ML20213F802
| ML20213F802 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/04/1987 |
| From: | Alexion T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8705150466 | |
| Download: ML20213F802 (46) | |
Text
-
MAY 0 4~ 1987
. Docket No. 50-483 LICENSEE: Union Electric Company:
FACILITY: Callaway Plant
SUBJECT:
SUMARY.0F MEETINGS WITH UNION ELECTRIC REGARDING RELOAD FOR CYCLE '3 -
"AND POWER UPRATING AMENDMENT REQUESTS On April 29, 1987, the licensee presented to the staff the reload for Cycle 3 and power uprating license amendment requests. Participants at the reload and uprating~ meetings are listed in Enclosures 1 and 2, respectively; and slides used-during the presentations are in Enclosures 3 and 4, respectively..
The staff review of the applications has just begun and these meetings were intended to provide the reviewers with an introductory summary of the
' applications. The staff did not identify any major problem areas with the applications at this time.
/s/ -
Thomas W. Alexion, Project Manager Project Directorate III-3 Division of Reactor Projects
Enclosures:
As Stated cc: See Next Page J
Office: PRf 4. PD/PDIII-3 Surname: ' TAl' tg DWigginton Date: 05/ /87. 05/1/87
%OU3NN e
$3
_ _ _ _ _ _ _ _ - _ _ _ _ _ - = _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ - - _ _ _
Mr. D. F. Schnell Callaway Plant Union Electric Company' Unit No. I cc:
J. O. Cermak, CFA Inc. Lewis C. Green, Esq.
4 Professional Dr., Suite 110 Green, Hennings & Henry Gaithersburg, MD 20879 Attorney for Joint Intervenors St. Louis, Missouri 65751 Gerald Charnoff, Esq.
Thomas A. Baxter, Esq. Ms. Marjorie Reilly Shaw, Pittman, Potts & Trowbridge Energy Chairman of the League of
'1800 M Street, N. W. Women Voters of Univ. City, M0 Washington, D. C. 20037 7065 Pershing Avenue University City, Missouri 63130 Mr. G. L. Randolf General Manager, Operations Mr. Donald Bollinger, Member Union Electric Company Missourians for Safe Energy Post Office Box 620 6267'Delmar Boulevard Fultor., Missouri 65251 University City, Missouri 63130 U. S. Nuclear Regulatory Commission Pr. Dan I. Bolef, President Resident Inspectors Office Kay Drey, Representative RR61 Board of Directors Coalition
>j Steedman, Missouri 65077 for the Environment St. Louis Region Mr. Donald W. Capone, Manager 6267'Delmar Boulevard
- . Nuclear Engineering University City, Missouri 63130
? Union Electric Company Post Office Box 149 St. Louis, Missouri 63166 Chris R. Rogers, P.E.
Manager - Electric Department 301 W. High Post Office Box 360 Jefferson City, Missouri 65102 Regional Administrator U. S. NRC, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Ronald A. Kucera, Deputy Director Department of Natural Resources P. O. Box 176 Jefferson City, Missouri 65102 Mr. Bart D. Withers Pesident and Chief Executive Officer Wolf Creek Nuclear Operating Corporation ,
P. O. Box 411 Burlington, Kansas 66839
- w. . - , .. . .
t
+7
. , _ , L MAY 0 4 '1987 ~
{j p
-NRC POR
' Local PDR .
PDIII-3 r/f. '
-PDIII-3 s/f DWigginton ,
. TAlexion PKreutzer. '
. 0GC-Bethesda '
EJordan. '
t JPartlow
' 1ACRS (10)- .
MDunenfeld -
SDiab "
,' JKnox . .
(cc: LicenseeandPlantServiceList).
s 4
)
t J
l 6
E i
f
- i
!r.
i l
r w
1
- - - - . . .,- , _ . ._.,-mt', _
- - , - . . r,-.. -e w,, +. , te . , , .-.-,;3 . ,..
r ENCLOSURE I RELOAD FOR CYCLE 3 PEETING - APRIL 29, 1987 ATTENDANCE LIST NAME ORGANIZATION Tom Alexion -NRC/PDIII-3 Marvin Dunenfield NRC/SRXE Sammy Diab NRC/SRXB Al Passwater UE/ Licensing Dave Shafer UE/ Licensing
' Sue.Hauser W/Sys. Int.
Carole Leach U/Non-Loca Barbara Samardzich ' W/NFD-T&'i Design Keith Forcht U/ Licensing Stan Devidson 9/NFD-Fuel Licensing Keith Hock UE Nuclear Fuel.
Michael Young W/ Nuclear Safety John Knox NRC/SELB
, , . _ _ . . _ _ _ , - . _ , , , , . . , - - , - ~ .___ ,. _.
l ENCLOSURE 2 POWER'UPRATING MEETING - APRIL 29, 1987 ATTENDAkCE LIST.
hAME ORGAP!IZATION Tom Alexion. NRC/PDIII-3 Janak Raval _ NRR/SPLB Sammy Diab- NRR/SRXB Dave Shafer UE/ Licensing Carole Leach W/Non-Loca Barbara Samardzich U/T8H Design Keith Forcht U Licensing Stan Davidson 9/NFD Fuel Licensing Keith Hock UE - Nuclear Fuel Michael Young W/ Nuclear Safety Sue Hauser R Systems Int.
Al Passwater UE/ Licensing
(vC c_ .c AGENDA CALLAWAY PLANT CYCLE 3 LICENSidG MEETING APRIL 29, 1987 I. IdTRODUCTI0d II. CALLAWAY BACKGROUND CYCLE 2 DESIGil CYCLE 2 ACCIDEdT ANALYSIS POWER LEVEL 111. CYCLE 3 SUBMITTAL TECHillCAL SPECIFICATION CHANGES IV. CYCLE 3 LICENSING BASIS FUEL FEATURES THERMAL HYDRAULIC DESIGd NON-LOCA TRAdSIENT ANALYSIS LOCA ANALYSIS V. SCHEDULE CONSIDERAT10dS VI. CONCLUSIONS
i CYCLE 2 DESIGd o CORE C0ftSISTS OF:
84 0FA (40 AT 3.4 w/0 u-235)
' (44 AT 3.8 w/o u-235) 109 LOPAR (45 AT 2.6 w/o u-235)
(64 AT 3.1 w/o u-235) o JESIGd EdERGY - 400 FPD (EXCLUDING COASTDOWN)
I o CYCLE AVERAGE BURduP - 16,000 MWD /MT o buRdABLE ABSORBER - WABA RODS l
. I
_ J
- - - ^ - -
l CYCLE 2 ACCIDEi4T AilALYSIS l o DilB LIMITING ACCIDEliTS UTILIZED:
Il1 PROVED THERMAL DESIGN PROCEDURE- (ITDP)
WRB - 1 DNB CORRELATION o LARGE BREAK LOCA ;
ANALYSIS OF RECORD - BART - PCT.- 2153*F (ALSO PERFOR11ED USING BASH) - PCT - 2026*F i
! o SilALL BREAK LOCA HOTRullP PCT - 1299'F
. o SPENT FUEL RACKS REANALY2ED FOR 4.2 W/0 U-235
l *
~
1 t
CYCLE 2 POWER LEVEL CURRENTLY LICENSED -
3411 NW 1 i MALYSIS PERFORMED -
3565 MWT 1
(ALLOWANCE FOR 10% SG TUBES PLUGGED) i
]
j 1
CYCLE 3 SUBMITTAL ULiiRC - 1470 DATED MARCH 31, 1987 UL(iRC - 1491 DATED APRIL 15, 1987
CYCLE 3 TECH SPEC CHANGES CORE SAFETY LIMITS (liiCREASED BYPASS. FLOW DUE TO V-5) 0TA T, OPAT, RC FLOW VALUES, add ATo (DUE T0 tiETHODOLOGY UPGiiADE)
REVISED BASES TO REFLECT WRB-2 DNB CORRELATION (REtJUIRED BY CHAliGE TO V-5)
REVISED R0D DROP Tine (REQUIRED BY CHANGE TO V-5) -
1 ,
REVISED AXIAL FLUX DIFFEREifCE SPEC j (IMPROVES OPERATING FLEXIBILITY BY ADDING RESTRICTED 3
AFD BAiiD Ai40 POWER RESTRICTIONS TO ALLOW CONTINUED l OPERATI0ii VilDER CERTAIN C0dDIT10NS.)
REVISED F0 PEAKING FACTOR SURVEILLANCE (ADDS OPERATING FLEXIBILITY DUE TO DIRECTLY M0.11TORiiiG PARAMETER OF INTEREST)
REVISED DNB PARAMETERS l (REFLECT VANTAGE 5 FUEL) 4 -
IdCREASED RCS ACCUMULATOR VOLUME RANGE (CONSISTENT WITH LOCA ANALYSIS)
J
.-...,.,m- ..-- ,,r-.------
,--.----,-,,7.,,-,~,--en--.-..m.,, - - - - -.--- . ._-..-y,y- ---7 <y -------,7. - . - +.,,-..,r,, , .- , - - - , -
l i
. . l
, l l
VANTAGE-5 FUEL FEATURES
- l
't REFERENCE WCAP-10444-P-As l i
r i
j l
i i
- IN"EGRAL FUEL BURNABLE ABSORBER ,
I i
!
- INTERMEDIATE FLOW MIXERS i
e RECONSTITUTABLE TOP N0ZZLE
- EXTENDED BURNUP l
l i
e AXIAL BLANKETS {LATER CYCLES}
l
l CALLAWAY CYCLE 3 CORE / THERMAL-HYDRAUUC DESIGN 4
i
- e 13 - LOPAR ASSEMBUES 84 - OPTlWlZED FUEL ASSEMBUES 96 - VANTAGE-5 ASSEMBUES e WABAs AND IFBAs o ;
PEAK ROD F-DELTA-H = 1.435 (CORRESPONDS TO 1.55 LOCA/NON-LOCA SAFETY ANALYSIS F-DELTA-H)l l
- e 420 EFPD i
i FUTURE CYCLES i
e IFBAs ONLY i e PEAK ROD F-DELTA-H = 1.527 (CORRESPONDS TO l 1.65 LOCA/NON-LOCA SAFETY ANALYSIS F-DELTA-1 l
! THERWAL-HYDRAVUC DESIGND'sCONTINUED}
l :
- ALL OTHER THERMAL-HYDRAVUC DESIGN PARAMETERS SAME AS CYCLE 2 ANALYSES '3565 MWT,382630 l
GPM,ETC.}
l e SUGHT INCREASE IN CORE BYPASS FLOW DUE TO l i
l INTRODUCTION OF VANTAGE-5 FUEL i
i l e VANTAGE-5 SAFETY UMIT DNBR'S SELECTED SUCH THAT LOPAR/0FA DESIGN IS UMITING {l.E. ONLY; CHANGE IN CORE UMITS IS DUE TO INCREASED BYPASS FLOW}
i !
l
- TECH-SPEC CHANGES INCLUDE ADDITION OF WRB-2
( CORRELATION, V-5 DESIGN / SAFETY UMIT DNBR'S, USE OF 24,000 MWD /MTV BU UMIT FOR ROD BOW l .
l PENALTY.
1
_ _ - _ _ . - - _ - - - . - - - . - - - - .-. _ L
THERMAL-HYDRAULIC DESIGN l
l PARAMETER EUEL VALUE DNBR CORRELATION LOPAR/0FA WRB-1 VANTAGE-5 WRB-2 DESIGN LIMIT DNBR's LOPAR/0FA TYP-1.34 THM-1.32 VANTAGE-5 TYP-1.33 THM-1.32 l l
SAFETY LIMIT DNBR's LOPAR/0FA TYP-1.45 THM-1.42 VANTAGE-5 TYP-1.69 THM-1.61 !
l i
l DNBR MARGIN AVAILABLE LOPAR/0FA 7%
VANTAGE-5 18% ,
TRANSITION CORE PENALTIES LOPAR 0 0FA 2%
VANTAGE-5 11%
PEAK R0D F-DELTA-H LOPAR/0FA 1.55 VANTAGE-5 1.65
..,e*,--,c-.. .m,. . - - . - , - - + , - - , _mm w,- - - . , ....,.,--.r-u-_m.,,r.,,- - , - - , - - - - _ _ - , --,,,,nroy.r.~,,,y -
w-,-,-,-
CALLAWA Y ACCIDENT ANAL YSIS LICENSING AND DESIGN BASES CYCLE 2 CYCLE 3 LICENSING DESIGN LICENSING DESIGN STD/OFA ----> STD/OFA/V5 ---->
1.55 FaH ---------------------------->
1.65/V5 NMTC ----------------> PMTC 2.32 Fq ----------------> 2.50 3411 MWt 3565 ------------------>
$0% SGTP ---------------------------->
15%"
M V5 REPORT REANALYSES O
l 1
CALLAWA Y V5 REPORT l CORE THERMAL LIMITS APPLICABILITY j l
I OFA */ LOPAR i
6.3% CORE BYPASS FLOW l
FaH = i . 55 / 0. 3 MUL T l 10% OR $5% S/G TUBE PLUGGING i SAL DNBRs ,
l N ITDP WRB-2 i.42/i.45 l i
\ \
- V5+ )
j l
6.3% CORE BYPASS FLOW i FaH = 1. 65 / 0. 3 MUL T
- i0% OR i5% S/G TUBE PLUGGING
} SAL DNBRs l M ITDP WRB-2 i.61/i.69 i
l + - TRANSITION CORE EFFECTS ACCOUNTED FOR W/
l GENERIC DNB MARGIN
l CALLAWAY V-5 REPORT f REANALYSIS / DESIGN FEATURE MATRIX ,
15.1 V5 PWTC FAH FQ FW WALFUNCTION l EXCESSIVE LOAD INCREASE l
- STEAMUNE DEPRESSURIZATION STEAMUNE BREAK l 1
15.2 l LOSS OF LOAD / TURBINE TRIP X j STATION BLACK 0UT X LOSS OF NORMAL FEEDWATER X l
~
FEEDUNE BREAK X l 15.3 i
COMPLETE / PARTIAL LOSS OF FLOW X X X l LOCKED ROTOR X X X X 15.4 ROD WITHDRAWAL FROM SUBCRITICAL X R0D WITHDRAWAL FROM POWER X-RCCA MISOPERATION X X STARTUP OF INACTIVE LOOP X
4 !
l CALLAWAY V-5 REPORT t
REANALYSIS / DESIGN FEATURE WATRIX (CONTIN i
i 15.4 V5 PWTC FAH FQ I BORON DILUTION X i
- FUEL ASSEMBLY IN IMPROPER POSITION ROD EJECTION X X X 15.5 INADVERTENT ECCS i
CVCS WALFUNCTION l
l l 15.6
) RCS DEPRESSURIZATION X I
6.2 W/E RELEASE FOR STEAMUNE BREAK
- i
- DONE FOR UPRATING LICENSING REPORT l . ,
l
l' l
CALLAWAY V5 REPORT s FSAR ACCIDENT ANALYSIS / EVALUATION MATRIX f
REANALYSIS EVALUATION 15.1 COOLDOWN EVENTS i FW WALFUNCTION X EXCESSIVE LOAD INCREASE X STEAMUNE DEPRESSURIZATION X STEAMUNE BREAK X 1
15.2 HEAT EVENTS X
LOSS OF LOAD / TURBINE TRIP STATION BLACK 0UT X LOSS OF NORWAL FEEDWATER X i
FEEDUNE BREAK X i 15.3 LOSS OF FLOW EVENTS ,
I l COMPLETE / PARTIAL LOSS OF FLOWX LOCKED ROTOR X
, = - . - ..--.---,--.._n,----.---.,,, - - - , , - - , . --n- m -, , , . - - - . . . - - - - ,- ._~,,.._,-----.,n _n, ,,n. , , , . - , . ,_ , . , - ,,.r. ,,,.,,n-.....,.,,
I
)
CALLAWAY V5 REPORT FSAR ACCIDENT ANALYSIS / EVALUATION WATRIX (CONT) l
)
- 15.4 REACTIVITY AN0MAUES REANALYSIS EVALUATION ROD WITHDRAWAL FROM SUBCRITICAL X ROD WITHDRAWAL FROM POWER X RCCA WISOPERATION X STARTUP 0F INACTIVE LOOP X i
BORON D!LUTION X FUEL ASSEMBLY IN IMPROPER POSITION X ROD EJECTION X
, 15.5 INCREASE IN RCS INVENTORY INADVERTENT ECCS . X CVCS WALFUNCTION . X 15.6 DECREASE IN RCS INVENTORY RCS DEPRESSURlZATION X .
l l
l ECCS LOCA ANALYSES i INPUTS FOR CALLAWAY LOCA ANALYSES VANTAGE-5 FUEL
, CORE POWER UPRATING TO 3565 MWt 15% SGTP FQT = 2.50 Fm = 1.65 K(r) CURVE 3rd LINE SEGMENT REMOVAL l
l l
I 1
- - . - - - -- - . , . _ , . - _ . . -_ - .- --.a
i . .
LARGE BREAK LOCA ANALYSIS l
BART (ANALYSIS OF RECORD) l OPTIMlZED FUEL l
CORE POWER UPRATING TO 3565 MWt l l
10% SGTP l FQT = 2.32 l Fm = 1.55 PCT = 2153*F '
l l
l MARGIN NEEDED FOR VANTAGE-5 FUEL l l
TRANSITION CORE PENALTY 50*F PENALTIES DUE TO INCREASES IN FQT, Fm, and SGTP 1000F to 1500F 1500F to 2000F BASH IS UTILIZED TO PROVIDE MARGIN
j SMALL BREAK LOCA ANALYSIS NOTRUMP (ANALYSIS OF RECORD)
OPTIMlZED FUEL CORE POWER UPRATING TO 35G5 MWt 10% SGTP i
FQT = 2.32
% = 1.55 PCT = 1299"F MARGIN NEEDED FOR VANTAGE-5 FUEL PENALTIES DUE TO INCREASES IN FQT, F.H, t and SGTP 100*F to 150*F REMOVAL OF 3rd LINE SEGMENT 1000F 200*F to 2500F e
9
4 ACCOUNTING OF LOCA MARGIN LARGE BREAK 10CFR50.46 LIMIT 22000F BART (ANALYSIS OF RECORD) 21530F
'
- ESTIMATED BASH BENEFIT -2500F
, TRANSITION CORE PENALTY +500F t
- PENALTIES DUE TO INCREASES IN FQT, Fm, and SGTP +1000F RESULT PCT < 22000F
- BENEFITS & PENALTIES ARE APPROXIMATE
=. . . . _ . _ _- . .- _ _ ..
ACCOUNTING OF LOCA MARGIN SMALL BREAK -
10CFR50.46 LIMIT 22000F NOTRUMP (ANALYSIS OF RECORD) 12990F
'Ki r) 3rd LINE SEGMENT RiEMOVAL PENALTY +100'F
' PENALTIES DUE TO INCREASES IN FQT, %, and SGTP +1500F RESULT PCT < 2200*F !
- PENALTIES ARE APPROXIMATE i
J t
I e
d
, - - . ., m,
LOCA ANALYSES COMPARISON LARGE BREAK 1
BART (ANALYSIS OF RECORD) BASH (APRIL 1987)
OFA FUEL VANTAGE-5 FUEL 3565 MWt CORE POWER 3565 MWt CORE POWER 10% SGTP 15% SGTP FQT = 2.32 FQT = 2.50 Fm = 1.55 % = 1.65 PCT = 21530F PCT = 20140F*
- DOES NOT INCLUDE 500F TRANSITION CORE PENALTY P
l
\
l i
l
- l LOCA ANALYSES COMPARISON SMALL BREAK NOTRUMP NOTRUMP (ANALYSIS OF RECORD) (APRIL 1987)
OFA FUEL VANTAGE-5 FUEL 3565 MWt CORE POWER 3565 MWt CORE POWER 10% SGTP 15% SGTP FQT = 2.32 FQT = 2.50 FAH = 1.55 FAH = 1.65 PCT = 12990F PCT = 15280F t
O 8 4
ADDITIONAL INFORMATION BASH MASS DIFFERENCE MODIFICATIONS MINOR IMPACT ON THE CALLAWAY LOCA ANALYSIS BEFORE MODIFICATIONS MASS DIFFERENCE = 230 LBM (<0.9%)
PCT = 20040F AFTER MODIFICATIONS MASS DIFFERENCE = 61 LBM (<0.4%)
PCT = 20140F IMPACT ON PCT IS 100F FOR CALLAWAY
-- - e, ,- - - , - , - , , - , ,, -. n. - - - ,-- c---,-
l I
i l
1 CONFIRMATION OF POWER SHAPE SENSITIVITY FOR INCREASED FQT and Fm RE-ANALYZED FOR A 7.5 FT PEAKED POWER SHAPE FQT = 2.4525 ON K(r) CURVE AT 7.5 FT Fm = 1.65 RESULTS CHOPPED COSINE SKEWED TO TOP 6.0' PEAK 7.5' PEAK FQT = 2.50 FQT = 2.4525 Fm = 1.65 Fm = 1.65 PCT = 2014cF PCT = 1974*F ;
l l
l i
CHOPPED COSINE STILL LIMITING FOR INCREASED FQT and Fm
)
SCHEDULE CONSIDERATI0iiS CYCLE 3 STARTUP
~ 10/15/87 REQUESTED CYCLE 3 LICEiiSE AME14DMEi1T APPROVAL 10/1/87 BEGlii REFUEL 2 OUTAGE
~ 9/1/87
~ 6/1/87-BEGId RECEIPT OF CYCLE 3 FUEL CYCLE 3 SUBi11TTAL 3/31/87 e
e
CONCLUSIONS o ALL METHODOLOGIES HAVE BEEN PREVIOUSLY REVIEWED AND APPROVED BY NRC o INVOLVES NO UNREVIEWED ENVIRONMENTAL QUESTION
! o INVOLVES NO SIGNIFICANT HAZARD
~< ;
L: Ct _. .
AGENDA CALLAWAY UPRATING MEETING APRIL 29, 1987 i
I. INTRODUCTION
. II. CALLAWAY BACKGROUND CYCLE - 2
- CYCLE - 3
- UPRATING SUBMITTAL
- CYCLE 3 TECH SPEC CHANGES III. UPRATING CONSIDERATIONS
- HISTORY
- WCAP - 10263
- scope OF EVALUATION NSSS BOP IV.- SCHEDULE CONSIDERATIONS V. CONCLUSIONS 4
e
CALLAWAY BACKGROUND
~
CYCLE - 2 CYCLE -LICENSED CORE POWER
. LEVEL-.(MWTH) 3411 3565 3
- NSSS OUTPUT-(MWTH) 3425- '3579 DESIGN ENERGY. 400 FPD 420~FPD
. (AT UPRATED. POWER)
FUEL TYPE . STD'/0FA =STD/0FA/V-5 CYCLE-BURNUP-(MWD /MT) 16,000 18,000-1 I
I 4
?
's AC.CIDENT-ANALYSIS CYCLE 2 AND CYCLE 3 ANALYSES HAVE BEEN PERFORMED AT UPRATED POWER CONDITIONS WITH 10% SG TUBES ASSUMED PLUGGED.
CYCLE 2 CYCLE 3 DNB LIMITING ITDP* ITDP ACCIDENT WRB-1 DNB CORRELATION WRB-2 DNB CORRELATION LARGE BREAK LOCA BART BASH SMALL BREAK LOCA NOTRUMP NOTRUMP SPENT FUEL RACKS 4.2 W/0 U-235 4.25 W/0'U-235**
IMPROVED THERMAL DESIGN PROCEDURE (ITDP)
' ** SEPARATE SUBMITTAL (ULNRC-1422; 12/19/86) i i
1 UPRATING SUBMITTAL ULNRC - 1471 DATED MARCH 31, 1987 ULNRC - 1494 DATED APRIL 21, 1987 i
e J
L
^N = A-- a_ ,
UPRATING LICENSE AND SPEC CHANGES
- O LICENSE CHANGE TO REFLECT CORE POWER LEVEL OF 3565 MWTH 0 DELETE DEFINITION OF DESIGN THERMAL POWER (N0 LONGER REQUIRED SINCE RATED AND DESIGN WILL BE-THE SAME)
O REVISE CORE SAFETY LIMITS (FIGURE 2.1-1)
(BASED ON CYCLE 3 CORE AT UPRATED CONDITIONS) 0 REVISED NOTES ASSOCIATED WITH OPAT AND OTAT.
~
l
CA__AWAY CO R E 30WER U 3 RA~ \ G 8 - STO RY O r U 3 RA~ N GS l 8 WCA3 ' 0263 M _"- 0 30_0GY 8 SC03E Or NSSS Er 0RT A3RIL 29, ' 987
l HISTORY OF UPRATINGS l 0 SEVERAL WESTINGH0USE PWR'S HAVE RECENTLY UPRATED ,
THEIR POWER LEVELS INCLUDING:
- SALEM UNIT #1 0 3350 --3423 MWt 0 UNIT #2 POWER LEVEL I
e UCENSE AMENDMENT - 2/86
- NORTH ANNA UNITS #1 AND #2 0 2785 MWt --2910 MWt 8 STRETCH RATING G LICENSE AMENDMENT 8/86 l l
0 F0LLOWED WCAP-10263 METHODOLOGY APRIL 29,1987 -
WCAP-10263 METHODOLOGY FUNDAMENTAL PROPOSITIONS:
0 REVIEW ONLY POWER RELATED ASPECTS OF THE PLANT DESIGN 8 LICENSING CRITERIA AND ACCEPTANCE STANDARDS APPLICABLE TO CURRENT PLANT OPERATION APPLY e CURRENT ANALYTICAL TECHNIQUES WILL BE USED l APRIL 29,1987 i
l 1
- I WCAP-10263 M ET-1030_0GY SCOPE OF REVIEW
'8 F ASIBILITY STUDY
- SE" P_AN" PARAME"ERS
- PER 0RM DES GN LIMl"NG ANA_YSES.
9 M3LEMENTATl0N PROGRAM l
)E"A _ED NSSS EVA_UATION l 1
- BALANCE 07 PLANT SYSTEMS AN) 1
- EQU 3 MENT EVA_UATIONS APRIL 29,1987 l
s SSS DE~A _ED REV EW i
! NSSS SYSTEMS IM3ACT:
1 8 A3 PROVED FINA_ PLANT 3ARAMEERS :
9 VER FlE) A)EQUACY OF RCS, CVCS, RHR, l
- APRIL 29,1987
NSSS JE Al_ED R V EW NSSS EQUl3 MENT EVA_UATION:
VER FID S"RUCTURA_ INTEGRITY 0 COMPONENTS AT UPRATD CON)T10sS .
8 R ACTOR INTERNA _S S CONTR0_ RO) DRIVE MECFAN SMS S R AC"0R C00 AN" PUM3 0 PRIMARY SYSTEM 31 PING S PRESSURIZER 0 ST AM GENERATOR A3R _ 29,1987
- a - , - .- , ,-, -- ,.
CA__AWAY CO R E POWER U 3 RA"lN G 8 3L' MW: -- 3565 MW':
0 lAll3 _EM Es A" O s 3 ROGRAM - COMP _ETE e NO FAR) WARE MO) CA~ loss 0 _ ICE \S \G SUBM ~~~A_S ,70_LOWE)
WCA3 ' 0263 M _~-030 LOGY 9 SIM LAR TO SA_EM #' AN) NOR"- ANNA
- ' As) #2 U3RATisGS l
A3RIL 29,1987
B0P REVIEW
- SYSTEMS
. TURBINE GENERATOR MAIN FEEDWATER MAIN. STEAM CONDENSATE FEEDWATER HEATER EXTRACTION, ETc..
CIRCULATING WATER AFW CCW CLCW SW ESW.
HVAC SYSTEMS ELECTRICAL SYSTEMS TRANSIENT / ACCIDENT ANALYSES -
MSLB - CONTAINMENT RESPONSE SGTR CONCLUSION f
ALL FSAR SAFETY CRITERIA MET AT 3579 MWT, ORIGINAL DESIGN OF SYSTEMS AND COMPONENTS ENVELOPES CONDITIONS AT-3579 MWT.(WITH EXCEPTION OF TURBINE - GENERATOR WHICH MAY.BE LIMITED AT VWO CONDITIONS OF 3565 MWT).
-- s - - - - . .
SCHEDULE CONSIDERATIONS CYCLE 3 STARTUP APPROX.. 10/15/87.
REQUEST UPRATING LICENSE AMENDMENT APPROVAL 10/15/87 -
BEGIN REFUEL 2 OUTAGE' APPROX. '9/1/87-CYCLE 3 SUBMITTAL 3/31/87 I
e 1
1
__ , _._,_ - _ . _ . _ . . . . - - , _ . , - _