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{{#Wiki_filter:__ . - _ _ _ . . _ _ . - - _ _ _ _ . _ _ | {{#Wiki_filter:__ . - _ _ _ . . _ _ . - - _ _ _ _ . _ _ | ||
AVERAGE DAILY LNIT POWER LEVEL | AVERAGE DAILY LNIT POWER LEVEL O. o m eT NO. 50 - m | ||
O. o m eT NO. 50 - m | |||
---------------- _-_ =----- | ---------------- _-_ =----- | ||
UNIT PEACH BOTTOM UNIT 2 | UNIT PEACH BOTTOM UNIT 2 DATE MAY 9, 1980 | ||
DATE MAY 9, 1980 | |||
------------------= ------- | ------------------= ------- | ||
COMPANY PHILADELPHIA ELECTRIC COMPANY | COMPANY PHILADELPHIA ELECTRIC COMPANY | ||
- . _ = - - _ _ _ = - - - _--..-------- | - . _ = - - _ _ _ = - - - _--..-------- | ||
W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR | W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH APRIL 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-f;E T ) (MWE-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 2,3 0 8 , | ||
TELEPHONE (215) 841-5022 | |||
MONTH APRIL 1980 | |||
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-f;E T ) (MWE-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 2,3 0 8 , | |||
0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 1 | 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 1 | ||
16 0 | 16 0 8005s10gg | ||
8005s10gg | |||
. . . . u. u, | . . . . u. u, 00C4FT NO. 80 - 277 DATE MAY 0 1980 COMPLETED BY PHILADELPHIA ELECTRIC C0 PAND W.M.ALDEN W | ||
ENGINEER-IN-CHARGE NUCLEAR SECTICN GE NE R A T I ON OIVISION-NOCLFAo TELEPHO*E (215) 841-5022 | |||
00C4FT NO. 80 - 277 | |||
DATE MAY 0 1980 COMPLETED BY PHILADELPHIA ELECTRIC C0 PAND | |||
W.M.ALDEN W | |||
ENGINEER-IN-CHARGE NUCLEAR SECTICN | |||
__=- | __=- | ||
OpF2AT!Nr. STATUS | OpF2AT!Nr. STATUS | ||
.___.... _______ .- = ____ - __ _-- _=---________ | .___.... _______ .- = ____ - __ _-- _=---________ | ||
l . UN I T Na uf : FEACH BOTTOM UNIT 2 1 NOTES: THIS UNIT IS IN ITS l | l . UN I T Na uf : FEACH BOTTOM UNIT 2 1 NOTES: THIS UNIT IS IN ITS l | ||
Line 64: | Line 39: | ||
FOURTH REFUELING OUTAGE. I | FOURTH REFUELING OUTAGE. I | ||
...______._______ l l | ...______._______ l l | ||
: 3. LICENS50 THERMAL POWER (MWT): 3293 l | : 3. LICENS50 THERMAL POWER (MWT): 3293 l I | ||
l l | |||
4 NAM 8 PLATE RATING IGRCSS MwEl: 1152 1 1 | |||
__________ ____ l | __________ ____ l | ||
%. C8 SIGN ELECTRICAL RATING (NET MWEl l 1065 l I | %. C8 SIGN ELECTRICAL RATING (NET MWEl l 1065 l I | ||
_________ l | _________ l | ||
: 6. l M A X IM UM OSPENDABLE CAPACITY (GROSS MWE): 1048 I l | : 6. l M A X IM UM OSPENDABLE CAPACITY (GROSS MWE): 1048 I l l l | ||
: 7. Maxl"UM DEFENDAeLE CAPACITY l NET MWE): 1051 l l B. | |||
l l | |||
: 7. Maxl"UM DEFENDAeLE CAPACITY l NET MWE): 1051 l l | |||
B. | |||
IF CHANGES UCCUR IN C ADACITV RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE 4 | IF CHANGES UCCUR IN C ADACITV RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE 4 | ||
PowFR LEvfL TO WHICH EFSielCTED. IF ANY (NF1 MWEli | PowFR LEvfL TO WHICH EFSielCTED. IF ANY (NF1 MWEli | ||
Line 84: | Line 53: | ||
THis MONTH YR-TO-DATE CUMULATIVE ' | THis MONTH YR-TO-DATE CUMULATIVE ' | ||
: 11. H9uRS IN RFPORTING PERIOD 719 2,901 ^1.047 | : 11. H9uRS IN RFPORTING PERIOD 719 2,901 ^1.047 | ||
: 12. NUME E R OF MOUR S RF AC TOR L'AS CRITICAL 0 1,441 30.106 | |||
: 12. NUME E R OF MOUR S RF AC TOR L'AS CRITICAL 0 1,441 | |||
30.106 | |||
.__. ____- _ = = . - | .__. ____- _ = = . - | ||
: 13. RE ACTOR RESERvF SHUTOOWN HOURS 0.0 0.0 | : 13. RE ACTOR RESERvF SHUTOOWN HOURS 0.0 0.0 | ||
- = _ - ____ | - = _ - ____ | ||
0.0 | 0.0 14 HOUR S GE NE R A T00 ON-L IN E 0.0 1,390.7 38,373.0 | ||
14 HOUR S GE NE R A T00 ON-L IN E 0.0 1,390.7 38,373.0 | |||
: 15. UNIT RESERVF S'UTOOWN HOURS 0.0 0.0 0.0 | : 15. UNIT RESERVF S'UTOOWN HOURS 0.0 0.0 0.0 | ||
: 16. GRGS$ THtRMAL ENFRGY GENEPATED (MWH) 0 3.831,770 110.597.414 | : 16. GRGS$ THtRMAL ENFRGY GENEPATED (MWH) 0 3.831,770 110.597.414 | ||
Line 103: | Line 63: | ||
- _ = _ _ . . _ _ _ ......- | - _ = _ _ . . _ _ _ ......- | ||
36.314 210 | 36.314 210 | ||
: 16. NE T E LECTR ICEL FNERGY GENERATED (MLH) * -1.517 1.195.873 34.811.658 14 UNIT SERVICE F4CTOR 0.0 47.9 75.2 | |||
: 20. UNIT AVAIL ABILITY FACTOR 0.0 47.9 75.2 | |||
: 21. UNIT CAPACITY FACTOR tOSING MOC NET) 0.0 39.2 64.9 | |||
: 16. NE T E LECTR ICEL FNERGY GENERATED (MLH) * -1.517 1.195.873 34.811.658 14 UNIT SERVICE F4CTOR 0.0 47.9 | : 22. UNIT CAPACITY FACTOR (US ING DE R NET) 0.0 38.7 64.0 2 3. UNI T FORCEO QUTAGE RAlf 0.0 0.0 6.1 | ||
75.2 | |||
: 20. UNIT AVAIL ABILITY FACTOR | |||
0.0 47.9 75.2 | |||
: 21. UNIT CAPACITY FACTOR tOSING MOC NET) 0.0 39.2 | |||
64.9 | |||
: 22. UNIT CAPACITY FACTOR (US ING DE R NET) 0.0 38.7 | |||
64.0 | |||
2 3. UNI T FORCEO QUTAGE RAlf 0.0 0.0 6.1 | |||
..------= | ..------= | ||
24 SHulD0wNS SCHEDULFD OVER NE*T 6 M ON T HS (TYPE. DATE. AND OUR ATION OF EACH): | 24 SHulD0wNS SCHEDULFD OVER NE*T 6 M ON T HS (TYPE. DATE. AND OUR ATION OF EACH): | ||
UNIT ? SHUTDOWN FOR FCue TH REFUELING. | UNIT ? SHUTDOWN FOR FCue TH REFUELING. | ||
: 25. IF sHUTOO*N AT END OF REPOR1 PERIOD. ESTIMATED DATE OF STARTUP: 7/13/90 2 e . UN I T S IN 1EST STATUS IPRIOs 10 COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY | : 25. IF sHUTOO*N AT END OF REPOR1 PERIOD. ESTIMATED DATE OF STARTUP: 7/13/90 2 e . UN I T S IN 1EST STATUS IPRIOs 10 COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPFRATION o - NEGATIVE VALUE REPORTED FOR CONSISTENCY WITH FEDERAL ENERGY REGULATORY COMMTMSTON e | ||
INITIAL ELECTRICITY | |||
COMMERCIAL OPFRATION | |||
o - NEGATIVE VALUE REPORTED FOR CONSISTENCY WITH FEDERAL ENERGY REGULATORY COMMTMSTON e | |||
LnIT SHLTDOWNS AND P0wER RECUCTION> DOCMET NO. $0 - 277 | LnIT SHLTDOWNS AND P0wER RECUCTION> DOCMET NO. $0 - 277 | ||
__..._-_-__. ==......._-_. | __..._-_-__. ==......._-_. | ||
UNIT NAME DEACH BOTTOM UNil 2 | UNIT NAME DEACH BOTTOM UNil 2 CATE MAY o. 1880 | ||
CATE MAY o. 1880 | |||
_ __. =..._____........_-_ | _ __. =..._____........_-_ | ||
a EPOR T MONTH A PR IL , 19PO COMPLETED BY PHI L a DE LPHI A ELECTRIC COMPANY | a EPOR T MONTH A PR IL , 19PO COMPLETED BY PHI L a DE LPHI A ELECTRIC COMPANY | ||
..__.._ _.. _ - _ = = - ............_-.._ | ..__.._ _.. _ - _ = = - ............_-.._ | ||
, W.".ALDEN ENGINEER-IN-CHAkGE NUCLEAR SECTION GENER ATI DN DIVI S ION-NUCL E AR TELEPHONE (215) 841-5022 | , W.".ALDEN ENGINEER-IN-CHAkGE NUCLEAR SECTION GENER ATI DN DIVI S ION-NUCL E AR TELEPHONE (215) 841-5022 I i l l l METHOL OF l LICENSEE ISYSTEMICOMPONENTI CAUSE AND CORRECTIVE l lTYPElDURATION14EASONISHUTTING D0wNi EVENT l CODE l CODE I ACTION TO NO.I DATE I (Ill (HOURSil (2) l PEACIOR (3) l REPORT s 1 (4) l (5) l PREVENT RECURRENCE I I I l i I I I I 9 l 800401 i Sl 719.0 1 C 1 2 i NONE I RC l FUELXX l CONTINUATION 05 REFUEL OUTAGE. | ||
I i l l l METHOL OF l LICENSEE ISYSTEMICOMPONENTI CAUSE AND CORRECTIVE l lTYPElDURATION14EASONISHUTTING D0wNi EVENT l CODE l CODE I ACTION TO NO.I DATE I (Ill (HOURSil (2) l PEACIOR (3) l REPORT s 1 (4) l (5) l PREVENT RECURRENCE I I I l i I I I I 9 l 800401 i Sl 719.0 1 C 1 2 i NONE I RC l FUELXX l CONTINUATION 05 REFUEL OUTAGE. | |||
I i 1 ----- 1 I 1 1 1 l l 8 1 719.0 l l l l l l (Il (21 (3) (4) | I i 1 ----- 1 I 1 1 1 l l 8 1 719.0 l l l l l l (Il (21 (3) (4) | ||
F - FORCEO REASON METHOD EXHIPli G - I NST R UC T ION S S - S CHE DULE D A - EQUIPMENT F A I L U4 E (EXPLAIN) 1 - MANUAL FOR PRE P A R A TION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOWaTIC SCRAM. EVENT REPORT (LERI D - REGUL ATORY RE STRICTION 4 - OTHER (EXPLAIN) FILE INUREG-Ol61) | F - FORCEO REASON METHOD EXHIPli G - I NST R UC T ION S S - S CHE DULE D A - EQUIPMENT F A I L U4 E (EXPLAIN) 1 - MANUAL FOR PRE P A R A TION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOWaTIC SCRAM. EVENT REPORT (LERI D - REGUL ATORY RE STRICTION 4 - OTHER (EXPLAIN) FILE INUREG-Ol61) | ||
Line 158: | Line 84: | ||
G - OPERATIONAL ERROR (EXPLAIN) | G - OPERATIONAL ERROR (EXPLAIN) | ||
H - OTHERIEXPLAINI EXHIBIT I - SAME SOURCE | H - OTHERIEXPLAINI EXHIBIT I - SAME SOURCE | ||
AVERAGE OAIL: UNIT POWER LEVEL DOCKET NO. 50 - 278 | |||
AVERAGE OAIL: UNIT POWER LEVEL | |||
DOCKET NO. 50 - 278 | |||
--------- -------- _ _ = _ - _ _ _ _ - | --------- -------- _ _ = _ - _ _ _ _ - | ||
UNIT PEACH BOTTOM UNI T 3 | UNIT PEACH BOTTOM UNI T 3 DATE MAY 9, 1980 | ||
DATE MAY 9, 1980 | |||
= | = | ||
COMPANY PHILADELPHIA ELECTRIC COMPANY | COMPANY PHILADELPHIA ELECTRIC COMPANY | ||
-------- = ----- ------ | -------- = ----- ------ | ||
W.M.ALDEN E NG IN E E R -IN-CH A RG E NUCLEAR SECTION GENERATION DIVISION-NUCLEAR | W.M.ALDEN E NG IN E E R -IN-CH A RG E NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 j | ||
l MONTH APRIL 19530 i DAY AVERAGE OAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL , | |||
TELEPHONE (215) 841-5022 | |||
MONTH APRIL 19530 i | |||
DAY AVERAGE OAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL , | |||
(MWE-NET) (MWE-NET) l l | (MWE-NET) (MWE-NET) l l | ||
1 1073. 17 1071 l 2 1071 18 1069 3 1032 19 1069 4 967 20 1071 5 1072 21 1072 6 1071 22 1069 7 1065 , 23 1068 9 , 1064 24 1067 9 1012 25 1064 10 1024 26 1068 11 1040 27 1069* | 1 1073. 17 1071 l 2 1071 18 1069 3 1032 19 1069 4 967 20 1071 5 1072 21 1072 6 1071 22 1069 7 1065 , 23 1068 9 , 1064 24 1067 9 1012 25 1064 10 1024 26 1068 11 1040 27 1069* | ||
Line 188: | Line 100: | ||
0004t 1 NO. - | 0004t 1 NO. - | ||
27P ! | 27P ! | ||
."O | ."O DATF MAY 9, 1980 COMPLETED BY PHILA0FLPHIA FLECTRIC CDuPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISICN-NUCLcAA TELEPHONE (215) 841-5022 GPERATING STATut | ||
DATF MAY 9, 1980 | |||
COMPLETED BY PHILA0FLPHIA FLECTRIC CDuPANY | |||
W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISICN-NUCLcAA TELEPHONE (215) 841-5022 | |||
GPERATING STATut | |||
: 1. UN I T NAME: PEACH EOTTOM UNIT 3 l NOTES: THIS UNIT FXPERIFNCED TWO | : 1. UN I T NAME: PEACH EOTTOM UNIT 3 l NOTES: THIS UNIT FXPERIFNCED TWO | ||
...._............ ___ ............ I l t | ...._............ ___ ............ I l t | ||
Line 205: | Line 107: | ||
MAJOR POWER REDUCTIONS l | MAJOR POWER REDUCTIONS l | ||
__== | __== | ||
l | l l | ||
l | |||
: 3. LICFNSED THkRMAL POWER (MWil: 3293 l AND NO OUTAGES. | : 3. LICFNSED THkRMAL POWER (MWil: 3293 l AND NO OUTAGES. | ||
...= ..== - - - | ...= ..== - - - | ||
l | l l l 4 NAMEPLITE RATING (GROSS :4WE): 1152 l I | ||
l l 4 NAMEPLITE RATING (GROSS :4WE): 1152 l | |||
I | |||
l l | l l | ||
: 5. OE %1GN ELECTRICAL RATING (NET MWE ): 1065 i I l l 6. | |||
wartMUM DE PENDA>L E C AP AC IT Y (GROSS MWE): 1096 l t l l | |||
: 7. MAXIMUM OSPENOABLE CAPACITY (NET MWE): 1035 1 1 | : 7. MAXIMUM OSPENOABLE CAPACITY (NET MWE): 1035 1 1 | ||
P. 15 CHANGES OCCUR IN C A PAC IT Y RA T INGS ( ITFMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASCNS: | P. 15 CHANGES OCCUR IN C A PAC IT Y RA T INGS ( ITFMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASCNS: | ||
9 POWFR lev 5L TG aHILH R E STRICTED, IF ANY (NET MWE): | 9 POWFR lev 5L TG aHILH R E STRICTED, IF ANY (NET MWE): | ||
Line 231: | Line 120: | ||
i f THIS MONTH YR-TO-DATE CUMULATIVE | i f THIS MONTH YR-TO-DATE CUMULATIVE | ||
: 11. HOURS IN REPORTING PERIOD 714 .2,903 46,443 | : 11. HOURS IN REPORTING PERIOD 714 .2,903 46,443 | ||
: 12. NUMPE R OF MOURS RE AC TOR WAS CRITICAL 714 2,410 | : 12. NUMPE R OF MOURS RE AC TOR WAS CRITICAL 714 2,410 | ||
* 37,256 * | * 37,256 * | ||
..._________ .... =_ | ..._________ .... =_ | ||
: 13. REACTOR RESERVE SHUTOOWN HOURS 0.0 0.0 | : 13. REACTOR RESERVE SHUTOOWN HOURS 0.0 0.0 0.0 | ||
0.0 | |||
... _ . . - =..___ | ... _ . . - =..___ | ||
14 HOURS GENER A TOR ON-LINE 719.0 2,303.5* 36,235.3 * | 14 HOURS GENER A TOR ON-LINE 719.0 2,303.5* 36,235.3 * | ||
: 15. UNIT RESERVF SHUTOOWN HOURS 0.0 0.0 | : 15. UNIT RESERVF SHUTOOWN HOURS 0.0 0.0 | ||
, 0.0 lb. GR US S THERMAL ENERGY GEN (EATED (MWM) 2,339,743 7,333,210 101,ES2,364 | , 0.0 lb. GR US S THERMAL ENERGY GEN (EATED (MWM) 2,339,743 7,333,210 101,ES2,364 | ||
Line 251: | Line 135: | ||
: 20. UNIT AVAILABILITY FACTOR 100.0 10 .3 * | : 20. UNIT AVAILABILITY FACTOR 100.0 10 .3 * | ||
==- _.-. -- | ==- _.-. -- | ||
77.2 | 77.2 * | ||
* | : 21. UN11 CAPACITY FACTOR (USING MDC NET) 102.3 79.4 65.3 | ||
: 21. UN11 CAPACITY FACTOR (USING MDC NET) 102.3 79.4 | |||
65.3 | |||
: 12. UN]T C AP AC IlY FACTOR (USING OER NET) 94.4 77.1 | : 12. UN]T C AP AC IlY FACTOR (USING OER NET) 94.4 77.1 | ||
___- __._.._ = | ___- __._.._ = | ||
Line 269: | Line 146: | ||
24 SHU10DWNS SCHE 00L EO OVE R NEXT o MONTHS ( TYPE, DATE . AND DUR ATION UF EACH): | 24 SHU10DWNS SCHE 00L EO OVE R NEXT o MONTHS ( TYPE, DATE . AND DUR ATION UF EACH): | ||
: 29. IF 590T00wN AT END OF REPORT PERICD, ESTIMATED DATE OF STARTUP: | : 29. IF 590T00wN AT END OF REPORT PERICD, ESTIMATED DATE OF STARTUP: | ||
26 UNITS IN TEST STATUS (PRIOR 10 COMMERCIAL OPERATICN): FORECAST ACHIEVE 0 INITIAL CRITICALITY | 26 UNITS IN TEST STATUS (PRIOR 10 COMMERCIAL OPERATICN): FORECAST ACHIEVE 0 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION | ||
INITIAL ELECTRICITY | |||
COMMERCIAL OPERATION | |||
* THE SE VALUES A0 JUSTED TO CORRECT 24 HR. ERR 04 IN MARCH DATA FOR | * THE SE VALUES A0 JUSTED TO CORRECT 24 HR. ERR 04 IN MARCH DATA FOR | ||
.,wRS. GENERATCR ON LINE, HRS. RE ACTOR CRITICAL, AND FORCED OUTAGE HRS. | .,wRS. GENERATCR ON LINE, HRS. RE ACTOR CRITICAL, AND FORCED OUTAGE HRS. | ||
- -- ~ | - -- ~ | ||
t UNIT SHulDOWNS ANC POWER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE MAY 9, 1960 RE POR T MON TH APRIL, 1680 COMPL E TED BY PHIL ADE LPHI A ELECTRIC COMPANY | |||
t UNIT SHulDOWNS ANC POWER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 | |||
DATE MAY 9, 1960 RE POR T MON TH APRIL, 1680 | |||
COMPL E TED BY PHIL ADE LPHI A ELECTRIC COMPANY | |||
___= _ _ _ = _ . -- | ___= _ _ _ = _ . -- | ||
W.H.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 | |||
W.H.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION | |||
GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 | |||
# _ =___. _____________ | # _ =___. _____________ | ||
l I I I l I METHOD OF l LICENSEE lSYSTEMICOMPONENTl CAUSE AND CORRECTIVE lTYPElDURATIONlREASONISHUTTING DOWNI EVENT l CODE I CODE l ACTION TO NO.I LATE I 1111 (HOURSil (2) l REACTOR (3) l REPORT a 1 (4) l (5) l PREVENT RECURRENCE I I i 1 1 I I I I O B l 80040) 1 5 1 0.0 l B l 4 l NONE l HA I VALVEX l LOAD OROP TO REPAIR TUBE LEAK IN 28 WATER l t i l i i l l I BOX AND 83 TURBINE CONTROL VALVE. | l I I I l I METHOD OF l LICENSEE lSYSTEMICOMPONENTl CAUSE AND CORRECTIVE lTYPElDURATIONlREASONISHUTTING DOWNI EVENT l CODE I CODE l ACTION TO NO.I LATE I 1111 (HOURSil (2) l REACTOR (3) l REPORT a 1 (4) l (5) l PREVENT RECURRENCE I I i 1 1 I I I I O B l 80040) 1 5 1 0.0 l B l 4 l NONE l HA I VALVEX l LOAD OROP TO REPAIR TUBE LEAK IN 28 WATER l t i l i i l l I BOX AND 83 TURBINE CONTROL VALVE. | ||
Line 307: | Line 163: | ||
F - FORCED REASON METHOD | F - FORCED REASON METHOD | ||
% 5 - S C HE DUL E D A - EGUIPMENI FAILURt (EXPLAIN) EXHIb1T G - INSTRUC TIONS 1 - MANUAL FOR PREPARATION OF DATA R - MAINTENANCE OR TEST 2 - MANUAL SCRAM. | % 5 - S C HE DUL E D A - EGUIPMENI FAILURt (EXPLAIN) EXHIb1T G - INSTRUC TIONS 1 - MANUAL FOR PREPARATION OF DATA R - MAINTENANCE OR TEST 2 - MANUAL SCRAM. | ||
C - REFUELING ENTRY SHEETS FOR LICENSEE | C - REFUELING ENTRY SHEETS FOR LICENSEE 3 - AUTOMATIC SCRAM. EVENT REPORT (LER) | ||
O - REGULATORY EESTRICTIGN 4 - OTHER (ExplAINI FILE INUREG-0161) | O - REGULATORY EESTRICTIGN 4 - OTHER (ExplAINI FILE INUREG-0161) | ||
E - OPERATOR TRAINING + LICENSE E X A M IN A T IGN F - ADMINISTRATIVE (5) | E - OPERATOR TRAINING + LICENSE E X A M IN A T IGN F - ADMINISTRATIVE (5) | ||
G - OPERATIONAL ERDOR (EXPLAINI H - STHERIEXPLAINI EXHIBIT I - SAME SOURCE 1 | G - OPERATIONAL ERDOR (EXPLAINI H - STHERIEXPLAINI EXHIBIT I - SAME SOURCE 1 | ||
PEACH BOTTOM ATOMIC POWER STATION NARRATIVE | PEACH BOTTOM ATOMIC POWER STATION NARRATIVE | ||
Line 324: | Line 175: | ||
Oraining and decontamination of the torus to accommodate modifications was completed April 11. The control rod blade exchange and ISI were completed on April 15. The draining and decontamination of the reactor well was completed on April 16. Upon completion of the uncoupling of 37 control rod drives and shutdown of the CRD system on April 21, the reactor vessel water level was lowered to facilitate installation of new design feedwater spargers and perform core spray system pipe replacement external to the reactor vessel . | Oraining and decontamination of the torus to accommodate modifications was completed April 11. The control rod blade exchange and ISI were completed on April 15. The draining and decontamination of the reactor well was completed on April 16. Upon completion of the uncoupling of 37 control rod drives and shutdown of the CRD system on April 21, the reactor vessel water level was lowered to facilitate installation of new design feedwater spargers and perform core spray system pipe replacement external to the reactor vessel . | ||
UNIT 3 OPERATIONS On April 3, a load reduction to approximately 660 MW was begun in order to replace a limit switch on one of the main turbine control valves. | UNIT 3 OPERATIONS On April 3, a load reduction to approximately 660 MW was begun in order to replace a limit switch on one of the main turbine control valves. | ||
The control valve was " failed closed" and the limit switch was replaced. | The control valve was " failed closed" and the limit switch was replaced. | ||
Following this the valves were tested and the unit returned to full power by April 4. During this reduced power operation, a condenser Icak was also corrected. On April 8, the 3A reactor feed pump turbine tripped due to high vibration. This required a load reduction to approximately 940 MWe, After the reactor system was stabilized, load was increased to approximately 1055 MWe. This limit was maintained until early on. April 11, when the unit was returned to full load. | Following this the valves were tested and the unit returned to full power by April 4. During this reduced power operation, a condenser Icak was also corrected. On April 8, the 3A reactor feed pump turbine tripped due to high vibration. This required a load reduction to approximately 940 MWe, After the reactor system was stabilized, load was increased to approximately 1055 MWe. This limit was maintained until early on. April 11, when the unit was returned to full load. | ||
On April 12, a load reduction of 100 MWe was made so that the other two feed pumps could be taken out of service one at a time to accomnodate lubricating their couplings. On April 13, the Unit 3D RHR pump s0ction line was discovered to have a leak at a drain tap. | On April 12, a load reduction of 100 MWe was made so that the other two feed pumps could be taken out of service one at a time to accomnodate lubricating their couplings. On April 13, the Unit 3D RHR pump s0ction line was discovered to have a leak at a drain tap. | ||
The pump was declared inoperable and appropriate surveillance tests were successfully completed. A cracked weld on the drain tap was suc-cessfully repaired and the pump was restored to service. On April 23, during testing of turbine valves,' the No. 1 Combined Intercept Valve closed but did not " disc dump" and fast close through the last few percent of its travel. The problem was determined to be with an electrical coil which operates a solenoid on the valve. The coil was replaced on April 25 and the valve was satisfactorily tested. | The pump was declared inoperable and appropriate surveillance tests were successfully completed. A cracked weld on the drain tap was suc-cessfully repaired and the pump was restored to service. On April 23, during testing of turbine valves,' the No. 1 Combined Intercept Valve closed but did not " disc dump" and fast close through the last few percent of its travel. The problem was determined to be with an electrical coil which operates a solenoid on the valve. The coil was replaced on April 25 and the valve was satisfactorily tested. | ||
Dockst No. 50-277 Attachment to Menthly Operating Report for April, 1980 REFUELING INFOT4ATION | Dockst No. 50-277 Attachment to Menthly Operating Report for April, 1980 REFUELING INFOT4ATION | ||
: 1. Name of facility: | : 1. Name of facility: | ||
Line 358: | Line 205: | ||
September, 1990 | September, 1990 | ||
.. I)ockst No. 50-278 | .. I)ockst No. 50-278 Attachment to Monthly Operating Report for April, 1980 REFUELING INFORMATION | ||
Attachment to Monthly Operating Report for April, 1980 REFUELING INFORMATION | |||
: 1. IM e of facility: | : 1. IM e of facility: | ||
Peach Bottom Unit 3 | Peach Bottom Unit 3 |
Latest revision as of 20:30, 18 February 2020
ML19323D384 | |
Person / Time | |
---|---|
Site: | Peach Bottom ![]() |
Issue date: | 05/09/1980 |
From: | Alden W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
To: | |
Shared Package | |
ML19323D382 | List: |
References | |
NUDOCS 8005210516 | |
Download: ML19323D384 (9) | |
Text
__ . - _ _ _ . . _ _ . - - _ _ _ _ . _ _
AVERAGE DAILY LNIT POWER LEVEL O. o m eT NO. 50 - m
_-_ =-----
UNIT PEACH BOTTOM UNIT 2 DATE MAY 9, 1980
= -------
COMPANY PHILADELPHIA ELECTRIC COMPANY
- . _ = - - _ _ _ = - - - _--..--------
W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH APRIL 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-f;E T ) (MWE-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 2,3 0 8 ,
0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 1
16 0 8005s10gg
. . . . u. u, 00C4FT NO. 80 - 277 DATE MAY 0 1980 COMPLETED BY PHILADELPHIA ELECTRIC C0 PAND W.M.ALDEN W
ENGINEER-IN-CHARGE NUCLEAR SECTICN GE NE R A T I ON OIVISION-NOCLFAo TELEPHO*E (215) 841-5022
__=-
OpF2AT!Nr. STATUS
.___.... _______ .- = ____ - __ _-- _=---________
l . UN I T Na uf : FEACH BOTTOM UNIT 2 1 NOTES: THIS UNIT IS IN ITS l
.__.______________.___.________.__ l t
- 2. Rr oce TING *ERIGO: APRIL, 1980 i
__. ==
FOURTH REFUELING OUTAGE. I
...______._______ l l
- 3. LICENS50 THERMAL POWER (MWT): 3293 l I
l l
4 NAM 8 PLATE RATING IGRCSS MwEl: 1152 1 1
__________ ____ l
%. C8 SIGN ELECTRICAL RATING (NET MWEl l 1065 l I
_________ l
- 6. l M A X IM UM OSPENDABLE CAPACITY (GROSS MWE): 1048 I l l l
- 7. Maxl"UM DEFENDAeLE CAPACITY l NET MWE): 1051 l l B.
IF CHANGES UCCUR IN C ADACITV RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE 4
PowFR LEvfL TO WHICH EFSielCTED. IF ANY (NF1 MWEli
- 10. 4EASONS FOR RFSTRICTIONS. IF ANY:
e l
THis MONTH YR-TO-DATE CUMULATIVE '
- 11. H9uRS IN RFPORTING PERIOD 719 2,901 ^1.047
.__. ____- _ = = . -
- 13. RE ACTOR RESERvF SHUTOOWN HOURS 0.0 0.0
- = _ - ____
0.0 14 HOUR S GE NE R A T00 ON-L IN E 0.0 1,390.7 38,373.0
- 15. UNIT RESERVF S'UTOOWN HOURS 0.0 0.0 0.0
- 16. GRGS$ THtRMAL ENFRGY GENEPATED (MWH) 0 3.831,770 110.597.414
- 17. GROSS ELECTRIC AL ENERGY GENERATED (MWa) 0 1.255,980
- _ = _ _ . . _ _ _ ......-
36.314 210
- 16. NE T E LECTR ICEL FNERGY GENERATED (MLH) * -1.517 1.195.873 34.811.658 14 UNIT SERVICE F4CTOR 0.0 47.9 75.2
- 20. UNIT AVAIL ABILITY FACTOR 0.0 47.9 75.2
- 21. UNIT CAPACITY FACTOR tOSING MOC NET) 0.0 39.2 64.9
- 22. UNIT CAPACITY FACTOR (US ING DE R NET) 0.0 38.7 64.0 2 3. UNI T FORCEO QUTAGE RAlf 0.0 0.0 6.1
..------=
24 SHulD0wNS SCHEDULFD OVER NE*T 6 M ON T HS (TYPE. DATE. AND OUR ATION OF EACH):
UNIT ? SHUTDOWN FOR FCue TH REFUELING.
- 25. IF sHUTOO*N AT END OF REPOR1 PERIOD. ESTIMATED DATE OF STARTUP: 7/13/90 2 e . UN I T S IN 1EST STATUS IPRIOs 10 COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPFRATION o - NEGATIVE VALUE REPORTED FOR CONSISTENCY WITH FEDERAL ENERGY REGULATORY COMMTMSTON e
LnIT SHLTDOWNS AND P0wER RECUCTION> DOCMET NO. $0 - 277
__..._-_-__. ==......._-_.
UNIT NAME DEACH BOTTOM UNil 2 CATE MAY o. 1880
_ __. =..._____........_-_
a EPOR T MONTH A PR IL , 19PO COMPLETED BY PHI L a DE LPHI A ELECTRIC COMPANY
..__.._ _.. _ - _ = = - ............_-.._
, W.".ALDEN ENGINEER-IN-CHAkGE NUCLEAR SECTION GENER ATI DN DIVI S ION-NUCL E AR TELEPHONE (215) 841-5022 I i l l l METHOL OF l LICENSEE ISYSTEMICOMPONENTI CAUSE AND CORRECTIVE l lTYPElDURATION14EASONISHUTTING D0wNi EVENT l CODE l CODE I ACTION TO NO.I DATE I (Ill (HOURSil (2) l PEACIOR (3) l REPORT s 1 (4) l (5) l PREVENT RECURRENCE I I I l i I I I I 9 l 800401 i Sl 719.0 1 C 1 2 i NONE I RC l FUELXX l CONTINUATION 05 REFUEL OUTAGE.
I i 1 ----- 1 I 1 1 1 l l 8 1 719.0 l l l l l l (Il (21 (3) (4)
F - FORCEO REASON METHOD EXHIPli G - I NST R UC T ION S S - S CHE DULE D A - EQUIPMENT F A I L U4 E (EXPLAIN) 1 - MANUAL FOR PRE P A R A TION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOWaTIC SCRAM. EVENT REPORT (LERI D - REGUL ATORY RE STRICTION 4 - OTHER (EXPLAIN) FILE INUREG-Ol61)
E - OPERATOR TRAINING + LICENSE EXAMINATION F- ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
H - OTHERIEXPLAINI EXHIBIT I - SAME SOURCE
AVERAGE OAIL: UNIT POWER LEVEL DOCKET NO. 50 - 278
-------- _ _ = _ - _ _ _ _ -
UNIT PEACH BOTTOM UNI T 3 DATE MAY 9, 1980
=
COMPANY PHILADELPHIA ELECTRIC COMPANY
= ----- ------
W.M.ALDEN E NG IN E E R -IN-CH A RG E NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 j
l MONTH APRIL 19530 i DAY AVERAGE OAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL ,
(MWE-NET) (MWE-NET) l l
1 1073. 17 1071 l 2 1071 18 1069 3 1032 19 1069 4 967 20 1071 5 1072 21 1072 6 1071 22 1069 7 1065 , 23 1068 9 , 1064 24 1067 9 1012 25 1064 10 1024 26 1068 11 1040 27 1069*
12 1031 28 1069 13 1071 29 1067 14 1070 30 1070 15 1075 16 1066
- Ad. justed for daylight savings time.
0004t 1 NO. -
27P !
."O DATF MAY 9, 1980 COMPLETED BY PHILA0FLPHIA FLECTRIC CDuPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISICN-NUCLcAA TELEPHONE (215) 841-5022 GPERATING STATut
- 1. UN I T NAME: PEACH EOTTOM UNIT 3 l NOTES: THIS UNIT FXPERIFNCED TWO
...._............ ___ ............ I l t
- 2. AE P09 T1NG PER IOC: APRIL, 1980 l
.- .___ .=--
MAJOR POWER REDUCTIONS l
__==
l l
- 3. LICFNSED THkRMAL POWER (MWil: 3293 l AND NO OUTAGES.
...= ..== - - -
l l l 4 NAMEPLITE RATING (GROSS :4WE): 1152 l I
l l
- 5. OE %1GN ELECTRICAL RATING (NET MWE ): 1065 i I l l 6.
wartMUM DE PENDA>L E C AP AC IT Y (GROSS MWE): 1096 l t l l
- 7. MAXIMUM OSPENOABLE CAPACITY (NET MWE): 1035 1 1
P. 15 CHANGES OCCUR IN C A PAC IT Y RA T INGS ( ITFMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASCNS:
9 POWFR lev 5L TG aHILH R E STRICTED, IF ANY (NET MWE):
- 10. REASONS FOR RESTRICTIONS, 15 ANY:
i f THIS MONTH YR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 714 .2,903 46,443
- 12. NUMPE R OF MOURS RE AC TOR WAS CRITICAL 714 2,410
- 37,256 *
..._________ .... =_
- 13. REACTOR RESERVE SHUTOOWN HOURS 0.0 0.0 0.0
... _ . . - =..___
14 HOURS GENER A TOR ON-LINE 719.0 2,303.5* 36,235.3 *
- 15. UNIT RESERVF SHUTOOWN HOURS 0.0 0.0
, 0.0 lb. GR US S THERMAL ENERGY GEN (EATED (MWM) 2,339,743 7,333,210 101,ES2,364
...-.=_-- .. -- -
- ==
- 17. GROSS ELECTRIC AL ENERGY GENERA 1ED IMwH) 7aG.100 2,470,150 33,056,010
_..._.... __ .=-- __ __ _______ .
- 18. NET ELECTRICAL ENFRGY GENERATED IMwH) 761,515 2,385,028 31,729,828 19 UNIT SERVICE FACTOR 100.0 79 3* 77.2 *
- 20. UNIT AVAILABILITY FACTOR 100.0 10 .3 *
==- _.-. --
77.2 *
- 21. UN11 CAPACITY FACTOR (USING MDC NET) 102.3 79.4 65.3
___- __._.._ =
63.5
_ _ = . __----. _..
- 23. UNTT FORCED OUTAGS RATE 0.0 6.0
- 6.8
- __........__ ==- ____ _ ____________
24 SHU10DWNS SCHE 00L EO OVE R NEXT o MONTHS ( TYPE, DATE . AND DUR ATION UF EACH):
- 29. IF 590T00wN AT END OF REPORT PERICD, ESTIMATED DATE OF STARTUP:
26 UNITS IN TEST STATUS (PRIOR 10 COMMERCIAL OPERATICN): FORECAST ACHIEVE 0 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
.,wRS. GENERATCR ON LINE, HRS. RE ACTOR CRITICAL, AND FORCED OUTAGE HRS.
- -- ~
t UNIT SHulDOWNS ANC POWER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE MAY 9, 1960 RE POR T MON TH APRIL, 1680 COMPL E TED BY PHIL ADE LPHI A ELECTRIC COMPANY
___= _ _ _ = _ . --
W.H.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022
- _ =___. _____________
l I I I l I METHOD OF l LICENSEE lSYSTEMICOMPONENTl CAUSE AND CORRECTIVE lTYPElDURATIONlREASONISHUTTING DOWNI EVENT l CODE I CODE l ACTION TO NO.I LATE I 1111 (HOURSil (2) l REACTOR (3) l REPORT a 1 (4) l (5) l PREVENT RECURRENCE I I i 1 1 I I I I O B l 80040) 1 5 1 0.0 l B l 4 l NONE l HA I VALVEX l LOAD OROP TO REPAIR TUBE LEAK IN 28 WATER l t i l i i l l I BOX AND 83 TURBINE CONTROL VALVE.
I l l l l l l l l O
6 i *C040* 1 F 1 0.0 l A l 4 l NCNE I I l l l l I CH l PUMPXX l LOAD DROP FOR REACTOR FEED PUMP TRIP DN I I I ----- 1 1 l l HIGH VIBRATIONS.
I l l l 1
, I I I - l l I l i I L '
4 (1) (2) , (3) (4)
F - FORCED REASON METHOD
% 5 - S C HE DUL E D A - EGUIPMENI FAILURt (EXPLAIN) EXHIb1T G - INSTRUC TIONS 1 - MANUAL FOR PREPARATION OF DATA R - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
C - REFUELING ENTRY SHEETS FOR LICENSEE 3 - AUTOMATIC SCRAM. EVENT REPORT (LER)
O - REGULATORY EESTRICTIGN 4 - OTHER (ExplAINI FILE INUREG-0161)
E - OPERATOR TRAINING + LICENSE E X A M IN A T IGN F - ADMINISTRATIVE (5)
G - OPERATIONAL ERDOR (EXPLAINI H - STHERIEXPLAINI EXHIBIT I - SAME SOURCE 1
PEACH BOTTOM ATOMIC POWER STATION NARRATIVE
SUMMARY
OF OPERATING EXPERIENCES APRIL, 1980 UNIT 2 OPERATIONS The unit remains shutdown to accommodate refueling, modifications, and maintenance work. The removal of fuel from the reactor was completed on April 6. Changeout and verification of LPRMS was completed on
- April 8, 1980. Control rod blade changeout was completed on April 14.
Oraining and decontamination of the torus to accommodate modifications was completed April 11. The control rod blade exchange and ISI were completed on April 15. The draining and decontamination of the reactor well was completed on April 16. Upon completion of the uncoupling of 37 control rod drives and shutdown of the CRD system on April 21, the reactor vessel water level was lowered to facilitate installation of new design feedwater spargers and perform core spray system pipe replacement external to the reactor vessel .
UNIT 3 OPERATIONS On April 3, a load reduction to approximately 660 MW was begun in order to replace a limit switch on one of the main turbine control valves.
The control valve was " failed closed" and the limit switch was replaced.
Following this the valves were tested and the unit returned to full power by April 4. During this reduced power operation, a condenser Icak was also corrected. On April 8, the 3A reactor feed pump turbine tripped due to high vibration. This required a load reduction to approximately 940 MWe, After the reactor system was stabilized, load was increased to approximately 1055 MWe. This limit was maintained until early on. April 11, when the unit was returned to full load.
On April 12, a load reduction of 100 MWe was made so that the other two feed pumps could be taken out of service one at a time to accomnodate lubricating their couplings. On April 13, the Unit 3D RHR pump s0ction line was discovered to have a leak at a drain tap.
The pump was declared inoperable and appropriate surveillance tests were successfully completed. A cracked weld on the drain tap was suc-cessfully repaired and the pump was restored to service. On April 23, during testing of turbine valves,' the No. 1 Combined Intercept Valve closed but did not " disc dump" and fast close through the last few percent of its travel. The problem was determined to be with an electrical coil which operates a solenoid on the valve. The coil was replaced on April 25 and the valve was satisfactorily tested.
Dockst No. 50-277 Attachment to Menthly Operating Report for April, 1980 REFUELING INFOT4ATION
- 1. Name of facility:
Peach Bottom Unit 2
- 2. Scheduled date for next refueling shutdown:
Fourth refueling outage in progress since March 21.
3 Scheduled date for restart following refueling:
July 13, 1980 14 Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes.
If answer is yes, what, in general, will these be?
Technical specification changes to accc==cdate reload fuel.
Modifications to reactor core operating limits are expected.
- 5. Scheduled date(s) for submitting proposed licensing action and supporting information:
1 Amendment application submitted February 19
- 6. Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
Initial utilization of General Electric pre-pressurized Fuel Assemblies for this Unit.
7 The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) Core - No Fuel Assemblies ,
(b) Fuel pool -
1382 Irradiated Fuel Assemblies j 292 Unirradiated Fuel Assemblies <
- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
l The spent fuel pool storage capacity has been relicensed for 2816 fuel assemblies.
9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
September, 1990
.. I)ockst No. 50-278 Attachment to Monthly Operating Report for April, 1980 REFUELING INFORMATION
- 1. IM e of facility:
Peach Bottom Unit 3
- 2. Scheduled date for next refueling shutdown:
March 7, 1981 3 Scheduled date for restart following refueling:
Pay 23,1981
- h. Will refueling or resu=ption of operation thereafter require a technical specification change or other license amendment?
Yes.
If answer is yes, what, in general, will these be?
Technical specification changes to accoc=odate reload fuel.
Modifications to reactor core operating limits are expected.
5 Scheduled date(s) for submitting proposed licensing action and i supporting information:
January 23, 1981
- 6. Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or perfor=ance analysis methods, significant changes in fuel design, new operating procedures:
None expected.
7 Thenu=beroffuelassemblies(a)inthecoreand(b)inthespent fuel storage pool:
(a}. Core -
76h Fuel Assemblies (b) Fuel pool -
712 Irradiated Fuel Assemblies
- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
The spent fuel pool storage capacity has been relicensed for 2816 fuel assemblies.
9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
September, 1991.