ML20024G728
| ML20024G728 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/12/1991 |
| From: | Robert Stransky Office of Nuclear Reactor Regulation |
| To: | Marsh L Office of Nuclear Reactor Regulation |
| References | |
| TAC-79384, NUDOCS 9104290025 | |
| Download: ML20024G728 (29) | |
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April 12, 1991 Docket No. 50-341 MEMORANDUM FOR:
L. B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects III/IV/V FROM:
Robert Stransky, Project Manager Project Directorate 111-1 Division of Reactor Projects lil/IV/V
SUBJECT:
SUMMARY
OF MEETING WITH GENERAL ELECTRIC (GE) AND BWR OWNER UTILITIES CONCERNING GUIDELINES FOR BWR POWER UPRATES (TAC NO. 79384)
A meeting between the NRC staff, GE Nuclear Energy, and a number of interested utilities was held on March 20, 1991, at the Fermi site to discuss the status of efforts underway by GE and the staff to develop a generic program for the submittal and review of BWR power uprate amendment requests. A list of attendees is included as Attachment 1.
GE representatives presented an overview of their current efforts to generate a comprehensive list of review topics for power uprate applications, and also reviewed progress being made to develop bounding analyses for various systems and components which are common to BWRs. Additional presentations were made by Detroit Edison Company (DECO) and the Powe" Authority of the State of New York (NYPA) cor.cerning the status of pending power uprate applications for Fermi 2 and Fitzpatrick.
A-copy of the slides presented at the meeting is included as Attachment 2.
Following the presentations, a roundtable discussion was held between members of the staff, GE, and the utilities.
Preliminary comments and questions concerning GE Licensing Topical Report (LTR) NEDC-31897P, " Generic Guidelines for GE Boiling Water Reactor Power Uprate," were delivered by the staff. These comments dealt with the content and format of the LTR, the possibility of performing generic bounding analyses for components and systems comon to different BWRs, and the need to assure that previous NRC Bulletins and Generic Letters GE Service Information Letters, and other industry experiences are properly addressed with respect to reactor operation at an increased power level. GE lI 9104290025 910412 PDR ADOCK 05000341 NRC HLE CENT Jfr01 i
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conmitted to respond to these and other forthcoming questior.s from the staff during the next meeting, to be held at NRC Headquarters.
1 A tentative schedule for the submittal of a revised LTR and supporting generic analyses was presented by the f:FC ev (Messed. Although General Electric is pursuing a generit oppruoch for power uprates, time constraints may require thet Fermi-2 and Fitzpatrick anendment applications for power uprate contain a significant amount of plant-specific analyses. Subsequent plants, however, should be able to mole use of CE_ generic BWR analyses in their power uprate requests. Additionally, several utilities commented that prepar6 tion for a plant power uprate requires a review of the entire plant, not just the systems and issues which need to be presented to the NRC for review. A statement was t6de that information from these additional reviews should be retained on-site for possible NRC scrutiny.
The staff ond GE agreed to meet on at least a monthly basis to ensure that activities releted to the power uprate program remain on schedule. Tht he:it meeting between the staff and GE is scheduled for April 17, 1991, at 119C Headquarters, t,
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ert Stransky, Fr 4tct Manager
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Project Directorate !!I-1 Division of Reactor Frejects Ill/1V/V Attethments:
1.
Attendees C.
Slides cc:
CE Power Uprate Distribution I
2 consnitted to respond to these and other forthcoir.ing questions from the staff during the next meeting, to be held at NRC Headquarters.
A tentetive schedule for the submittal of a revised LTR and supporting generic 4
analyses was presented by the NRC and discussed. Although General Electric is pursuing a generic approach for power uprates, time constraints may require that fermi-2 and Fitzpatrick amendment applications for power uprate contain a significant amount of plant. specific analyses.
Subsequent plants, however, should be able to make use of GE generic BWR analyses in their power uprate requests. Additionally, several utilities contnented that prtprt tivi, for a plant power uprate requires a review of the entire plant, not just the systens and issues which need to be presented to the NRC for review. A statement was made that information from these ac'ditional reviews should be reteiried cri-site for possible NRC scrutiny.
The staff and GE agreed to r er,t cn at least a monthly basit to ensure that activities related to tre power uprate program remain on schedule. The next meeting between the staff and GE is scheduled for April 17, 1991, at NRC Headquarters.
/s/
Robert Strinsky, Project Manager Project Directorate 111-1 Division of Reactor Projects Ill/IV/V Attachments:
1.
Attendees E.
Slides cc:
GE Power Uprate Distribution DISTRIBUTION Fo M File NRC & LOCAL PDRs PD31 R/F OGC WPEGG ACRS(10)
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2k GE POWER UPRATE DISTRIBUTION F. Miraglia J. Partlow W. Russell S. Varga B. Boger J. Zwolinski i
E. Leeds R. Lobel A. Thadani G. Holahan J. Richercson B. D. Liaw C. McCracken G. Hubbard C. Y. Cheng K. Parcrewski R. Jones L. Lois S. Newberry L. Phillips.
J. Norberg D. Tereo S. Hou G..Bagchi F. Rosa F. Congel L. Cunningham W. Beckner M. Young L. B. Marsh J. Stang R. Capra D. Brinkman B. ficCabe E. Adensula T. Le W. Butler
- G. Suh R. Clark M. Thadani S. Dembek
- J. Dyer P. Eng-J. Ilu.non
-J. Hall D. llatthews K. Jabbour I
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Mr. William Orser Detroit Edison Company Fermi-2 Facility.
CC:
John Flynn, Esq.
Senior Attorney Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health P. O. Box 30195 Lansing, Michigan 48909 Mr. Walt Rogers U.S. Nuclear Regulatory Commission Resident Inspector's Office 6450 W. Dixie Highway Newport, Michigan 48166 Monroe County Office of Civil Preparedness-963 South Raisinville Monroe, Michigan 48161 Regional Administrator, Region ill U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Ms. Lynne Goodman Director - Nuclear Licensing Detroit Edison Company Fermi Unit 2 6400 North Dixie Highway Newport, Michigan 48166 I
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Attadinent i
. LIST OF ATTENDEES BWR POWER UPRATE MEETING MARCH 20, 1991 Name Utility D. Robare GE K.
Berry GE E. Eckert GE J. Lafferty NYPA M. Deora Deco L. Wooden DECO R. Salmon DECO R. Newkirk DECO L. Go'odman DECO W.
Pegg NRC/PD31 R. Stransky NRC/PD31 L. B. Marsh NRC/PD31 W. McNeil DECO J. Nicholson SWEC M. May DECO C.
Tully GPCo C. Wiedersum PECo D. Alexander PSE&G A. Ho PSE&G M.
Mjaatvedt PP&L T.
Fay NMPC
4 GE Nuclear Energy t
BWR 4
t Interim Information Exchange Meeting l
l MARCH 20,1991 i
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BWR POWER UPRATE Introduction Dave Robare (GE)
Tad Marsh (NRC) t Utility Presentations l
DECO NYPA GE Presentation Licensing Evaluations Kathy Berry Engineering Evaluations Gene Eckert 9
i Discussion & Summary 4
I 4
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BWR POWER UPRATE BWR Submittal Status (To NRC)
Ferrni 2 10/1/91*
l FitzPatrick 11/91*
j Nine Mile Point 2 4Q91 Susquehanna 1&2 3/92*
r Hanford 2 92*
1 (2) Unit BWR/4 Region 11 92 i
(1) Unit BWR/4 Region I (2) Unit BWR/4 Region I
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- Letter of Intention Sent to NRC
BWR POWER UPRATE Generic Licensing Evaluations Review all GLs, IEBs, IENs, SILs, USis, TMI items - Identify those which are Power Dependent Generic Safety Evaluation - drait complete o
Unreviewed Safety Issue Considerations j
o No Significant Hazards Considerations j
o Technical Specification Cnanges~
EOP Impact - draft complete l
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i BWR POWER UPRATE - LICENSING EVALUATIONS (cont.)
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l EOP Impact I
t Operator Actions Do Not Change l
Conditions at which Actions are Specified May Change l
Some EOP Variables and Curves May Require Recalculation 1
4 l
o Heat Capacity Level Limit 1
0 Maximum Core Uncovery Time Limit o
Minimum Core Flooding Interval I
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Minimum RPV Flooding Pressure j
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Technical Evaluations - Two Levels of Generic NRC
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Review i
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ESTABLISH METHODOLOGY AND ANALYSIS ASSUMPTIONS f
B)
DEMONSTRATE THAT. NSSS-DRIVEN INPUT TO TECHNICAL EVALUATIONS IS BOUNDING AT UPRATED CONDITIONS (current SAR information or additional generic information to be provided in l
LTR) l ALL OTHER' ASPECTS EVALUATED AT PLANT UNIQUE LEVEL f
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Technical Evaluations Examples of Analysis /
Evaluation Scope 1
Transients / Accidents i
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1 Containment Response and Structural l_oads 1
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Environmental Qualification Radiological Releases (10CFR100) i I
Stability j
ATWS i
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BWR POWER UPRATE - TECHNICAL EVALUATIONS (cont)
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Transient and Accident Ana. lyses - Generic LTR will Establish Scope, Methods, Power Levels SCOPE OF ANALYSIS IN PLANT SPECIFIC SUBMITTALS - ALL LIMITING ACCIDENTS AND TRANSIENTS WILL BE ANALYZED LOCA Analysis of Full Spectrum of Break Sizes Turbine-Generator Trip (with Bypass Failure)
Feedwater Controller Failure Loss of Feedwater Heater Rod Withdrawal Error Loss.of all Feedwater Flow (confirm RCIC adquacy)
ASME Overpressure Protection Analysis (confirm SRV adequacy)
s BWR POWER UPRATE - TECHNICAL EVALUATIONS (cont.)
i i
Transient and Accident Analyses (cont.)
i i
i, i.
NON-LIMITING EVENTS ARE NOT REQUIRED TO BE ANALYZED 1
(Consistent with GESTAR, Reload Submittals, MEOD, SLO, etc.)
i Pump Trips i
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Flow Control Failure i
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t etc. (complete list in LTR) i i
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i BWR POWER UPRATE - TECHNICAL EVALUATIONS (cont.)
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l Transient and Accident Analyses (cont.)
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l METHODS ARE GENERICALLY ESTABLISHED l
l l
LOCA - Two Sets of Approved Methods Available l
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o LAMB / SCAT / SAFE /REFLOOD/ CHASTE Methods j
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LAMB / SCAT / SAFER /GESTR i
Transients - Methods Defined in GESTAR and Generic LTR by i
Event l
l
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i l
POWER LEVEL TO BE ASSUMED FOR EACH EVENT - GENERIC 4
APPROVAL LOCA - 102% Total Power and 102% Hot Bundle (s)
MCPR Transients - 100% (GEMINI Methods per GESTAR)
Overpressure (or other) Transients - 102%
j i
'IYPICAL TRANSIENT EVENTS ANALYZED FOR POWER UPRATE Primary Model Power Level Umitine Fuel Thermal Marrtn Events
[or Analvsla
(% Unrated)
- 1. Generator Load Rejection with Dypass Failure ODYN 100
- 2. Turbine Trip with Bypass Fauure ODYN 100
- 3. Feedwater Controller FaDure Max..Oemand ODYN 100
- 4. Pressure Regulator Downscale Fr.M @WR6)
ODYN 100
- 5. Loss of Feedwater Heater REDY or 3D SIM 100
- 6. Inadvertent HPCI Start (If applicab%
REDY 102
- 7. Rod Withdrawal Error 3D SIM 100
- 8. Slow Recirculation Increase (Kr, MCPR )
3D SIM (equiv) 100 f
Pressure Regulator Failure open
- REDY 102 10.
Jnadvertent Opening of SRV
- REDY/ SAFER 102 11.
Generator Load Rejection ODYN 100 12.
Turbine Trip ODYN 100 j
13.
Main Steam Isolation Valve Closure ODYN 100 l
14 Loss of Condenser Vacuum ODYN 100 l
15.
Loss of Offsite Power REDY/ODYN 102/100 16.
Loss of Feedwater Flow REDY/ SAFER 102 17.
Recirculation Pump Trip
- REDY 102 18.
Recirculation Flow Controller REDY 102 Fauure Decrease
- 19.
Recirculation Pump Seizure
- REDY 102 l
20.
Abnormal Startup of Idle Recirculation REDY Partial Pump
- 21.
Reciruelation Flow Controller Fauure.
REDY Partial Increase
- 22.
Inadvertent Pump Start RfDY Partial (As Applicable)
- Events marked are not significantly impacted by power uprate. Others may not be reanalyzed depending upon uprate conditions.
1 i
BWR POWER UPRATE - TECHNICAL EVALUATIONS (cont.)
Containment Analyses
)
ALL LIMITING SAR CASES WILL BE ANALYZED IN EACH PLANT l
l SPECIFIC SUBMITTAL l
NON-LIMITING CASES WILL NOT BE ANALYZED - GENERIC BASIS 1
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l Intermediate Breaks l
Alternate Lineups on Containment Cooling Systems i
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Drywell Bypass Leakage l
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BWR POWER UPRATE - TECHNICAL EVALUATIONS (cont.)
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Containment Analyses (cont.).
l t
METHOD FOR CONTAINMENT EVALUATION - GENERIC APPROACH j
i i
Using Accepted Methods, show (if possible) that Design Values j
i for Containment Pressure, Temperature, and Dynamic Loads have Sufficient Margin to Cover Power Uprate r
Include Consideration of Operating Pressure and SRV Setpoint i
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j Increases i
l Evaluate Short and Long Term Responses and Break Flows that l
can impact Loads i
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BWR POWER UPRATE - TECHNICAL EVALUATIONS (cont.)
L f
Equipment Evaluations i
d Areas where Bounding Equipment Evaluations may be Performed for Generic Approval i
Nuclear Boiler Equipment (common components - appIIed to j
l j
several plants) l SRVs (e.g., all Target Rock valves, etc.)
l o
l 0
MSIVs o
Main Steam Flow Restrictors 4
o Muclear Boiler Instruments 7
s l
o Recirculation Valves i
i o
Control Rod Drives l
i Low Pressure ECCS Systems j
t Injection modes (LPCS & LPCI mode of RHR) l o
o Shutdown Cooling (RHR) j i
i i
i
j BWR POWER UPRATE - TECHNICAL EVALUATIONS (cont.)
Equipment Evaluations (cont.)
HPCI o
Evaluation for New (Bounding) Operating Pressure inventory control (non-LOCA, Bounded by RCIC Evaluation) l o
o Small break LOCA performance (Generally Limiting Failure)
J RCIC I
o Evaluation for New (Bounding) Operating Pressure inventory control (non-LOCA, documented by Product o
Line/ Size) l HPCS l
o inventory control (non-LOCA, Bounded by RCIC Evaluation) 1 o
Small break LOCA performance (Generally Limiting Failure) i i
i
l l
- l
.i BWR POWER UPRATE - TECHNICAL EVALUATIONS (cont.)
b Other Generic Technical Evaluations l
Plant Operating Map (e.g., Relative to Maximum Core Flow) i
}
i Generic Method of Selecting Plant Operating Pressure i
1 Generic Method of Selecting New Safety System Setpoints l
Confirm Adequacy of Core Spray Distribution j
i Confirm SLMCPR for Uprated (Flatter) Power Distribution l
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SUMMARY
Generic Effort Fully. Underway NRC Questions and Comments Solicited Major LTR Revision ~5/91 o
Licensing issues resolution Expanded methodology descriptions o
o Results of Generic Equipment Evaluations o
Plant licensing report scope detailed GE/NRC/ Utility Meetings Encouraged Seek LTR Approval Prior.to First Plant Submittal
v t
NEW YORK POWER AUTHORITY FITZPATRICK NUCLEAR PLANT POWER UPRATE PROGRAM STATUS UPDATE 1.
NUCLEAR STEAM SUPPLY SYSTEMS 1
VENDOR - GENERAL ELECTRIC NUCLEAR ENERGY WORK STARTED IN AUGUST OF 1990 TASKS COMPLETED:
FINAL REACTOR HEAT BALANCE CALCULATIONS EVALUATION OF ESSENTIAL SYSTEMS AT UPRATE CONDITIONS (I.E. ECCS, PLANT COOLING SYSTEMS)
POWER TO FLOW MAP IMPACT ON INSTRUMENT ANALYTICAL SETPOINTS WORK IN-PROGRESS:
CONTAINMENT ANALYSES EVALUATION OF REACTOR INTERNAL PRESSURE DIFFERENCES ANALYSES NSSS PIPING' EVALUATION NEUTRON MONITORING SYSTEM EVALUATIONS RADIOLOGICAL EVALUATION NSSS SCOPE IS EXPECTED TO BE COMPLETED IN AUGUST OF 1991
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2.
TURBINE GENEMIQR VENDOR - GENERAL ELECTRIC TURBINE WORK STARTED IN OCTOBER OF 1990 t
TASK COMPLETED:
TURBINE UPRATE HEAT BALANCES WORK IN-PROGRESS:
ENGINEERING REVIEW OF TURBINE GENERATOR ENGINEERING REVIEW OF MOISTURE SEPARATOR REHEATER MAIN GENERATOR AND AUXILIARY EQUIPMENTS COOLING REQUIREMENTS IUR3IN E _GENRRATOR WORK IS EXPECTED TO BE COMPLETED BY JU 4 E0 : 199; 3.
LICENSING AND DOCKET REVIEW WORK STARTED IN JANUARY OF 1991 DOCKET REVIEW PERFORMED BY IN-HOUSE STAFF TASK INCLUDES REVIEW ALL PRIOR REGULATORY COMMITMENTS (GENERIC LETTERS, BULLETINS, NOTICES, ETC.)
WORK EXPECTED TO BE COMPLETED BY AUGUST OF 1991 4
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BALANCE OF PLANT (BOP) SYSTEMS VENDOR - STONE & WEBSTER ENGINEERING CORPORATION WORK STARTED IN SEPTEMBER OF 1990 TASKS COMPLETED:
CIRCULATING WATER SYSTEM REVIEW RADI0 ACTIVE WASTE MANAGEMENT REVIEW ENVIRONMENTAL IMPACT REVIEW WORK IN-PROGRESS:
HIGH ENERGY LINE BREAK ANALYSES AND EQ REQUIREMENTS ACCIDENT ANALYSES REVIEW STEAM AND POWER CONVERSION SYSTEMS REVIEW E0P WORK IS EXPECTED TO BE COMPLETED BY SEPTEMBER _OF 1991 OVERALL SCHEDULE NO CHANGE IN SCHEDULE IS ANTICIPATED NOVEMBER 1991 - FITZPATRICK 4% POWER UPRATE SUBMITTAL (INCLUDES NSSS AND BOP LICENSING REPORTS)
NOVEMBER 1992 - IMPLEMENTATION OF 4% UPRATE
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POWER UPRATE FERMI 2 PROGRAM i
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GOAL IS TO REALIZE STRETCH POWER l
- Plant Design Basis is 3430 MWt Full resources and management support in place a
o SCHEDULE License Amendment Submittal 10/91 NRC Approval 09/92 l
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- Implement in RF03 10/92
- Achieve Uprate Power 11/92 l
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LICENSING EFFORT IS ONE OF UPDATINO ANALYSIS i
Original radiological analysis performed at 3430 MWt
- Rebase analyses to 1.02x3430 MWt (per RO 1.49) l o
TRANSIENT AND ACCIDENT ANALYSIS
- GE performing limiting analyses for licensing submittal
- All Chapter 15 events will be addressed in submittal, either quantitatively or qualitatively.
LOCA analysis being redone using SAFER /OESTER i
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RADIOLOGICAL ASSESSMENTS
- Boundmg Accident Doses in Ch 15 will be reanalyzed by GE.
Using current methods
- Remaining Dose Assessments will be evaluated at 102% of 3430 MW' Doses in UFSAR analyzed at 3430 MWt New doses calculated by scaling up UFSAR values by 1.02 o
BALANCE OF PLANT ACTIVITIES
- BOP evaluations have beDun
- Licensing Scope Evaluations include: HELO. EO. safety related piping, missiles and jet impingement Safety System Performance (e g. EECW, RHRSW, D/0)
- Engmeeting Evaluations for Performe.nce Power conversion systems Turbine-Generator designed for 105%
Reactor pressure to inctease 25 psi to accommodate steam flow thru TCVs o
MODIFICATIONS
- Do not anticipate significant modifications
- Setpoint changes associated with Rx pressure increase
- SRV setpoints increase 25 psi l
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