ML18153A777
| ML18153A777 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/06/1995 |
| From: | Sanders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18153A778 | List: |
| References | |
| 95-273A, NUDOCS 9510120173 | |
| Download: ML18153A777 (8) | |
Text
{{#Wiki_filter:I PRIORITY l. ~(ACCELERATED RIDS PROCESSING) ~ REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NBR:9510120173 DOC.DATE: 95/10/06 NOTARIZED: NO DOCKET# FACIL: 50-281 Surry Power Station, Unit 2, Virgi'nia Electric & Powe 05000281 P AUTH.NAME AUTHOR AFFILIATION SANDERS,R.F. Virginia Power (Virginia Electric & Power Co.) RECIP.NAME RECIPIENT AFFILIATION R Document Control Branch (Document Control Desk)
SUBJECT:
Forwards Rev 1 to *"COLR Surry 2 Cycle 13 Pattern UG," for Jul 1995.Changes results of accident reanalyses performed to support core uprate TS revs & implementation program. DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR _l_ ENCL j__ SIZE:/-1-- :>': TITLE: OR Submittal: General Distribution NOTES: INTERNAL: EXTERNAL: NOTES: RECIPIENT COPIES ID CODE/NAME LTTR ENCL P:02-1 LA 1 1 BUCKLEY,B 1 1 ACRS 6 6 NRR/DE/EMCB 1 1 NRR/DSSA/SPLB 1 1 NUDOCS-ABSTRACT 1 1 NOAC 1 1 1 1 NOTE TO ALL "RIDS" RECIPIENTS: RECIPIENT ID CODE/NAME PD2-1 PD FILE CENTER
- ffiHTCB NRR/DSSA/SRXB OGC/HDS2 NRC PDR COPIES LTTR ENCL 1
1 1 1 1 1 1 1 1 1 0 1 PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D8 (415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR. DOCUMENTS YOU DON'T NEED! TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 18 05000281 I 0 R I T y 1 D 0 C u M E N T
e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 6, 1995 United States Nuclear Regulatory Commission Atteintion: Document Control Desk Wa:3hington, D. C. 20555 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY SUBRY POWER STATION UNIT 2 Serial No. 95-273A NA&F/RTR-CGL RO Docket Nos. 50-281 License Nos. DPR-37 REVISED CYCLE 13 CORE OPERATING LIMITS REPORT As required by Technical Specification 6.2.C, attached is a copy of the revised Core Opeirating Limits Report (COLR) for Surry Unit 2 Cycle 13 Pattern UG. This mid-cycle revision of the COLR is necessitated by the implementation of core uprate (from 2441 MWt to 2546 MWt) at power during Unit 2 Cycle 13. The changes to the Cycle 13 COLR, transmitted by a June 1, 1995 letter (Serial No. 95-273), include
- 1) an increase in the Moderator Temperature Coefficient from +3 pcm/°F to +6 pcm/°F at less than 50% of rated power and 2) separate FL\\H limits for LOPAR and SIF fuel.
These changes are the result of the accident reanalyses performed to support the core uprate technical specification revisions and implementation program. If you have questions or require additional information, please contact us. Very truly yours, R. F. Saunders, Vice President Nuclear Operations Attachment - Core Operating Limits Report - Surry 2 Cycle 13 Pattern UG, Revision 1 cc: Mr. S. D. Ebneter, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station 9510120173 951006 PDR ADOCK 05000281 ... -.P. _____ '."'--*-a--, ___,~PDR
e CORE OPERATING LIMITS REPORT SURRY 2 CYCLE 13 PATTERN UG Revision 1 July,* 1995 S2C13/UG COLR, Rev. 1 (July 95) 9510120180 951006 PDR ADOCK 05000281 P PPR Page 1 of 6
e 1..0 CORE OPERATING LIMITS REPORT 'I'he Surry 2 Cycle 13 Core Operating Limits Report (COLR) has been revised to reflect changes in COLR parameters impacted by the implementation of the core uprate (increase in thermal power from 2441 MW to 2546 MW) for Surry Power Station Unit 2. Accident reanalyses for core uprate utilized a maximum positive moderator temperature coefficient of +6 pcm/°F versus the previous analysis value of +3 pcm/°F. Technical Specifications 3.1.E and 5.3.A.6.b place an upper limit of +6 pcm/°F on the MTC.
- Section 2.1 of this COLR has been revised to incorporate the +6 pcm/°F value.
The increase in power requires that a reduction in the F~H limit be made to ensure that the LOPAR fuel still meets thermal-hydraulic requirements. To accommodate this without unnecessarily penalizing the SIF fuel, separate F~H limits for LOPAR and SIF fuel have been established which ensure DNB limits are met for the applicable fuel type. This change is reflected in COLR section 2. 4 Nuclear Enthalpy Rise Hot Channel Factor - Ft.H(N). This Core Operating Limits Report for Surry Unit 2 Cycle 13 operation at uprate conditions has been prepared in accordance with the requirements of Technical Specification (TS) 6.2.C. The Technical Specifications affected by this report are: TS 3.1.E and TS 5.3.A.6.b - Moderator Temperature Coefficient TS 3.12.A.2 and TS 3.12.A.3 - Control Bank Insertion Limits TS 3.12.B.1 and TS 3.12.B.2 - Power Distribution Limits S2Cl3/UG COLR, Rev. 1 (July 95) Page 2 of 6
2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.2.C. 2.1 Moderator Temperature Coefficient (TS 3.1.E and TS 5.3.A.6.b) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are: +6.0 pcm/°F at less than 50 percent of RATED POWER, or +6.0 pcm/°F at 50% of Rated Power and linearly decreasing to O pcm/°F at Rated Power 2.2 Control Bank Insertion Limits (TS 3.12.A.2) 2.2.1 The control rod banks shall be limited in physical insertion as shown in Figure 1. 2.3 Heat Flux Hot Channel Factor-FO(Z) (TS 3.12.B.1) FQ(Z) s FQ(Z) s CFQ p CFQ 0.5
- K(Z) FOR P > 0.5
- K(Z) for P s 0.5 THERMAL POWER where:
P = -------------- RATED POWER 2.3.1 CFQ = 2.32 2.3.2 K(Z) is provided in Figure 2. S2C13/UG COLR, Rev. 1 (July 95) Page 3 of 6
2 *. 4 Nuclear Enthalpy Rise Hot Channel Factor - F.t..H (N) (TS 3.12. B.1) F.t..H(N) s CFDH * (1 + PFDH * (1 - P)) THERMAL POWER where: P = ------------- RATED POWER 2.4.1.a 2.4.1.b 2.4.2 CFDH = 1.56 for Surry Improved fuel (SIF} CFDH = 1.346 for LOPAR fuel PFDH = 0.3 S2C13/UG COLR, Rev. 1 (July 95) Page 4 of 6
e FIGURE 1 CONTROL BANK INSERTION LIMITS FULLY WITHDRAVv'N = 227 Steps / .475, 2. 7) V / / / C BanK .. v 1.0, 18~) / / / // /.,,,. z 230 220 210 200 190 180 170 160 0 150 ~ V / ci5 - 140 0 C C.. ~ 130 a..... ~ ~ 120 ~ ~ 110 5 g-100 ffi §_ 90 0 o* 80 a: 70 60 50 40 30 20 10 0 co. 1s1; / / .-{a, 23) 0 0.1 / / V / / D Bark // / /v V / / / 0.2 0.3 0.4 0.5 0.6
- 0. 7 0.8 FRACTION OF RATED THERMAL POWER S2C13/UG COLR, Rev. 1 (July 95) 0.9 Page 5 of 6
FIGURE 2 K(Z) - NORMALIZED FQ AS A FUNCTION OF CORE HEIGHT 1.2 1.1 6, 1.0 1 (1 2. 0.925 -- 0.9 0.8 - N - 0 LL 0 0.7 UJ N
- i < 0.6
- l:
C: 0 z I 0.5 N - ~ 0.4 0.3 0.2 0.1 0 0 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (FT) S2C13/UG COLR, Rev. 1 (July 95) Page 6 of 6}}