ML17309A562

Provides Summary of Public Meeting on 941005 W/Util to Provide Update on Evaluation of Steam Generator Replacement & Fuel Reload Changes at Plant,Currently Scheduled for Spring of 1996

ML17309A562
Person / Time
Site:	Ginna
Issue date:	11/23/1994
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9412010209
Download: ML17309A562 (116)

Text

PR.IC3R.I EY 1 (ACCELERATED RIDS P ROC ESSIVE G REGULATORY INFORMATXON DXSTRXBUTION SYSTEM (RIDS)ACCESSION NBR: 9412010209 DOC.DATE: 94/11/23 NOTARIZED:

NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFXLIATION JOHNSON,A.R.

Project Directorate I-3

SUBJECT:

Provides summary of public meeting on 941005 w/util to provide update on evaluation of steam generator replacement

&fuel reload changes at plant.,currently scheduled for spring of 1996.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:

General Distribution DOCKET 12 05000244 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON(A TNTERNA: FILE CENTEB 01 RR/DRCK/HI CB NRR/DSSA/SPLB NUDOCS-ABSTRACT=

EXTERNAL'OAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DE/EELB NRR/DRPW NRR/DSSA/SRXB OGC/HDS3 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE!CONTACT'I'HE DOCL'WIENTCONTROL DESK, ROON I PI-37 I EXT.504-20S3)TO ELI ifINATE YOI'R NAZI E FROif DISTRIBUTION LIS'I'S I'OR DOCL MEN'I'S YOI.'ON"I'L'ED!TOTAL NUMBER OF COPIES, REQUIRED: LTTR 13 ENCL 12 AHn ROCHESTER GAS AND EIECTRIC CORPORATION

~89 FASTAVENIJE, ROCHESTER, N.Y IrI&9-0001 ARFA CODE716 546-2700 ROBERT C.MECREDY Vice President Nvdear Operations November 23, 1994 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555

Subject:

Public Meeting on October 5, 1994 to discuss Steam Generator Replacement and Fuel Reload Changes for 1996 R.E.Ginna Nuclear Power Plant Docket No.50-244

Dear Mr.Johnson:

On October 5, 1994 a public meeting was held between Rochester Gas and Electric staff and members of the NRC to provide an update on the evaluation of the steam generator replacement and fuel reload changes at Ginna Station, currently scheduled for the spring of 1996.The purpose of the presentations was to demonstrate that the Steam Generator Replacement Project could proceed within the provisions of 10CFR50.59.

This letter provides a summary of the meeting.RG&E presented the results of the accident/transient preliminary safety evaluation, including the five accident/transients which were analyzed in detail.This evaluation had been previously provided to the staff.RG&E noted that it is our intention to make the analysis of the Low Temperature Overpressurization transient performed for this project the analysis of record for Ginna Station.The staff (Mark Caruso)stated that formal NRC review of this analysis was not required.RG&E presented the status of the 1996 Fuel Reload Analysis.It was requested that the staff expedite the review of the Westinghouse COBRA-TRAC LOCA methodology, Addendum 3, since the results of this review could impact the analysis for the reload.The staff responded that they were aware of the need to finish this review.RG&E also noted that with the proposed transition to Improved Standard Technical Specifications, there would be no need for any License Amendment Requests to support the 1996 Fuel Cycle.RG&E followed with a presentation on the results of the primary system piping stress analysis results.The presentation indicated that all acceptance criteria continued to be met.RG&E also presented an outline of the current proposed methodology for installing the replacement steam generators.

This presentation onnnC.Q 9412010209 941i23 PDR ADQCK 05000244 p PDR 00 4 0 I' included changes from information previously presented most notably the method of removal of concrete from the containment.

Mock-up testing has demonstrated that removal of the concrete using automated hydraulic jack hammers is preferred over other available options.Detailed information on the rigging scheme, haul routes, insulation and pipe cutting and welding was also presented.

Finally, RG&E presented our plans regarding the extensive radiological protection measures being contemplated, including our plans for original steam generator on-site storage;purchase and use of dosimetry; pipe-end decontamination methods;dome decontamination; and a dome liner and concrete activation study.NRC staff indicated that all analyses to date appeared to be satisfactory, and no challenges to the 10CFR50.59 process being proposed by RGGE were envisioned.

Attached are copies of the presentation overheads from the meeting.RGGE appreciates the valuable input and cooperation provided by the staff at this meeting.Very truly yours, Robert C.Mecredy Attachment BJF/354 xc: Mr.Allen R.Johnson (Mail Stop 14D1)Project Directorate I-3 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 USNRC Ginna Senior Resident Inspector 0 J J~4 e

~9412010209 Ginna Station Bechtel Rochester Gas and Electric Ginna Station Steam Generator Replacement NRC Status Update October 5, 1994 I.INTRODUCTION II.PROJECT STATUS/OVERVIEW Fabrication Status Installation Status G.Wrobel B.Carrick III.RSG SAFETY EVALUATION Preliminary Safety Evaluation Accident Analyses Containment Analysis Low Temperature Overpressurization IV.1996 FUEL RELOAD B.Flynn R.Eliasz~Steam Generator Replacement Interface~Improved Technical Specifications Interface LUNCH V.RCS PIPING ANALYSIS B.Carrick VI.REPLACEMENT STEAM GENERATOR INSTALLATION RCS Pipe Cutting/Welding Rigging Scheme/Drop Analysis Containment Dome Openings Steam Generator Insulation/Containment Sump Analysis VII.RADIOLOGICAL PROTECTION MEASURES VIII.SUBMITTAL SCHEDULE B.Carrick M.Fitzsimmons B.Flynn A.Herman B.Flynn OS October 94 JY f Ginna Station Bechtel 8'lVI~Qmpson Rochester Gas and Electric OVERVIEW Two Loop W NSSS BA,W"Like-in-Kind" Replacement SGs Install Via Construction Openings in Containment Dome Spring, 1996 Outage 67 Days Breaker-to-Breaker Outage 05 October 94

+Ginna Station Bechtel lpmp son Rochester Gas and Electric FABRICATION STATUS Lower Shell Assy NDE Prior to PWHT Upper Shell Assy In Fabrication Bundle Internals In Fabrication Tubes (I-690)PPQ-2@VALINQX Steam Separators/Upper Bundle Assy In Fabrication Feedwater Header Parts on Order 05 October 94 Babcock&Wilcox Canada Advanced Series.PWR Replacement Steam Steam noate Hgn ethctency moteture seParstors Sundle Inspection access duct~Feodwetef Inlet g Feedwstor header Stemless sleet IOCUceelal tuho'suppore gnd~I)~SIOWdOWn header ntNSn I I H~lt~.~fr.~Integral vsrtrcal support v I Pnmary noaste Pnmary stde manwsy t heron es Ietmtnd gxwos ouletde nleneton~end otetvl oetloAnonco conetweto n Ih el elms~IOWn tlenetNte end teec let teen ewnenle~ocr ton Ior mecenotn teeeoory m ooetwnnl~nchteee htoh cttcltlerlnI tense~oltnetew ctotoel ond ootetnto neet IIegnoton~uee nottnotd noo euooon\~Icanotn oteenoo tnnmdorr~IT thermo~entete end sotet oew eterne Isntttere I Aw teetolHI et tees ntoo lnntwtnstced I otenon~eorm ntlh weetn eedtlr twnno Se lsell onow~o eoeteltne contsnene o'%tete Ioo eo Oeno~/ectleew mwwcoon eno eettnenmce

Ginna Station I Bechtel i BWI I simpson<CD Rochester Gas and Electric INSTALLATION STATUS Detailed Conceptual Studies Completed Major Subvendors Identified Bechtel Proceeding with Engineering 1995 Outage Scope Established 199S Outage as"Dry Run" Engineering Construction Planning Administrative Radiation Protection 05 October 94

Ginna Station Bechtel lpmpocn Rochester Gas and Electric V Events~UFSAR Chapter 15 Transient Analyses~UFSAR Chapter 6 Containment Integrity UFSAR Chapter 5 Overpressure Design Transients Method~Identify Acceptance Criteria~Identify Pertinent Parameters

~Evaluate Change: Benefit/Detriment/No effect Results~Acceptance Criteria for All Events Met~Only Five Transients Required Detailed Analysis 05 October 94 AHO R.E.Ginna Steam Generator Replacement Equipment Comparison Ginna Station BVVI Bee%el~PICNl Rochester Gas and Electric Manuf./Model Primary Side Pressure Drops (0%plug)Nozzle inlet to Nozzle outlet Primary Side Flow for above dp's Heat Transfer Areas 0%Plugging 15%Plugging 20%Plugging Tubing OutsideDiameter Avg'.Wall Thickness Number of Tubes Material Volumes, primary side Inlet Plenum Tubes Outlet Plenum Existing W/44 (feedring) 33.5 psi 34.6 E06 Ibm/hr 44430 sq.ft.37765 sq.ft.0.875 in 0.050 in 3260 Inconel 600, MA 133 cu.ft.675.5 cu.ft.133 cu.ft.Replacement BWI (feedring) 31.0 psi 35.0 E06 ibm/hr 54001 sq.ft.43200 sq.ft.0.750 in 0.0431 in 4765 Alloy 690, TT 130 cu.ft.710 cu.ft.130 cu, ft., Secondary Volume, Total Secondary Water Mass, nominal 100%(1520 MWt)0%(HZP)Secondary Mass Flow, 100%Steam Line Orifice Size Initial Steam Pressure, 100%4580 cu.ft.85,410 ibm 130,120 ibm 3.3 E06 ibm/hr 4.37 sq.ft.830 psia 4513 cu.ft.86,257 ibm 118,836 ibm 3.3 E06 ibm/hr 1.4 sq.ft.877 psia 0 05 October 94 Ginna Station Bechtel CD Rochester Gas and Electric EVALUATE ANALYZE X X X X X X X X X X'X X X X X X X X X X X 15.1 Increase in Heat Removal by the Secondary System 15.1.1 Decrease in Feedwater Temperature 15.1.2 Increase in Feedwater Flow 15.1.3 Excessive Load Increase Incident 15.1.4 Inadvertent Opening of a SG Relief/Safety Valve 15.1.5 Steam Line Breaks Inside and Outside Containment 15.1.6 SG Relief Valve and Feedwater Control Valve Failure 15.2 Decrease in Heat Removal by the Secondary System 15.2.1 Steam Pressure Regulator Malfunction 15.2.2 Loss of External Electrical Load 15.2.3 Turbine Trip 15.2.4 Loss of Condenser Vacuum 15.2.5 Loss of Offsite Power to the Station Auxiliaries 15.2.6 Loss of Normal Feedwater Flow 15.2.7 Feedwater System Pipe Breaks 15.3 Decrease in RCS Flowrate 15.3.1 Flow Coastdown Accidents 15.3.2 Locked Rotor Accident 15.4 Reactivity and'Power Distribution Anomaities 15.4.1 Uncontrolled RCCA Withdrawal from Subcritical 15.4.2 Uncontrolled RCCA Withdrawal at Power 15.4.3 Startup of an Inactive Reactor Coolant Loop 15.4.4 CVCS Malfunction 15.4.5 RCCA Ejection 15.4.6 RCCA Drop 15.5 Increase in RCS Inventory 15.6 Decrease in RCS Inventory 15.6.1 Inadvertent Opening of a Pressurizer Safety or Relief Valve 15.6.2 Radiological Consequences of Small Lines Carrying RC Outside Containment 15.6.3 Steam Generator Tube Rupture 15.6.4 Primary System Pipe Ruptures 15.6.4.1 SBLOCA 15,6.4.2 LBLOCA 15.7 Radiological Release From a Subsystem or Component 15.7.1 Radiological Gas Waste System Failure 15.7.2 Radiological Liquid Waste System Failure 15.7.3 Fuel Handling Accidents 15.8 Anticipated Transients Without Scram X X Chapter 6, Chapter 5 6.2.1.2 Containment Integrity 5.2.2 Low Temperature Overpressurization 05 October 94 Ginna Station Bechtet lp peen I CD Rochester C3 as and Electric 15.1.6 SG Relief Valve and Feedwater Control Valve Failure~Increased Heat Transfer Area 15.2.2 Loss of External Electrical Load~Best Benchmark Data~Overpressure Design Transient 15.6.3 Steam Generator Tube Rupture (overfill)

~~Smaller Total Volume 5.2.2 Low Temperature Overpressurization

~Increased Heat Transfer Area~Modeling Enhancements

~RIM.Overpressure Protection 6.2.1.2 Containment Integrity-Steam Line Break~Increased Heat Transfer Area Smaller Nozzle Area 05 October 94 GINNA RELAP5 MODEL 886 460 STEAM LNE Mssv 440 446 470 876 MSIV$7$8$1 480 8$0 8$0 MQV 47$876 STEAM LNE 870 SSC 880 866 860 1 7$0 770 0 802 MFN Pump B HTR soe 01 soe 802 MFW soe Pump A soe HTR 810 880 870 m CC 0 i5 7iO 7CC 746 MAIN FEEDWATER 8 412 MAIN FEEOWATER A 8'I 4 816$14 42 818418$20 eee eCo 733OS$34$33 431 430 sai 422$22 82e 830 832 834 733O7 73$O 733 732~733O ago 733OI 10'IL lg la~1$~'16~18'08 O7 Qe+2 126O'I aaaol 733 oe 733oe 734 733O3 733O 733OI 726 OI'02 420 el 6 426%1 eaao7 saao Ll3 eag 833O3 83/O 833OI O7 OJ O6 O4 226OI IL-12-'I g ge Ig~'I 8 833O saao 833O Sag 833 833OI 12'I 221 22$130 120 220 230 136 IIC 113'110 106 100 200 206 210 213 216 236 13$146 170 176 1$0 2$0 276 270 as6 238 Iio 140 Rc Pump B 146 REACTOR VESSEL RC 240 Pump A 2e6 Ig$168 268 24$160 166 266 260

Ginna reactor vessel and core model hot leg 102 350 106 302 360 eakage path upper plenum 354 352 upper plenum 368 hot leg nozzle 10'03 100 cold leg nozzle 326 324 1 05 cold leg nozzle 320 318 316 330 328 312 375 310 380

Ginna Station Bechtel C)Rochester Gas and Ftectrfc SG Relief Valve and Feedwater Control Valve Failure~Response Less Severe than OSG Initial Pressure is Higher Feedwater Valve is closer to full open~Reactor Trip not Predicted'5 October 94 1.14 RGE-Combined Valve Failure Event Comparison of OSG and RSG 1.12 1.10 1.08 U 1.06 0 0 1.04 O 6$U 1.02 1.00//////////////////Fraction of full power-OSG----Fraction of full power-RSG 10 20 30 40 50 Transient time, Sec Rochester Gas and Electrtc Loss of External Electrical Load~Peak Primary Pressure Unchanged Reactor Trip on High Pressure Unchanged~Peak Secondary Pressure Slightly Higher, Acceptable Higher Initial Pressure 05 October 94

2800 RGE-Loss of Electric Load-RELAPS data Comparison of OSG and RSG acceptance criterion 2600 (0~~CL Q 2400 CL L N 2200-pzr pressure-OSG Pzr Pressure-RSG IIQHBNBIHI 2000 10 20 30 40 50 Transient time, sec RGE-Loss of Electric old-RELAP5 data.Comparison of OSG and RSG 1200 CU M 1100 CL 0)(p 1000 CL 900 (3 GO (I (I ll I Utl INK lNIIRillggllgglg llllg i acceptance criterion-SG dome press-OSG I-SG DOME P-RSG 800'10 20 30 T Transient time, sec 40 50

AHD Ginna Station Bechtegl pldfl I CD Rochester Gas and Electric Steam Generator Tube Rupture More Margin to Overfill Smaller Break Area due to Smaller Tube Higher Initial Secondary Pressure Release Rates Lower 05 October 94

RGE OSG/RSG SGTR COMPARISON USING R5/M2 VER 20HP LEGEND-OSG-RSG gg 80 0 0 0 1200 Time (sec)2000 2800 3200 RGE OSG/RSG SGTR COMPARISON USING RS/M2 VER 20HP LEGEND OSG-A RSG-A 0 2400 a Q l600 C 0 0 l600 Time (sec)'000 2800 3200 Ginna Station Bechtel lpmpson'Rochester Gas and Electric Low Temperature Overpressurization Model improvements Accounted for Loop Delta-P's Potential Flow Choking at PORV Modeled Explicit RHR System Model for Limiting RHR Overpressurization Case Detailed Pump Start Modeling Instrument Tolerances Included RCS Metal Mass Modelled Results~All Acceptance Criteria Met~Limiting Transients Unchanged~Analysis will be Ginna Analysis of Record 05 October 94 RHR SYSTEM MODEL Primary Loop (LTOP Active Loop)Hot Leg Primary (inactive Loop)Cold Leg 100 280 450 469 sink 453 RHR pump B 462 Heat exchanger B 463 RHR Relief Valve 468 451 452 473 472 455 461 460 457 454 RHR pump A Heat exchanger A 475 456

RESULT S OF LTOP RUNS ID Description Peak pressure Allowable per Margin Peak pressure Structural Margin in the Reactor Appendix 6 in psi in RHR system allowable in psi Vessel,psia in psia in psia in psia Case1 Mass addition case 85>F primary 480.19 554.7 74.51 598.43 674.70 76.27 Case2 Heat addition case 85<F primary 548.84 554.7 5.86 643.22 674.70 31.48 Case 3 Heat addition case 320>F primary 565.29 1664.7 1099.41 657.08 674.70 17.62 Note: In Case 3, the peak RV pressure occurs at 21.6 secs and the peak RHR system pressure occurs at 10.7 secs.ln Case1, the peak RV pressure is taken from the strip file of the plot of the parameter, P 3)p

Ginna Station Bechtel lpmpson I Rochester Gas and Electric Containment Integrity-Main Steamline Break 18 Cases Analyzed~RELAP/CONTEMPT

~All Results Acceptable, Lower Peak Pressure (-56 psig)Detailed Modeling Of Feedwater System Flow Restrictor Comparable Initial Inventories 05 October 94

Preliminary esults, Worst Case Steam Line Break 1.1 Split Break, MSlV Failure 60 50 (302.5s, 55.9669 40 a 30~I O.T 20 10 0 0 50 150 Time, sec 250 300 350 400 Ginna Station Bechtegl Lp4ce<<I CD Rochester Gas and Electn'c~New Westinghouse Fuel Fabrication Contract~Insert Vantage-5 Fuel vs.OFA Fuel F.Increase From 1.66 TO 1.75 F,<Increase From 2.32.TO 2.50~Will Incorporate New SG's In New Analysis~Cycle Length Increase From Annual To 18 Months Increase SFP Enrichment Limit From 4.25 w/o To 5.0 w/o TvE Window Of 559'o 573.5'ccident Analysis Will Be Valid Over The Window Redo Reactor Vessel Internal Analysis Using LBB 05 October 94 Ginna Station i Bechtel CD Rochester Gas and Electric TYpe Fuel Rod O.D.14 X 14 OFA 0.40 In Vantage 5 0.40 In Fuel Cladding Material Z,4 Z,4 Active Fuel Length 141.4 In 141.4 In Blanket Region/Enrichment Center Region Enrichment 6 In/Nat.Up To 4.25 w/o 6 In/2.6 w/o Up To 5.0 w/o Bottom Nozzles DFBN DFBN Grids 2 Top And Bottom 7 Mid Intermediate Flow Mixing Discharge Burnups INCONEL-718 Z,4 None Low 40s GWD/MTU INCONEL-7,18 Z,4 None Mid 50s GWD/MTU 05 October 94 cn fQ c C 4P>2>9 O CI CJ 6 8 Cl cn Ca 6 O~O CP U g O~O c5 O cn~B eo g 8 O<a cn CJ g 7a 00+Q O C Q OC cn~Vl M~~V1 5 O C V C5)O-" E O C IQ O U>,c'a RQ<Vs O~C6>).v~a JD cn Cl x 0Žg C4 c R QX A CV CV a X C 0 M Eg O O c5 c O cn C4+cn+uo tD O O cn cn cn cn 0 0 hl cn F d Cl gg"v 4 a O Cp u b cn~~cn O 0 O O O~O C 8 C5 Vs O CC O O~a5 OOU'~O O g cC R Q 0 0 0 0 O O O c C~DR)O c5 CC C4 0 0 0 0 0 C O 0 0 0 g VQ~~ca<<~HKU M4l&~cf I/j IQ I/j Ginna Station ewi I Bechtel,[I Rochester Gas and Electric 1996 Fuel Reload 15.5 15.6 15.7 15.8 Increase in RCS Inventory Decrease in RCS Inventory 15.6.1 Inadvertent Opening of a Pressurizer Safety or Relief Valve 15.6.2 Radiological Consequences of Small Lines Carrying RC Outside Containment 15.6.3 Steam Generator Tube Rupture 15.6.4'Primary System Pipe Ruptures 15.6.4.1 SB LOCA 15.6.4.2 LBLOCA Radiological Release From a Subsystem or Component 15.7.1 Radiological Gas Waste System Failure 15.7.2 Radiological Liquid Waste System Failure 15.7.3 Fuel Handling Accidents Anticipated Transients Without Scram EVALUATE X X X X X X ANALYZE X X X Chapter 6, Chapter 5 6.2.1.2 Containment Integrity 5.2.2 Low Temperature Overpressurization X (8WNT)05 October 94

)

Ginna Station Bechtel C)Rochester Gas and Electric Use Westinghouse.

Question COBRA/TRAC

?Addendum 04 Or?Addendum P3 B.E.Addendum 44 Addendum P3-2200'CT-100'CT Improvement

?NRC Approval Steady State Initialization Complete.Need To Start Transient Runs October 9, 1994 I 05 October 94

AHO Ginna Station Bechtel 2)cD Rochester Gas and Electnc Implementation February 1996~COLR~PTLR No Need for NRC Submittal 05 October 94 r

Ginna Station Bechtel Lp peon Rochester Gas and Electrfc Data Preparation Finalize Input Data Start Analysis Draft Report Final Report 4/1/94 9/30/94 9/30/94 5/1/95 7/1/95 Submit Report To NRC Cycle 26 Startup 8/1/95 5/30/96 05 October 94 Ginna Station Bechtet CD Rochester Gas and Electric R E.GINNA STEAM GENERATOR REPLACEMENT STRUCTURAL EVALUATION OF EFFECTED COMPONENTS 4 SYSTEMS 05 October 94

38 MAIN STEAM LINE STEAM GENERATOR IA 38 MAIN STEAM LINE STEAM GENERATOR I REACTOR COOLANT PUMP IB IC-FEEOWATER I.INE IR FEEOHATER LINE UPPER SUPPORTS ANO SNUBBERS{TVP.)COLO LEG HOT LEG HOT LEG INTERMEOIATE SuPPORTS ITVP.)CROSSOVER LEG COLO LEG LOWER SUPPORTS ITYP.)REACTOR COOLANT PUMP I A REACTOR VESSEL VIEW OF NSSS SYSTEM FOR GINNA NUCLEAR STATION

Ginna Station I Bechtel CD Rochester Gas and Electric REACTOR COOLANT SYSTEM PIPING ANALYSIS Scope Changes+5%Deadweight

+1 ft Center of Gravity Model Development Benchmarking Model Enhancements Expected Results Cunent Status/Schedule Preliminary Piping Results Vessel/Support Evaluations Attached Piping Evaluations Scheduled Completion 12/1/94 05 October 94

~leyt a v BENCFB4ARK RESULTS MODAL RESPONSE~Ginna Station EI ec~htel/Oson~CD CD Rochester Gas and Electric PARTICIPATING COMPONE NT RC PUMP-LOOP A RC PUMP-LOOP B RC PUIVIP-LOOP A RC PUMP-LOOP B S/G-LOOP A S/G-LOOP B S/G-LOOP A S/G-LOOP B RC PUIVIP LOOP A RC PUIVIP LOOP A RC PUMP LOOP A RC PUMP LOOP B S/G-LOOP A S/G-LOOP B REACTOR VESSEL REACTOR VESSEL RC PUMP-LOOP A S/G-LOOP B S/G-LOOP A MODAL DIRECTION Z-TRANSLATION Z-TRANSLATION X-TRANSLATION X-TRANSLATION X-TRANSLATION Z-TRANSLATION Z-TRANSLATION X-TRANSLATION Z-TRANSLATION Z-TRANSLATION Z-TRANSLATION 2-TRANSLATION Y-TRANSLATION Y-TRANSLATION X-TRANSLATION Z-TRANSLATION X-TRANSLATION Z-TRANSLATION Z-TRANSLATION B&W MODEL FREQUENCY (Hz)5.0992 5.2135 6.6992 6.785 7.7842 8.0593 8.1639 8.5241 11.236 13.045 13.353 13.803 15.129 15.168 18.644 19.679 23.483 24.872 25.496 W MODEL FREQUENCY (Hz)4.94 5.06 6.53 6.65 7.69 8.15 8.28 8.65 12.5 13.0 13.3 13.6 15.1 15.1 17.9 22.5 23.9 23.6 24.3 PERCENT DIFFERENCE 3%3%3%2%1%-1%1%-1%-10%p%p 0%0%4%13%2%5%0 05 October 94 Ginna Station i Bechtel j', Rochester Gas and Electric BKNCM4ARK RKSVLTS OBK VESSEL NOZZLE LOADS Vessel Nozzle Reactor Vessel%Difference (Loop Ail3)~Hot Leg~Cold Leg 22%/83%8%/12%Steam Genentor~Hot Leg~Pump Suction 24%/84%15%/17%RC Pump~Pump Suction~Pump Discharge (Cold Leg)13%/14%12%/30%Percentages all Indicate an INCREASE in Calculated Load Over that of the Current Analysis.05 October 94 Rochester Gas and Electric MODEL ENHANCEMENTS/DIFFERENCES Consistent Mass Modeling Explicit Modeling of Supports Frequency Cutoff@30 Hz N-411 Damping Single Anchor Point 3 Single Spectra Closely Spaced Modes Via 10%Rule Explicit ACP Analysis for HELB 05 October 94 Ginna Station Bechtet CD Rochester Gas and Electric Z14~4~I~IS I~IS~t 10 440 110 4 ZS tt~411 ll~~10 14 ZI~~14 ZZO~t0 ttt~10 t10 414 t10~14 tI~~S4 10~1~t40 I S4 OZIOI44 ZOI 0IZW VIEW B-8 SOSSISO 00'OV 00 lI~0 XI 11~SZS 1 It ll~SZS li 0 Sll 1~4~St 14t~SO 104~St Z00~44 101~SS 0 I 0 ZOI SIZ SI~ZOZ SI~100 010 SI~114~44 ZSS~I~~14~It 110~10 t1~~41 11~~44 t10~00~40 Ginna Station Bechte/I SOA Rochester Gas and Electric 5Q I A N Sl~1l~Sl~1 I 0 I I I S S L I Loop SSO SOO~I OO~I SILt~O~4~1--r-.-gOt'I t I OOS SOO L.OOP 2~I1~I~/g I I~IO~I~~IS~I~~11/14~11~I~~, t LLS I SOS8 GInna Statton etvt+'tvt t Beche jt ANO Rochester Gas and Elecvic~759 1SJ 770~758 2I'62 755 77J (REF.POINT)TEO A60VE ICOE 2JS 750 i 2JS 21'54 772 75J 77 I 751~7SS~755~754 J74'S/G LOWER LATERAL SUPPORTS~QI 0 JSJ'J4J I 00 J29'I 2~Oe Ql J I~~OSI 9 I 4 JI 2i 0~RPPIÃT LOCATION~40 9 I 5 280'ICP TIE ICOS AI4)STEAH GE%RATTH I OCR lATERAL SLPPOI ITS~JO~osJ~QS4~905 QIS 255'U Y E SEEaczv 5 INTERIOR STRUCTLHE E Y U SHIELO 6UILDING WALL MODEL Ginna Station Bechtegl/pion~Rochester Gas and Electric CURRENT EXPECTATION Deadweight

-Increase (<5%)Thermal-Same Seismic-UnknownModel Enhancements Decrease Loads-Cold Leg.Increase Loads-Hot Leg Increased Weight Overall Effect-Loads Increase-More Margin for Cold Leg'-Less Margin for Hot Leg LOCA-Inctiase (<15%)Blowdown Initial Conditions Will Use 15'F Reduced TVG HELB-Decease 05 October 94 4

'C0 f Ginna Station I Bechte/Rochester Gas and F/ectr/c I PIPING STRESSES ANSI 831.1 EQUATION No.Equation 11 (DW.+Press)Equation 12-Upset/Design (DW+Press+OBE)Equation 12-Emerg.(DW+Press+SSE)RCS PIPING SEGMENT HOT LEG COLD LEG PUMP SUCTION HOT LEG COLD LEG PUIVIP SUCTION HOT LEG COLD LEG PUMP SUCTION 88cW MODEL PIPING STRESS (Ksi)63%52%48%61%56%47%45 46%38%W MODEL PIPING STRESS (Ksi)43%41%41 o/o 4p 41%41%30oio 30%30%Equation 12-Faulted HOT Lf G (DW+Press+COLD LEG (SSE+DBPR P)PUIVIP SUCTION 47%41%37%4p 4p 40%Equation 13 IVlax Thermal Range+OBE Equation 14 Max Thermal Range+OBE+DW+Press HOT LEG COLD LEG PUMP SUCTION HOT LEG COLD LEG PUMP SUCTION 61%19%9%61%29%22o/o 36%20%27%38 25%35%05 October 94 Ginna Station Becht/et tthnttSCn~Rochester Gas and Electric PROPOSED INSTALLATION OVERVIEW During 1995'perating Cycle~Receive RSGs~Site Improvements/Buildings

~Tower Crane for Dome Access~Erect Construction Equipment on Dome~Drill/Cut Outer Layer (~6"-8")~Position Lampson Transilift

~Transport Ec Stand RSGs Outside Containment Cold Shutdown/Defueling Set up Auxiliary Crane Initiate Concrete/Rebar Removal from Dome Remove Interferences from Interior of Dome Remove Interferences from Around OSGs Cut Secondary Side Piping (MS, FDWTR)Set up Equipment for RCS Cutting DECON/Encapsulate OS 6 Exterior Set up Backup Spent Fuel Pool Cooling 05 October 94 0

(>>pinna Slalion t Bechtel Rochester Gas and Electric PROPOSED INSTALLATION OVERVIEW (Continued)

Reactor De-Fueled (SGR"Window")I~Cut/Remove Dome Liner~Cut RCS Piping 0 Remaining Secondary Lines (B/D, Level)~Lift/Remove OSGs&Lift/Install RSGs~Refit/Reweld Liner for Dome~Establish Containment Integrity~Weld Secondary Side&, RCS Piping~Establish RCS&Secondary Side Integrity~Begin Replacing Rebar~Begin Pouring Concrete to Close Dome Openings Refueling/Cold Shutdown (Fuel in Reactor)4 Complete Rebar&, Concrete Work Concrete Cure Complete Dome Interference Replacement Complete Replacement of Interferences Near RSGs Disassemble/Remove Equipment from Containment Structural Integrity Test RCS ASME Section XI Leak Test Startup/At Power RSG Performance Tests/Monitoring RSG Level Control Tuning Disassembly of Dome Construction Equipment Dismantling of Site Improvements/Buildings 05 October 94 SITE PLAN GINNA NUCLEAR POWER STATION 0 Glnna Station Bechtel simpson CD Rochester Gas and Electric RCS PIPE CUTI1NG Cut Method 2 Cut (1 Hot Leg;1 Cold Leg)Bracing Deadweight Supports Only Contingency is Cold Leg Elbow Replacement Welding Automatic Remote Machine Narrow Gap Weld Prep 5'evel Weld Both Sides to Ease Fit-Up 316 SST Filler NDK~Inspect per ASME Section XI~Surface;Volumetric; Leak Test~Research and Development In-Progress for ISI 05 October 94 AHO I Ginna Station Bec~htelg/I Qmpun>CD CD Rochester Gas and Electnc WELD PREP R (Typical)B2 1/2 max M 304 M-1/2 BWI Ginna Station 8echte jt i 0$0A Rochester Gas and Electnc ADJACENT WELDS SHOP WELD g-152)SAFE END (FORGED 316L/316LN)UTTER g-152)RS/G NOZZLE (SA-50S CL 3)CLADDING (309L/300L)FKLD WELD (ER 316)RCS ELBOW (CAST 316 SST)

Ginna Station Bechtel CD Rochester Gas and Electrfc Movement of Lampson Crane into Protected Area During Plant Operation~No Swing of Boom Over Safety Related Structures Transportation of New SG's to Stand-Up Frame During Operation Upending New SG's for Prep Work and Insulation Installation

~Stand-up Location Outside Drop Zone 05 October 94

MOVEMENT OF LAMPSON CRANE INTO PROTECTED AREA DURING OPERATION SLIDE 1 Ginna Station Bechtel Lp peon Rochester Gas and Electric Removal of Old SG's Cold Shutdown, Fuel Removed from Containment

~Single Lift Point~Within Load Drop Analysis Parameters Defined by Dome Openings~Engineered Foundation Precludes Only Experienced LTL Failure~No Movement of LTL;Slight Rotations During Extractions Downending to Fixture in Yard East of Containment

~SG Maintained Close to Ground~SG Does not Pass Over Site Structures s~Transportation to OSGSF Via Transporter 05 October 94

'E.>>V g>~~h t*\)4-"o r, tg l k'I$'4 k t t 1 LAMPSON TRANSI-L IF T SCRIVE EYE (BY OTHERS)\1 I I I I~I I I I I~I I I 1 I I I I I I I I I I I I I I~PIN (NK-014PI)&KEEPER R 90'INK PLATE (N-014LKI)

SEE NOTE 11 OLO STEAN GENERATOR I~~~~~~~~V I (I/g)PLUG PIN (N-0)4PI)&KEEPER R PLUG I I~I I 0 I~I PARTIAL ELEVATION OF OLO STEAM GENERATOR I/=I'-0

'~, 1 1 t rO C'I p ,I C C~C'%r, J~pf".~'.g-'"'~s'g;~'.lN~i),~r;.'.:.'..

',4."';" pi~V~)\'~I , lg~rj l JlA~-J yl I I~'I,.1~'w'I'I b.'I'I'I J..1 tI.t m K I J JI C.I~It I'If~I t'tt 4 I I I I I I E\4 h~i~aV.~,,vr.t , q'~!~~4.4".i',~q I., gl I

,'r gpss'!'<<1 4'(4 C l i'.?.\'g4~,;~)1 i'M.~g~"'~fi',I 1 lf q!tH'5 C~beg;~1 l J g: kf~~l,q J A, gV J.s+~t t's t 1 Ginna Station BWI Bechtgl CD Rochester Gas and Electric Rigging New S/6's Movement of Crane with Load on Engineered Foundations

~No Movement of LTL Once Hoisting has Begun (Lift Position)~Slight Rotations During Insertion~Boom and Load Prohibited From Passing Over SFP 05 October 94 STEAM GENERATOR RIGGiNG TO THE OOZE I I L SLIDE 3

Ginna Station Bechtel lplllpOOh Rochester Gas and Electric Dome Construction Openings~"A" S/6 Hexagon,"B" S/6 Hexagon with Slot~Conforms to Load Drop Analysis Parameters

~S/6 Precluded from Impacting SFP

)

A EXTENT QF CHIP BACK OPENlNG OUTLlNES-(sg)i ie il/i PARTIAL PLAN OF CON DOME Ginna Station BN~Bechtel POOh Rochester'es and Electnc Concrete Removal Process~360'upport Platform"CROWN" (Concrete Removal Outside Walkway Network)~Excavation from Top of Openings~No Strongbacks

~No Enclosures Over Openings~Utilizes Automated Hydraulic Jack Hammers 05 October 94

"CROWN'ONCRETE REMOVAL OUTSIDE WALKWAY NETWORK, au.AROUND EXTENT OF CHIP BACK OPENING OUTLINES I II I I I)it CaJtVEO/IS 0)l~~C~~0/PARTIAL PLAN OF CONTAI DOME SLIDE 2 glAQQAVEP JACK HA~%5 MACHINES TO BE MOUOfAIm ROWN-o"+~IREE'~I N po-e+0-EL'Ii Q o C C'~Qa, d S~Ir4 Q(IS i.'4 1 P4HTlW~II, TVP.CATCH CONTAlNMENT ALL AROUND~~I~P~~VEt.5RZIHG I-~H-.PBo'-8~~~~A SECTION SECTIONAL VIEW OF CONTAINNIENT DOME SHOWNG'CROWN'LIDE 3

Glnna Station BWI BecI1 teI Rochester Gas and Electrfc Concrete Test Block Program Completed in 6/94~Automated Jackhammer Demonstration

~Determined Best Excavation Technique~Determined Machining Impact Energy Level~Determined Machine Sensitivity and Operator Control 05 October 94

)

Ginna Station Bechtel CD CD Rochester Gas and Electric Test Block Conclusions

~Machine won't Damage Rebar or Liner~Concrete Breaks Clean Off Liner~Excavation Quantities Support Outage Scheduling

~Additional Engineering Ongoing to Support Removal Sequencing 05 October 94 Ginna Station Bechtel CD CD Rochester Gas art d Efectric Repair of Containment Dome~Reuse Existing Liner Plate Cadweld Rebar Splices or Stick-Weld

~Leak Channel Integrity Liner Stiffeners may be Required~Monolithic Pour 05 October 94 Ginna Station Bechtet CD Rochester Gas and Electric Structural Analysis Containment Opening Design by Bechtel Load Drop Analysis Dictates Hole Parameters Dome with Opening Structurally Adequate Crown Loadings Input to Analysis~Repair Sequencing Ongoing~RGAE Containment Model for Overcheck 05 October 94 CONTAMENf (gast oa be~opjuiq@)DONE OPENING Op+S~/~S'~4~A WW.F: 4'.~,l E g-~IS egr A DETAIL I/R~I'R~SUDE 0.

~-gl Rochester Gas and Electric Current Configuration

~One Generator-Mirror~One Generator-Mirror/Asbestos

~Single Sump Design Precedes RG 1.82 Horizontal Grating Vertical Screen in Sump Replacement Plans~Blanket or Blanket/Mirror

~Sump Will Be Evaluated Upgrade To Improve Will Not Meet RG 1.82 Possibility of Creditting Platforms 05 October 94 qe Ginna Station Bechtel Bitt'I Pooh CD Rochester Gas and Electric RP Activities Already Addressed~Working with Plant RP Staff on Issues Common to Plant/Project Outage Success Incentive Based Contractor RP Technician Specification/Contract Member of LLRW Technical Subcommittee Electronic Dosimetry Evaluation, Selection and Funding Project RP Instrumentation Estimated Needs Purchased Majority from North Anna SGRP Group~Old Steam Generator Disposal Options On-Site'nterim Storage is Current Plan 05 October 94 I

BWI Glnna Station Bechtel Rochester Gas and Electric RP Activities Already Addressed (Continued)

Inquired with Vendors on Alternative Methods for Disposition of OSGs Will Continue to Investigate Alternatives

~Pipe-End Decontamination Methods Witnessed Two Different Methods: CO, and Sponge Blast (Demonstrations)

Tentative Approval for Sponge Blast Plan to Witness Sponge Blast Application at V.C.Summer SGR Outage~Man-Rem Incentive for Prime Contractor 05 October 94 Glnna Station Bechtel I c)u Rochester Gas and Electrtc Ongoing Activities

~, Project RP Plan Being Drafted Interface Specification has been Completed and Incorporated Procedure Reviews for Incorporation Plant Commitments Tracked for Incorporation V.C.Summer SGRP Visit Key RP Staff Will Witness Important Evolutions Allow Incorporation of Lessons Learned on Pipe-End Decontamination

~Prime Contractor Submittal Review Procedure Reviews Facility Designs 05 October 94 k4 Ginna Station BWI Bee I Rochester Gas and Electric Ongoing Activities (Continued)

Site Layout and Personnel Flowpaths Work Plans Concrete Plans Crane and Dome Decontamination Dome Liner and Concrete Activation Study Asbestos Insulation Removal Optical Templating Interference Modifications 05 October 94 Ginna Station Bechtel Rochester Gas and Electrfc Component Preliminary Safety Evaluation Final Report/50.59 Safety Evaluation September 1994 May 1995 Installation Activities Safety Evaluation Of Containment Openings August 1995 Safety Evaluation of Rigging And Handling July 1995 Safety Evaluation Of Steam Generator Piping May 1995 Safety Evaluation Of Steam Generator Insulation Testing and Inspection Plan May 1995 June 1995 05 October 94 1 I