ML20215G127
| ML20215G127 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/30/1986 |
| From: | Alden W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8612240312 | |
| Download: ML20215G127 (15) | |
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l AVERAGE DAILY WIT POE3 LEVEL DOCKET 15. 50 - 277 WIT PEACH BOTTOM LA4IT 2 DATE DECEfSER 15, 1986 COMPANY PHILADELPHIA ELECTRIC COMPANY N.N.ALDEN ENGIM ER-IN-CHARGE LICENSING SECTION 88JCLEAR SENERATION DIVISION TELEPHOE (115) 841-5022 MONTH NOVEPSER 1986 DAY AVERAGE DAILY PONER LEVEL DAY AVERAGE DAILY POMER LEVEL 499tE-NETI (PME-NET 3 1
898 17 860 2
1065 18 1047 3
1028 19 1074 4
1043 to 1077 5
1065 21 1077 6
1067 22 1075 7
1067 13 1076 8
1072 24 1077 9
1070 25 1076 10 1072 26 1076 11 1071 27 1077 12 1071 28 1076 13 1068 29 1078 e
14 1071 30 1070 15 779 16 842 9612240312 861130
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4VERAGE DAILY (MIT POMR LEVEL DOCKET No. 50 - 278 UNIT PEACH BOTTOM LMIT 3 DATE DECEMER 15, 1986 COMPANY PHILADELPHIA ELECTRIC COMPANY N.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION 84JCLEAR GEMRATION DIVISION TELEPN0fE (215) 841-5022 NONTH NOVE MER 1986 DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY POMER LEVEL IPME-NET)
(PME-NET 1 s
1 0
17 1072 2
0 18 1072 3
0 19 1070 4
0 20 1071 5
0 21 1070 6
0 ft 1071 7
44 23 1027 8
372 24 998 9
658 25 1051 10 813 26 1067 11 745 27 1069 12 1023 28 1074 13 1062 29 1075 14 1060 30 1069 15 1071 16 1064 l
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OPERATING DATA REPORT DOCKET NO. 50 - 277 DATE DECEPSER 15, 1986 CfMPLETED BY PHILADELPHIA ELECTRIC CCNPANY M.M.ALDEN tNGINEER-IN-CHARGE UCENSING SECTION peJCLEAR GENERATION DIVISION TELEPHONE I215) 841-5022 OPERATING STATUS
- 1. WIT NAME: PEACH BOTTOM WIT 2 l NOTES: WIT 2 W?ERIENCED ONE l
l l
- 2. REPORTING PERIDO: NOVEPSER, 1986 l
SCHEDULED LOA 0 REDUCTION.
l l
l
- 3. LICENSED THERMAL PONERIP9fT):
3293 l
l l
l
- 4. NAMEPLATE RATING (3ROSS 194E):
1152 l
l 3
l
- 5. DESIGN ELECTRICAL RATING INET 794E):
1065 l
l
- 6. MAXItut DEPENDABLE CAPACITY IGROSS 994Els 1098 l
l g
l
- 7. MAXItRJM DEPENDABLE CAPACITY INET 99E ):
1051 l
l C. IF CHANGES OCCUR IN CAPACITY RATINGS IITEMS PMSEst 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
- 9. PONER LEVEL TO NHICH RESTRICTED, IF ANY (NET P94E):
- 10. REASONS FOR RESTRICTIONS IF ANY:
I THIS MONTH YR-TO-DATE CLMULATIVE
- 11. HOURS IN REPORTING PERIOD 720 8,016 108,768 I
i
- 12. POSER OF HOURS REACTOR HAS CRITICAL 720.0 6,528.8 71,723.0
- 13. REACTOR RESERVE SHUTD0604 HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR ON-LINE 720.0 6,270.0 69,398.8
- 15. WIT RESERVE SHUTD0D04 HOURS 0.0 0.0 0.0
___=
- 15. GROSS THERMAL INERGY GENERATED (P94H) 2,301.888 19,153,838 205.420.353
- 17. GROSS ELECTRICAL ENERGY GENERATED (P94H) 771,530 6,345,820 67,558,780
= __
- 18. IET ELECTRICAL E9ERGY GEPEPATED tt94HI 747,976 6.107,556 64,699,851 PAGE 1 0F 2
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OPERATING DATA REPORT ICONTIl4JED)
DOCKET NO. 50 - 277 DATE DECEISER 15, 1986 THIS MONTH YR-TO-DATE CLMJL,LTIVE
- 19. LMIT SERVICE FACTOR 100.0 78.2 63.8
- 20. LMIT AVAILABILITY FACTOR 100.0 78.2 63.8
- 21. LMIT CAPACITY FACTOR IUSING MDC NET) 98.8 72.5 56.6
- 22. LMIT CAPACITY FACTOR ILI5ING DER NET) 97.5 71.5 55.9
- 23. LMIT FORCED OUTAGE RATE 0.0 20.3 13.7
- 24. SHUTD0DNS SCHEDULED DVER NEXT 6 MONTHS ITYPE, DATE, AND DURATION OF EACH18 REFUELING OUTAGE FEBRUARY 7,1987 To MAY s,1987
- 15. IF SHUTD0DN AT END OF REPORT PERIDO ESTIMATED DATE OF STARTUP
- 26. WITS IN TEST STATUS IPRIOR TO COPMERCIAL OPERATION)*
FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 INITIAL ELECTR1 CITY 02/18/74 COPMERCIAL OPERATIDH 07/05/74 9
PAGE 2 0F 2 1
(
.c s OPERATING DATA REPORT
'd DOCKET No. 50 - 278 l
DATE DECEPSER 15, 1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY N.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION NUCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022 OPERATING STATUS
- 1. UNIT MAMEt PEACH B01 TOM LMIT 3 l HOTES: UNIT 3 EXPERIENCED ONE l
l l
- 2. REPORTING PERIODI NOVEPBER,1986 l
FORCED MAIAJAL SCRAM.
l l
l
- 3. LICENSED THERNAL PONERIPMT)*
3293 l
l l
l
- 4. NAMEPLATE RATING (GROSS PME):
1152 l
l l
l S. DESIGN ELECTRICAL RATING INET PMElt 1065 I
l l
l
- 6. MAXIttM DEPENDABLE CAPACITY EGROSS PME) 1098 l
l l
l
- 7. MAXIttJM DEPENDABLE CAPACITY tIET PME I 1035 l
l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS IITEMS 1429ER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS
- 9. PONER LEVEL TO NHICH RESTRICTED, IF ANY INET 19tE la
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR-TO-DATE CUPtJLATIVE
- 11. HOURS IN REPORTING PERIOD 720 8,016 104,664 l
12.14JteER OF 140URS REACTOR NAS CRITICAL 583.3 5,175.3 73,788.5
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR ON-LINE 562.0 4,801.3 71,655.7
- 15. LMIT RESERVE SHUTDOM4 HOURS 0.0 0.0 0.0 It. GROSS THERMAL ENERGY GENERATED (PMH) 1,694,664 13,644,917 208,641,581
- 17. GROSS ELECTRICAL ENERGY GENERATED IPMH) 564,310 4.445,860 68,439,530
- 18. NET ELECTRICAL EEasY GEERATE0 INNH) 544,915 4,251,319 65,644,060 PAGE 1 0F 2
c.,
1 I
I OPERATING DATA REPORT (CONTIMJED)
DOCKET NO. 50 - 278 l
j DATE DECEtBER 15, 1986 THIS NONTH YR-TO-DATE CLMJLATIVE
- 19. WIT SERVICE FACTOR 78.1 59.9 68.5
- 20. WIT AVAILABILITY FACTOR 78.1 59.9 68.5
- 21. UNIT CAPACITY FACTOR (USING NDC NET) 73.1 51.2 60.6
- 22. UNIT CAPACITY FACTOR (USING DER !ET) 71.1 49.8 58.9
- 23. LMIT FORCED OUTAGE RATE 21.9 20.3 8.1
- 24. SHLIFD00@tS SCHEDULED OVER NEXT 6 NONTHS ITYPE, DATE, AND DURATION OF EACHis SAFE-END/ PIPE NELD INSPECTION JAMJARY 3,1987 TO JAMJARY 23, 1987
- 25. IF SHUTDODN AT END OF REPORT PERIOD, ESTINATED DATE OF STARTUP
- 26. UNITS IN TEST STATUS E PRIOR TO CotHERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 COPMERCIAL OPERATION 12/23/74 f
I i
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PAGE 2 0F 2 i
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LMIT SHUTD0604S AM) PONER REDUCTIONS DOCKET No. 50 - 277 IA4IT NAME PEACH BOTTOM LMIT 2 DATE DECE)SER 15, 1986 REPORT MONTH NOVEMER, 1966 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY N.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION MJCLEAR GENERATION DIVISION TELEPHONE I215) 841-5022 I
1 l
l l PETH00 0F l LICENSEE ISYSTEMICOMPONENTI CAUSE AND CORRECTIVE l
l TYPE l DURATION I RE ASON I SHUTTING DODN l EVENT l CODE l CODE I ACTION TO NO.I DATE l t13l tHOURS3l t2) l REACTOR E3) l REPORT S l t4) l (5) l PREVENT RECURRENCE i............................
1 I
I I
I I
I I
I 33 1 861115 l SI 0.0 l
8 l 4
l N/A l R8 1 777777 l LOAD REDUCTION TO 54% PONER FOR I
I l
l l
l l
l l
1.1 CONTROL ROD PATTERN ADJUSTMENT.
l l
l l
l l
l l
l 2.I LEAK TESTING OF THE B1 NATER80X.
I I
I ----- 1 I
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(2)
(3)
(4) l F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS I S - SCHEDULED A - EQUIPMENT FAILURE IEXPLAIN) 1 - MAMJAL FOR PREPARATION OF DATA 8 - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT ILER)
D - REGULATORY RESTRICTION 4 - OTHER IEXPLAIN)
FILE IMJREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5) t t
G - OPERATIONAL ERROR IEXPLAIN)
H - OTHERIEXPLAIN)
EXHIBIT I - SAME SOURCE I
IA4IT SHUTD0Dets Ale PONER REDUCTIONS DOCKET NO. 50 - 278 WIT NAME PEACH BOTTOM LAdIT 3 DATE DECEteER 15, 1986 REPORT fENTH NOVEISER, 1966 Cot 9LETED BY PHILADELPHIA ELECTRIC COMPANY N.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION PAJCLEAR GENERATION DIVISIEW TELEPHONE 1215) 841-5022 l
I l
l l PETH00 0F l LICENSEE lSYSTEMICOMPONENTl CAUSE AND CORRECTIVE l
lTYPEIDURATIONIREASONISHUTTING 00M41 EVENT l CODE I CODE l ACTION TO NO.I DATE l i1)1 (HOURS)l I2) l REACTOR I3) l REPORT S l t4) I t5) l PREVENT RECURRENCE 1
I I
I I
I I
I i
19 1 861101 l F i 158.0 l A l 2
1 3-46-22 l MG I DEMINX l MANUAL SCRAM AS A RESULT OF PERSISTENT MAIN l
l l
l l
1 l
l l STEAM LINE HIGH RADIATION CLUSED BY A RESIN I
l l
l l
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l l INJECTION NHILE PLACING THE **3E" CONDENSATE I
l l
l l
l l
l l FILTER /DEMINERALIZER INTO SERVICE ICONTII4JED I
I i
1 1
I I
I I FROM lo/so/s6).
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I l
i I
I I
i 15a.0 l I
I 1
l l
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(1)
(2)
(3)
(4)
F - FORCED REASON METH00 EXHIBIT G - INSTRUCTIO*4S S - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MAPAJAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LER) l D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)
FILE (t4JREG-0161) l E - OPERATOR TRAINING + LICENGE EXAMINATION l
F - ADMINISTRATIVE I5) l G - OPERATIONAL ERROR IEXPLAIN)
H - OTHERIEXPLAIN)
EXHIBIT I - SAME SOURCE I
a-l Peach Bottom Atomic Power Station Narrative Summary of Operating Experience November, 1986 UNIT 2 Unit 2 began the report period operating at reduced power (700 MWe) for condenser waterbox inspections.
One leak was found and repaired in the B-1 waterbox.
Load recovery was completed on November 1.
On November 3, load was reduced to 58% power due to runback of the Electro-Hydraulic Control (EHC) System and "B"
recirculation pump, caused by a voltage spike on the. static inverter which supplies the primary control feed for the recirculation pump and EHC runback logic.
A recorder was setup to monitor the DC input i
of the battery system to the 120V AC output of the static inverter on the "B" recirculation pump; however, no other major transients were detected.
Load recovery was completed on November 4, and full load was maintained through November 14.
On November 15, a load reduction was taken to 70% power for condenser waterbox inspections..One leak was discovered and repaired in the B-1 waterbox.
Full load was restored on November 17.
On November 17,. load was reduced to approximately 64% power as a result of runbacks of the EHC and "B" recirculation pump caused by problems with the static inverter similar to those experienced on November 3.
The chart recorder was again placed in service to monitor transients of the recirculation pump.
One relay in the recirculation pump logic was replaced in an effort to eliminate a potential cause of the problem.
Continued monitoring of the battery system DC input to the 120V AC output for the static inverter still has not indicated the cause of the static inverter problems and EHC and "B"
recirculation pump runbacks.
Full load I
was recovered on November 18 and continued through the end of the report period.
UNIT 3 Unit 3 began the report period shutdown to accommodate reactor water chemistry recovery following a resin injection while i
placing the "E" condensate filter demineralizer into service.
While the unit was shutdown, repairs were made to the "C" and "E"
l IRMs, circulating water pump and motor, and to four hydraulic i
control unit accumulator instrument block valves.
I j
Reactor startup was initiated on November 5, but was terminated i
shortly thereafter when it was determined that control rod drive (CRD) 10-47 and its control blade were uncoupled.
Unit 3 was l
returned to service on November 6 after safety evaluations were
,,n._,,-.---,--,..-,.
us Attachm3nt to Monthly Operating Report for November, 1986 Page 2 performed for operation with 10-47 and three other rods fully inserted.
The unit operated at approximately 20% power until November 8, to stabilize reactor water conductivity.
Load was then increased to 65%, and condenser waterbox inspections were initiated.
Tube leaks and loose plugs were found and repaired in the A-1, B-2 and C-2 waterboxes.
Load recovery was completed on November 12 and continued through the end of the report period.
i
1s Docket No. 50-277 Attachment to Monthly Operating Report for October, 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 2, 1987.
l 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.
u, Docket No. 50-277 Attcchm:nt to Monthly Operating Report for October, 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, 1992 (February, 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, 1998 (March, 1995, with reserve full core discharge) l l
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'vd
-a 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 3.
Scheduled date for restart following refueling:
September 9, 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:
Reload 7 License Amandment to be submitted January 7, 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 o
Docket No. 50-278 Attcchm2nt to Monthly Operating Report for October, 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 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 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) l l
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 December 15, 1986 1215)841-4000 Docket Nos. 50-277 50-278 Director Office of Inspection & Enforcement US Nuclear Regulatory Commission Washington, DC 20555 Attention:
Document Control Desk
SUBJECT:
Peach Bottom Atomic Power Station Monthly Operating Report Gentlemen:
Attached are twelve copies of the monthly operating report for Peach Bottom Units 2 and 3 for the month of November, 1986, forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.
Very truly yours, W. M. Alden Engineer-In-Charge Licensing Section Nuclear Support Department Attachment cc:
Dr. T.
E. Murley, NRC Mr. T.
P. Johnson, Resident Inspector Mr. Stan P. Mangi, Dept. of Envir. Rescurces Mr.
P. A. Ross, NRC (2 copies)
Mr. R. J.
Clark, NRC Project Manager Mr. Thomas Magette, Maryland Power Plant Siting INPO Records Center
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