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Line 24: |
Line 24: |
| Miller at (804) 273-2771. | | Miller at (804) 273-2771. |
| Very truly yours, | | Very truly yours, |
| -?I E. S. Grecheck | | -?I E. S. Grecheck Vice President Nuclear Support Services Commitments made in this letter: |
| -
| |
| Vice President Nuclear Support Services Commitments made in this letter: | |
| : 1. No new commitments are made in this letter. Consistent with previous commitment: | | : 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. | | The Large Break LOCA re-analysis for Surry will be submitted by March 31, 2006. |
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Category:Letter
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[Table view] Category:Report
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[Table view] Category:Miscellaneous
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ML12166A5192012-06-14014 June 2012 Transmittal of Final Accident Sequence Precursor (ASP) Analysis ML12073A3852012-03-0808 March 2012 Resources Services, Inc., Notification Letter That Surry Power Station Not Received a Copy of the Waste Shipment Record (Wsr) Signed by the Owner or Operator of the Designated Waste Disposal Site ML12046A8492012-02-27027 February 2012 Review of the Steam Generator Tube Inservice Inspection Report for the Refueling Outage in 2010 ML12024A0782011-12-28028 December 2011 State-of-the-Art Reactor Consequence Analysis (Soarca); Exclusive Summary for the Full NUREG for Peach Bottom and Surry ML1120701442011-07-26026 July 2011 Draft Letter Report, Entitled Risk-Informing EP Oversight: Evaluation of EALs Using Saphia Pilot Study of Peach Bottom and Surry ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML12124A2972010-03-11011 March 2010 Soarca Documents Review/Approval Process ML12124A2962010-02-25025 February 2010 Soarca Peer Review Comments ML0929905702009-10-26026 October 2009 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0820701992008-07-18018 July 2008 Order EA-03-009 Sixty-Day Report Reactor Pressure Vessel Head Inspection Results ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0623300712006-08-16016 August 2006 Fitness-for-Duty Program Semi-Annual Performance Data Report ML0634101622006-02-27027 February 2006 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0523501142005-08-22022 August 2005 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0523504842005-08-22022 August 2005 Owner'S Activity Reports ML0518804802005-07-0707 July 2005 Day Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML0514603252005-05-25025 May 2005 .2 & 3, North Anna Power Station Units 1 & 2, Surry Power Station Units 1 & 2 - Nuclear Liability Insurance Endorsement ML0506001202005-02-28028 February 2005 Owner'S Activity Reports ML0505403042005-02-22022 February 2005 Fitness-for-Duty Program Semi-Annual Performance Data Report Correction of Information ML0505300392005-02-21021 February 2005 Fitness-for-duty Program Semi-Annual Performance Data Report ML0424501642004-08-31031 August 2004 Transmittal of Fitness-for-Duty Program Semi-Annual Performance Data Report for Millstone, North Anna, and Surry Power Stations ML0318903372003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Millstone, Nort ML0234303432002-12-0202 December 2002 Response to Request for Additional Information, Dominion'S Reload Nuclear Design Methodology Topical Report ML19094A2461971-11-0404 November 1971 Transmittal of Final Report Concerning the Operating License Review 2023-02-22
[Table view] |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICMOND,VIRGINIA 23261 July 7, 2005 U S . Nucle r Regulatory Commission Serial No. 5-383 Attention: Document Control Desk NL&OS/GDM RO Washington, DC 20555 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 10CFR50.46(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 10CFR50.46. 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 10CFR50.46 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 10CFR50.46(b)(l). However, the PCT Assessments for 10CFR50.46(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 10CFR50.46(a)(3)(i). A 30-day report is therefore required to report the PCT assessment results.
10CFR50.46(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 10CFR50.46 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 10CFR50.46 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.
Attachments
- 1. Report of Changes in Westinghouse Large Break LOCA ECCS Evaluation Model -
Surry Power Station Units 1 and 2
- 2. Reporting of 10CFR50.46 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 11555 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 11555 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 Attachment 1, 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 10CFR50.46. 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
-122°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 Attachment 1, 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 10CFR50.46(b)(l). An evaluation was also performed to determine if the reported changes are significant. The PCT Assessments for 10CFR50.46(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 10CFR50.46 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 10CFR50.46 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 Attachment 2, Page 1 of 2 10CFR50.46 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 21 17 MARGIN ALLOCATIONS (Delta PCT)
A. Prior Permanent ECCS Model Assessments
- 1. LBLOCNSeismic SG Tube Collapse
- 2. BASH EM Transient Termination
- 3. LOCBART Fluid Property Logic Issue B. Planned Plant Change Evaluations
- 1. None 0 C. 2005 Permanent ECCS Model Assessments
- 1. LOCBART ZIRLOTMCladding Specific Heat Model Error 16 (2)
- 2. PAD 4.0 Initial Pellet Temperatures -122 (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 0 E. Other Margin Allocations
- 1. None 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 10CFR50.46(a)(3)(i).
Serial Number 05-383 Docket Nos. 50-280/281 Attachment 2, Page 2 of 2 10CFR50.46 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 Analysis Date: 2001 Vendor: W estinghouse FQ: 2.32 FAH: 1.62 Fuel: SIF SGTP (%): 15 Notes: None Clad TemD (OF) Notes LICENSING BASIS Analysis of Record PCT 21 17 MARGIN ALLOCATIONS (Delta PCT)
A. Prior Permanent ECCS Model Assessments
- 1. LBLOCNSeismic SG Tube Collapse
- 2. BASH EM Transient Termination
- 3. LOCBART Fluid Property Logic Issue B. Planned Plant Change Evaluations
- 1. None 0 C. 2005 Permanent ECCS Model Assessments
- 1. LOCBART ZIRLOTMCladding Specific Heat Model Error 16 (2)
- 2. PAD 4.0 Initial Pellet Temperatures -122 (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 0 E. Other Margin Allocations
- 1. None 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 10CFR50.46(a)(3)(i).