ML17263A180

Summary of 930225 Meeting W/Util in Rockville,Md Re Steam Generator Replacement.List of Attendees,Meeting Agenda & Discussion Matl Encl

ML17263A180
Person / Time
Site:	Ginna
Issue date:	03/10/1993
From:	Andrea Johnson Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9303160241
Download: ML17263A180 (86)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 10, 1993 Docket No. 50-244 LICENSEE:

Rochester Gas and Electric Corporation FACILITY:

Ginna Nuclear Power Plant

SUMMARY

OF MEETING WITH ROCHESTER GAS AND ELECTRIC. CORPORATION ON STEAM GENERATOR REPLACEMENT - FEBRUARY 25, 1993 Rochester Gas and Electric Corporation (RG&E), in a meeting with NRR management on February 25, 1993, at NRC Headquarters, presented their current plans for steam generator (SG) replacement at the Ginna plant.

RG&E made the decision to continue nuclear power generation with the Ginna plant in mid-June

1992, when filing a report with the New York State Public Service Commission.

RG&E s decision is a result of their Integrated Resource Plan (IRP) which includes a conservative 15-year plan to the expiration of the Ginna operating license in September 2009.

RG&E recently issued a purchase order to Babcock

& Wilcox International (B&W Intl) Cambridge, Ontario, for procurement of new steam generators.

Bechtel has also been awarded the contract as the SG installation contractor.

RG&E's schedule would include SG fabrication from January 1993 to January 1996, preliminary engineering and preparation for plant design/installation

.from January to June 1993, detail design engineering from July 1993 to January 1995, pre-outage modifications from March 1995 to February

1996, and SG installation from March to June 1996.

The major topics presented by RG&E in the February 25th meeting were their cost effective basis and results of their IRP, SG replacement by new SGs, including SG transport, containment integrity, SG drop potential, effects on Updated Final Safety Analysis Report (UFSAR) Technical Specifications (TS),

as low as reasonably achievalbe (ALARA), acceptance testing/examinations and a

status of their existing Westinghouse Series 44 SGs.

RG&E discussed their evaluation of removing and installing a one-piece (full SG assembly) through the containment dome.

Options applicable to other plants were not applicable for the Ginna plant.

RG&E's evaluation is based on minimizing containment handling and movement, shorter outage schedule (74 days),

less expensive, less radiation exposure (300 man-rem) and installation of a full shop assembly.

The removal and replacement would be accomplished using a large mobile crane.

RG&E went on to discuss the potential containment roof construction

openings, SG rigging and liner plate reinstallation weld details.

RG&E discussed using principally a 10 CFR 50.59 review process (facility

changes, tests and experiments conducted without prior Commission approval).

RG&E discussed using a licensing approach where necessary, i.e.,

a license 930316024i 9303f0'DR ADOCK 05000244,,

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March 10, 1993 amendment per 10 CFR 50.90 and 50.91, to deal with essential TS changes, and appropriate NRC inspection/review of safety evaluations and responses to NRC questions.

Enclosur'e 1 is a list of meeting attendees.

A copy of the meeting agenda and discussion material is included in Enclosure 2.

Enclosures:

1.

List of Attendees 2.

Meeting agenda and discussion material lS/

Allen K. Johnson, Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc w/enclosures:

Licensee and service list OFFICE LA:PDI-Q PH:PDI-D:PDI-3 D

NANE DATE TClark

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93 WButler 0 93 OFFICIAL RECORD COPY FILENAME: GIHT225.SUM

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March i0, 1993 amendment per 10 CFR 50.90 and 50.91, to deal with essential TS changes, and appropriate NRC inspection/review of safety evaluations and responses to NRC questions.

Enclosure 1 is a list of. meeting attendees.

A copy of the meeting agenda and discussion material is included in Enclosure 2.

Enclosures:

1.

List of Attendees 2.

Meeting agenda and discussion material Allen R. Johnson Project Manager Pr 't Dire ate I-3 Division o Reactor Projects I/II Office of Nuclear Reactor Regulation cc w/enclosures:

Licensee and service list

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Thomas A. Moslak, Senior Resident Inspector R.E. Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road

Ontario, New York 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Hs.

Donna Ross Division of Policy Analysis 5 Planning New York State Energy Office Agency Building 2 Emp'ire State Plaza

Albany, New York 12223 Charlie Donaldson, Esq.

Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Nicholas S.

Reynolds Winston

& Strawn 1400 L St.

N.W.

Washington, DC 20005-3502 Hs. Thelma Wideman

Director, Wayne County Emergency Hanagement Office Wayne County Emergency Operations Center 7370 Route 31

Lyons, New York 14489 Hs. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness ill West Fall

Road, Room ll Rochester, New York 14620 Dr. Robert C. Mecredy Vice President, Nuclear Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649

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Enclosure 1

NRC MEETING WITH ROCHESTER GAS AND ELECTRIC CORPORATION R.E.

GINNA NUCLEAR POWER PLANT STEAM GENERATOR REPLACEMENT FEBRUARY 25, 1993 LIST OF MEETING ATTENDEES NAME TITLE John F. Smith Robert C. Mecredy Geor e Wrobel Jim Ralei h

RGS.E RGKE RGKE

STS, Inc.

ORGANIZATION Javier Zarzvela Charles Hanson B. D. Liaw R. A. Skokowski M. D. Smith Chen P.

Tan Steve Hoffman Robert Rothman Frank Con el Al Johnson Walt Butler H. F. Conrad V. M. McCree C. Crai Harbuck Geoff Hornseth Arnold Lee OEAB NRC DRSS/RPB NRC NRR DE NRC NRR PDI-3 Bechtel NRC/NRR/DE ECCB NRC NRR/ADAR NRC NRR ECGB NRC NRR DRSS NRC DRPI II/PDI-3 NRC/DRPI II PDI-3 NRC EMEB NRC NRR OEDO NRC NRR DORS OTSB NRC NRR EMCB NRC NRR EMEB

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DISTRIBUTION:*Enclosure 2

--Docket-File*

NRC

& Local PDRs*

PDI-3 Reading*

T. Murley/F. Miraglia J. Partlow S. Varga J.

Calvo W. Butler A. Johnson*

T. Clark OGC E. Jordan C.

Hanson B. D. Liaw R. Skokowski C.

P.

Tan S.

Hoffman R.

Rothman F.

Congel H. F. Conrad C. Harbuck G. Hornseth A. Lee ACRS (10)

V. McCree, EDO J. Linville, RI*

J. Durr, RI W. Hodges, RI*

W. Lazarus, RI M. Knapp, RI J.

Richardson B. Grimes G. Zech J. Strosnider R. Jones G. Bagchi*

E. Murphy*

T. Shedlosky*

cc:

Licensee

& Service List

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Enclosure 2

NRC BRIEFING Robert C. Mecredy George 3.

Wrobel 3ohn F. Smith February 25, 1993

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AGENDA

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Integrated Resource Planning R. Mecredy

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Steam Generator Replacement Decision R. Mecredy

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Project Implementation J. Smith Break

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Update since 9/16/92 NRC Meeting J. Smith/G. Wrobel

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Open Discussion

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INTEGRATED RESOURCE PLAN Business Oecisions

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long-range electric generation planning

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long-range demand side management plan

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industrial customer retention

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clean air act compliance

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Ginna steam generator replacement

't

GINNA STATION STEAM GENERATORS Current Impacts on Plant Performance

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net plant electric rating

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annual refueling outages

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annual maintenance expense 15 Mw 10-15 days 3.0 million

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annual collective radiation exposure 60 person rem

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forced outages (last 5 years) 15 days

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GINNA STATION STEAM GENERATORS Future Steam Generator Performance

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inner row u-bend cracking

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Inconel 60Q tube plugs

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free span cracking

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outer row u-bend cracking

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tube defects at support plates

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1991 PLAN SUMMER LOAD & CAPACITY Existing & Expected Resources Required Capability w/o DSM Required Capability w/DSM

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1500

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1+4 4

500' 1

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0 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year It Syetem Gilboa Green Mountain Hydro Quebec Iet Hyae Station 5 Station 2 Station 26 Aliscellaneous Niagara II Nudear Ginna Nine Mile Fitzpatrick Russell 1

Russell 2 Russell 3 Russell 4 Beebee 12 III oe Oswego 6 Beebee 13 Station 9 Allegany Cogen 3/9/92/SUM-LOAD/ewo

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INTEGRATED RESOURCE PLAN Existing Plant Options Beebee 12 Russell 1-2 Russell 3-4 Ginna low S coal low S coal low S coal operate scrubbers scrubbers scrubbers replace SG repower repower repower retire retire retire retire

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INTEGRATED RESOURCE PLAN Business Climate

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industry regulation

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limited growth opportunities

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environmental concerns

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technological changes

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GINNA OPERATIONAL INPUT

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continue high plant capacity factor

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modest real growth in O&M expenses

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significant capital expenditures through 1996 to reflect current initiatives, more normal levels thereafter

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operation through current license period (2009) license renewal a future decision

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14 AVERAGE REAL RESIDENTIALRATE (1991 8's) m 'l0 O

1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 This is not intended to be a forecast of Non-Residential Rates.

These data were prepared for comparison of scenarios only.

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NON-RESIDENTIALRATES VS. COGENERATION (1991 4's) 56 0

4 O

Non-Residential Rates 0

1S91 1992 1S93 1S94 1S95 1996 1S97 1SS8 1999 2000 2001 2002 2003 2004 2005 2006 2007 This is not intended to be a forecast of Non-Residential Rates.

These data were prepared for comparison of scenarios only.

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INTEGRATED RESOURCE PLAN Business Strategy

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seek customer partnerships

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retire some existing generation

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use environmentally compatible fuels

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continue to operate Ginna and decide steam generator replacement

CONTINUED GINNA OPERATION

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valuable corporate asset

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excellent performance record

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best integrated resource plan

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present value of revenue requirements

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maintain fuel diversity

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decision relies on continuing safe, reliable, economical operation

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STEAM GENERATOR REPLACEMENT Occision Process

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involved management and Board of Directors

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assessed safety, reliability and economic issues for options

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POTENTIAL ISSUES Coastdown Option

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existing steam generator performance causes price to exceed market forced early retirement increased reliance on natural gas which results in price uncertainty forced outages

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safety and regulatory concerns regarding existing steam generators causes price to exceed market

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POTENTIAL ISSUES S/8 Replacement Option

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installation cost exceeds estimates

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installation time exceeds estimates

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installation cost causes price to exceed market in near term

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later premature retirement causes price to exceed market

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PROPOSED RATE TREATMENT

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capital cost target

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variance sharing mechanism

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outage time agreement

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REPLACEMENT DECISION

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enhances plant operational performance

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maintains capability of resource

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improves ability to manage long-term production costs

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dependent on safe, reliable, and increasingly economical operation

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PR CT IMPLEMENTATI N

~ STATUS OF EXISTING STEAM GENERATORS

~ REPLACEMENT METHODOLOGY

~ EQUIPMENT STATUS

~ INSTALLATIONSTATUS jfsmtg02.240

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REPAIR STATUS S/G-A S/G-B UNMEPAB&DTUBES 2520 (77.3%)

1S13 (55.6%)

PLUGGED TUBES 185 (5.7%)

313 (9.6%)

SLEEVED TUBES 555 (17.0%)

1134 (34.8%)

3260 (100%)

3260 (100%)

STEAM GENERATOR TUBESHEET DEFECTS DEFECTS 250 200 150 100 50 0

1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 2007 2009

~ A-S/G IB-s/G JANUARY 18, 1991 FIGURE 9

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STEAM GENERATOR TSP DEFECTS DEFECTS 1200 1000 800 600 400 200 0

1991 1993 1995 1997 1999 2001 2003 2005 2007 2009 MA-S/G IB-S/G JANUARY 18, 1991 PIGURH 10

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STEAN GENERAL

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SITE PLAN GINNA NUCLEAR POWER STATION

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~ S/G'S ORDERED FROM BABCOCK4 WILCOXINTERNATIONAL

~ 54,000 SQ. FT. SURFACE AREA

~ INCONEL 690 TUBING, THERIACALYTREATED

~ PHYSCIALLYSMdE SIZE AS EXISTING S/G'S

~ PRZVIARYSIDE PRESSURE DROP THE SPIKE AS EXISTING

~ 3/4" TUBING

~ 4760 TUBES

~ POWER RATINGTHE SAIVIE

~ DELIVERYFEBRUARY 1996

~ CO G TO WORK WIHiSGRG

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IN TALLATI N TA

~ BIDDERS LIMITEDTO:

MK-FERGUSON BECHTEL POWER CORPORATION

~ INII'IALBIDS DECEMBER 1992

~ BEST AND FINALOFFER FEBRAVARY1993

~ FINALCONTRACT NEGOTIATIONSUNDERWAYWITHBECHTEL

~ INSTALLATIONIVLMCH1996

~ OUTAGE LENGTH

- 68 DAYS (AGGRESSIVE SCHEDULE)

- 95 DAYS HARP)

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GINNA SG REPLACEME T 50.59 ISSUES 1.

CHAPTER 15 ACCIDENTS EVENTS SCREENING SENSITIVITIES BAW ANALYSIS UNREVIEWED SAFETY QUESTIONS (IF ANY)

SUBMITTED FOR NRC REVIEW 2.

SEISMIC/STRUCTUIML 3.

LOCA/SLB CONTAINMENTANALYSIS 4.

RCS INTERFACE FLOW, DP

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SG DROP CONSIDERATIONS SAFETY-RELATED EQUIPMENT (SFP)

SFP SECONDARY MISSILES OFFSITE DOSES (SG, RAD TAlNKS)

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THER ISSUES 1996 WILLALSO COMMENCE USE OF NEW FUEL TYPE, AS WELL AS 18-MONTH FUEL CYCLE EXPECT LICENSE AMENDMENTAPPLICATION IN THIS TIME FRAZZLE

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STEAM OUTLET NOZZLE 2 -18" SECONDARY MANWAYS AU ARY FE ATER NOZ E

85 SECONDARY CYCLONES 85 PRIMARY CYCLONES 16" FEEDWATER NOZZLE U-BEND SUPPORT ASSEMBLY 8

- LATTICE GRID SUPPORTS 4r<<

M60 V-TUSES O. D.

0" WALL TRIANGULAR PITCH HAIN SUPPORT PADS 2 -31" I. D.

PRIMARY NQZZLES 2 -18" PRIMARY MANWAYS ROCHESTER GAS K

ELECTRIC GINNA POWER STATION

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7 COMPARISON of SG DESIGNS PRELIMINARY-FEBRUARY 1993 SG DESIGN ATTRIBUTE ORIGINALSG REPLACEMENT SG POWER RATING

'POWER

'HEATTRANSFER RATE 764 MWt 2.61 E+9 Btu/hr/SG 764 MWt 2.61 E+9 Btu/hr/SG PRESSURE BOUNDARY-DESIGN

'PRIMARYPRESSURE

'SECONDARY PRESSSURE

'PRIMARYTEMPERATURE

'SECONDARYTEMPERATURE 2500 psia 1100 psia 650F 556F 2500 psia 1100 psia 650F 556F THERMALHYDRAULICS

'PRIMARYFLOW RATE (MIN)

'PRIMAR. PRESSURE DROP

'COLD LEG TEMPERATURE

'HOT LEG TEMPERATURE

'STEAM FLOW

'STEAM PRESSURE

'MOISTURE CARRY OVER

'FEEDWATER FLOW RATE

'PLUGGING MARGIN(HEATTRANSFER) 33 E+6 Ibs/hr/SG 32 psi 0% plugged 545F 601F 3.3 E+6 Ibs/hr/SG 800 psia 0.25%

3.34 E+6 Ibs/hr/SG 15%

33 E+6 Ibs/hr/SG 32psi 0%plu ged 545F 601F 0% plugged 3.3 E+6 Ibs/hr/SG 875 psia 0 10%

3.34 E+6 Ibs/hr/SG 20%

TUBE BUNDLE PARAMETERS

'TYPE

'TUBE DIAMETER

'TUBES PER GENERATOR

'TUBE WALLTHICKNESS

'PITCH PATTERN

'HEATTRANSFER AREA U-Bend 875" 3260 050" 1.234" Square 44430 sq ft U-Bend 75" 4765 043H 1.019" Tria ular 54000 sq ft

'TUBE MATERIAL

'SUPPORTS Inconel Allo 600 Inconel Allo 690 Carbon Steel Drilled Plates Stainless Steel Lattice Bars PHYSICAL PARAMETERS

'DIAMETERS

-Built per dwg W/679J441 Replicate OSG physical envelope

'FLOODED WEIGHT

'FLOODED CENTER OF GRAVITY

'PRIMARYVOLUME

'SECONDARY VOLUME

'MS FLOW RESTRICTOR TYPE

'MS FLOWAREA 963,600 Ibs 346" from support pads 928 cu ft/SG 4579 cu ft/SG None (MS line venturi)

N/A 970,000 Ibs 353" from support pads 974 cu ft/SG 4567 cu ft/SG Int ral SG Flow Restrictor To be Determined CSGDJFS.XLS Page 1

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REACTOR COOLANT PUMP 18 14 FEEOWATER LINE 14" FEEOWATER LINE UPPER SUPPORTS ANO SNUBBERS (TYP.)

COLO LEG HOT LEG HOT LEG INTERMEOIATE SUPPORTS (TYP.)

CROSSOVER LEG COLO LEG LOWER SUPPORTS (TYP.)

REACTOR COOLANT PUMP 1A REACTOR VESSEL VIEW OF NSSS SYSTEM FOR GIN¹( NUCLEAR STATION

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~ PHASE 2 DETAILEDENGINEERING

~ PHASE 3 IMPLEMENTATION

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~ PRIIWLRYLOOP ROOMS / LOWER S/G COMPARTMENTS

~ S/G COMPARTMENTS FROM LOWER LATEEVG SUPPORTS TO TOP OF S/G

~ ALLFLOOR LEVELS IN CONTA&tMENTBUILDING

~ CONTAPGQENT ROOF INTERIOR SURFACE

~ CONTAINMENTBRIDGE CRANE

~ CONTAPlMENT JIB CRANES

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