ML17157A840
| ML17157A840 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/19/1991 |
| From: | Robert Stransky Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-79384, NUDOCS 9109120182 | |
| Download: ML17157A840 (37) | |
Text
August 19, 1991 Docket Nos.
50-387 and 50-388 DISTRIBUTION See Attached List LICENSEE: Pennsylvania Power & Light Company (PP8 L)
UTILITY:
Susquehanna Units 1 and 2
SUBJECT:
SUMMARY
OF MEETING WITH PENNSYLVANIA POWER AND LIGHT COMPANY (PP&L)
ON AUGUST 8, 1991 REGARDING POWER UPRATE AMENDMENT RE(UEST USING GENERAL ELECTRIC GUIDELINES (TAC NO. 79384)
A meeting was, held on August 8, 1991, at NRC headquarters, between members of the NRC staff and representatives of the Pennsylvania Power and Light Company (PP8L) and General Electric (GE).
The purpose of the meeting was to discuss a
number of issues related to the licensee's forthcoming amendment request to increase core rated thermal power.
A list ot attendees is included as,
and a copy of all non-proprietary meeting slides is included as Enclosure 2.
The proposed submittal for increased rated thermal
- power, as described by PP8 L representatives, follows the generic guidelines previously published by GE, with the exceptions that the Susquehanna submittals will include provisions for increased core flow in order to provide additional tlexibility, and that the loss of coolant accident (LOCA) consequences related to the proposed uprate will be analyzed using GE's SAFER/GESTR computer model, even though Susquehanna uses Seimens (previously ANF) fuel.
A presentation was made by GE during the meeting which endorsed the use of the SAFER/GESTR code with non-GE fuel.
Additionally, PP&L will be seeking to reanalyze their ultimate heat sink (UHS) assuming a two degree increase in the maximum cooling pond temperature in order to improve operational flexibilityduring summer months.
During the meeting, PP8 L representatives outlined their proposed schedule for the submittal of their power uprate amendment
- request, as well as the submittal of associated core reload analyses (to provide sufficient fuel for uprated operating conditions) and required modifications to plant systems.
The plant modifications are minor, primarily consisting of changing reactor safety relief valve setpoints and performing a GE recommended modification to the reactor core isolation cooling (RCIC) system in order to improve reliability.
The licensee will also be installing additional clamps to jet pump pressure sensing lines to prevent the sensing lines from vibrating during increased flow conditions.
The staff will be working with PP8 L to resolve a number of minor issues which were raised during the meeting.
An additional meeting will be held with PP&L to address these issues and to further discuss the licensee's proposed schedule.
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Robert Stransky, Lead Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV/V MC HlE CENTR CSPW)
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Wu McBrearty Bagchi Rosa Congel Cunningham Beckner Young B. Marsh Stang Capra Brinkman McCabe Adensam LeButler Milano Clark Raleigh Dembek Dyer Eng Hannon Hall Matthews Jabbour (12G18)
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Pennsyl vani a Power 8 Light Company Susquehanna Steam Electric Station Units 1
8 2
CC:
Jay Silberg, Esq.
- Shaw, Pittman, Potts 8 Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power 8 Light Company 2 North Ninth Street Al 1 entown, Pennsyl vani a 18101 Mr. J.
M. Kenny Licensing Group Supervisor Pennsyl vani a Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U.
S.
Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsylvania P.
0.
Box 2063 Harrisburg, Pennsylvania 17120 Mr. Jesse C. Tilton, III Allegheny Elec.
Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harri sburg, Pennsyl vani a 17108-1266 Mr.
S.
B. Ungerer Joint Generation Projects Department Atlantic Electric P.O.
Box 1500 1199 Black Horse Pike Pleasantville, New Jersey 08232 Regional Administrator, Region I U.S.
Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company 2 North Ninth Street Al 1 entown, Pennsyl vani a 18101 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company 1009 Fowles Avenue Berwick, Pennsylvania 18603 Mr. Robert G.
Byram Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Al 1 entown, Pennsyl vani a 18101 Mr. Harold W.
Kei ser Senior Vice President
- Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Al 1 entown, Pennsyl vani a 18101
C'IST OF ATTENDEES SUSQUEHANNA POWER UPRATE MEETING AUGUST 8i 1991 Enclosure 1
NAME ORGANIZATION J.
RALEIGH J.
KENNY G.
SOZZI G. MILLER J.
BLAKESLEE J.
BARTOS R.
SGARRO G.
HUBBARD T. HICKS R.
STRANSKY C. I.
WU M. McBREARTY D.
PANKRATZ J.
IBARRA J.
DECKER M. MJAATVEDT M. ADELIZZI K.
PARCZEWSKI T. ROSCIOLI L. B.
MARSH R.
FRAHM S.
JONES M. McCOY NRR/PD12 PP&L GE PP&L PP&L PP&L PP&L NRR/SPLB STS NRR/PD31 NRR/EMEB NRR/EMEB GE NRR/SICB GE PP&L PP&L NRR/EMCB PP&L NRR/PD3 1 NRR/SRXB NRR/SPLB NRR/SRXB
Enclosure 2
SUSQUEHANNA POWER UPRATE PPKL AND NRC MEETING AUGUST 8, 1991
IVlEETIN P
~
Inform the IE'RC regarding the Susquehanna Power Uprate Project.
~
Highlight unique aspects of PPRL licensing submittal.
~
Gain general NRC concurrence on PPAL approach and implementation schedule.
PPAL/NRC MEETING ON POWER UPRATE FOR SUSQUEHANNA t 5. 2 August 8, 1991 MANAGEMENTPERSPECTIVE........
J.
Blakeslee IMPLEMENTATIONSTRATEGY.......
R.
Sgarro PROJECT OVERVIEW..............
J.
Bartos
~ Background
~ Highlights of SSES Submittal SSES-Specific Analyses Required Modifications Required Tech Spec Changes RELOAD/SAFETY ANALYSISISSUES...
G.
Sozzi (GE)
~ increased Core Flow
~ SAFER/GESTR SUKGCARY......................
J.
Blake slee
PP L
LEAR DEPARTMENT MI I "To operate,
- maintain, and support Susquehanna such that the station reliably and efficiently generates the maximum amount of power without compromising public or employee safety."
MANAGEMENTPERSPECTIVE; POWER UPRATE PPRL has made a major corporate commitment in pursuing Popover Uprate for Susquehanna.
MANAGEMENTPERSPECTIVE: POWER UPRATE PPRL is cormmitted to the ongoing generic efforts between the NRC and industry.
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Actively involved in development of topical reports.
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Communications with GE and other lead plants ongoing and will continue during NRC review.
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Submittals will be consistent with generic approach where possible.
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Unique aspects of SSES design/implementation will be highlighted.
MA1VAGEMENTPERSPECTIVE: POWER UPRATE PPRL has put the resources in p1ace to support the work.
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Project Organization staffed and operating.
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Necessary modifications funded and planned for 1992 outages.
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Licensing submittals on schedule for mid-1992.
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Implementation activities under review.
Power Uprate Implementation Schedules 1992 1993 1994 SSES-U1 3/7 S/W 6RFO 6/ s Uprate Licensing Report Submittal 9/i i i i/19 6/15 7RFO Ul 8 Implement Uprated Reload Uprate Analysis Submittal 17 months SSES-U2 9/IP. I I/27 SRFO 3/12 S/2O i2/i4 6RFO 6/is Uprate Licensing Report Submittal U2 7 Uprated Reload Analysis Submittal Implemen t Vprate 23 months
SUSQUEHANNA POWER UPRATE HISTORY o PRELIMINARYSTUDIES INITIATEDIN 1988 o DETAILEDFEASIBILITYSTUDY CONDUCTED IN 1990 o SUPPORT OF GENERIC EFFORT COMMENCED IN SEPT OF 1990 o COMPLETED FEASIBILITYSTUDY IN DECEMBER OF 1990 o PROJECT APPROVED IN JANUARYOF 1991 o NRC LETTER OF INTENT ISSUED IN JANUARYOF 1991 o ENGINEERING COMMENCED IN JANUARYOF 1991
FEASIBlllTYSTUDYRESULTS o A 50k STEAM FLOW INCREASE IS FEASIBLE t
o 3443 MWth WILLSUPPORT A 5'/ STEAM FLOW INCREASE o NO MAJOR COMPONENT REPLACEMENTS ARE REQUIRED o TWO SYSTEM MODIFICATIONSARE REQUIRED o TWO AREAS OF MAJOR REANALYSISARE RECOMMENDED o THE UPRATE IS ECONOMICALLYJUSTIFIABLE o A 30 PSI REACTOR PRESSURE INCREASE IS RECOMMENDED o A POWERlFLOW MAP CHANGE IS RECOMMENDED
REACTOR PRESSURE INCREASE o INCREASED TURBINE STEAM PASSING CAPACITYOPTIONS
- OPERATE WITH THROTTLE VALVESWIDE OPEN
- REDUCE TURBINE STEAM FLOW RESISTANCE
- INCREASE TURBINE INLET PRESSURE BY INCREASING REACTOR PRESSURE o INCREASED REACTOR PRESSURE IS PREFERRED OPTION
- MAINTAINSADEQUATE TURBINE CONTROL
- MINIMUMIMPACTON TURBINE EFFICIENCY
- MINIMUMCOST
- 104oo
'100 0
B2 A2 INCRF ASEO OPERATiNG RANGE WITH QPRATE ExAMPLE 2 F
Bl AI EXAMPLE 1
CURRENT OPERATING RANGE EXAMPLE 1
EKAMPLE 2 O
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NATURAL CIRCULATION NORMAL POWER ASCENSION CAVITATION INTERLOCKS MINIMUM FLOW ISTARTUPI CORE FLOW 1% RATEOI Figure 5-1.
Typical Pmrer/Hmr Map (Uprate to 105% Steam Hmr) Exampks for Plants Ath Dllferent Current Core Hmr OperatIng Optfons Exampk 1:
Extended Load Une Llmlt hnalysls (ELLLA) plus 5% Increased Core
. HO1Ir Exampk 2:
Maximum Extended Operating Domain (MEOD)
RECOMMENDEDPOS'ERlFLON'MAP OPTION INCREASE CORE FLOW LIMITBY 8%
- MAINTAINSRECIRCULATION FLOW WINDOW
- ANALYSISCOMPLETED IN MARCH OF 1986
- LEAST IMPACT ON OPERATING MCPR
- MINIMUMIMPACTON RELOAD ANALYSIS
- REDUCES THE NUMBER OF ROD ADJUSTMENTS
- REDUCES BURDEN ON THE OPERATING STAFF 1
- REQUIRES RESOLUTION TO JET PUMP SENSING LINE VIBRATIONCONCERNS
SUSQUEHANNA SPECIFIC ANALYSES o 10CFR50 APPENDIX K ANALYSIS
- IMPLEMENTSAFERlGESTR METHODOLOGY
- DECREASE PCT's AND IMPROVE MAPLHGR MARGIN
- SAFER/GESTR APPLIED TO ANF FUEL o ULTIMATEHEAT SINK ANALYSIS
- REANALYZESPRAY POND TEMPERATURE TRANSIENT
- ASSUME 2 DEGREE POND TEMPERATURE INCREASE
- IMPROVE OPERATING MARGIN
REQUIRED MODIFICATIONS o RCIC START-UP OVERSPEED TRIPS
- IMPLEMENTGE SIL NO. 377 RECOMMENDATIONS
- HIGHER REACTOR PRESSURE INCREASES OVERSPEED START-UP TRANSIENT
- THROTTLE RCIC ON START-UP o JET PUMP SENSING LINE VIBRATION
- INCREASED CORE FLOW INDUCES JET PUMP INSTRUMENT LINE VIBRATION
- ALTER SENSING LINE NATURALFREQUENCY
- INSTALLADDITIONALSENSING LINE CLAMPS
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I REA ED RE FL M SCOPE OF EVALUATION
- 1986 ANALYSIS RESULTS
- 104. 4P/108F
SUMMARY
/CONCLUSION
- MINIMAL SAFETY IMPACT EXPERIEN E
APPROXIMATE NUMBER WI F
1 4
6 20 7
W/
ICF G.L.
SOZZX GE NUCLEAR ENERGY AUGUST 8, 1991
NEDC 31090 DRF L1240728 CLASS II MARCH 1988 DAC 308 SAFETY REVIEW OF SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 AT CORE FLOW CONDITIONS ABOVE RATED FLOW THROUGHOUT CYCLE 1 AND FINAL FEEDWATER TEMPERATURE REDUCTION S, WOLF GENERALI ELECTRIC
NEDC-31090 CONTENTS
~Pa e
ABSTRACT ACKNOWLEDGMENTS 1.
INTRODUCTION AND
SUMMARY
vi 2.
3.
SAFETY ANALYSIS
- 2. 1 Abnormal Operational Transients 2'. 1 Limiting Transients 2, 1.2 Overpressurization Analysis
- 2. 1.3 Rod Withdrawal Error 2.2 Fuel Loading Error 2.3 Rod Drop Accident 2,4 Loss-of-Coolant Accident Analysis 2.5 Thermal-Hydraulic Stability MECHANICAL EVALUATION OF REACTOR INTERNALS AND FUEL ASSEMBLY
- 3. 1 Loads Evaluation 3.2 Loads Impact 3.2. 1 Reactor Internals 3.2.2 Fuel Assemblies 1
2-1 I
2-2 2-3 2-3 2-3 2
2-4 3-1 3-1 3-2 3-2 3-2 4.
FLOW-INDUCED VIBPATION 5.
FEEDWATER NOZZLE AND FEEDWATER SPARGER fATIGUE USAGE
CONTAINMENT ANALYSIS 7.
OPERATING LIMITATIONS 8.
REFERENCES 4-1 5
1 5-2 5
3 6-1 7-1 8-1
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Table 2-1 CORE-MIOE TRAHSIENT ANALYSIS RESULTS AT ICF ANO/OR FFMTR Transient a Oescriptlon Figure fuel Power b
Number Exposure (I HBR)
Rated Feedwater Temperature Flow Reduction (I NBR)
( f)
Naximum Neutron f lux (X Initial)
Maximum Hax imum Core Avg. Naximum Haximum Steam Surface Borne Vessel Line Heat flux Press.
Press.
Press.
( 7 Initial)(psig)
(ps ig)
(psig) aCPR LRHBP LRNBP Ref.
1 EOEC 104.4 100
- 2. I EOCI 104.4 108 479.5 427.2 120.4 1189 1220 1190 0.21 118.3 1185 1219 1187 0.21 FMCF FMCF Ref.
1 EOEC 2.3 EOCI 104.4 100
)04.4 108 282.4 272.6 117.5 1160 1192 1160 0.17 116.6 1155 1187 1155 0.17 m
n I
Cl C)
LRNBP < Load rejection with bypass failure, FMCF
~ feedwater controller failure to maximum demand, b.
EOEC
~ End of equiiibri~ cycle; EOCI
~ end of cycle l.
c.
Reduction of feedwater temperature from nominal rated feedwater temperature (382.7'F) and at rated conditions.
d.
aCPR based on initial CPR which yields HCPR
~ 1.06; uncorrected for ODYH Options A and B.
SAFER/GESTR APPLI ATI T
U Q
EHA 0
TYPICAL BWR LOCA RESPONSE SYSTEM
RESPONSE
FUEL ROD
RESPONSE
0 APPLICATION TO SUSQUEHANNA BWR 4/STANDARD ECCS NON GE FUEL 0
OTHER APPLICATIONS ECCS PARAMETER RELAXATION G.L.
SOZZI GE NUCLEAR ENERGY AUGUST 8, 1991
II%
gj'
~
~
I 1200 900 BWR LOCA RESPONSE (TYPICAL) 600 g
300 40 30 60 90 120 TAF 20
~)
BAF LJJ 10 l
30 60 90 120 5.0 4.0 o
3 0
I 2.0 1.0 30 60 90 120 1000 750 500 I
250 30 60 TINE (SEC)
Fuel Rod Res onse FUEL CLAD GAP t = 0 sec t = 30 sec
Stored Energy Effect on Heat Flux
2.2 Sigma
-- Nominal Decay Heat O
O 0$
L.
.8 l
ll llll
.B l l l l l l I
.4 l
l e2 l
No
~O 0
0 0
20 40 60 Time (seconds) 80 100
Stored Energy Effect on Peak Clad Temperature 5000
2.2 Sigma Nominal C5 LI CL E
800 BOO
~~O 400 200 20 40 eo Time (seccnds}
80 100
Table 6-1 TYPICAL PLANT PARAMETER RELAXATIONS Parameter Relaxation Diesel Generator Start Up Time Relaxation
+
10 seconds LPCS Flow Rate LPCS Injection Valve:
Pressure Permissive Stroke Time LPCS Pump Start Up Time 90Z of Rated
- 100 psi
+
10 seconds
+ 20 seconds LPCI Flow Rate LPCI Injection Valve.'ressure Permissive Stroke Time LPCI Pump Start Up Time 90X of Rated
- 100 psi
+
18 seconds
+ 25 seconds Recirculation Discharge Valve Stroke Time
+
10 seconds HPCI Start Up Time
+ 30 seconds ECCS Water Level Setpoints Level 3 (Scram)
Level 2 (HPCI/RCIC Initiation)
Level 1 (LPCS/LPCI/ADS Initiation)
- 12 inches 12 inches 8 inches 6-2
2000 1 800 AFTER REIAXATIQN BEFORE RELAXATION 1600 EE. 1400 I
4~ 1200 E
UZ 8 1000 a.
800 600 SUCTION BREAKS DISCHARGE BREAKS 400 200 0
0 BREAK AREA (ft2l Figure 6-1.
Effect of Parameter Relaxation on Hominal Break Spectrum 6-4
MARF
~
PPRL is committed to uprating the licensed power level of the Susquehanna units.
~
We willfollow the agreed upon generic guidance and monitor the review of the submittals that precede ours.
~
We have and will continue to interact with the NRC on issues unique to Susquehanna in order to resolve them as early in the review process as possible.
~
We appreciate the NRC commitment to review Power Uprate proposals generically and request that this commitment be extended to PPAL's specific approach and schedule.
GENERAL DESCRIPTION OF SUSQUEHANNA SES PLANT OPERATOR: PENNSYLVANIAPOWER & LIGHTCo.
LOCATION OF PLANT: NEAR BERWICK PA.
NSSS:
TWO GE 8WR-4 REACTORS REACTOR DESCRIPTION:
- 3293 Mwth
- 251 INCH DIA. VESSEL
- 2 LOOP JET PUMP RECIRCULATION
- 764 FUEL ASSEMBLIES (ANF 9X9)
- ACTIVE FUEL HEIGHT = 150 INCHES REACTOR COOLANT SYSTEM DESCRIPTION:
- DIRECT CYCLE, WATER COOLED
- CORE COOLANT FLOW RATE = 100,000,000 LBM/HR
- FEEDWATER INLETTEMPERATURE = 383 DEGREES F
- STEAM OUTLET TEMPERATURE = 544 DEGREES F
- STEAM DOME PRESSURE = 1000 PSIA
- STEAM CAPACITY = 13,464,500 LBM/HR REACTOR COOLANT INJ ECTION SYSTEMS
- REACTOR CORE ISOLATION COOLING SYSTEM
- HIGH PRESSURE COOLANT INJECTION SYSTEM
- LOW PRESSURE CORE SPRAY SYSTEM
- LOW PRESSURE COOLANT INJECTION SYSTEM TURBINE DESCRIPTION:
- TANDEM COMPOUND, SIX FLOW
- INLETSTEAM TEMPERATURE = 540 DEGREES F
- INLETSTEAM PRESSURE = 965 PSIA
- STEAM FLOW = 13,464,000 LBM/HR GENERATOR DESCRIPTiON:
- OUTPUT = 1050 MWe
- SPEED = 1800 RPM
- VOLTAGE = 24,000 VOLTS ULTIMATEHfAT SINK:
- 24,285,000 GALLONSPRAY POND
- 264 SPRAY RISERS
- AREA = 352,285 SQ. FEET
GENERAL DESCRIPTION OF SUSQUEHANNA SES PLANT CONTAINMENTDESCRIPTION:
- MARKII CONTAINMENT
- OVER/UNDER DRYWELLAND SUPPRESSION CHAMBER
- REINFORCED CONCRETE WITH A STEEL LINER
- 82 DOWNCOMERS
- INTERNALDESIGN PRESSURE = 53 PSIG
- DRYWELLDESIGN TEMPERATURE = 340 DEGREES F
- WETWELL DESIGN TEMPERATURE = 220 DEGREES F SUSQUEHANNA MILESTONES:
APPLICATION FOR CONSTRUCTION PERMIT - APRIL 1, 1971 CONSTRUCTION PERMIT ISSUED BY AEC - NOV. 2, 1973 UNIT 1 RECEIVES OPERATING LICENSE - JULY 17, 1982 UNIT1 COMMERICALOPERATION - JUNE 8, 1983 UNIT 2 RECEIVES OPERATING LICENSE - MARCH 23, 1984 UNIT2 COMMERICALOPERATION - FEBRUARY 12, 1985
DISTRIBUTION ocket ~
NRC 6 Local PDRs PD31 Rdg file PD11 Rdg file 14/E/21 J. Partlow 12/G/18 B. Boger J. Zwolinski L. Marsh R. Stransky J. Raleigh 14/E/21 A. Chaffee, EAB llAl OGC E. Jordan MNBB-3701 B. Grimes 9/A/2 G Hubbard 8/D/1 C. I.
MQ 7/E/23 M. McBrearty 7/E/23 J. Ibarra 8/H/3 K. Parczewski 7/D/4 ST Jones 8/D/1 M. McCoy 8/E/23 R. Prahm 8/E/23 ACRS (10)
K. Brockman, 17/G/21 R. Lobel, 17/G/21 K. Abraham, RI J.
Strasma, RIII P. Shuttleworth cc:
Licensee/Applicant 8 Service List