ML18153B460

Summary of 940118 Meeting W/Representatives of VEPCO in Rockville,Md Re Approach Being Taken in Relation to Surry Core Uprate,Scheduled to Be Submitted on 940715

ML18153B460
Person / Time
Site:	Surry
Issue date:	02/08/1994
From:	Buckley B Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9402180038
Download: ML18153B460 (50)

Text

..

February 8,.4 Docket Nos. 50-280 and 50-281 LICENSEE:

Virginia Electric and Power Company FACILITY:

Surry Power Station, Units 1 and 2

SUMMARY

OF JANUARY 18, 1994, CORE UPRATE MEETING On January 18, 1994, a meeting was held with representatives of the Virginia Electric and Power Company (VEPCO) in Rockville, Maryland.

The purpose of the meeting was to provide VEPCO with an opportunity to discuss the approach that they are taking with regard to their SURRY CORE UPRATE report which is scheduled to be submitted on July 15, 1994.

The current licensed core power level is 2441 megawatts thermal (MWt), or 822 megawatts electric (MWe), while the uprated core power level would be 2546 MWt, or 856 MWe.

The 856 MWe core uprate power is equal to the original plant design "stretch" power.

A list of attendees and meeting handouts are enclosed.

VEPCO's presentation addressed (1) planned and potential plant modifications, (2) completed and on-going safety analyses, (3) licensing aspects, and (4) schedule and cost benefits.

Upon completion of the meeting, the licensee provided two additional handouts addressing 1) the on-going program regarding the universal container system for spent fuel storage, and 2) VEPCO's 5-year license renewal initiative.

Enclosures:

As Stated cc w/enclosures:

See next page OFFICE LA: PDII-2 NAME Elana ff-/'

DATE 02/ 7 /94 (Original Signed By)

Bart C. Buckley, Sr. Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Distribution Docket File NRC & Local PDRs PDII-2 RF TMurley/FMiraglia JPartlow HGarg PM: eDll-2 D:PD./ -2 BBub~y' Hij,rl tr 02/ C/ /94 I **

02\\i /94 SKlementowicz TSullivan SVarga OGC GLainas EJordan HBerkow JDavis BBuckley LLois Elana ADummer CWa RLobez KKarwoski LPlisco,EDO RII ACRS (10) MSinkule, RII OFFICIAL RECORD COPY - DOCUMENT NAME: C:\\AUTOS\\WPDOCS\\SURRY\\MTNOT.CUM 1<"..*1,......, -*,.,

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'I Docket Nos. 50-280 and 50-281

• February 6,~94 LICENSEE:

Virginia Electric and Power Company FACILITY:

Surry Power Station, Units 1 and 2

SUMMARY

OF JANUARY 18, 1994, CORE UPRATE MEETING On January 18, 1994, a meeting was held with representatives of the Virginia Electric and Power Company (VEPCO) in Rockville, Maryland.

The purpose of the meeting was to provide VEPCO with an opportunity to discuss the approach that they are taking with regard to their SURRY CORE UPRATE report which is scheduled to be submitted on July 15, 1994.

The current licensed core power level is 2441 megawatts thermal (MWt), or 822 megawatts electric (MWe), while the uprated core power l eve 1 would be 2546 MWt, or 856 MWe.

The 85.6 MWe core uprate power is equal to the original plant design "stretch" power.

A list of attendees and meeting handouts are enclosed.

VEPCO's presentation addressed (1) planned and potential plant modifications, (2) completed and on-going safety analyses, (3) licensing aspects, and (4) schedule and cost benefits.

Upon completion of the meeting, the licensee provided two additional handouts addressing 1) the on-going program regarding the universal container system for spent fuel storage, and 2) VEPCO's 5-year license renewal initiative.

Enclosures:

As Stated cc w/enclosures:

See next page OFFICE LA: PDII-2 PM:

(Original Signed By)

Bart C. Buckley, Sr. Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Distribution Docket File NRC & Local PDRs PDII-2 RF TMurley/FHiraglia JPartJ OW-JCallan HGarg SKlementowicz TSullivan SVarga OGC Glainas EJordan HBerkow JDavis BBuckley Llois ET an a ADunvner CWa RLobez KKarwoski LPlisco,EDO RII ACRS (10) HSinkule, RII DATE 02 7 94 02 C/

94 02 {,

94 OFFICIAL RECORD COPY - DOCUMENT NAME: C:\\AUTOS\\WPDOCS\\SURRY\\MTNOT.CUM

Virginia Electric and Power Company cc:

Michael W. Maupin, Esq.

Hunton and Williams Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, Virginia 23219 Mr. Michael R. Kansler, Manager Surry Power Station Post Office Box 315 Surry, Virginia 23883 Senior Resident Inspector Surry Power Station U.S. Nuclear Regulatory Commission Post Office Box 166, Route 1 Surry, Virginia 23883 Mr. Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23209 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Robert B. Strobe, M.D., M.P.H.

State Health Commissioner Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218 Surry Power Station Attorney General Supreme Court Building 101 North 8th Street Richmond, Virginia 23219 Mr. M. L. Bowling, Manager Nuclear Licensing & Programs Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, Virginia 23060 Mr. W. L. Stewart Senior Vice President - Nuclear Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, Virginia 23060

SURRY CORE UPRATING MEETING January 18, 1994 List of Attendees Bart Buckley Dave Sommers Jim Davis Lambros Lois Jamie Jacoby Gary Darden Kerry Basehore Wayne Harrell M. L. Bowling Ann Dummer Hukam Garg Cheng-Ih Wa Richard Lobel Stephen Klementowicz Ted Sullivan Ken Karwoski Office NRC/NRR VEPCO NRC/NRR NRC/NRR VEPCO VEPCO

• VEPCO VEPCO VEPCO NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR

Universal Container System *

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The UCS System

• Simple, Safe And Passive e-

• Limits The Handling Of Spent Fuel

• Limits Spent Fuel Transport

• Provides A Better Disposal Package

• Provides Needed Capacity Reduces The Total Cost Of Waste Disposal ewrrmzrrzn*rmnnrmwmnrsn s SF FEifffflMt!fffttt:t©M'fRttrttreea,,,wYtt1mM<<ilfWfftNt1tfftrMrtt11:etetWi/1w-cr** c, *' -o * * *:m*

PS059.14

Universal Container System (UCS)

• A Single Inner Container For Storage, Shipment, And Disposal Fuel Assembly UCS Inner Container PS059.6*13A

Standardized Steel Container Fuel Never Handled Again Encased In Reusable Overpacks Storage Transport Disposal PS059.7*14A

Universal Container System Status November, 1993 DOE Issued Draft Bid Package To Utilities, --

Vendors, And Others For Comments December, 1993 Industry (EEI/UWASTE) Endorsed The Concept And Expect DOE Approval

• May, 1994 DOE Request Bids

• August, 1994 Virginia Power Team Submit Bid December, 1995 DOE Schedule For Submitting UCS License Applications To NRC For Storage And Transport

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PS160.4

Virginia Power UCS Team Potential Team Members Virginia Power BWNT

- Transnuclear NAC Newport News Shipbuilding January 10, 1994 Initial Meeting February, 1994 Finalize Bid Participants And March, 1994 April, 1994 August, 1 994 Develop Agreement Develop Design Concept For Bid Initial Draft Of Bid, Scope Of Work, And Responsibilities Submit Bid

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Virginia Power Initial 5 Year

. License Renewal Initiative VIRGINIA POWER PT155.1 e.

Virginia Power Initial 5 Year License Renewal Initiative Virginia Power Is Considering License Renewal Applications For Surry And North Anna For An Additional 5 Years Because It Is

• Economically Attractive Due To Lower Busbar Costs

• Opportunity To Lower Near-Term Decommissioning Trust Collections

• May Reduce The Need For Rate Increases

• Provides More Incentive To Invest In Plant And Technological Upgrades To Maintain Higher Availability

• Demonstration Of License Renewal Approval Would Benefit The Entire Nuclear Industry And May Preclude Premature Permanent Shutdowns

• Provides Economically Competitive Additional Capacity Without Requiring Long-Term Commitments PT155.2 e

Nuclear 5-Year Life Extension Economic Analysis Assumptions:

80°/o Capacity Factor Effective Date 1997 O&M And Capital Expenditures Are Based On The 1993 - 1997 Five Year Plan Projections PT155.3 *300

Nuclear 5-Year Life Extension Economic Analysis Results:

Long-Term Effect The Net Present Value Savings In 1994 Dollars Exceeds $500 Million Annual Busbar Costs Are Reduced By About 3°/o Starting in 1997 Near-Term Effect Depreciation Expense Is Reduced Each Year,

$21 Million In 1997 And Up To $49 Million By 2011 Decommissioning Is Basically Unaffected, Early Year Reductions Offset By The Increase In Total Collections,

$6 Million Reduction In 1997 PT155.4 el e

Nuclear 5-Year Life Extension Economic Analysis Dollars In Millions Effect On Total Nuclear Depreciation Expense (Millions Of Day Collected Dollars) 270.....--~~~~~~~~~~~~~~~~~~~~~~~~~~

240 210 180 150 120 90 60 30 19941996 1998 2000 2002 2004 2006 2008 2010 2012 2014 2016 2018 2020 2022 2024 1995 1997 1999 2001 2003 2005 2007 2009 2011 2013 2015 2017 2019 2021 2023 2025 Base Case -

5 - Year Extension PT155.5 *305

Nuclear 5-Year Life Extension Economic Analysis Dollars In Millions Effect On Total Nuclear Decommissioning Collections (Millions Of Day Collected Dollars) 80---~~~~~~~~~~~~~~~~~~~~~---.

70 60 50 40 30 20 10 19941996 1998 2000 2002 2004 2006 2008 2010 2012 2014 2016 2018 2020 2022 2024 1995 1997 1999 2001 2003 2005 2007 2009 2011 2013 2015 2017 2019 2021 20232025 Base Case -

5 - Year Extension PT155.6

Virginia Power Initial 5 Year License Renewal Initiative This Initiative Is Intended To Complement The Full Twenty Year_Term License Renewal Efforts But Should Be Cheaper, Easier, And Quicker Virginia Power Strategy Is Predicated On The Premise That A 5 Year Application Should Be Significantly Less In Scope And Complexity Than What Is Currently Required Or Being Proposed

• Reliance On The Current Licensing Basis, The Maintenance Rule, And Existing Programs That Can Identify And Address Age Related Degradation Is Acceptable

• No Environmental Impact

• No Known Technical Limitations Identified To Date

• Safety Margins Inherent In The Current Licensing Bases Would Not Be Significantly Reduced

• Plant Design And Environmental Bases Are Conservative With Respect To Actual Plant Operation

• A No Significant Hazards Determination Should Be Reached PT155.7

Approach For An Initial 5 Year License Renewal Work Within The Proposed Revisions To 10 CFR 51 And 10 CFR 54, But Simplify Documentation Requirements And Reduce Need For Additional Analysis Obtain Industry EndorsementAnd Utilization PT155.8 e

SURRY POWER STATION CORE UPRATE VIRGINIA POWER JANUARY 18, 1994

INTRODUCTION VIRGINIA POWER E.W. HARRELL, VICE PRESIDENT NUCLEAR ENGINEERING SERVICES el

AGENDA INTRODUCTION GENERAL SCOPE AND PLANT MODIFICATIONS SAFETY ANALYSIS LICENSING SCHEDULE AND COST BENEFIT E. W. HARRELL J. Lm JACOBY G. L. DARDEN M. L. BOWLING E. W. HARRELL

SURRY CORE UPRATE EFFORT CURRENT LICENSED CORE POWER LEVEL OF 2441 MWt AND 822 MWe - UPRATED POWER LEVEL OF 2546 MWt AND 856 MWe UPRATED POWER LEVEL IS EQUAL TO ORIGINAL PLANT DESIGN "STRETCH" POWER LEVEL ANALYSES AND EVALUATIONS TO SUPPORT CORE UPRATE PROJECT HAVE BEEN ONGOING CURRENT EFFORT INVOLVES VALIDATING AND UPDATING PREVIOUS RESULTS TO REFLECT PRESENT PLANT CONDITIONS e

SURRY CORE UPRATE APPROACH SURRY APPROACH IS SIMILAR TO APPROVED NORTH ANNA UPRATE AND CONSISTENT WITH WESTINGHOUSE TOPICAL REPORT, WCAP-10263, WHICH OUTLINES CORE UPRATE GUIDANCE PRELIMINARY CONCLUSIONS DEMONSTRATE ACCEPTABILITY OF PLANT SYSTEMS AND COMPONENTS FOR UPRATED OPERATION PURPOSE OF THIS MEETING IS TO ADVISE NRC OF VIRGINIA POWER APPROACH AND SCHEDULE FOR SURRY CORE UPRATE IN ORDER TO FACILITATE NRC REVIEW e

GENERAL SCOPE AND PLANT MODIFICATIONS VIRGINIA POWER J. L. JACOBY, PROJECT ENGINEER FOR SURRY CORE UPRATE PROJECT NUCLEAR ENGINEERING I

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ORIGINAL VS. UPRATED RCS PARAMETERS ORIGINAL UPRATED REACTOR COOLANT SYSTEM NSSS POWER, MWt 2441 2554 THERMAL DESIGN FLOW, GPM 265500 265500 e

MASS FLOW, MILLION LBM/HR 100.7 101.1 PRESSURE, PSIA 2250 2250 TEMPERATURE, °F VESSEL OUTLET 605.6 605.6 VESSEL AVERAGE 574.3 573.0 STEAM GENERATOR OUTLET 543.0 540.2 STEAM GENERATOR STEAM TEMPERATURE, °F.

516.0 516.0 e

STEAM PRESSURE (MINIMUM GUARANTEED), PSIA 785.0 785.0 TOTAL STEAM FLOW, MILLION LBM/HR 10.66 11.23 FEEDWATER TEMPERATURE, °F 437.7 443.0 ZERO LOAD TEMPERATURE, °F 547.0 547.0

SURRY CORE UPRATE SCOPE AREAS EVALUATED CONSEQUENCES OF ACCIDENTS POSTULATED IN UFSAR CAPABILITY OF SYSTEMS AND EQUIPMENT TO MEET DESIGN BASES SPECIFIED IN UFSAR CAPABILITY OF EQUIPMENT TO MAINTAIN STRUCTURAL INTEGRITY UNDER CONDITIONS DEFINED IN UFSAR NSSS/BOP INTERFACES OPERATING LIMITS AND CONDITIONS CONTAINED IN TECHNICAL SPECIFICATIONS

SURRY CORE UPRATE SCOPE (continued)

PREVIOUS EVALUATIONS FOUND LITTLE IMPACT ON PLANT SYSTEMS AND COMPONENTS DUE TO UPRATED OPERATION CURRENT TASK

. REVERIFY BASES, METHODOLOGY, AND RESULTS OF PREVIOUS EVALUATIONS UPDATE PREVIOUS EVALUATIONS FOR PRESENT PLANT CONDITIONS 9

PERFORM PLA~T MODIFICATIONS, AS REQUIRED

EXAMINATION OF SYSTEMS, COMPONENTS, AND INTERFACES

_KEV NSSS AND BOP SYSTEMS, COMPONENTS, AND INTERFACES PREVIOUSLY EVALUATED PRELIMINARY CONCLUSIONS NSSS SYSTEMS ARE ACCEPTABLE AND IN COMPLIANCE WITH APPLICABLE CODES, STANDARDS, AND CRITERIA NSSS COMPONENTS ARE ACCEPTABLE AND ENVELOPED BY ORIGINAL DESIGN OR GENERIC COMPONENT DESIGN NSSS/BOP INTERFACES ARE ACCEPTABLE ACCEPTABILITY OF MASS AND ENERGY RELEASES REQUIRES ANALYTICAL REFINEMENTS OR PLANT MODIFICATIONS -

EVALUATION ONGOING BOP SYSTEMS ARE ACCEPTABLE WITH MINOR EXCEPTIONS TO BE ADDRESSED PRIOR TO UPRATED OPERATION e

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PLANT MODIFICATIONS COMPLETED MODIFICATIONS STEAM GENERATOR MOISTURE CARRYOVER MODIFICATIONS ON 1A, 18, 1C, AND 2A PLANNED MODIFICATIONS FIFTH POINT FEED HEATER DRAIN NOZZLE REINFORCEMENT DURING UNIT 21994 RFO AND UNIT 1 1995 RFO POTENTIAL MODIFICATIONS STEAM GENERATOR MOISTURE CARRYOVER MODIFICATIONS ON 28 AND 2C -TESTING MAY SHOW THAT MODIFICATIONS NOT NECESSARY INSIDE RECIRC SPRAY PUMP IMPELLER REPLACEMENT, IF NECESSARY, DURING UNIT 2 1994 RFO AND UNIT 1 1995 RFO RECIRC SPRAY NOZZLE REPLACEMENT, IF NECESSARY, DURING UNIT 2 1994 RFO AND UNIT 1 1995 RFO PROTECTION AND CONTROL SETPOINT REVISIONS AFTER LICENSE AMENDMENT APPROVAL

SAFETY ANALYSIS VIRGINIA POWER G. L. DARDEN, SENIOR STAFF ENGINEER NUCLEAR ANALYSIS AND FUEL

SAFETY ANALYSIS EVALUATION APPROACH EVALUATION APPROACH OF WCAP-10263 APPLIED IMPACT OF CORE UPRATE BEING EVALUATED TO VERIFY COMPLIANCE WITH RESPECT TO CURRENT PLANT LICENSING BASIS IMPACT OF CORE UPRATE ALSO BEING EVALUATED TO DETERMINE IF ANY UNREVIEWED SAFETY QUESTIONS EXIST EVENTS ADVERSELY AFFECTED BY PROPOSED OPERATING CONDITIONS BEING REANALYZED REANAL YSES EMPLOY CURRENT NRC-APPROVED ANAL VTICAL METHODS OR METHODOLOGY e

SAFETY ANALYSIS EVALUATION APPROACH

( continued)

ANALYTICAL METHODS BEING USED W NSSS CODES AND STANDARD THERMAL-HYDRAULIC DESIGN PROCEDURE (NRC APPROVED TOPICAL)

VIRGINIA POWER NSSS CODES AND STATISTICAL DNBR EVALUATION METHODOLOGY (NRC APPROVED TOPICAL)

W LOCA EVALUATION MODELS AND MASS AND ENERGY RELEASE MODEL (NRC APPROVED TOPICAL)

STONE & WEBSTER CONTAINMENT RESPONSE MODEL (EXISTING UFSAR BASIS USING LOCTIC CODE)

VIRGINIA POWER RADIOLOGICAL DOSE METHODOLOGY (NUREG-0800 RADIOLOGICAL DOSE METHODOLOGY APPLIED WITH LOCADOSE CODE)

NSSS ACCIDENT EVENTS CATEGORIZED BY IMPACT OF CORE UPRATE UFSAR EVENTS REQUIRING NO FURTHER VALIDATION OR REANALYSIS RCCA WITHDRAWAL FROM SUBCRITICAL CONDITION STARTUP OF AN INACTIVE REACTOR COOLANT LOOP

NSSS ACCIDENT EVENTS CATEGORIZED BY IMPACT OF CORE UPRATE (continued)

UFSAR EVENTS REQUIRING VALIDATION RUPTURE OF MAIN STEAM PIPE - CORE AND CONTAINMENT EFFECTS MAXIMIZED AT ZERO LOAD CONDITIONS, WHICH ARE NOT CHANGED FOR UPRATED OPERATION CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION EVENTS WITH EXISTING LICENSING BASIS ANALYSIS PERFORMED AT UPRATED CONDITIONS LOSS OF NORMAL FEEDWATER RUPTURE OF MAIN FEEDWATER PIPE EXCESSIVE HEAT REMOVAL DUE TO FEEDWATER SYSTEM MALFUNCTION SMALL BREAK LOSS OF COOLANT ACCIDENT RUPTURE OF A CONTROL ROD DRIVE MECHANISM HOUSING {ROD EJECTION)

NSSS ACCIDENT EVENTS CATEGORIZED BY IMPACT OF CORE UPRATE (continued)

UFSAR EVENTS REQUIRING REANALYSIS UNCONTROLLED RCCA WITHDRAWAL AT POWER CONTROL ROD ASSEMBL V DROP/MISALIGNMENT EXCESSIVE LOAD INCREASE INCIDENT COMPLETE LOSS OF REACTOR COOLANT FLOW PARTIAL LOSS OF REACTOR COOLANT FLOW LOCKED ROTOR INCIDENT LOSS OF EXTERNAL ELECTRICAL LOAD LARGE BREAK LOSS OF COOLANT ACCIDENT

SURRY CORE UPRATING

SUMMARY

ACCIDENT ANAL VSIS RESULTS FOR SELECTED COMPLETED ANALYSES SMALL BREAK LOSS OF COOLANT ACCIDENT KEV ASSUMPTIONS AND RESULTS CORE POWER, MWT 2546 HEAT FLUX HOT CHANNEL FACTOR, FQ 2.32 ENTHALPY RISE HOT CHANNEL FACTOR, FdH 1.65 ACCUMULATOR WATER VOLUME, FT3 EACH 1025 e

REACTOR VESSEL FLOWRATE, GPM 265500 STEAM GENERATOR TUBE PLUGGING (UNIFORM) 15°/o PEAK CLAD TEMPERATURE, °F LIMITING CASE BREAK 1839 3 INCH COLD LEG

SURRY CORE UPRATING

SUMMARY

ACCIDENT ANAL VSIS RESULTS FOR SELECTED COMPLETED ANAL VSES (continued)

LARGE BREAK LOSS OF COOLANT ACCIDENT KEY ASSUMPTIONS AND RESULTS CORE POWER, MWT HEAT FLUX HOT CHANNEL FACTOR, FQ ENTHALPY RISE HOT CHANNEL FACTOR, FdH ACCUMULATOR WATER VOLUME, FT3 EACH REACTOR VESSEL FLOWRATE, GPM STEAM GENERATOR TUBE PLUGGING (UNIFORM)

PEAK CLAD TEMPERATURE, °F LIMITING CASE BREAK 2546 2.32 1.62 1000 265500 15°/o 2120 0.4 CD DECLG e

LOCA MASS AND ENERGY RELEASES AND CONTAINMENT INTEGRITY OPERATION AT PROPOSED UPRATED CONDITIONS, WHILE ACCOMMODATING CURRENT TECH SPEC LIMITS AND SYSTEM CHARACTERISTICS, REQUIRES IMPROVEMENT IN ANALYSIS MARGIN MARGIN POTENTIALLY AVAILABLE FROM MASS AND ENERGY AND CONTAINMENT RESPONSE ANALYTICAL REFINEMENTS OR MODIFICATIONS TO CONTAINMENT HEAT REMOVAL EQUIPMENT ANALYSES ARE UNDERWAY TO QUANTIFY POTENTIAL MARGIN FROM EACH SOURCE

. I

LOCA MASS AND ENERGY RELEASES AND CONTAINMENT l*NTEGRITV (continued)

ANALYTICAL REFINEMENTS BEING INVESTIGATED REMOVE EXCESS CONSERVATISMS IN MASS AND ENERGY ANALYSIS AND CONTAINMENT RESPONSE ANALYSIS MODEL INPUTS CREATE A MORE RIGOROUS INTERFACE OF MASS AND ENERGY ANALYSIS AND CONTAINMENT RESPONSE ANAL VSIS ASSUMPTIONS AND DATA USAGE QUANTIFY INCREASED CONTAINMENT HEAT REMOVAL CAPABILITY FROM POTENTIAL MODIFICATIONS INSIDE RECIRC SPRAY PUMP IMPELLER REPLACEMENT RECIRC SPRA V NOZZLE REPLACEMENT PRELIMINARY RESULTS: EARLY FEBRUARY 1994 FINAL ANALYSIS: APRIL 1994 I

• ACCIDENT RADIOLOGICAL CONSEQUENCES DOSE CONSEQUENCES OF EVENTS FOR SURRY CORE UPRATE BEING RECALCULATED UPRATE ANALYSES PERFORMED WITH LOCADOSE CODE ASSUMPTIONS CONSISTENT WITH NUREG-0800 GUIDELINES ATMOSPHERIC DISPERSION FACTORS USED WERE DETERMINED FOR SURRY SITE METEOROLOGY BASED ON NRC REGULATORY GUIDE 1.145 I -

ACCIDENT RADIOLOGICAL CONSEQUENCES (continued)

EVENTS SELECTED WERE THOSE WHICH COULD POTENTIALL V PRODUCE SIGNIFICANT CONTROL ROOM OR OFFSITE DOSE CONSEQUENCES LARGE BREAK LOSS OF COOLANT ACCIDENT STEAM GENERATOR TUBE RUPTURE LOCKED ROTOR INCIDENT MAIN STEAM LINE BREAK FUEL HANDLING ACCIDENT WASTE GAS DECAY TANK RUPTURE

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ACCIDENT RADIOLOGICAL CONSEQUENCES PRELIMINARY CONCLUSIONS APPLICABLE THYROID, SKIN, AND WHOLE BODY LIMITS MET FOR ALL EVENTS CONTROL ROOM 30-DAY DOSE (GDC 19)

EXCLUSION AREA BOUNDARY 2-HOUR DOSE (10CFR100)

LOW POPULATION ZONE 30-DAY DOSE (10CFR100)

ANALYSES INCORPORATED WOG METHODOLOGY FOR EVENTS AFFECTED BY STEAM GENERATOR TUBE

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UNCOVERY (LOCKED ROTOR AND STEAM GENERATOR e

TUBE RUPTURE)

ANALYSIS MARGIN INCREASED FOR THE LIMITING EVENT (LARGE BREAK LOSS OF COOLANT ACCIDENT)

SAFETY ANALYSIS EVALUATION

• STATUS

SUMMARY

ANALYSES FOR UPRATED OPERATION WILL MEET APPLICABLE ACCEPTANCE CRITERIA WHILE ACCOMMODATING EXISTING PLANT EQUIPMENT CAPABILITY CONTAINMENT EVALUATION UNDERWAY TO MINIMIZE PLANT MODIFICATIONS INCORPORATING REVISED ANALYTICAL METHODS (E.G., STATISTICAL DNBR, LBLOCA EVALUATION MODEL, RADIOLOGICAL EVALUATION)

ACCOMMODATING FUTURE CORE DESIGN REQUIREMENTS EXPECTATION IS THAT FINAL RESULTS OF MOST NSSS ACCIDENT ANALYSES, CONTAINMENT ANALYSES, AND EVENT RADIOLOGICAL CONSEQUENCES WILL CONTAIN MORE MARGIN TO ACCEPTANCE CRITERIA THAN EXISTING ANALYSES c

• LICENSING VIRGINIA POWER M. L. BOWLING, MANAGER NUCLEAR LICENSING AND PROGRAMS r

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LICENSING SUBMITTAL LEVEL OF DETAIL OF SUBMITTAL WILL BE COMPARABLE TO UFSAR UPDATE SUBMITIAL WILL ADDRESS METHODOLOGY AND SCOPE OVERVIEW NSSS UPRATING SAFETY EVALUATION BOP UPRATING SAFETY EVALUATION DESCRIPTION OF ANY REQUIRED MODIFICATIONS SIGNIFICANT HAZARDS CONSIDERATION TECHNICAL SPECIFICATION REVISIONS

TECHNICAL SPECIFICATIONS EXPECTED TO BE REVISED TECHNICAL SPECIFICATIONS ADDRESSING NSSS POWER LEVEL T-AVERAGE OVERTEMPERATURE AND OVERPOWER DEL TA-T PARAMETERS OTHER IMPACTED SETPOINTS AND LIMITS BASED ON ACCIDENT REANAL VSES

LICENSING CONCLUSIONS SURRY APPROACH IS SIMILAR TO APPROVED NORTH ANNA UPRATE AND CONSISTENT WITH WESTINGHOUSE TOPICAL REPORT, WCAP-10263 REANAL YSES EMPLOY CURRENT NRC-APPROVED ANALYTICAL METHODS OR METHODOLOGY PRELIMINARY CONCLUSIONS DEMONSTRATE ACCEPTABILITY OF PLANT SYSTEMS AND COMPONENTS FOR UPRATED OPERATION COMPLIANCE WITH RESPECT TO CURRENT PLANT LICENSING BASIS WILL BE MAINTAINED e

SCHEDU-LE AND COST BENEFIT VIRGINIA POWER E.W. HARRELL, VICE PRESIDENT NUCLEAR ENGINEERING SERVICES

CORE UPRATE SCHEDULE COMPLETION OF VALIDATION AND REANALYSIS BY APRIL 1994 SUBMITTAL OF LICENSE AMENDMENT FOR NRC REVIEW AND APPROVAL PLANNED FOR JULY 15, 1994 SCHEDULE FOR POTENTIAL PLANT MODIFICATIONS UNIT 1 - END OF 1995 RFO (NOVEMBER 1995)

UNIT 2 - END OF 1994 RFO (JA_NUARY 1995)

THIS SCHEDULE PERMITS IMPLEMENTATION UPON NRC APPROVAL IMPLEMENTATION AT POWER IS PLANNED AS WAS DONE FOR NORTH ANNA e

RESULTS OF ECONOMIC STUDY OF SURRY CORE UPRATE ASSUMPTIONS 4.5% UPRATE OF SURRY UNITS 1 AND 2

$5.0 MILLION TOTAL CAPITAL EXPENDITURES IN 1995 80% CAPACITY FACTOR EFFECTIVE DATE OF JANUARY 1, 1996 DECOMMISSIONING DATES UNIT 1 - MAY 31, 2012 UNIT 2 - JANUARY 31, 2013 RESULTS NET PRESENT VALUE INCREASED BY $133.6 MILLION WHICH IS A 10.7 o/o IMPROVEMENT e