ML051930356
| ML051930356 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley  |
| Issue date: | 07/11/2005 |
| From: | FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML051930356 (34) | |
Text
Beaver Valley Power Station Unit 1 Replacement Steam Generator Proj ct Working Level Meeting:
Replacement Steam Generator License Amendment Request July 11, 2005 1 1~s~egyula FENOC Oprtn
Agenda
- Introduction ............................ (Greg Halnon)
- Background .......................... (Mark Manoleras)
- RAI Inter-relationships ................ (John Maracek)
- Concluding Remarks ................(MarkManoleras)
- Comments / Questions ..................... ... (All) 2FrsnegNulaOprin FENOC
Desired Outcome Provide NRC with:
- General understanding of replacement steam generator (RSG) license amendment request (LAR) & its relationship to other BVPS LARs
- Overview of proposed project approach and schedule
- Facilitate efficient and quality transfer of information FENOC FirstEnergy Nuclear Operatig Company
Background
Mark Manoleras ManagerBV Design Engineering 4 .....
FENOC nrp Nuclea O eai jn'
Background
Full Potential With RSG 5
FENOC FirstEnergy Nuclear Operating Company
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Background
- Submitted April 2Q05
- Needed for RSG Implementation, Feb.
2006 (1R17 Refueling Outage)
- Based on EPU Analysis at 2900 MWt
-RSG LAR does not request a power increase 6
FENOC FirstEnergy Nuclear Operating Comp'any
Background
- Start up from 1R17 with RSGs is dependent upon:
Approval of Containment Conversion
>LAR 1A-317, Submitted June 2004, Approval anticipated - Sept 2005
- Approval of Best Estimate LOCA
>LAR 1A-318, Submitted October 2004, Approval anticipated - Sept 2005 7
FENOC FirstEnergy Nuclear Operating Cornpaniy
Overview of RSG LAR Ste/e Sarver Staff Licensing Engineer 8
FENOC FirstEnergy Nuclear Operating Company _
- RSG LAR:
- Technical specification change numbering consistent with EPU LAR
- Licensing Report format and numbering consistent with EPU Licensing Report (LR)
FENOC FirstEnergy Nuclear Operarlng Conpany
- RSG specific 4
- EPU analysis required to implement RSG LAR 4
- EPU and other changes 15 10 FENOC FirstEnergy Nuclear OpemaIng Cmpany _
- RSG Licensing report contains only the portions of the EPU analyses needed to support the eight-hanges
RSG LAR Overview Change Number 4 (Analysis Change)
Technical Specification 2.1.1.1 SAFETY LIMITS - REACTOR CORE Two different departure from nucleate boiling(DNB) correlations:
- Vantage 5, WRB-1, DNBR 2 1.17
- Robust Fuel Assemblies, WRB-2M, DNBR Ž 1.14 12 2~s~eg FENOC ulerO§na
RSG LAR Overview Change Number 7 (RSG Change)
Technical Specification 3.3.1 1 REACTOR TRIP SYSTEM INSTRUMENTATION Changes Steam Generator Water Level Low-Low 13 FENOC isneyNcea prtn~'
RSG LAR Overview Change Number 8 (Analysis Change)
Technical Specification 3.33.1 REACTOR TRIP SYSTEM INSTRUMENTATION Overtemperature AT and Overpower AT equations 14 FENOC
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RSG LAR Overview Change Number 11 (RSG Change)
Technical Specification 3.3.2.1 ESFAS INSTRUMENTATION Steam Generator Water Level High-High Steam Generator Water Level Low-Low 15 v FENOC FistEnrgyNcerprtn~
RSG LAR Overview Change Number 14 (RSG Change)
Technical Specification 3.4.5 STEAM GENERATORS
- deletion of non-applicable methodologies (all sleeving and alternate repair criteria)
- deletion of single cycle approvals (alloy 800 and W star)
- clarification of inservice inspection schedule 16FrstEnergy FENOC Nuclear OeratingCornpany
,.,w Change Number 19 (Analysis Change)
Technical Specification 3.5.5 ECCS - SEAL INJECTION discharge pressure for seal injection flow 17 FENOC
RSG LAR Overview Change Number-23 (Analysis Change)
Technical Specification 6.9.5 CORE OPERATING LIMITS REPORT
- WCAP-14565-P-A - VIPRE computer code
- WCAP-1 5025-P-A - WRB-2M Correlation 18
- FENOC FirstEnerqy NucfenrOperatig~rpan ;;_
- NRC approval of licensing basis changes required under IOG-FR50.59:
- Expansion of the selective implementation of Alternative Source Term (AST) methodology.
- Additional use of ANS 1979 decay heat + 2G uncertainties.
19 FENOC FirstEnergy Nuclear Operating Company;'
- Current licensing basis utilizes AST:
- Radiological Analysis
>Control Rod Ejection Accident (CREA)
> Loss of Coolant Accident (LOCA)
>Fuel Handling Accident (FHA) 20 FENOC FirstEnergy Nuclear Operating Company _
- Requested Selected Expansion of AST
- Main Steam Line Break (MSLB) outside containment
- Steam Generatr Tube Rupture (SGTR)
- Locked Rotor Accident (LRA)
- Loss of AC Power (LACP)
- Small Line Break (SLB) outside 21 containment FENOC FirstEnergy Nuclear Operating Company _
RSG LAR Overview ANS 1979 decay heat + 2 a uncertainties (Used to determine Mass & Energy Releases)
- Approved in March 1979 for LOCA.
22 FENOC FirstEnergy Nuclear Operating Corn
RAI Inter-relationships John Maracek Staff Licensing Engineer 23 FENOC FkstEnerpy Nuclear Operating Company;
RAI Inter-relationships
> 1st set of RAI Responses submitted (L-05-078 dated May 26, 2005)
>2nd set of RAI Responses submitted (L-05-112 dated July 8, 2005)
>3rd set of RAI'skteceived on July 5, 2005 24 FirstEnergy Nuclear Operating Cornpanyl
RAI Inter-relationships
- Certain EPU RAI's have been identified by BVPS as applicable to both EPU & RSG
- Responses to the RAI's also provide additional information applicable to RSG FENCI 25 FirstEnergy Nuclear Operating Copa n'
RAI Inter-relationships 1st Set of RAls: Applicable to EPU & RSG
- EEIB (Electrical and l&C)
> Electrical Systems:
Section 10.10 Electrical EQ (RAI's H.11 & H.12)
> Instrumentation & Control:
Section 5.10 I&C; RTSIESFAS Setpoints (RAI's 1.2 thru 1.5)
- EMEB (Mechanical & Civil Engr)
> Structural Loading Considerations; Section 4 NSSS Components (RAI's N.5 & N.14) 4 *' i ': a 26FrtEnryNcerOeangC FENOC pay -
RAI Inter-relationships
- SRXB (Reactor Systems)
Section 3.2 NSSS Control Systems: OP Prot (RAI B.1)
Section 4.3 Fuel System Design (RAI D.11)
Section 5 Safety Analysis: General Q's (RAI's A.1 &2,A.5-7, A.9-11)
Section 5 LOCA (RAI's E.1 thru E.30)
Section 5.3.2 RCCA (RAI's G.1, G.2, H.1-3, 1.1 & 1.2)
Section 5.3.5 Uncontrolled Boron Dilution (RAI's J.1 thru J.4)
Section 5.3.6 LOL/TT (RAI K.1)
Section 5.3.7 Loss of Normal FW (RAI's L.1 thru L.3)
Section 5.3.8 Loss of AC Power (RAI's M.1 thru M.3)
Section 5.3.9 FW System Malfunction (RAI's N.1 & N.2 27 FirstEnergy Nuclear Operating
RAI Inter-relationships 2nd Set of RAls: Applicable to EPU & RSG
- SRXB (Reactor Systems - Con't)
Section 5.3.10 Excessive Load Increase (RAI's 0.1 thru 0.4)
Section 5.3.11 Accidental RCS Depress (RAI's P.1 thru P.3)
Section 5.3.12 Rupture Main Stm Pipe (RAI's Q.1 thru Q.19)
Section 5.3.14 Loss of RCS Flow (RAI R.1)
Section 5.3.15 RCP Locked Rotor (RAI's S.1 thru S.6)
Section 5.3.17 Rupture Main FW Pipe (RAI's U.1 thru U.8)
Section 5.3.18 Spurious Si (RAI's V.4 thru V.8)
Section 5.3.19 Steam Pipe Break (RAI's W.1 thru W.7)
Section 5.4 SG Tube Rupture (RAI's X.1 thru X.6)
Section 5.8 ATWS (RAI's Y.1 & Y.2)
Section 6.1 Fuel T-H Design (RAI's Z.1 & Z.2)
Section 10.7 SBO (RAI A.12) 28
.ef FENOC FirstEnergy Nuclear Operating Company _
RAI Inter-relationships
- IROB (Reactor Operations)
Section 5.4 SGTR: EOPs (RAI's X.5 & X.6) 29 FENOC FirstEnergy Nuclear OperatIng CompnyI
RAI Inter-relationships 3rd Set of RAls (dated June 30, 2005)
- Environmental Considerations
- Plant Systems
- Electrical (follow-up questions)
- RAl's Applicable to both EPU & RSG:
- Plant Systems: RAI Question #5 (Section 9.23 AFW - MSLB) 30 FENOC FirstEnergy Nuclear Operating Com pan_
Concluding Remarks Mark Manoleras ManagerBV Design Engineering 31 FENOC
Concluding Remarks
- Dependent on approval of Containment Conversion and BELOCA 32 FENOC FirstEnergy Nuclear Opemr~g Corpany _
Comments/Questions 33 FENOC FirstEnergy Nuclear Opetg pany
Comments / Questions
-AST
-I&C LOCA
- non-LOCA
- Clarifications - 3rd Set of RAls
- (other) 34 FENOC FrstEnergyNuclear Operating Company