ML20213A302
| ML20213A302 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/31/1986 |
| From: | Middleton L PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20213A275 | List: |
| References | |
| NUDOCS 8702030205 | |
| Download: ML20213A302 (13) | |
Text
4 e
AVERAGE DAILY UNIT PONER LEVEL DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE JANUARY 15,1987 COMPANY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTNENT TELEPHONE IP151 841-6374 MONTH DECEMBER 1986 DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY POHER LEVEL (PME-NET)
(P94E-NET )
i 1
1074 17 1075 2
1078 18 1073 3
1074 19 1071 4
1075 20 761 5
1076 21 991 6
1072 22 1071 7
1076 23 1077 8
1076 24 1075 9
1077 25 1073 10 1075 26 1073 11 1076 27 1071 12 1075 28 1068 13 1070 29 1071 14 1069 30 1072 15 1074 31 1067 16 1070 8702030205 870126 PDR ADOCK 05000277 R
AVERAGE DAILY UNIT P0HER LEVEL DOCKET No. 50 - 278
....=_
UNIT PEACH BOTTOM UNIT 3
=--___
DATE JANUARY 15,1987 COMPANY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 MONTH DECEMBER 1986 DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY P0HER LEVEL (INE-NET)
(INE-NET) 1 1068 17 945 2
1073 18 829 3
1023 19 1038 e
4 949 20 1052 I
5 1020 21 1047 6
1004 22 1000 7
1019 23 1030 8
1047 24 1033 l
9 1051 25 1033 10 1038 26 741 11 1042 27 933 12 1021 28 80 13 85 29 0
1 14 0
30 0
13 743 31 0
1 16 1000
OPERATING DATA REPORT EOCKET No. 50 - 277 DATE JANUARY 15,1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPAtN L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION MJCLEAR SUPPORT DEPARTMENT TELEPHONE I2151 841-6374 OPERATING STATUS
- 1. UNIT NAMEt PEACH BOTTOM UNIT 2 i NOTES: UNIT 2 EXPERIENCED ONE l
l l
- 2. REPORTING PERIOD DECEteER, 1986 l
SCHEDULED LOAD REDUCTION.
l l
l
- 3. LICENSED THERMAL P0HERt WT)*
3293 l
l l
l
- 4. NAMEPLATE RATING ICROSS MHElt 1152 l
1 1
I
- 5. DESIGN ELECTRICAL RATING INET W E):
1065 I
l I
l
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS P94E 1* 1098 I
l l
l
- 7. MAXIMUM DEPENDABLE CAPACITY INET 794E) 1051 l
l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE RCASONSt
- 9. P0HER LEVEL TO HHICH RESTRICTED, IF ANY (HET W E):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744 8,760 109,512
- 12. NureER OF HOURS REACTOR MAS CRITICAL 744.0 7,272.8 72,467.0
- 13. REACTOR RESERVE SHUTDO W HOURS 0.0 0.0 0.0 1^,.
HOURS GENERATOR ON-LINE 744.0 7,014.0
,70,142.8
- 15. UNIT RESERVE SHUTDOW HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (t94H) 2,411,016 21,564,854 207,831.369
- 17. GROSS ELECTRICAL ENERGY GENERATED lt94H) 812,220 7,158,040 68,371,000
- 12. NET ELECTRICAL ENERGY GENERATED tt94H) 789,009 6.896,565 65,488,860 PAGE 1 0F 2 u.gy, e.--
OPERATING DATA REPORT (CONTINUED 1 DOCKET NO. 50 - 277 DATE JANUARY 15,1987 THIS MONTH YR-TO-DATE CUMULATIVE
- 19. UNIT SERVICE FACTOR 100.0 80.1 64.1
- 20. UNIT AVAILABILITY FACTOR 100.0 80.1 64.1
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 100.9 74.9 56.9
- 22. UNIT CAPACITY FACTOR (USING DER NET) 99.6 73.9 56.2
- 23. UNIT FORCED OUTAGE RATE 0.0 18.5 13.6
- 20. SHUTDOE SCHEDULED OVER NEXT 6 MONTHS ITYPE, DATE, AND DURATION OF EACH18 REFUELING OUTAGE FEBRUARY 7,1987 TO MAY 8,1987
- 25. IF SHUT 00694 AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPt
- 26. UNITS IN TEST STATUS (PRIOR TO Cort 1ERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 COMMERCIAL OPERATION 07/05/74 i
r l
1 PAGE 2 0F 2 j
i i
l sg
- I OPERATING DATA REPORT DOCKET No. 50 - 278 DATE JANUARY 15,1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPAtt(
L. L. MICOLETCN TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 OPERATING STATUS Unit 3experkencedtwo l
- 1. UNIT NAMEt PEACH BOTTOM UNIT 3 NOTES:
l forced outages, one i
- 2. REPORTING PERIOD DECEMBER, 1986 l
forced load reduction, l l
and two scheduled load i
- 3. LICENGED THERMAL P0HERENHT):
3293 l
reductions.
l 1
I
- 4. NAMEPLATE RATING (GROSS MHE):
1152 I
I l
l
- 5. DESIGN ELECTRICAL RATING (NET MHElf 1065 l
l 1
I
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS 794E): 1098 l
l l
l
- 7. MAXIMUM DEPENDABLE CAPACITY INET MHE):
1035 l
l G. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUPSER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSt
- 9. P0HER LEVEL TO HHICH RESTRICTED, IF Aff( (NET 994E):
- 10. REASONS FOR RESTRICTIONS IF ANY:
THIS MOP (TH YR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744 8,760 105,408
- 17. NUPBER OF HOURS REACTOR HAS CRITICAL 744.0 5,919.3 74,532.5
- 13. REACTOR RESERVE SHUTDOPG4 HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR ON-LINE 614.0 5.415.3
- 72,269.7 0.0 0.0 0.0
- 15. LHIT RESERVE SHUTDO,6! FOURS
- 16. GROSS THERMAL ENERGY GENERATED (79tH) 1,878,072 15,522,989 210,519,653
- 17. GROSS ELECTRICAL ENERGY GENERATED (t94H) 616,342 5,062,202 69sO55,872
- 12. NET ELECTRICAL ENERGY GENERATED (t94H) 598,033 4.849,352 66.242,093 PAGE 1 0F 2 typ
OPERATING DATA REPORT (CONTINUED)
DOCKET NO. 50 - 278 DATE JA?AJARY 15,1987 THIS MONTH VR-TO-DATE CtMULATIVE
- 19. UNIT SERVICE FACTOR 82.5 61.8 68.6
- 20. UNIT AVAILABILITY FACTOR 82.5 61.8 68.6 fl. UNIT CAPACITY FACTOR (USING HDC NET) 77.7 53.5 60.7
- 22. UNIT CAPACITY FACTOR IUSING DER NET) 75.5 52.0 59.0
- 23. UNIT FORCEO OtJTAGE RATE 16.0 19.9 8.2
- 20. SHUTDOHNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):
- 25. IF SHUTDODN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPI 6/18/88
- 26. UNITS IN TEST STATUS (PRIOR TO CatHERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 CotttERCIAL OPERATION 12/23/74 e
a 8
PAGE 2 0F 2
UNIT SHUTDOHrG AND P0HER REDUCTIONS DOCKET NO. 50 - 277 UNIT NAME PEACH BOTTOM UNIT 2 DATE JANUARY 15.1987 REPORT MONTH DECEMBER, 1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 I
I l
l l METHOD OF l LICENSEE ISYSTEMICOMPONENTI CAUSE AND CORRECTIVE I
ITYPElDURATIONIREASONISHUTTING DO W )
EVENT l CODE I CODE I ACTION TO
.1 DATE I (lli (HOURS)! 12) l REACTOR 13) l REPORT B l (4) l (5) l PREVENT RECURRENCE l
1 l
l I
I i
1 -
1 yI861210l S I 000.0 l B l 4
l N/A l RB l CONROD l LOAD REDUCTION TO 61% P0HER FOR CONTROL ROD I I l.
l l
l l
l l
l PATTERN ADJUSTMENT.
I I
I ----- 1 I
I I
I I
1 I
I I
I i
I I
I 1
l (1)
(2)
(3)
(4) 1
- FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS
- SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
1/ENT REPORT (LER)
D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)
FILE (NUREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
EXHIBIT I - SAME SOURCE l
H - OTHERLEXPLAIN) l t
UNIT SliUTDOHNS AND P0HER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTFOM UNIT 3 DATE JANUARY 15,1987 REPORT MONTH DECEMBER, 1986 COMPLETED BY PHILADELPHIA ELECTRIC C'OMPANY L. L. MIDDLETON-TECHNICAL ASSISTANT LICENSING SECTIC'4 NUCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 l
......= =-
l l
l l
l METHOD OF l LICENSEE ISYSTEMICOMPONENTl CAUSE AND CORRECTIVE
)
I TYP E l DURATION I RE ASON I SHUTTING DOHN I EVENT l CODE l CODE l ACTION TO
) DATE I (1)] (HOURS)I (2) l REACTOR 13) l REPORT 8 l (4) I (5) l PREVENT RECURRENCE g...
- D I
I I
I I
I I
l C 861203 l F i 000.0 i B l 4
i N/A l CE l VALVEX l LOAD REDUCTION TO 62% P0HER FOR REPLACEMENT OF
~
0 l
l l
l l
l l
l THE REACTOR CORE ISOLATION C00 LING lRCIC) 0 1
1 1
I l
l l
l MD-16 STEAM LINE ISOLATION VALVE PACKING.
O l
i I
I I
I I
I B 861213 l F l 041.7 l B l 1
1 N/A I HB 1 PIPEXX l TURBINE HAS MANUALLY HITH REACTOR P0HER 0
l l
l l
l l
l l REMAINING AT APPROXIAMATELY 20% TO ACC0tt10DATE
!0 l
I l
l l
I l
l STEAM LEAK REPAIRS ON THE "D" MAIN STEAM LINE
!Q l
l l
l l
l l
l INLET FLANGE TO THE HIGH PRESSURE TURBINE.
B l
i I
I I
I I
l
,0 E61217 I S I 000.0 i B l 4
l N/A I HF l HTEXCH l LOAD REDUCTION TO 61% P0HER FOR LEAK TESTING l0 l
l i
l l
l l
1 0F "C1" AND "C2" HATERBOXES, AND CONTROL RCD B
I l
l l
1 l
l l PATTERN ADJUSTMENT.
B I
I I
I I
I I
i j0 861226 l S I 000.0 i B l 1
1 N/A l HF 1 HTEXCH l LOAD REDUCTION TO 612 MHE FOR CONDENSER l0 1
.I I
I I
I I
I HATERBOX 1TJBE LEAK INSPECTIONS IN THE B2 I
I I
I l
l l
l l HATERBOX, AND CONTROL ROD PATTERN ADJUSTMENT.
I I
I I
I I
I I
I ll 861223 l F l 000.3 l B l 1
i N/A l H3 I PIPEXX l MANUAL SHUTD0kN FOR STEAM LEAK REPAIRS ON THE ll l'
l l
l l
l l
l "C" MOISTURE SEPARATUR DRAIN TA?E MANHAY AND l
l l
l l
l l
l l THE "D" INLET FLANGE TO THE HIGH PRESSURE ll l
1 I
I I
I I
I TURBINE.
Il i
I ----- 1 I
i i
l I
b_
l l 130.0 l l
I l
l l
I FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS
' SCHEDULED A - EQUIPMENT FAILURE IEXPLAIN) 1 - MA?AJAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LER)
D - REGULATORY RESTRICTION 4 - OTHER IEXPLAIN)
FILE INUREG-D161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE I5)
I;L -
Peach Bottom Atomic Power Station Narrative Summary of Operating Experience December, 1986 1
UNIT 2 The unit continued operating at full power and maintained full load until December 20.
On December 20, load was reduced to 625 MWe to accommodate control rod pattern adjustment and testing of main steam isolation valve 86-D.
Load recovery was completed on December 21, and full power was maintained through the end of the report period.
UNIT 3 The unit operated at full power until December 3, when load was reduced to 700 MWe to accommodate packing leak repairs to the Reactor Core Isolation Cooling system outboard isolation valve.
The repairs were completed and full load was recovered on December 4.
On December 13, with the reactor remaining critical at approximately 20% power, the turbine was manually tripped to repair a leak on the
'D' main steam line inlet flange to the high prbssure turbine.
The turbine-generator synchronized with the grid on December 14, and load was increased to 97% power on December 16.
On December 17, load was reduced to 690 MWe for condenser waterbox tube leak inspections.
One tube leak was found and repaired in the C-1 waterbox.
Load was increased to 98% power on Decemb r 18.
9 On December 26, load was reduced to 612 MWe for control rod pattern adjustment and condenser waterbox tube leak inspections.
No leaks were found and load was increased to 98% power on December 27.
On December 28, Unit 3 was manually shutdown to repair steam leaks on the
'C' moisture separator drain tank manway, and again -
on the
'D' main steam line inlet flange to the high pressure turbine.
While shutdown, repairs were also made to condenser tube leaks in the A-1, B-1, and B-2 waterboxes, and to the
'B' recirculation pump M-G set breaker.
Unit 3 ended the report in start-up following the mini-outage.
~- ' " ' '
Docket No. 50-277 Attachment to Monthly Operating Report for December, 1986 UNIT 2 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 2 2.
Scheduled date for next refueling shutdown:
February 7, 1987 3.
Scheduled date for restart following refueling:
May 8, 1987 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.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
Reload 7 license amendment to be submitted January 9, 1987.
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 - 1462 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 been requested or is planned, in number of fuel assemblies:
The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblies.
Replacement higher density fuel racks were approved by the NRC on February ~19, 1986 which increases the licensed fuel pool capacity to a total of 3819 fuel bundles in each fuel pool.
This modification was completed on November 15, 1986.
4 Docket No. 50-277 Attachment to Monthly Operating l
Report for December, 1986 Page 2 UNIT 2 REFUELING INFORMATION (Continued) 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity, prior to the completion of the new fuel racks installation:
March, 1998 (March 1995, with reserve full core discharge)
E g
4
- 4 e
4 9
se
e.
Docket No. 50-278 Attachment to Monthly Operating Report for October, 1986 UNIT 3 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 3 2.
Scheduled date for next refueling shutdown:
September 12, 1987 x
3.
Scheduled date for restart following refueling:
l-June 13, 1988 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.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
l neload 7 License Amendment to be submitted February 5, 1988 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 - 1496 Fuel Assemblies, 6 Fuel Rods v
s Docket No. 50-278 Attachment to Monthly Operating Report for December, 1986 Page 2 UNIT 3 REFUELING INFORMATION (Continued) 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 relicens d for 3819 fuel assemblies.
Replaceme.nt higher density, fuel racks were approved by the NRC on February 19, 1986 which increases the licensed fuel pool capacity to a total of 3819 fuel bundles in each fuel pool.
This modification is scheduled to begin late January 1987.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity, prior to the completion of'the new fuel racks installation:
March, 1993 (September, 1987, with reserve full core discharge) 10.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the relicensed capacity, subsequent to the completion of the new fuel racks installation:
March, 1999 (March, 1996, with reserve full core discharge) e G
i
..-g e..-
, - -