ML17157B970

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Summary of 920805 Meeting W/Util & GE Re PP&L Licensing Strategy & NRC Schedules for Technical Review of Licensee Power Uprate Submittal
ML17157B970
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 08/19/1992
From: Raleigh J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TAC-M83426, TAC-M83427, NUDOCS 9208260215
Download: ML17157B970 (29)


Text

Docket Nos.

50-387 August 19, 1992 and 50-388

~

~

LICENSEE:

Pennsylvania Power and Light Company (PP&L)

FACILITY:

Susquehanna Steam Electric Station (SSES),

Units 1 and 2

SUBJECT:

SUMMARY

OF MEETING WITH PENNSYLVANIA POWER AND LIGHT COMPANY REGARDING THE POWER UPRATE SUBMITTAL FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2 (TAC NOS.

M83426 AND H83427)

A meeting was held on August 5, 1992, at NRC Headquarters, between members of the NRC staff and representatives of the licensee and General Electric (GE).

The purpose of the meeting was to discuss PP&L's licensing strategy and NRC staff schedules for the technical review of the licensee's power uprate submittal, A list of attendees is enclosed (Enclosure 1).

Discussions were made on many facets of the licensee's approach to power uprate for SSES, Units 1 and 2.

The more significant items discussed pertained to the licensee's schedule for the various sections of the power uprate submittal and the NRC staff review schedule.

The PP&L power uprate submittals incorporate increased core flow and the use of the GE codes SAFER/GESTR as applied to Siemens Nuclear Power Corporation (SNP) fuels.

To facilitate the NRC staff review, the licensee has closely followed the approach used by Fermi in addressing power uprate and will postpone submittal of related technical specification changes until power uprate is to be implemented on each unit.

The current schedule for the completion of the technical staff review of PP8 L's power uprate submittals is targeted for July 1993.

The attending staff wa's satisfied with the licensee's approach and was confident that the review could be completed on or ahead of this schedule.

The licensee currently plans to implement power uprate on Units 1 and 2 in May 1995 and May 1994, respectively.

The slides presented at the meeting are enclosed (Enclosure 2),

/s/

James J. Raleigh, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosures:

1.

List of Attendees 2.

Meeting Agenda cc w/enclosures:

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Docket Nos.

50-387 and 50-388 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 August 19, 1992 LICENSEE:

Pennsylvania Power and Light Company (PP&L)

FACILITY:

Susquehanna Steam Electric Station (SSES),

Units 1

and 2

SUBJECT:

SUMMARY

OF MEETING WITH PENNSYLVANIA POWER AND LIGHT COMPANY REGARDING THE POWER UPRATE SUBMITTAL FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2 (TAC NOS.

M83426 AND M83427)

A meeting was held on August 5, 1992, at NRC Headquarters, between members of the NRC staff and representatives of the licensee and General Electric (GE).

The purpose of the meeting was to discuss PPLL's licensing strategy and NRC staff schedules for the technical review of the licensee's power uprate submittal.

A list of attendees is enclosed (Enclosure 1).

Discussions were made on many facets of the licensee's approach to power uprate for SSES, Units 1 and 2.

The more significant items discussed pertained to the licensee's schedule for the various sections of the power uprate submittal and the NRC staff review schedule.

The PPLL power uprate submittals incorporate increased core flow and the use of the GE codes SAFER/GESTR as applied to Siemens Nuclear Power Corporation (SNP) fuels.

To facilitate the NRC staff review, the licensee has closely

.followed the approach used by Fermi in addressing power upr ate and will postpone submittal of related technical speciffcation changes until power uprate is to be implemented on each unit.

The current schedule for the completion of the technical staff review of PPEL's power uprate submittals is targeted for July 1993.

The attending staff was satisfied with the licensee's approach and was confident that the review could be completed on or ahead of this schedule.

The licensee currently plans to implement power uprate on Units 1

and 2 in May 1995 and May 1994, respectively.

The slides presented at the meeting are enclosed (Enclosure 2).

Enclosures:

1.

List of Attendees 2.

Meeting Agenda cc w/enclosures:

See next page James J. Raleigh, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Pennsylvania Power 8 Light Company Susquehanna Steam Electric Station, Units 1 5 2 CC:

Jay Silberg, Esq.

Shaw, Pittman, Potts 5 Trowbridge 2300 N Street N.WE Washington, D.C.

20037 Bryan A. Snapp, Esq.

Assistant Corporate Counsel Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr, J.

M. Kenny Licensing Group Supervisor Pennsylvania Power L Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.

Box 35 Berwick, Pennsylvania 18603-0035 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth'of Pennsylvania P. 0.

Box 2063 Harrisburg, Pennsylvania 17120 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.

212 Locust Street P.O.

Box 1266 Harrisburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,

Box 1797 Berwick, Pennsylvania 18603 Mr. Robert G.

Byram Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101

ENCLOSURE I PP&L POWER UPRATE MEETING I

NAME J.

RALEIGH A.

LEE R.

STRANSKY T.

COLBURN S.

JONES G.

HUBBARD R.

SCHOLL M.

RAZZAQUE D.

PRAKRATZ C.

LEHMANN R.

SGARRO M. MJAATVEDT J.

BARTOS MD DETAMORE ORGANIZATION NRC/DRPE/PDI-2 NRC/DET/MEB NRC/DRPW/PDIII NRC/DRPW/PDIII NRC/DST/SPLB NRC/DST/SPLB NRC/DST/SICB-C NRC/DST/SRXB GE - NUCLEAR PP&L PP &L/NRA-LIC.

PP&L/ENG TECH.

PP&L/ENG TECH.

PP&L/PU-PM

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BlCLOSURE 2 AGENDA NRC/PPRL MEETING ON POWER UPRATE FOR SUSQUEHANNA UNITS 1%2 AUGUST 5, 1992 0

INTRODUCTIONS 0

MANAGEMENTOVERVIEW.. M.

B.

DETAMORE 0

LICENSING STRATEGY.....

R.

R.

SGARRO 0

LICENSING REPORT.......

J.

A. BARTOS DEVELOPMENT 0

TECHNICALISSUES INCREASED CORE FLOW....

C.

R. LEHMANN USE OF SAFER/GESTR......

C.

R. LEHMANN OTHERS?

0 NRC FEEDBACK

I l

PPL.L NUCIEUKR QKPART4IIKTiMSSkQN "To operate, maintain, and support Susquehanna such that SAd generates the maximum compromising public or employee safety."

POMER UPRATE PROJECT OBJECTIVE

'TO ZNCREASE THE GROSS ELECTRZCAL GENERATION OF BOTH SUSQUEHANNA SES UNITS BY 50 MWE AT THE LOWEST CAPITAL COST AND WITHOUT COMPROMZSZNG PUBLIC OR EMPLOYEE SAFETY.

THE UPRATED POWER LEVEL WILL BE ACHIEVED AS PART OF POWER ASCENSION FOLLOWING U2-6RIO (SPRING 1994)

AND U1-8RIO (SPRING 1995)."

Power Uprate Project Organization Project Manager Michael B. Detamore Licensing Lead Rocky Sgarro Nuclear Fuels Engineering Lead Ghet Lehmann Engineering Project Manager John Bartos Modifications Project Manager Plant Groups Engineering Team M. Mjaatvedt D. Kostelnik R. Gentenaro D. Stevens P. Furman M. Boghdadi M. Growthers K. Browning D. Lochbaum J. Cajigas R. Schuyler A. Rieder J. Klucar General Electric Bechtel Operations ystems Engineering NSSS BOP Electrical and l8G*

Computers Programs

& Testing hemistry raining aintenance I8c C Electrical Mechanical

LICENSING STR4TEGF 0

BACKGROUND 0

BASIC PLAN SUBMIT TWO UNIT LICENSING REPORT............

6/15/92 (C)

SUBMIT CONFIRMATORY TRANSMITTALS...............

4Q92 1Q93 SUBMIT TWO UNIT COLR AMENDMENTREQUEST.........

12/92 RECEIVE NRC APPROVAL OF LICENSING REPORT AND COLRS... 7/93 SUBMIT UNIT 2 POWER UPRATE AMENDMENTREQUEST.........

4Q93 RECEIVE NRC APPROVAL FOR UNIT 2.- POWER UPRATE.........

3/1/94 IMPLEMENTUNIT 2 POWER UPRATE AFTER 6R&;IO.... 5/94

LICENSING STRATEGY (Cont'd.)

SUBMIT UNIT 1 POWER UPRATE AMENDMENTREQUEST.........

4Q94 RECEIVE NRC APPROVAL FOR UNIT 1 POWER UPRATE.........

3/1/95 IMPLEMENTUNIT 1 POWER UPRATE AFTER 8RAIO.... 5/95

SAFER/GESTR LOCA REPORT

~ SAFER/GESTR - LOCA REPORT NE DC-32071 P

~ APPLICATION OF SAFER/GESTR GE-NE-187-09-0692 TO SUSQUEHANNA UNITS 1 AND 2 WITH SNP 9X9-2 FUEL

~ GE PROPRIETARY AFFIDAVIT

1 I

I

TECHNICAL SPECIFICATION MARKUPS MARKUPS OF ANTICIPATEDOPERATING LICENSE AND TECHNICALSPECIFICATION CHANGES NEEDED TO SUPPORT POWER UPRATE WITH INCREASED CORE FLOW.

er 4

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RESPONSE TO NRC QUESTIONS THIS SECTION CONSISTS OF PP8cL RESPONSES TO THE NRC REQUESTS THROUGH JUNE 1, 1992 FOR ADDITIONAI INFORMATIONREGARDING DETROIT EDISON COMPANY'S POWER UPRATE SUBMITTALFOR FERMI-2, AS IF THESE REQUESTS HAD BEEN APPLICABLE TO PP&L'S SUSQUEHANNA STEAM ELECTRIC STATION.

~Wq UPRATED CONDITIONS THERMALPOWER STEAM FLOW TURBINE INLETPRESSURE CORE/RECIRC. FLOW FEEDWATER TEMPERATURE ELECTRIC OUTPUT (PP&L)

(GE)

IMPACTEVALUATIONS (PP&L)

(8ECHTEL)

(PP&UVENDOR)

NSSS RB(CTOR HEAT BAlANCE CONTAINMENTANALYSIS RECTOR VESSEL ANALYSIS ECCS ANALYSIS REACTIVITY CONTROL OFF. SITE RAD. ANALYSIS INSTRUMENTATION (GE)

(PP&L)

BOP SYSTEMS GENERATION SUPPORT ESW RHRSW UHS HVAC RADWASTE INSTRUMENTATION PIPING ANALYSIS ClASS 1 CLASS2&3 B31.1 EQ ANALYSIS FUELCYClE CORE DESIGN OVERPRESSURE EVALUATIONS TRANSIENT EVALUATIONS TURBINEGENERATOR TURBINETHERMAL TURBINE MECHANICAL TURBINE SUPPORT GENERATOR NON-SYSTEM EVALUATIONS HELB STATION BLACKOUT ATWS APPENDIX

'R'N SITE RADANALYSIS DYNAMICLOADS AS BUILTEVALUATION IPEJEOP'S ENVIRONMENTAL I

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I UCENSING REPORT CONFIRMATORY TRANSMITTAL PQWER UPRATE PROJECT - ENGINEERING FLQW CHART

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I SUSQUEHANNAPOWER UPRATE INCREASED CORE FLOW 0 Increase to 108%

0 Needed for Flow Window o Old = 87% to 100%

~

o New = 93'%o 1089o 0 WithinRange ofOther ICF's 0 Evaluated in 1986 for Susquehanna o GE Report Prepared - Not Submitted o No Safety Problems 0 NRC Interested in "Deltas"

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SVSQVEHANNAEXTENDED OPERATING POWER FLOW MAP

~ n ee 120 110 100

@0 90 80 C

70 50 40 CC 20 10 0

Power/Row als A: 62P/30F B r 69P/41F C: lOOP/81F D - 1045P/93F I: 104.5P I IOOF F: 104SP/108F G: lOOP I IOSF

~ 8: 23P/ IOIF I: 23P /100F

): 23P/4lf K - lOOP I IOOF I.: 49P /30F g: 58P/42F n

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Twornp Spcofg0%)

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i00% RedLine Cavrmron Ioterlock lCF 120

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110 ~

100 <

@0 90 ~

80 gO 70 ~

50 L 30 u 20 0 10 n

In 20 30 Nore:

Thermal Power is % origina) rated ( 3293 M'9t'()

40 50 60 70 CORE FLOW (% Rated) 80 90 100 I IO 120

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SUSQUEHANNAPOWER UPRATE INCREASED CORE FLOW/ 1986 Evaluation 0 Reload Licensing Related o Detailed Evaluation w/ Reload Analyses o LimitingCases on P/F Map WillBe Determined o Abnormal Transients (GLR, FWCF, RFCF) o FuelLoading Error & RWE o RodDrop 0 LOCA o No Significant Effect (1986 Conclusion) o SAFER/GESTE Analysis ConGr~ This

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0 Stability o Increased Flow is More Stable o No Change to Current Rod Lines o PP&L Involved in Long Term Solution

SUSQUEHANNA POWER UPRATE INCREASED CORK FLOW/1986 Evaluation 0 Vessel Internals/Loads o Increases due to ICF Identified in LTR (e.g., RIPD's) o Stresses w/in Design Limits 0 Flow Induced Vibration o WithinLimits o Jet Pump Sensing Line Modification,

1 t

Power Uprate SAFER/GESTR LOCAAnalysis 0 SAFER/GESTR.Methodology 0 NRC Approved GE Method /Applied to 20 BWRs 0 Two Tyxes ofEvaluation:

1. Analysis w/Appendix KRequired Models
2. Best Estimate Statistical (95/95) 0 Criteria
1. Appendix KAnalysis PCT < 2200 F
2. Statistical Upper Bound PCT ( 1600 F
3. PCTupper bound < PCTApp K II 0 Decrease in PCT

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0 Increase MAPLHGRLimits 0 10.2 te'11.5 kw/8 0 Other Conservatisms 0 25 Second Diesel Start Time 0 12" Reduction. in Water Level Trips

1

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Power Uprate SAFER/GESTR LOCAAnalysis ApplicabilityofSAFER/GESTR to SNP 9x9 Fuel

/

0 Report GE XE187 09 0692 0 SNP 9x9 Fuel Similar to GE Fuels o SNP Fuel Data Reviewed o SNP Bundle Geometry Reviewed 0 Results Similar to Generic BWR/4 0 Second Peak Limited o PCT Detemnined by System Response and ECCS Performance o Stored Energy ofSecondary Importance

Power Uprate SAFERlGESTR LOCAAnalysis ApplicabilityofSAFER/GESTR to SNP 9x9 Fuel 0 Licensing Basis PCT o PCTLB PCTnominal + ADDER o AllTerms Calculated vr/SNP 9x9 Speci6c Inputs 0 Upper Bound PCT Q PCTUB = PCTnominal + ModelHQg Blas + 95/95 Term o Nominal PCT and 95/95 Term Calculated w/SNP 9x9 SpeciGc Inputs o Modelling Bias Applicable

- Results Similar to GE Results(GE 6,7,8,10,11)

- Second Peak Limited

Susquehanna SAFERlGESTR Results 0 Break Spectrum Study 0 App. Kand. nominal spectra are similar 0 Similar to Generic 8x8 Spectrum "

0 DBASuction w/false LOCA = worst App. K 0 0.1 ft break w/battery failure = worst nominal 0 Single Failure Study 0 Failures Considered

1. False LOCASignal
2. Battery
3. LPCIInjection Valve
4. Diesel-Generator
5. HPCI 0 Opposite UnitFalse LOCAis%orst (App. KSuction Break)

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