fig. 3.1-2' BLANK L Relocates'the control bank rod insertion limits to the COLR 3/4.2-l' 3.2.1 Axial Flux Difference Reflects the change from the Peaking Factor Limit Report to the COLR as the, source of AFD limits 33/4 2-1 3/4.2.1 Axial 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 FQ, K!Z),and W(2) functions Factor to the COLR.
The numerical FQ limit is l
replaced with a function FQRTP which is to be specified in the COLR.
3/4 2-5
.t.2.,2.2.c Fest Flux Hot Channel Factor Surveillance >e Requirements 3/4 1-6 4.2.2.2.2. Heat Flux Eut Chant.a1 l.
. Factor Surveillance Requirements 3/4 ' 2-6tt.
,4.2.2.3 Heat Flux Hot Channel Factor futveillance Pequirepents l
- 3/4 ' 2-6b A.2.7.4e Beat Flun Hot Channel l
Factor Searveil?asce Requitonents y
l 3/4 2-6c 4.2.2.4f Heat Flux Hot Channel Factor Surveillance Requirements 3/4 2-7 Fig. 3.2-1 K(2) VS. Core Height l
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-3/4 2-8 3.2.3 RCS. Flow Rate and Nuclear Relocates the F-delta H and RCS flow limits Enthalpy Rise Ete 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 vhich are to be defined in the COLR.
Attachm:nt 1 to Document Control Desk Letter
, Sept:mb:r 19,1989 Pcge 3 of 5 TECHNICAL SPECIFICATION AFFECTED BY PROPOSED AMENDMENT AND BRIEF DESCRIPTION OF CHANGE PAGE TECHNICAL SPECIFICATION CHANGE DESCRIPTION 3/4 2-9 4.2.3.2 Surveillance Requirements for RCS Flow R6te and Nuclear Enthalpy Rise Hot Channel Factor 3/4 2-10 Fig. 3.2-2 RCS 'fotal Flow Rate Relocates the F-delta H and RCS flow limits VS. R Three Loop Operation 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.
B3/4 2-3 3/4.2.2.2 and 3/4.2.3 Heat Flux Hot Channel Factor and RCS Flowrote and Nuclear Enthalpy Rise Hot Channel Factor-Bases B3/4 2-4 3/4.2.2.2 and 3/4.2.3 Heat Flux Hot Channel Factor and RCS Flowrate and Nuclear Enthalpy Rise Hot Channel Factor-Bases B3/4 2-5 3/4.2.5 DNB Parameters Bares Replaces the W-3 correlation DNBR design limit (1.30) with a general statement.
Three Correlations are in use on Summer Sthtion and the use of " design limit" as opposed to a numerical value is appropriate. These changes are an oreisite in the vantage 5 tech spee change request (And 75) and are parely administrative.
B3/4 4-1 3/4.4.1 Reactor Coolant Loops and Coolant Circulation 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.
Attichm:nt 1 to D: cum:nt Control D:sk Letter 5:pt:mb:r 19,1989 -
Page 4 of 5 TECHNICAL SPECIFICATION AFPECTED BY PROPOSED t
AMENDMENT AND BRIEF DESCRIPTION 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 Regior.al Administrator and Resident Inspector.
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- nt 1 to Docum:nt Control Desk I.etter R., /
.' September 19i1989J
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. LEGEND FOR ATTACHMENT 1 l
AFD-Axial Flux Difference
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FAHRTP-F-deltaH limit at rated thermal power -
. FORTP-FQ limit at Rated Thermal Power COLR-Core Operating 1.imits 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 PFA11. Power Factor Multiplier for F-deltaH RCS-Reactor Coolant System
- W(Z)- Cycle dependent function that accounts for power distribution transients encounted during normal operation m-