ML17325A430
| ML17325A430 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/30/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8711050198 | |
| Download: ML17325A430 (52) | |
Text
- r October 30, 1987 Docket Nos.
50-315 DISTRIBUTION:
and 50-316 NRC Im Local PDRS LICENSEE: Indiana and Michigan Power Company PDIII-3 r/f DWigginton FACILITY: Donald C.
Cook Nuclear Plant, Unit Nos.
1 and 2
OGC-Bethesda
SUBJECT:
SUMMARY
OF MEETING HELD ON OCTOBER 27, 1987 TO DISCUSS T-HOT AND PRESSURE REDUCTION PROGRAM EJordan JPar tlow ACRS(10)
The staff met with the licensee on October 27, 1987 to discuss the proposed program to reduce the T-hot and pressure of the reactor coolant system.
The licensee was supported by Advanced Nuclear Fuels (ANF) and Kraftwerk Union (KWU) in the presentation and program.
The list of attendees is included as Enclosure 1.
The licensee's presentation was made from viewgraphs which contained proprietary information.
A non-proprietary version which was provided to the NRC is included as Enclosure 2; the licensee will*formallysubmit ~the proprietary viewgraphs with the appropriate justifications for non-disclosure.
Some of the information did not appear.to be proprietary and this was br'ought to the licensee's attention.
The T-hot and pressure reduction effort will be applied to Unit 1 in the licensee's Phase I and is intended to prevent, or slow down the corrosion of the tubes in the Unit 1 steam generators.
The T-hot and pressure reduction, however, affect a number of NSSS and balance of, plant equipment and controls.
There are expected changes to some transient and accident analyses and considerations which must be given to fuel performance and containment. pressurization.
The licensee's Phase II and III will,include applicati'on to Unit 2, technical specification improvements, and plant enhancements which would require reanalysis and establish-ment of a new design basis for both Units.
The licensee's Phase I submittal is expected by May 1988.
NRC review in a timely fashion may be required to support the aim of reducing Unit 1 steam generator degradation due to corrosion.
Enclosures:
As stated
/s David L. Wigginton, Project Manager Project Directorate III-3 Division of Reactor.Projects cc:
See next page Office:
LA/P III-3 Surname:
Pg zer Date:
15 87 P
DIII-3 DWigginton 10/0/87 8711050198 871030 PDR
.*DOCK 05000315 P
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Yr. John Dolan Indiana and Michigan Electric Company Donald C.
Cook Nuclear Plant CC:
Mr. M. P. Alexich Vice President Nuclear Operations American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43215 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Sridgeman, Michigan 49106 W. G. Smith, Jr., Plant Manager Donald C.
Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Yayor, City of Bridgeman Post Office Box 366 Bridgeman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Yionitoring Section Office Division of Radiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. J. Feinstein American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
T-HOT AND PRESSURE REDUCTION MEETING DC COOK OCTOBER 27 1987 ENCLOSURE 1
NAME Dave Wigginton Jim Morgan Hussein Fouad Vance Vanderburg Richard Leonard Larry Phillips Shih-Liang Wu Douglas Malin Charlie Brown Klaus Zieglowski Peter Gruber Walter Pink Jerry Holm Harold Helf Frank Depisch Manfred Schmidt H. E. Williamson Chris Buchalet Barry Rederstorff L. Helks Mike Cleveland Angie Gilbert Chang Li ORGANIZATION NRR-PDIII-3 ANF AEPSC AEP AEPSC-NMFM RSB RSB AEPSC ANF KWU KWU KWU ANF KWU KWU KWU ANF AEP AEPSC ANF AEPSC DEST DEST
MEETING AGENDA AEP/NRC/ANF/KWU OCTOBER 27, 1987 8:30 INTRODUCTION J.
M.
CLEVELAND (AEP) 9:00 HYDRAULIC CONSIDERATIONS OF NSSS AND BOP - H.
HELF (KWU) 9:45 TRANSIENT ANALYSIS J.
S.
HOLM (ANF)
LOCA NON LOCA 10:15 FUEL MECHANICAL ANALYSIS C. A.
BROWN (ANF) 10:30 MECHANICAL CONSIDERATIONS OF NSSS AND BOP LOCA FORCES CONTAINMENT COMPONENTS P.
GRUBER (KWU)
K.
ZIEGLOWSKZ (KWU)
W. PINK (KWU) ll:00 CONCLUSION AND DISCUSSION J.
M.
CLEVELAND (AEP)
INTRODUCTION J.
M.
GLEVELAND MANAGER, NUCLEAR MATERIALS AND FUEL MANAGEMENT AEPSC
PURPOSE o
MINIMIZE D.
C.
COOK UNIT l STEAM GENERATOR TUBE DEGRADATION o
PROVIDE OVERVIEW OF WORK EFFORT TO JUSTIFY OPERATION OF D.
C.
COOK UNIT 1 AT REDUCED TEMPERATURE
& PRESSURE o
OBTAIN NRC
- COMMENTS, INTERFACE REQUIREMENTS AND REVIEW QUESTIONS ON WORK SCOPE AND SCHEDULE
WORK SCOPE
SUMMARY
REVIEW IMPACT OF CHANGED CONDITIONS ON ACCIDENTS AND TRANSIENTS o
NSSS AND BOP THERMAL HYDRAULICS SET POINTS CONTAINMENT COMPONENTS AND INSTRUMENTATZON o
FUEL o
CORE PHYSICS
ADVANCED NUCLEAR FUELS PRIOR EXPERIENCE WITH D.
C.
COOK PLANT o
SUPPLY OF SZX REGIONS OF RELOAD FUEL FOR D.
C.
COOK 1 o
SUPPLY OF THREE REGIONS OF RELOAD FUEL FOR D.
C.
COOK 2 ACCIDENT AND TRANSIENT ANALYSIS FOR BOTH REACTORS FUEL MECHANICAL/THERMALANALYSIS FOR BOTH REACTORS NEUTRONZC ANALYSIS/CORE DESIGN FOR BOTH REACTORS
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Bibiis Units A and B Location:
BibNs, near Vkrna, on the~
(Federal Repubic of Geanany)
Owner:
Rheinisch-VAa55Rsches Eieidrizi-tatswee AG. Essen Contract awarded:
1969 and 1971 Commissioned:
1975 and 1977 Moderator and coolant: H~
Fuel:
Rated capacity:
Unit A 1204 MW Unit B 1300 MW Type of cooling:
Riverwater and/or cooling tower CS C)
X g
a KrQmmes Location:
Contract awarded:
Scheduled date of commissioning:
Moderator and coolant:
Fuel:
Rated capacity:
Type of cooling:
near Geesthacht, on the Elbe (Federal Republic of Germany)
Kemkraftwerk Kr0mmel GmbH, Hamburg 1972 1983 H20 UO2 1316 MW Riverwater I
aaa Atucha 1 Location:
Contract awarded:
Commissioned:
Moderator and coolant:
Fuel:
Rated capacity:
ape of cooling:
Province of Atucha, on the Rio Para'e tas Patmas (Argentina)
Comisibn Nacional de Energia Atbmica, Buenos Aires 1968 1974 UnaiO2 367 MW Rhrerwater
- t
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<',p Kalkar Contract <<warded:
Moderator and coolant:
Fuel:
Rated capocfty:
ape ot cooling:
near Kalkar, on the Rhine (Federal Republic of Germany)
SchnelM3r0ter&emkraftwerks-geselschaft mbH, Essen 1972 Na UO2+ PuO2 327 MW Rtvefwater and/or ceoQng tower
Modificlt iorl irl NPP's t)erfortl)e(l hy Siemerls KWIJ NPP (ll(IIIIIIr'Ict III
(!I'(X r IlI'y) l)a to Meas(tres
'IIIertllaI Power 0 I d llew HW hv(.rage Coolant 1etIII)erat.
igvC 0 I d IIVW "I'-( C)
Coolant Pressure ol d llew PSI (h<II )
Generator Power old new MW Ohr I gl1(! I III
('l III('ll" I'WIJ/
I l(ti)
.'>(> lk(!I)I ilc(!III(!IIt Hl I II I'()1t(.'I I Ill I (.'>I'.>(.'
II I 983 IOII5 1050 564,t>
0'.)/)
5f>II. 8
.rX.55) 2I02.5
( III'>)
2 I 02. '.>
( l(6) 5(l'>
(iosg(!Il (Sietlletl.
KWIJ/
Swi tact I;ltld)
I'ow(>I I II( I <<tl'>t III I'J86 280(>
32()2 589.9 (3N,9) 5//
II (303) 229I
( l58) 2255 I)
IOIII)
Graf <<nrlteirlfeld (Sielllells KWU/
I Atj)
I'I evetlt 6 laddltlg Ox I d It I otl I I I I 98(t otl I y fot I I II ee Illolltlls 37(>5 32/5 58/. 6 (308.7) 5/9.2 (299) 2276.5 (157) 2182.2 (150.5) 123'5 101(t Ringhals (West itlgltouse/
QedLXI)
SG Hei) I acetll<<lit witll Power illcre;lse itl l9JO 2II38 26>60 580.8 580 e8 22(t8,9 (155 1) 22(t8.9 (155.1) 9(IO I I9IO/Ile
borg)erature.
I'ressure decrease Programs for st.retch out OI)erat ior) Node" I)erformed in Siemens KWU Plants Nf'P ulLNIufc'll tilll'I
(.tel)l) y)
I) ) t;)
Ihermal I'ower decrease f re>>
NW t <)
AVel (l<Je (.00 I <<fit Iemf)er;II. deere)se I ) u>>I "I ("(.) I()
Cool.)nt I'ressure decrease I ) om I'S I
( I);))
)
l i)
Of)eration Period llily'.l Grohn(I>>
(Sieme)).
KWU/
f RG) 5/('r;)l)f)r. 25/2 58/. (i
<<l)I)). 528.8 (5(8.7)
(21(;)
22/(
. 5 ')I)l)).
I 8<) I ~.
(I5/)
<I /)
Graf enrl)einfeld (Siemens KWII/
I-RG) 57( 5 <<I)I)r. 3350 587. 6
<<Pl)l
. 570~2 (308,7)
(2'j9) 2276.5 apl)r. 2l))b (157)
( lit8)
Al l Npp s milnuf I( Iure(l l)y stem)>>)',
KwU are I icense(l I or stretch out operat. Ion mode
D.
C.
COOK UNIT 1 REDUCED TEMPERATURE AND PRESSURE ANF and KWU WORKSCOPE ANF STANDARD REVIEW PLAN CHAPTER 4
& 15 ANALYSIS KWU IMPACT OF REVISED OPERATING CONDITIONS ON NSSS I
IMPACT OF REVISED OPERATING CONDITIONS ON BALANCE OF PLANT
SYSTEM DESIGN AND THERMAL HYDRAULICS H.
HELF MANAGERg SYSTEM HYDRAULIC DESIGN SIEMENS/KHU
METHODOLOGY USED
ITEMS TO BE ADDRESSED
COMPARISON OF ORIGINAL AND REVISED DESIGN PARAMETERS FOR D.
C.
COOK UNIT 1 CURRENT DESIGN REVISED DESIGN (PRELIMINARY)
PARAMETERS NSSS POWER
(%)
(MWT)
THFRMAL DESIGN FLOW (GPM//M /S)
RCS PRESSURE (PSIA/BAR)
RCS AVERAGE TEMPERATURES:
FULL LOAD
( F/
C)
ZERO LOAD
( F/
C)
STEAM GENERATOR:
100 3250 88500/5.582 2250/155 567. 8/298 547/286 STEAM TEMPERATURE
( F/
C) 516
~ 4/269
~ 1 STEAM PRESSURE (PSIA/BAR) 787
~ 2/54
~ 2 STEAM FLOW (10 lb/hr kg/s) 14.21/1790 6
ENTHALPY (Btu/1bm, kZ/kg) 1198. 0/2790
CRITERIA FOR PRIMARY PRESSURE DECREASE
v<
'4 0
D C Co~A k~<<
i~un I"~utwrmnn, Ac/~rC ~d rcuiJdu s4~~~)
EFFECTS OF TEMPERATURE DECREASE ON:
REACTOR POWER CONTROL STEAM DUMP CONTROL
Press+<<2' e'c~ jr edged~~
VERIFICATION OF REACTOR-TRIP AND SAFEGUARDS ACTUATION SETPOINTS:
KWU EVALUATION OF PRIMARY SYSTEM COMPONENT BEHAVIOUR:
IMPACT ON MAEN STEAM SYSTEM
IMPACT ON FEEDWATER SYSTEM
TRANSIENT ANALYSIS J.
S.
HOLM MANAGERg PWR SAFETY ANALYSIS
D.
C.
COOK UNIT 1 REDUCED TEMPERATURE AND PRESSURE ANALYTICALSUPPORT DISPOSITION OF SRP CHAPTER 15 EVENTS CHAPTER 15 EVENT ANALYSIS CHAPTER 4
ANALYSIS
D.
C.
COOK UNIT 1 REDUCED TEMPERATURE AND PRESSURE DISPOSITION OF EVENTS
THIS REVIEW OF PLANT INFORMATION WILL RESULT ZN EACH CHAPTER 15 EVENT BEING ASSZGNED TO ONE OF THE FOLLOWING FOUR CATEGORIES:
D.
C.
COOK UNIT 1 REDUCED TEMPERATURE AND PRESSURE PRELIMINARY EVENT SELECTION
ANF D.
C.
COOK UNlT 1 REDUCED TEMPERATURE AND PRESSURE LARGE BREAK LOCA
CORE PHYSICS REVIEW o
REVIEW OF CORE PHYSICS PARAMETERS REQUIRED FOR OPERATION AT THE REDUCED TEMPERATURE AND PRESSURE CONDITIONS o
EVALUATION OF IMPACT OF CHANGED OPERATION ON CORE PHYSICS DATA PRIOR TO IMPLEMENTATION
FUEL MECHANICAL ANALYSIS C. A.
BROWN
- MANAGER, PWR FUEL DESIGN
rUEL MKCP~ICAL ANALYSIS
GAS RELEASE BENCHMARKING OF RODEX2 FOR RODS OF WESTINGHOUSE MANUFACTURE ANF ROD NAME PM32 PW33 111I5 2416 2816 3018 3618 266 281 282 285
= 292 294 313 314 316 317 PROJECT SUPERRAMP SUPERRAMP BR3 BR3 BR3 BR3 BR3 ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA BASE EXPOSURE REACTOR BR3 BR3 BR3 BR3 BR3 BR3 BR3 ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA RAMP REACTOR STUDSVIK.R2 STUDSVIK.R2
GAS RELEASE BENCHMARKING.OF RODEX2 FOR RODS OF MESTINGHOUSE MANUFACTURE (CONTINUED)
ANF ROD NAME 318 328 331 335 344 363 364 365 368 385 386 PROJECT ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA BASE EXPOSURE REACTOR ZORITA ZORITA ZORITA ZORITA ZORITA ZORITA
. ORITA ZORITA ZORITA ZORITA ZORITA RAMP REACTOR
FIGURE 1 CALCULATED VERSUS MEASURED. GAS RELEASE -
RODEX2 "AR SUPERRAHP BR3 MESTIHGHOUSE FUEL RODS
FIGURE 2 CALCULATED VERSUS MEASURED GAS RELEASE -
RODEX2 FOR BR3 WESTINGHOUSE FUEL RODS
FIGURE 3 CALCULATED VERSUS MEASURED GAS RELEASE -
RODEX2 FOR ZORITA WESTINGHOUSE FUEL RODS
LOCA FORCES P.
GRUBER MANAGER, LOCA ANALYSIS SIEMENS/KWU
TECHNICAL APPROACH LOCA HYDROLOADS ON REACTOR PRESSURE VESSEL INTERNALS
CONTAINMENT EVALUATION K.
ZIEGLOWSKI SENIOR ENGINEER SIEMENS/KHU
TECHNICAL APPROACH CONTAINMENT PRESSURE AND SUBCOMPARTMENT EVALUATION
COMPONENTS STRESS EVALUATION H.
PINK MANAGER, MECHANICAL ENGINEERING SIEMENS/KWU
REVIEW OF THE STRESS ANALYSIS
~
TECHNICAL APPROACH
CONCLUSION J
~
M.
CLEVELAND MANAGER, NUCLEAR MATERIALS AND FUEL MANAGEMENT AEPSC
CONCLUSION o
DELIVERY OF SUBMITTAL ANTICIPATED MAY 1988 o
IMPLEMENTATION OF RTP AS SOON AS POSSIBLE o
FOLLOW UP QUESTIONS