ML051880480
| ML051880480 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/07/2005 |
| From: | Grecheck E Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 05-383 | |
| Download: ML051880480 (9) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICMOND, VIRGINIA 23261 US. Nucle July 7, 2005 r Regulatory Commission Serial No.
Attention: Document Control Desk Washington, DC 20555 5-383 NL&OS/GDM RO Docket Nos.
50-280/281 License Nos. DPR-32/37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 30-DAY REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 Pursuant to 1 OCFR50.46(a)(3)(ii), Virginia Electric and Power Company (Dominion) is providing information concerning changes to the Surry Power Station Units 1 and 2 large break LOCA ECCS Evaluation Model and its application in existing licensing analyses. Information is also provided which quantifies the effect of these changes upon reported results for Surry Units 1 and 2 and demonstrates continued compliance with the acceptance criteria of 1 OCFR50.46. provides information describing plant-specific model changes associated with the application of the Westinghouse large break LOCA evaluation model for Surry Units 1 and 2. These changes are in addition to those previously provided in Dominions 2004 1 OCFR50.46 Annual Report dated June 30,2005 (Serial No.05-380).
Information regarding the effect of the ECCS Evaluation Model changes upon the reported large break LOCA analysis of record (AOR) results is provided for Surry Units 1 and 2 in. To summarize the information in Attachment 2, the calculated peak cladding temperature (PCT) for Surry Units 1 and 2 is 1963°F. The Surry Units 1 and 2 large break LOCA results were confirmed to have sufficient margin to the 2200°F limit specified in 1 OCFR50.46(b)(l).
- However, the PCT Assessments for 1 OCFR50.46(a)(3)(i) accumulation are greater than the 50°F limit for reporting and thus represent a significant change based on the criterion established in 1 OCFR50.46(a)(3)(i). A 30-day report is therefore required to report the PCT assessment results.
1 OCFR50.46(a)(3)(ii) requires that the 30-day report include a proposed schedule for providing a reanalysis or taking other action as may be needed to show compliance with 1 OCFR50.46 requirements. In a letter dated May 21, 2003 (Serial No.03-350),
Dominion submitted the 2002 annual report of ECCS model changes, as well as a 30-day report due to a significant change in PCT for the Surry large break LOCA. In that letter Dominion committed to complete a re-analysis of the large break LOCA for Surry by March 31, 2006. No further action beyond the previous commitment is required to demonstrate compliance with 1 OCFR50.46 requirements.
Serial Number 05-383 Docket Nos. 50-280/281 Page 2 of 3 If you have further questions or require additional information, please contact Mr. Gary D.
Miller at (804) 273-2771.
Very truly yours, I?-
E. S. Grecheck Vice President - Nuclear Support Services Commitments made in this letter:
- 1. No new commitments are made in this letter. Consistent with previous commitment:
The Large Break LOCA re-analysis for Surry will be submitted by March 31, 2006.
Attach men ts
- 1. Report of Changes in Westinghouse Large Break LOCA ECCS Evaluation Model -
Surry Power Station Units 1 and 2
- 2. Reporting of 1 OCFR50.46 Margin Utilization - Westinghouse Large Break LOCA ECCS Evaluation Model - Surry Power Station Units 1 and 2
Serial Number 05-383 Docket Nos. 50-280/281 Page 3 of 3 cc:
U.S.
Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. S. R. Monarque US NRC One White Flint North 1 1555 Rockville Pike Mail Stop 8H12 Rockville, MD 20852-2738 Mr. R. E. Martin NRC Lead Project Manager - North Anna and Surry U. S. Nuclear Regulatory Commission One White Flint North 1 1555 Rockville Pike Rockville, Maryland 20852 Mr. N. P. Garrett NRC Senior Resident Inspector Surry Power Station
Serial Number 05-383 Docket Nos. 50-280/281 ATTACHMENT 1 REPORT OF CHANGES IN WESTINGHOUSE LARGE BREAK LOCA ECCS EVALUATION MODEL SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
Serial Number 05-383 Docket Nos. 50-280/281, Page 1 of 2 ReDort of Chanaes in Surw Power Station Units 1 and 2 Dominion recently performed site-specific sensitivity cases for the large break LOCA analysis for Surry Units 1 and 2. As a result of this analysis, changes in the PCT licensing basis were identified and assessed. The results of this PCT assessment are provided below.
Identification of ECCS EM Chanaes The current large break LOCA analysis for Surry Units 1 and 2 was performed using the Westinghouse BASH Evaluation Model. The LOCBART computer code is one of the codes used in the Westinghouse BASH Evaluation Model. The LOCBART code calculates the cladding temperature and oxidation transients for the highest powered fuel rod in the core, which are ultimately reviewed against the acceptance limits of 1 OCFR50.46. The four separate changes addressed in this evaluation are summarized below.
0 LOCBART ZIRLO Cladding Specific Heat Model Error Dominion quantified a Surry-specific sensitivity result to assess the impact of the revised LOCBART ZlRLO cladding specific heat model on the Surry analysis of record (AOR). Previously, Reference 1 reported a generic effect of +40°F for this item that was provided by Westinghouse. The Surry-specific sensitivity result quantifies the effect of this item as +16"F.
0 PAD 4.0 Initial Pellet Temperatures Dominion quantified a Surry-specific sensitivity result to assess the impact of using the PAD 4.0 fuel properties versus PAD 3.4 used in the Surry AOR.
Previously, Reference 1 reported a generic effect of -40°F for this item that was provided by Westinghouse. The Surry-specific sensitivity result quantifies the effect of this item as
-1 22°F.
Removal of Part-Length Control Rod Drive Mechanisms (CRDMs)
Dominion quantified the effect of an input correction in the previous calculation of the sensitivity result that assessed the removal of the Part-Length CRDMs. The previous result of +6"F was reported in Reference 1. Correction of the input error resulted in a PCT impact of -66°F.
Serial Number 05-383 Docket Nos. 50-280/281, Page 2 of 2 Pressurizer Surge Line Piping Schedule Reconciliation Dominion quantified a Surry-specific sensitivity result to assess the impact of a change in the surge line piping inner diameter (ID) and schedule assumed in the Surry AOR.
This item was addressed by Dominion and Westinghouse during preparation of model design inputs for a Surry Best-Estimate LBLOCA analysis. The documented design input data was used in the BASH sensitivity calculation. The design input involved revising the assumed surge line geometry from a 14-inch Schedule 160 to a 12-inch Schedule 140 pipe. This item has not been previously reported. The Surry-specific sensitivity result quantifies the effect of this item as +8F.
Conclusion Dominion has performed an evaluation of PCT for comparison to 10 CFR 50.46 requirements. The Surry Units 1 and 2 large break LOCA results were confirmed to have sufficient margin to the 2200°F limit specified in 1 OCFR50.46(b)(l). An evaluation was also performed to determine if the reported changes are significant. The PCT Assessments for 1 OCFR50.46(a)(3)(i) accumulation are greater than the 50°F limit for reporting; hence, the changes are significant and submittal of a 30-Day Report to the NRC is required. Previously, a commitment to reanalyze the large break LOCA for Surry was made in a May 21, 2003 letter (Serial No.03-350). Based upon the evaluation of this information, the associated changes in the applicable licensing basis PCT results and the previous commitment to submit the large break LOCA re-analysis for Surry by March 31, 2006, no further action is required to demonstrate compliance with 1 OCFR50.46 requirements.
References
- 1. Letter from E. S. Grecheck of Virginia Electric and Power Company to the USNRC dated June 30, 2005 (Serial No.05-380), Dominion Nuclear Connecticut, Inc.,
Virginia Electric and Power Company, Millstone Power Station Units 2 and 3, North Anna Power Station Units 1 and 2, Surry Power Station Units 1 and 2, 2004 Annual Report of Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46.
Serial Number 05-383 Docket Nos. 50-280/281 ATTACHMENT 2 REPORTING OF 1 OCFR50.46 MARGIN UTILIZATION WESTINGHOUSE LARGE BREAK LOCA ECCS EVALUATION MODEL SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
Serial Number 05-383 Docket Nos. 50-280/281, Page 1 of 2 1 OCFR50.46 Margin Utilization - Westinghouse Large Break LOCA Plant Name:
Surry Power Station, Unit 1 Utility Name:
Virginia Electric and Power Company Analvsis Information EM:
BASH Limiting Break Size:
Cd=0.4 Analysis Date:
2001 Vendor :
Westinghouse FQ:
2.32 FAH:
1.62 Fuel:
SIF SGTP (%):
15 Notes:
None Clad Temr, (OF1 Notes LICENSING BASIS Analysis of Record PCT MARGIN ALLOCATIONS (Delta PCT)
A.
Prior Permanent ECCS Model Assessments
- 1.
LBLOCNSeismic SG Tube Collapse
- 2.
- 3.
LOCBART Fluid Property Logic Issue B.
Planned Plant Change Evaluations
- 1.
None 21 17 0
C.
2005 Permanent ECCS Model Assessments
- 1.
LOCBART ZIRLOTM Cladding Specific Heat Model Error 16 (2)
- 2.
PAD 4.0 Initial Pellet Temperatures
-1 22 (21
- 3.
Removal of Part-Length CRDMs
-66 (2)
- 4.
Pressurizer Surge Line Piping Schedule Reconciliation 8
(21 D.
Temporary ECCS Model Issues
- 1.
None E.
Other Margin Allocations
- 1.
None 0
0 LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT=
1963 Notes:
{1}
A generic steam generator LOCNseismic load evaluation was performed by Westinghouse to quantify the potential steam generator tube collapse, which may occur at the time of the LOCA due to combined LOCA and seismic loads. Based on this analysis, a total steam generator tube reduction equivalent to 5% tube plugging was allocated as a permanent assessment for those plants that do not have a detailed analysis. The 5% steam generator tube plugging reduction will be used to account for the effects of a combined LOCNseismic event at Surry.
(2)
The accumulation of changes for these items (sum of absolute magnitudes) since the last 30-day report or reanalysis is greater than 50°F and is significant, as defined in 1 OCFR50.46(a)(3)(i).
Serial Number 05-383 Docket Nos. 50-280/281, Page 2 of 2 1 OCFR50.46 Margin Utilization - Westinghouse Large Break LOCA Plant Name:
Surry Power Station, Unit 2 Utility Name:
Virginia Electric and Power Company Analvsis Information EM:
BASH Limiting Break Size:
Cd=0.4 Vendor:
W estinghouse FQ:
2.32 FAH:
1.62 Fuel:
SIF SGTP (%):
15 Notes:
None LICENSING BASIS Analysis Date:
2001 Clad TemD (OF)
Notes 21 17 Analysis of Record PCT MARGIN ALLOCATIONS (Delta PCT)
A.
Prior Permanent ECCS Model Assessments
- 1.
LBLOCNSeismic SG Tube Collapse
- 2.
- 3.
LOCBART Fluid Property Logic Issue B.
Planned Plant Change Evaluations
- 1.
None 0
C.
2005 Permanent ECCS Model Assessments
- 1.
LOCBART ZIRLOTM Cladding Specific Heat Model Error 16 (2)
- 2.
PAD 4.0 Initial Pellet Temperatures
-1 22 (21
- 3.
Removal of Part-Length CRDMs
-66 (21
- 4.
Pressurizer Surge Line Piping Schedule Reconciliation 8
(2)
D.
Temporary ECCS Model Issues
- 1.
None E.
Other Margin Allocations
- 1.
None 0
0 LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT=
1963 Notes:
(1)
A generic steam generator LOCNseismic load evaluation was performed by Westinghouse to quantify the potential steam generator tube collapse, which may occur at the time of the LOCA due to combined LOCA and seismic loads. Based on this analysis, a total steam generator tube reduction equivalent to 5% tube plugging was allocated as a permanent assessment for those plants that do not have a detailed analysis. The 5% steam generator tube plugging reduction will be used to account for the effects of a combined LOCNseismic event at Surry.
(2)
The accumulation of changes for these items (sum of absolute magnitudes) since the last 30-day report or reanalysis is greater than 50°F and is significant, as defined in 1 OC FR50.46( a) (3) (i).