ML20079H135
| ML20079H135 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/10/1982 |
| From: | Alden N PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20079H133 | List: |
| References | |
| NUDOCS 8212160058 | |
| Download: ML20079H135 (9) | |
Text
e..._ _ __
CPERATI!G DATA REP!BT DOCKET ND. 50 - 277
.__.___=____=. - =._____..___
DATE DECEMBER 10, 1982 2._______
___.
C05PLETED BY PHILADELPHIA ELECTRIC COEPANY___
______...=-
W.H.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022
= - - - _ _ _ _ _.
= _ _ - - -. _.
OPERATING STATUS
- 1. UNIT NAME: PEACH BOTTOM UNIT 2 l NOTES: UNIT 2 EXPERIENCED ONE l
g g
- 2. REPORTING PERIOD: NOTEM BER, 1982 i
SCHEDULED LOAD REDUCTION l
g g
3293 l
AND ONE FORCED LOAD l
- 3. LICENSED THERNAL POWER (BWT) :
g g
____=
- 4. NAMEPLATE RATING (GROSS BWE) :
1152 i
REDUCTION.
l g
l
- 5. DESIGN ELECTRICAL RATING (NET MWE) :
1065 l
g g
l
- 6. BAIIMDB DEPENDABLE CAPACITY (GROSS MWE) : 1098 l
g g
l
- 7. HAIIMUM DEPENDABLE CAPACITY (NET BWE):
1051 l______.____._______..._________..________
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS HONTH YR-TO-DATE CUBULATIVE 720 8,016 73,704
- 11. HOURS IN REPORTING PERIOD
.__-= ----._
- 12. NUBBER OF HOURS REACTOR WAS CRITICAL 720.0 4,773.9 54,517.3 0.0 0.0 0.0
- 13. REACTOR RESERVE SHUTDOWN HOURS 720.0 4,523.7 52,980.2
-14. HOURS GENERATOR ON-LINE 0.0 0.0 0.0
- 15. UNIT RESERVE fHUTDOWN HOURS
- 16. GROSS THERMAL ENERGY GEN ER ATED (HUB) 2,303,501 13,508,410 154,731,726
=---
- 17. GROSS ELECTRICAL ENERGY GENERATED (MUR) 764,020 4,430,320 50,934,090
- 18. NET ELECTRICAL ENERGY GENERATED (MNE) 735,072 4,236,433 48,827,168
-_ =- --
100.0 55.4 71.9
- 19. UNIT SERVICE FACTOR 100.0 56.4 71.9
- 20. UNIT AVAILABILITY FACTOR
=-
..._==-_ =--
- 21. UNIT CAPACITY FACTOR (USING RDC NET) 97.1 50.3 63.0
- 22. UNIT CAPACITY FACTOR (USING DER NET) 95.9 49.6 62.2 0.0 3.5 7.8
- 23. UNIT FORCED OUTAGE RATE
- 23. SHUTDOWNS SCHEDULED OVER NEIT 6 BONTHS (TY P E, DATE, AND DURATION OF EACH):
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIM ATED D ATE OF STARTUPs
- 26. UNITS IN TEST STATUS (PR IOR TO COMMERCI AL OPER ATION) :
FORECAST ACHIETED INITIAL CRITICALITY INITIAL ELECTRICITY CosMERCIAL OPERATION 8212160058 821210 PDR ADDCK 05000277 R
f CPERATI;G DATA REPIRT DOCKET E0. 50 - 278 DATE DECEBBER 10, 1982
_e.____.___...---_-_.
COMPLETED BY PHILADELPHIA ELECTRIC COMPANY
-..____._ -- =--
N.R.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 CPERATING STATUS
- 1. UNIT NAME: PEACH BOTTOM UNIT 3 i NOTES: UNIT 3 EXPERIENCED ONE l
- 2. REPORTING PERIOD: NOVEMBER, 1982 i
SCHEDULED LOAD REDUCTION l
g g
- 3. LICENSED THERM AL POWER (5WT) :
3293 i
AND ONE FORCED LOAD l
g g
- 4. NAMEPLATE RATING (GROSS BWE) :
1152 i
REDUCTION.
l g
- 5. DESIGN ELECTRICAL RATING (WET RWE):
1065 l
l g
- 6. MAXI 505 DEPENDABLE CAPACITY (GROSS MWE) : 1098 l
l g
g
- 7. MAIIMUM DEPENDABLE CAPACITY (NET BWE):
1035 l
l
- 8. IF CH85GES OCCUR IN CAPACITY RATINGS (ITEMI NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE) :
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS BONTH YR-TO-DATE CUMULATITE
- 11. HOURS IN REPORTING PERIOD 720 8,016 69,600
- 12. NUMBER OF HOURS BEACTOR WAS CRITICAL 720.0 7,698.3 53,185.7 0.0 0.0 0.0
- 13. REACTOR RESER1E SHUTDOWN HOURS
~~~~55$85678
~~~~~~~
~~~~~
72676 7$636!6
-14. HOURS GENERATOR ON-LINE 0.0 0.0 0.0
- 15. UNIT RESERVE SHUTDOWN HOURS
-==..
- 16. GROSS THERMAL ENERGY GENER ATED (MWH) 2,234,611 24,307,144 150,998,666
- 17. GROSS ELECTRICAL EN ERGY GENERATED (MWR) 739,750 8,123,160 49,512,080
- 19. UNIT SERVICE FACTOR 100.0 95.2 74.5
- 20. UNIT AVAILABILITY FACTOR
_______=.
- 21. UNIT CAPACITY FACTOR (USING NDC NET) 95.3 94.5 66.0
- 22. UNIT CAPACITY FACTOR (USING DER NET) 92.6 91.8 64.1 0.0 4.8 7.5
- 23. UNIT FORCED OUTAGE RATE
- 24. SHUTDOWNS SCHEDULED OVER NEIT 6 50NTHS (TY PE, DATE, AND DURPTION OF EACH):
SCHEDULED SHUTDOWN FOR REFUELING AND MAINTENANCE, STARTS 2/12/83, FOR EIGHT WEEK OUTAGE.
- 25. IF SHUTDOWN AT END OF E3 PORT PERIOD, ESTIM ATED D ATE OF STARTUP:
- 26. UNITS IN TEST STATUS 8 PRIOR TO COMMERCI AL OPER ATION) :
FORECAST A CHI EVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 4
e up a
,w-
9 b
j
=
m UNIT SHUTDONNS AND PONER REDUCTIONS DOCKEY No. 50 - 277 UNIT NAME PEACH BOT OM UNIT 2 p
DATE DECEMBER 10, 1982 R EPORT MONTH NOVEMBER, 1982 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022
_=_-
l I
l l
3 METHOD OF l LICENSEE lSISTEMlCOMPONENTI CAUSE AND CORRECTIVE l
l TYPE lDURATIONIRE ASONl SHUTTING DONNl EVENT l CODE l CODE l ACTION TO NO.)
DAIE I (1) l (HOURS) l (2) l REACTOR (3) l REPORT 8 l (4) l (5) l PRETENT RECURRENCE 1
I I
I I
I I
I I
14 I 821102 l F l 00.0 l
D l 4
l NA l ZZ l ZZZZZZ l LOAD REDUCTION DDR TO LIMITATIONS ON l
l l
l l
l l
l l ALLON ABLE RIVER TEMPER ATURE DIFFERENTI AL.
- )
l 1
l l
l I
I I
l 15 l 821126 l S l 00.0 i
H l 4
1 NA l RC l ZZZZZZ l LOAD REDUCTION FOR THE ADJUSTMJNT OF THE l
l l
l 1
l l
l l CONTROL ROD PATTERN.
7) l l
1 I
I l
I I
l I
l 1 -
l l
I I
I I
- 7 e
(1)
(2)
(3)
(4)
M ETHOD EIMIBIT C - INSTRUCTIONS F - FORCED REASON S - SCHEDULED A - EQUIPMENT FAILURE (EIPLAIN) 1 - MANDAL FOR PREPARATION OF DATA B - M AINTEN ANCE OR TEST 2
- 1NUAL SCRAM.
ENTRY SHEETS FOR LICENSEE 3 - AUTOMATIC SCAAM.
EVENT REPORT (LER)
C - REFUELING D - REGULATORY RESTRICTION 4 - OTHER (EIPLAIN)
FILE (NUREG-0161)
E - OPER ATOR TRAINING + LICENSE EIAMINATION (5)
F - ADMINISTRATIV E G - OPER ATIONAL ERROR (EIPLAIN).
EINIBIT I - SAME SOURCE H - OTHER (EIPLAIN) e d
J d
,,..m.__...
- =
i m
M UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 278
=-
UNIT NAME PEACH BOTTOM UNIT 3 m
DATE DECEMBER 10, 1982
_
R EPORT MONTH NOVEMBE3, 1982 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY
=-_
W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022
---=
=
= = - - - - - - - - - - - -
=.
_ =--------___
1*
I I
I I
I METHOD OF I LICENSEE l SYSTEM lCOMPOWENTl CAUSE AND CORRECTIVE t
1 I TY P E l DU R ATI ON I RE ASON l SHUTTI N G DOW N I EVENT l CODE l CODE I ACTION TO 50 1 DATE l (1) l (HOUR S) I (2) l REACTOR (3) i REPORT e l
(4) l (5) l PREVENT RECURPENCE m
=
= --
1 I
l i
I I
I 1
l 17 l 821102 i F 1 00.0 i
D l 4
l NA l ZZ l ZZZZZZ l LOAD REDUCTION DDE TO LIMITATIONS ON t*
l l
l 1
I l
t I
l ALLOWABLE RIVER TEMPERATURE DIFFERENTIAL.
I I
I I
l l
l l
l 18 I 821112 i S I 00.0 i
H l 4
l NA I RC l ZZZZZZ l LOAD REDUCTION FOR THE ADJUSTMENT OF THE l
l
[
I l
l l
l l CONTROL ROD PATTERN AND REBOTAL OF STH l
t
[
l l
l l
l l HEATERS.
I l
1 --- -- l I
I I
I I
I*
I I
I -
l I
I I
I I
i
- =
b 93 (1)
(2)
(3)
(4)
METHOD EIHIBIT G - INSTRUCTIONS F - FOR C ED REASON S - SCHEDULED A - EQUIPMENT FAILURE (EIPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - M AINTENA NCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE 3 - AUTOMATIC SCRAM.
EVENT REPORT (LER)
C - REFUELING D - R EGULATORY RESTRICTION 4 - OTHER (EIPLAIN)
FILE (NU R EG-0161 )
E - OPERhTOR TRAINING + LICENSE EIAMINATION (5)
F - ADMINISTR ATIVE c - OPERATIONAL ERROR (EIPLAIR)
EINIBIT I - SAME SOURCE H - OTHER(EIPLAIN)
=
m
=
J h
-.-_,_.-..,..,..._,_2._.a.
A AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE DECEMBER 10, 1982 COMPANY PHILADELPHIA ELECfRIC COMPANY W.M.ALDEN ENGIN EER-IN -CHA RGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MO NTH NOVEMBER 1982 DAY AVERAGE D AILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (M WE-N ET)
(MWE-NET) 1 1015 17 1053 2
1014 18 1053 3
715 19 1051 4
862 20 1051 5
1018 21 1053 6
1046 22 1053 7
1050 23 1051 l
i 8
1050 24 1052 i
9 1049 25 1049 10 1047 26 7045 11 1052 27 834 12 1051 28 1019 13 1052 29 1043 14 1053 30 1049 15 1CS2 16 1049
AVERAGE DAILY UNIT POWER LEVEL DOCKET No. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE DECEMBER 10, 1982 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH NOVEMBER 1982 DAY AVERAGE DAILY POWER LEVEL DAY AYERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 1004 17 1025 2
969 18 1024 3
701 19 1018 4
934 20 1013 5
1023 21 1012 22 1009 6
1003 7
998 23 1009 8
997 24 1006 9
995 25 998 10 989 26 997 11 991 27 998 12 986 28 995 13 814 29 993 14 1036 30 993 j
15 1029 16 1024 e
-..,%eaea,g..os.
3 ep -,
Dockat No. 50-278 Attichment to Monthly Operating Report for November, 1982 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 3 2.
Scheduled date for next refueling shutdown:
February 12, 1983 3.
Scheduled date for restart following refueling:
April 8, 1983 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
i l
Yes If answer is yes, what, in general, will these be?
Technical Specifications to accommodate reload fuel.
Modifications to reactor core operating limits are expected.
5.
Scheduled date (s) for submitting proposed licensing action and supporting information:
December 24, 1982 6.
Important licensing considerations associated with refueling, f
e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, now operating procedures:
I None expected
\\
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a)
Core - 764 Fuel Assemblies (b)
Fuel Pool - 928 Fuel Assemblies, 6 Fuel Rods 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
=
Dockst No. 50-277
~
Attnchmsnt to Monthly Operating Report for November, 1982 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 2 2.
Scheduled date for next refueling shutdown:
October 15, 1983 3.
Scheduled date for restart following refueling:
December 10, 1983 4.
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 Specifications to accommodate reload fuel.
Modifications to reactor core operating limits are expected.
5.
Scheduled date(s) for submitting proposed licensing action i d supporting information:
September 10, 1983 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:
None expected 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a)
Core - 764 Fuel Assemblies (b)
Fuel Pool - 1170 Fuel Assemblies, 58 Fuel Rods
{
8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has I
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, 1990
-2.:
PEACH BOTTOM ATOMIC POWER STATION Narrative Summary of Operating Experiences November, 1982 Unit 2 On November 1, 1982, Unit 2 load was reduced due to the Technical Specification Limiting Condition for Operation (LCO) regarding river water delta T resulting from low flow in the Susquehanna River.
The magnitude of load drop necessary was reduced by negotiating with the State of Pennsylvania.
The load reduction continued until November 5, 1982 when the river water delta T returned to normal range.
On November 26, load was reduced to 350 MWe in order to accomplish a control rod pattern adjustment.
During this power reduction, several condenser tube leaks were repaired and the brushes on the B Recirculation Pump M-G set were replaced.
Power was increased on a flow ramp until full load was achieved on November 28.
Unit 3 On November 2, power was reduced in order to meet a Technical Specification LCO due to high river delta T.
This load reduction continued until November 5, at which time the delta T returned to normal range and the unit was returned to full load.
On November 12, power was reduced to 475 MWe to permit removal of the fifth feedwater heaters from service in preparation for extended core flow operation during the end of cycle coast down.
The unit power was increased on a flow ramp reaching full load on November 15.
A leak occurred in the D Residual Heat Removal System heat exchanger necessitating its removal from service for repairs during the period of November 14 through the 21.
Due to the uncertainty of completing this work within the seven days allowed by the Technical Specifications, which would require shutting down the reactor, an amendment to the Technical Specifications for temporary relief was requested and granted on November 19.
On November 22, the A Core Spray Loop was removed from service in order to repair a cracked weld on a one inch drain line.
The loop was returned to service on November 23.
No power reduction was associated with this work.
-