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 (ACCELERATED RIDS EY P ROC ESSIVE G

1 REGULATORY INFORMATXON DXSTRXBUTION SYSTEM (RIDS)

ACCESSION NBR: 9412010209 DOC. DATE: 94/11/23 NOTARIZED: NO DOCKET 12 FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 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 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 1 PD1-3 PD 1 1 JOHNSON(A 1 1 TNTERNA : FILE CENTEB 01 1 1 NRR/DE/EELB 1 1 RR/DRCK/HICB 1 1 NRR/DRPW 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT= 1 1 OGC/HDS3 1 0 EXTERNAL'OAC 1 1 NRC PDR 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 ifINATEYOI 'R NAZIE 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 the analysis of the Low Temperature Overpressurization transient is our intention to make 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 00 PDR ADQCK 05000244 p PDR

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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

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Ginna Station

~

9412010209 Bechtel Rochester Gas and Electric Ginna Station Steam Generator Replacement NRC Status Update October 5, 1994 I. INTRODUCTION G. Wrobel II. PROJECT STATUS/OVERVIEW B. Carrick Fabrication Status Installation Status III. RSG SAFETY EVALUATION B. Flynn Preliminary Safety Evaluation Accident Analyses Containment Analysis Low Temperature Overpressurization IV. 1996 FUEL RELOAD R. Eliasz

~ Steam Generator Replacement Interface

~ Improved Technical Specifications Interface LUNCH V. RCS PIPING ANALYSIS B. Carrick VI. REPLACEMENT STEAM GENERATOR B. Carrick INSTALLATION M.Fitzsimmons B. Flynn RCS Pipe Cutting/Welding Rigging Scheme/Drop Analysis Containment Dome Openings Steam Generator Insulation/Containment Sump Analysis VII. RADIOLOGICALPROTECTION MEASURES A. Herman VIII. SUBMITTALSCHEDULE B. Flynn OS October 94

JY 8'lVI f Ginna Station

~ Bechtel 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

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.PWR Replacement Steam Steam noate Hgn ethctency moteture seParstors Sundle Inspection access duct

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simpson CD Rochester Gas and Electric INSTALLATIONSTATUS 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

Ginna Station BVVI AHO Bee%el

~PICNl Rochester Gas and Electric R.E. Ginna Steam Generator Replacement Equipment Comparison Existing Replacement Manuf./Model W/44 (feedring) BWI (feedring)

Primary Side Pressure Drops (0% plug)

Nozzle inlet to Nozzle outlet 33.5 psi 31.0 psi Primary Side Flow for above dp's 34.6 E06 Ibm/hr 35.0 E06 ibm/hr Heat Transfer Areas 0% Plugging 44430 sq. ft. 54001 sq. ft.

15% Plugging 37765 sq. ft.

20% Plugging 43200 sq. ft.

Tubing OutsideDiameter 0.875 in 0.750 in Avg'. Wall Thickness 0.050 in 0.0431 in Number of Tubes 3260 4765 Material Inconel 600, MA Alloy 690, TT Volumes, primary side Inlet Plenum 133 cu. ft. 130 cu.ft.

Tubes 675.5 cu. ft. 710 cu.ft.

Outlet Plenum 133 cu. ft. 130 cu, ft.,

Secondary Volume, Total 4580 cu. ft. 4513 cu. ft.

Secondary Water Mass, nominal 100% (1520 MWt) 85,410 ibm 86,257 ibm 0% (HZP) 130,120 ibm 118,836 ibm Secondary Mass Flow, 100% 3.3 E06 ibm/hr 3.3 E06 ibm/hr Steam Line Orifice Size 4.37 sq. ft. 1.4 sq. ft.

Initial Steam Pressure, 100% 830 psia 877 psia 0

05 October 94

Ginna Station Bechtel CD Rochester Gas and Electric EVALUATE ANALYZE 15.1 Increase in Heat Removal by the Secondary System X 15.1.1 Decrease in Feedwater Temperature X 15.1.2 Increase in Feedwater Flow X 15.1.3 Excessive Load Increase Incident X 15.1.4 Inadvertent Opening of a SG Relief/Safety Valve X 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 X 15.2.3 Turbine Trip X 15.2.4 Loss of Condenser Vacuum X 15.2.5 Loss of Offsite Power to the Station Auxiliaries X 15.2.6 Loss of Normal Feedwater Flow X 15.2.7 Feedwater System Pipe Breaks Decrease in RCS Flowrate 15.3 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 X 15.4.2 Uncontrolled RCCA Withdrawal at Power X 15.4.3 Startup of an Inactive Reactor Coolant Loop X 15.4.4 CVCS Malfunction X 15.4.5 RCCA Ejection X 15.4.6 RCCA Drop X 15.5 Increase in RCS Inventory 15.6 Decrease in RCS Inventory X 15.6.1 Inadvertent Opening of a Pressurizer Safety or Relief Valve 15.6.2 Radiological Consequences of Small Lines Carrying RC Outside Containment X 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 X 15.7.2 Radiological Liquid Waste System Failure X 15.7.3 Fuel Handling Accidents X 15.8 Anticipated Transients Without Scram Chapter 6, Chapter 5 X 6.2.1.2 Containment Integrity X 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 STEAM LNE Mssv 8$ 1 STEAM LNE MSIV MQV 460 440 446 470 876 480 8$ 0 8$ 0 876 870 SSC 880 866 860

$ 7$ 47$ 1 0 802 soe 802 7$ 0 MFN 880 MFW Pump B soe Pump A HTR soe soe HTR 770 01 810 870 m

CC MAIN FEEDWATER 8 412 MAIN FEEOWATER A eee 0 8'I 4 816 7CC eCo

$ 14 i5 7iO 746 42 818418 $ 20 733OS $ 34 $ 33 431 430 sai 422 $ 22 82e 830 832 834 726 426

'08 733O7 aaaol OI 420 %1 eaao7 833O 10 O7 O7 73$ O 'IL Qe 733 oe el 6 saao OJ IL saao 733 lg 733oe '02 Ll3 O6 -12 833O 732~ la 734 eag O4 -'I g Sag 733O ~

1$ 733O3 833O3 ge 833 ago ~ '16 +2 733O 83/ O Ig 733OI ~ 18 126O'I 733OI 833OI 226OI ~ 'I 8 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 REACTOR VESSEL Iio 140 Rc RC 240 Pump B Pump A 146 2e6 Ig$ 168 268 24$

160 166 266 260

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

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

RGE - Combined Valve Failure Event 1.14 Comparison of OSG and RSG 1.12 1.10 1.08

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1.00 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

RGE - Loss of Electric Load - RELAPS data 2800 Comparison of OSG and RSG acceptance criterion

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(0 CL 2600 pzr pressure - OSG Pzr Pressure - RSG Q

2400 CL L

N 2200 IIQHBNBIHI 2000 10 20 30 40 50 Transient time, sec

RGE - Loss of Electric old - RELAP5 data.

Comparison of OSG and RSG 1200 acceptance criterion Utl INK lNIIRillggllgglg llllg i CU M 1100 CL 0)

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SG dome press - OSG SG DOME P - RSG 900 I

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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 80 gg 0

0 0 1200 2000 2800 3200 Time (sec)

RGE OSG/RSG SGTR COMPARISON USING RS/M2 VER 20HP LEGEND OSG-A RSG-A 0 2400 a

Q l600 C

0 0 l600 '000 2800 3200 Time (sec)

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 Primary Loop (inactive Loop)

(LTOP Active Loop) Cold Leg Hot Leg 100 280 469 450 sink RHR pump B 462 Heat exchanger B RHR Relief Valve 468 453 463 473 460 451 457 472 461 452 455 Heat exchanger A 475 454 RHR pump A 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 (302.5s, 55.9669 50 40 a

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0 50 150 250 300 350 400 Time, sec

Ginna Station Bechtegl

<<I Lp4ce 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 14 X 14 OFA Vantage 5 Fuel Rod O.D. 0.40 In 0.40 In Fuel Cladding Material Z,4 Z,4 Active Fuel Length 141.4 In 141.4 In Blanket Region/

Enrichment 6 In/Nat. 6 In/2.6 w/o Center Region Up To 4.25 Up To 5.0 Enrichment w/o w/o Bottom Nozzles DFBN DFBN Grids 2 Top And Bottom INCONEL-718 INCONEL-7,18 7 Mid Z,4 Z,4 Intermediate Flow Mixing None None Discharge Burnups Low 40s Mid 50s GWD/MTU GWD/MTU 05 October 94

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Rochester Gas and Electric 1996 Fuel Reload EVALUATE ANALYZE 15.5 Increase in RCS Inventory X 15.6 Decrease in RCS Inventory 15.6.1 Inadvertent Opening of a Pressurizer Safety or Relief Valve X 15.6.2 Radiological Consequences of Small Lines Carrying RC Outside X Containment 15.6.3 Steam Generator Tube Rupture 15.6.4'Primary System Pipe Ruptures 15.6.4.1 SB LOCA X 15.6.4.2 LBLOCA X 15.7 Radiological Release From a Subsystem or Component 15.7.1 Radiological Gas Waste System Failure X 15.7.2 Radiological Liquid Waste System Failure X 15.7.3 Fuel Handling Accidents X 15.8 Anticipated Transients Without Scram X Chapter 6, Chapter 5 6.2.1.2 Containment Integrity X 5.2.2 Low Temperature Overpressurization (8WNT) 05 October 94

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Ginna Station Bechtel C)

Rochester Gas and Electric Use Westinghouse. COBRA/TRAC B.E.

Question

? Addendum 04 Or

? Addendum P3 Addendum 44 -2200'CT Addendum P3 -100'CT Improvement

? NRC Approval Steady State Initialization Complete.

Need To Start Transient Runs October 9, 1994 I

05 October 94

Ginna Station Bechtel AHO

2) cD Rochester Gas and Electnc Implementation February 1996

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~ PTLR No Need for NRC Submittal 05 October 94

r Ginna Station Bechtel Lp peon Rochester Gas and Electrfc Data Preparation 4/1/94 Finalize Input Data 9/30/94 Start Analysis 9/30/94 Draft Report 5/1/95 Final Report 7/1/95 Submit Report To NRC 8/1/95 Cycle 26 Startup 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 38 MAIN STEAM LINE STEAM GENERATOR IA 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.)

LOWER SUPPORTS ITYP.)

CROSSOVER LEG COLO LEG 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

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CD CD Rochester Gas and Electric BENCFB4ARK RESULTS MODAL RESPONSE B&W MODEL W MODEL PARTICIPATING MODAL PERCENT FREQUENCY FREQUENCY COMPONE NT DIRECTION DIFFERENCE (Hz) (Hz)

RC PUMP- LOOP A Z-TRANSLATION 5.0992 4.94 3%

RC PUMP - LOOP B Z-TRANSLATION 5.2135 5.06 3%

RC PUIVIP- LOOP A X-TRANSLATION 6.6992 6.53 3%

RC PUMP - LOOP B X-TRANSLATION 6.785 6.65 2%

S/G - LOOP A X-TRANSLATION 7.7842 7.69 1%

S/G - LOOP B Z-TRANSLATION 8.0593 8.15 -1%

S/G - LOOP A Z-TRANSLATION 8.1639 8.28 1%

S/G - LOOP B X-TRANSLATION 8.5241 8.65 -1%

RC PUIVIP LOOP A Z-TRANSLATION 11.236 12.5 -10%

RC PUIVIP LOOP A Z-TRANSLATION 13.045 13.0 p%

RC PUMP LOOP A Z-TRANSLATION 13.353 13.3 p RC PUMP LOOP B 2-TRANSLATION 13.803 13.6 S/G - LOOP A Y-TRANSLATION 15.129 15.1 0%

S/G - LOOP B Y-TRANSLATION 15.168 15.1 0%

REACTOR VESSEL X-TRANSLATION 18.644 17.9 4%

REACTOR VESSEL Z-TRANSLATION 19.679 22.5 13%

RC PUMP - LOOP A X-TRANSLATION 23.483 23.9 2%

S/G - LOOP B Z-TRANSLATION 24.872 23.6 S/G - LOOP A Z-TRANSLATION 25.496 24.3 5%

0 05 October 94

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Rochester Gas and Electric BKNCM4ARKRKSVLTS OBK VESSEL NOZZLE LOADS Vessel Nozzle  % Difference (Loop Ail3)

Reactor Vessel

~ Hot Leg 22% / 83%

~ Cold Leg 8% /12%

Steam Genentor

~ Hot Leg 24% / 84%

~

Pump Suction 15% / 17%

RC Pump

~

Pump Suction 13% / 14%

~

Pump Discharge 12% / 30%

(Cold Leg)

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

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Rochester Gas and Electric CURRENT EXPECTATION Deadweight - Increase (<5%)

Thermal - Same Seismic - Unknown Model Enhancements Decrease Loads - Cold Leg

. Increase Loads - Hot Leg Increased Weight - Loads Increase Overall Effect - 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

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Rochester Gas and F/ectr/c I

PIPING STRESSES ANSI 831.1 RCS PIPING 88cW MODEL W MODEL EQUATION No. SEGMENT PIPING STRESS PIPING STRESS (Ksi) (Ksi)

Equation 11 HOT LEG 63% 43%

(DW. + Press) COLD LEG 52% 41%

PUMP SUCTION 48% 41 o/o Equation 12- HOT LEG 61% 4p Upset/Design COLD LEG 56% 41%

(DW+ Press PUIVIP SUCTION 47% 41%

+ OBE)

Equation 12- HOT LEG 45 30oio Emerg. COLD LEG 46% 30%

(DW+ Press+ PUMP SUCTION 38% 30%

SSE)

Equation 12- Faulted HOT LfG 47% 4p (DW + Press + COLD LEG 41% 4p (SSE + DBPR P) PUIVIP SUCTION 37% 40%

Equation 13 HOT LEG 61% 36%

IVlax Thermal Range COLD LEG 19% 20%

+ OBE PUMP SUCTION 9% 27%

Equation 14 HOT LEG 61% 38 Max Thermal Range COLD LEG 29% 25%

+OBE+ DW+ PUMP SUCTION 22o/o 35%

Press 05 October 94

Ginna Station Becht/et

~

tthnttSCn Rochester Gas and Electric PROPOSED INSTALLATIONOVERVIEW 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

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pinna Slalion t Bechtel Rochester Gas and Electric PROPOSED INSTALLATIONOVERVIEW (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 Bracing2 Cut (1 Hot Leg; 1 Cold Leg)

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

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CD CD Rochester Gas and Electnc WELD PREP R (Typical)

B2 1/2 max M304 M-1/2

Ginna Station BWI 8echte jt i 0 $ 0A Rochester Gas and Electnc ADJACENT WELDS SHOP WELD g-152)

UTTER g-152)

SAFE END (FORGED 316L / 316LN)

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

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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

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A EXTENT QF CHIP BACK OPENlNG OUTLlNES

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/i ie 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 WALKWAYNETWORK, EXTENT OF CHIP BACK au. AROUND OPENING OUTLINES I II I I I )it CaJtVEO

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PARTIAL PLAN OF CONTAI DOME SLIDE 2

glAQQAVEP JACK HA~%5 ROWN-

MACHINES TO BE MOUOfAIm o" +

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ALL AROUND Q o Ii C P4HTlW C'~

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'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

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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 DONE OPENING (gast oa be~ opjuiq@)

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~-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 Bitt'I Bechtel 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 Glnna Station BWI 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 c) uI 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 September 1994 Final Report / 50.59 Safety Evaluation 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 May 1995 Testing and Inspection Plan June 1995 05 October 94

1 I