ML051930356

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Steam Generator Replacement Meeting Slides
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)
v • d • e


Text

Beaver Valley Power Station Unit 1 Replacement Steam Generator Proj ct Working Level Meeting:

Replacement Steam Generator License Amendment Request July 11, 2005 FENOC 1~s~egyula Oprtn 1

Agenda

  • Introduction............................

(Greg Halnon)

  • Background..........................

(Mark Manoleras)

  • Overview of RSG LAR................. (SteveSarver)
  • RAI Inter-relationships................ (John Maracek)
  • Concluding Remarks................ (MarkManoleras)
  • Comments / Questions.....................

... (All)

FENOC 2FrsnegNulaOprin

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

  • Clearly articulate the EPU RAI's applicable to RSG
  • Facilitate efficient and quality transfer of information FENOC FirstEnergy Nuclear Operatig Company

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Background===

Mark Manoleras Manager BV Design Engineering FENOC nrp Nuclea O eai jn' 4

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Background===

Full Potential With RSG FENOC FirstEnergy Nuclear Operating Company 5

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Background===

- Submitted April 2Q05

- Needed for RSG Implementation, Feb.

2006 (1R17 Refueling Outage)

- Independent of EPU LAR

- Based on EPU Analysis at 2900 MWt

-RSG LAR does not request a power increase FENOC FirstEnergy Nuclear Operating Comp'any 6

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Background===

  • Start up from 1R17 with RSGs is dependent upon:

Approval of Containment Conversion

>LAR 1A-317, Submitted June 2004, Approval anticipated - Sept

- Approval of Best Estimate 2005 LOCA

> LAR 1A-318, Submitted October 2004, Approval anticipated - Sept 2005 FENOC FirstEnergy Nuclear Operating Cornpaniy 7

Overview of RSG LAR Ste/e Sarver Staff Licensing Engineer FENOC FirstEnergy Nuclear Operating Company 8

RSG LAR Overview

- Technical specification change numbering consistent with EPU LAR

- Licensing Report format and numbering consistent with EPU Licensing Report (LR)

FirstEnergy Nuclear Operarlng Conpany

RSG LAR Overview

  • EPU Unit 1 technical specification changes in EPU LAR

- RSG specific 4

- EPU analysis required to implement RSG LAR

- EPU and other changes 4

15 FENOC FirstEnergy Nuclear OpemaIng Cmpany 10

RSG LAR Overview

  • RSG LAR contains eight (8) technical specification changes needed to support replacement of SG's
  • RSG Licensing report contains only the portions of the EPU analyses needed to support the eight-hanges
  • No new analyses beyond those provided in the EPU LAR FENOC 1 1 F

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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 FENOC 12 2~s~eg 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 FENOC 13 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 FENOC 1 4

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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 v

FENOC 1 5 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 FENOC 16FrstEnergy Nuclear Oe ratingCornpany

RSG LAR Overview

,.,w Change Number 19 (Analysis Change)

Technical Specification 3.5.5 ECCS - SEAL INJECTION discharge pressure for seal injection flow FENOC 17

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

-FENOC 1 8 FirstEnerqy NucfenrOperatig~rpan

RSG LAR Overview

  • 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.

FENOC FirstEnergy Nuclear Operating Company;'

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RSG LAR Overview

  • Current licensing basis utilizes AST:

- Radiological Analysis

>Control Rod Ejection Accident (CREA)

> Loss of Coolant Accident (LOCA)

>Fuel Handling Accident (FHA)

FENOC FirstEnergy Nuclear Operating Company 20

RSG LAR Overview

  • 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 containment FENOC FirstEnergy Nuclear Operating Company 21

RSG LAR Overview ANS 1979 decay heat + 2 a uncertainties (Used to determine Mass & Energy Releases)

  • Approved in March 1979 for LOCA.
  • Requested in Containment Conversion LAR for MSLB inside containment.
  • Requested in RSG LAR for MSLB outside containment.

FENOC FirstEnergy Nuclear Operating Corn 22

RAI Inter-relationships John Maracek Staff Licensing Engineer FENOC FkstEnerpy Nuclear Operating Company; 23

RAI Inter-relationships

  • EPU RAls Received to-date 3 sets of EPU RAI's

> 1 st 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 FirstEnergy Nuclear Operating Cornpanyl 24

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 information applicable to RSG additional FENCI FirstEnergy Nuclear Operating Copa n' 25

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

FENOC 26FrtEnryNcerOeangC pay

RAI Inter-relationships

  • 2nd Set of RAls: Applicable to EPU & RSG

- SRXB Section Section Section Section Section Section Section Section Section Section Section (Reactor Systems) 3.2 NSSS Control Systems: OP Prot (RAI B.1) 4.3 Fuel System Design (RAI D.11) 4.4 CRDM (RAI C.1) 5 Safety Analysis: General Q's (RAI's A.1 &2, A.5-7, A.9-11) 5 LOCA (RAI's E.1 thru E.30) 5.3.2 5.3.5 5.3.6 5.3.7 5.3.8 5.3.9 RCCA (RAI's G.1, G.2, H.1-3, 1.1 & 1.2)

Uncontrolled Boron Dilution (RAI's J.1 thru J.4)

LOL/TT (RAI K.1)

Loss of Normal FW (RAI's L.1 thru L.3)

Loss of AC Power (RAI's M.1 thru M.3)

FW System Malfunction (RAI's N.1 & N.2 FirstEnergy Nuclear Operating 27

RAI Inter-relationships 2nd Set of RAls: Applicable to EPU & RSG

- SRXB Section Section Section Section Section Section Section Section Section Section Section Section (Reactor Systems - Con't) 5.3.10 5.3.11 5.3.12 5.3.14 5.3.15 5.3.17 5.3.18 5.3.19 Excessive Load Increase (RAI's 0.1 thru 0.4)

Accidental RCS Depress (RAI's P.1 thru P.3)

Rupture Main Stm Pipe (RAI's Q.1 thru Q.19)

Loss of RCS Flow (RAI R.1)

RCP Locked Rotor (RAI's S.1 thru S.6)

Rupture Main FW Pipe (RAI's U.1 thru U.8)

Spurious Si (RAI's V.4 thru V.8)

Steam Pipe Break (RAI's W.1 thru W.7) 5.4 SG Tube Rupture (RAI's X.1 thru X.6) 5.8 ATWS (RAI's Y.1 & Y.2) 6.1 Fuel T-H Design (RAI's Z.1 & Z.2) 10.7 SBO (RAI A.12)

FENOC FirstEnergy Nuclear Operating Company 28

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RAI Inter-relationships

  • 2nd Set of RAls: Applicable to EPU & RSG

- IROB (Reactor Operations)

Section 5.4 SGTR: EOPs (RAI's X.5 & X.6)

FENOC FirstEnergy Nuclear OperatIng CompnyI 29

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)

FENOC 30 FirstEnergy Nuclear Operating Com pan_

Concluding Remarks Mark Manoleras Manager BV Design Engineering FENOC 31

Concluding Remarks

  • Submittal of stand-alone RSG LAR based on EPU analyses
  • RSG LAR content and format intended to provide NRC with opportunity to optimize synergy with EPU
  • RSG LAR approval requested - January 2006 (to support 1 R17 outage)
  • Dependent on approval of Containment Conversion and BELOCA FENOC 32 FirstEnergy Nuclear Opemr~g Corpany

Comments/Questions FENOC FirstEnergy Nuclear Opetg pany 33

Comments / Questions

  • Questions by Staff Reviewers specific to RSG LAR?

-AST

-I&C LOCA

- non-LOCA

- Clarifications - 3rd Set of RAls

- (other)

FENOC 34 FrstEnergyNuclear Operating Company

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