ML20206R949
| ML20206R949 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/31/1986 |
| From: | Alden W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8609190284 | |
| Download: ML20206R949 (15) | |
Text
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j-.
g, Peach Bottom Atomic Power Station m
Narrative Summary of Operating Experience August, 1986 E
UNIT 2 y
Unit 2 began the report period operating at full power.
On August 7, the unit was manually scrammed due to excessive packing leakage on the reactor core isolation cooling (RCIC) testable I
During the outage, repairs were also performed to
[
the moisture separator manway seals and position indicating probes (PIDs).
The outage was extended to perform internal wiring inspections on 83 Limitorque valve operators to ensure E
compliance with the NRC environmental qualification (EQ) i requirements.
On August 26, all EQ inspections and necessary repairs were completed, and the unit was returned to service.
On August 30, a load reduction to 650 MWe was taken to accommodate a control rod k
pattern adjustment.
Unit 2 ended the report period escalating in power towards full
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load.
Y Unit 3 s
Unit 3 began the report period in startup following a reactor scram on high neutron flux (July 19), and a subsequent, mini-a outage for maintenance.
The turbine-generator was placed on line August 2.
The same day, the "C" condensate pump was manually tripped as a result of a failure of the motor lower guide bearing.
Failure of
[
the guide bearing caused the rotor to damage the stator.
Unit 3 operated at approximately 85% power due to the unavailability of 5
the "C" condensate pump.
The motor was replaced with one from Limerick Unit 2, and the "C" condensate pump was returned to service on August 30.
On August 11, the reactor scrammed on low level following the trip on the load center breaker 3G4.
The trip of the load center I
breaker removed the power to the "A"
lube oil pump for the "C"
reactor feedpump (RFP).
The "B"
lube oil pump started; however, its lube oil pressure regulator malfunctioned, causing the "C" RFP turbine to trip when its thrust bearing wear ring detector sensed high oil pressure.
While the unit was shutdown, internal wiring inspections were performed on 83 Limitorque valve operators to ensure compliance with environmental qualification requirements.
Additionally, the air blower on the E-3 diesel generator was replaced.
Unit 3 startup began on August 28, but was terminated shortly thereafter, due to blown fuse on the hotwell level controller, resulting in a transfer of condensate to the Condensate Storage Tank (CST).
Subsequently, the level control and instrumentation 8609190284 860831 JJE PDR ADOCK 05000277 ll'
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R PDR l
... 9 Attachment to Monthly Operating Report for August, 1986 Page 2 were modified to provide individual fuses on the condensate panel to minimize the potential for overflowing the CST.
Startup commenced on August 29, and the turbine-generator was placed on line August 30.
Unit 3 ended the report period operating at 87%.
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Docket No. 50-277 Attachment to Monthly Operating Report for August, 1986 UNIT 2 REFUELING INFORMATION 1.
Nan.e of facility:
Peach Bottom Unit 2 2.
Scheduled date for next refueling shutdown:
February 28, 1987 3.
Scheduled date for restart following refueling:
May 30, 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 December 12, 1986.
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 procedure.9:
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 is scheduled for completion by January 31, 1987.
Docket No. 50-277 Attachm2nt to 1
Monthly Operating Report for August, 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 poo'. assuming the relicensed capacity, subsequent to the completion of the new fuel racks installation:
March, 1995 (March,.1998, with reserve full core discharge) 4 L
_ _ ~... -.,
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Docket No. 50-278 Attachmant to Monthly Operating Report for August, 1986 UNIT 3 REFUELING INFORMATION 1
1.
Name of facility:
Peach Bottom Unit 3 2.
Scheduled date for next refueling shutdown:
September 12, 1987 3.
Scheduled date for restart following refuelirg:
September 10, 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 Amendcent 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
Docket No. 50-278 Attachm:nt to Monthly Operating Report for August, 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 wnich increases the licensed fuel pool capacity to a total of 3819 fuel bundles in each fuel pool.
This modification will be implemented following completion of a similar change for Unit 2.
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) r_
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AVCASE DAILY 1981T PEMER LEVEL DOCKET HD. 50 277 (MIT PEACH BOTTON L941T 2 DATE SEPTEfEER 15, 1986 COMPANY PHILADELPHIA ELECTRIC COMPANY W.H.ALDEN ENGINEER-IN-CHARGE LICEN5ING SECTION EfCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022 NOPUM AUGUST 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (P0fE-NET)
(PedE-NET) 1 1939 17 0
2 1037 18 0
3 1941 19 0
4 1940 20 0
5 1042 21 0
6 1942 22 0
7 117 23 0
8 0
24 0
9 0
25 0
10 0
26 1
11 0
27 361 12 0
28 850 13 0
29 972 14 0
30 978 15 0
31 922 16 0
AVERAGE DAILY WIT POWE] LEVEL DOCKET De. 50 - 278 LMIT PEACH BOTTOM WIT 3 DATE SEPTEISER 15, 1986 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICEN5ING SECTION 18JCLEAR GENERATION DIVISIDH TELE. N (215) 841-5022 MONTH AUGUST 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL E F5dE-NETI (PteE-NETI I
O 17 0
2 251 18 0
3 638 19 0
4 837 20 0
5 830 21 0
6 926 22 0
7 884 23 0
8 878 24 0
9 891 25 0
10 869 26 0
11 178 27 0
12 0
28 0
13 0
29 0
14 0
30 421 15 0
31 825 u
l
OPERATING DATA REPORT DOCKET ND. 50 - 277 DATE SEPTEPBER 15, 1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY N.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION WCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022 OPERATING STATUS
- 1. LMIT NAMES PEACH BCTTOM UNIT 2 l HOTES: tMIT 2 EXPERIENCED ONE l
l
- 2. CEPORTING PERIODI AUGUST, 1986 l
FORCED 58UTD0bM APO ONE l
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- 3. LICENSED THERMAL PUNERIteiTI 3293 l
SCHEDULED LOAD REDUCTION.
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- 4. NAMEPLATE RATING (EROSS P9dE):
1152 l
l l
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- 5. DESIGN ELECTRICAL RATING INET tedE):
1065 l
l l
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- 6. MAXIttJM DEPEteABLE CAPACITY (GROSS PedE)* 1998 l
l l
l
- 7. MAXIttJM DEPEteABLE CAPACITT (HET tedE):
1051 l
l
- 8. IF CHANGES OCCtm IN CAPACITY RATINGS (ITEMS PARBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL 70 le1ICH RESTRICTED, IF ANY (HET t9dE)*
- 10. REASONS FOR RESTRICTIONS. IF ANY8 THIS MONTH YW-TO-DATE CUMULATIVE
- 11. NOLRS IN REPORTING P;RIOD 744 5,831 106.583
- 12. PARBER OF NOL5tS REACTOR NAS CRITICAL 289.2 4,689.9 69,884.1
- 13. CEACTOR RESERVE SNUTD0let NOURS 0.0 0.0 0.0
- 13. NotRS GENERATOR ON-LINE 270.2 4,544.0 67,672.8
- 15. tMIT RESERVE SNUTD0 bet NOLRS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (Ptet) 797,880 13,770.062 200.036.577
- 17. GROSS ELECTRICAL ENERGY GENERATED (Ptoll 262.070 4.548.530 65.761.490
- 18. NET ELECTRICAL ENERGY GENERATED (ttet) 246,062 4.376.087 62.968.382
- 19. LMIT SERVICE FACTOR 36.3 77.9 63.5
_,_.r
Docket No. 50-277
- 20. LMIT AVAILABILITT FACTOR 35.0 50.5 68.1
- 21. LMIT CAPACITT FACTON EUSING tec HET) 25.6 40.7 60.2
- 22. UNIT CAPACITT FACTOR IUSING DER NET) 24.9 39.5 58.5
- 23. LMIT FORCED OUTAGE RATE 65.0 23.4 7.9 ti. SHUTD06045 SCHEDULED DVER NEXT 6 MONTHS (TTPEe DATE. Ape DURATION OF EACH)2 SAFE-Ete/ PIPE WELD INSPECTION JAPRAARY 3,1967 TO JAPAJARY 23, 1967
- 25. IF SHUTD0let AT Ele OF REPORT PERIOD, ESTIMATED DATE OF STARTUP*
- 26. LMITS IN TEST STATUS (PRIOR TO CDPMERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITT 08/07/74 INITIAL ELECTWICITT
_.__/_01/ 74 09 CorMERCIAL OPERATION
____/23/74 12 e
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e OPE ~ATING DATA REPORT DOCKET ND. 50 - 278 DATE SEPTEIBER 15, 1986 COMPLETED BT PHILADELPHIA ELECTRIC COMPANT
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st.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION 14JCLEAR GENERATION DIVISION TELEPHONE I2151 841-5022 OPERATING STATUS
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- 1. 1MIT NAME8 PEACH BOTTOM (MIT 3 l HOTES IMIT 3 EXPERIENCED TWO l
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- 2. REPORTING PERIOct AUGUST, 1986 l
FORCED REACTOR SCRAM l
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- 3. LICENSED THERMAL POWERIP0fTit 3293 l
SHUTD0letS.
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- 4. NAMEPLATE RATING (GROSS 70dEls 1152 l
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- 5. DESIGN ELECTRICAL RATING INET ft4Els 1065 l
l 1
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- 6. MAXIltM DEPEleABLE CAPACITY (GROSS 19dEls 1098 l
l l
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- 7. MAXIltM DEPEteABLE CAPACITY (HET P0 fels 1035 l
l 8.~ IF CHANGES DCCl#l IN CAPACITT RATINGS (ITEMS DAJISER 3 THROUGH 71 SINCE LAST REPORT. GIVE REASONSI t
- 9. POWER LEVEL TO letICH RESTRICTED IF ANT ENET PO4Eli
- 10. REASONS FOR RESTRICTIONS. IF ANYt THIS MONTH YW-TO-DATE CUPEILATIVE
- 11. HOURS IN REPORTING PERIOD 744 5,831 102.479
. ~..___
- 12. PARSER OF HOL5tS REACTOR MAS CRITICAL 307.2 3,235.0 71.848.2
- 13. REACTOR RESERVE 54UTD0l#4 NotAIS 0.0 0.0 0.0 1%. HOURS GENERATOR ON-LINE 260.5 2,942.0 69,7 %.4
- 15. LMIT RESERVE SHUTD0let HOL5tM 0.0 0.0 0.0
- 16. GROSS THERMAL ENERST GENERATED (ftell 677,880 7.992.485 202.989.149
- 17. GROSS ELECTRICAL ENERGT GENERATED Iftet) 211.200 2.580.150 66.573.820 IS. NET ELECTHICAL ENERGT GENERATED (f9M) 197.303 2.454.990 63.847,731
- 19. LMIT SERVICE FACTOR 35.0 50.5 68.1 i
a
Docket No. 50-278
- 20. WIT, AVAILABILITY FACTOR 36.3 77.9 63.5
- 21. WIT CAPACITY FACTOR IUSING f9C NET) 31.5 71.4 56.2
- 22. UNIT CAPACITY FACTOR (U5ING DER NET) 31.1 70.5 55.5
- 23. WIT FORCED OUTAGE RATE 63.7 20.0 13.5
- 24. SHUTD0lef5 SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE. APG DIAEATION OF EACHis CEFUELING OUTAGE FEBRUARY 28, 1987 TO MAY 30, 1987
- 25. IF SHUTD0 led AT EPs OF REPORT PERICO, E5TIMATES DATE OF STARTUPI
- 26. WITS IN TEST STATUS (PRIOR TO COP 91ERCIAL OPERATIONlt FORECAST ACHIEVED INITIAL CRITICALITY
___.___/_7 3 09/16 INITIAL ELECTRICITY
_../18 /.74 02 COPf1ERCIAL OPERATION
_../.05 /74 07 4
(MIT SHUTD0tNS AM POWER REDUCTIONS DOCKET NO. 50 - 277 LMIT NAME PEACH BOTTOM LMIT E DATE SEPTEPEER 15, 1966 REPORT MONTH AUGUST 1966 COMPLETED BY PHILADELPHIA ELECTRIC COMPANT N.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTICH I4JCLEAR GENERATION DIVISIDH TELEPHONE (2151841-5022 l
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lTTPElDLRATIONlREASONISHUTTING D0lNl EVENT l CODE l CODE l ACTIDH TO NO.I DATE l (131 (HOURSll (2) l REACTOR (3) l REPORT 3.
l (4) l (5) l PREVENT RECURRENCE
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I 27 l 860807 l F l 473.8 l A l 1
l 2-86-19 l CE l VALVEX l MANUAL SHUTD0lN DUE TO RCIC TESTABLE CHECK l
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1 (1)
(2)
(3)
(4)
F. FORC O REASON METHOD EXHIBIT G - INSTRUCTIONS S - SCHEDULED A. EGUIPMENT FAIL (EE (EXPLAIN)
- 1. MAPAJAL FOR PREPARATION OF DATA B. MAINTENANCE OR lf*'"
2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LER) 0 - REGULATORT RESTRICTION 4 - OTHER (EXPLAIN)
FILE (HUREG-0161)
E - OPERATOR TRAINING e LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G. OPERATIONAL ERROR (EXPLAIN)
N - OTHER(EXPLAIN)
EXHIBIT I. SAME SOURCE L
n_-_--_________
Y LMIT SHUTD0ledS AM POWER REDUCTIONS DOCKET NO. 50 - 278 tMIT NAME PEACH BOTTOM LMIT 3 DATE SEPTEPBER 15, 1986 REPORT MONTH AUGUST, 19%
COMPLETED BT PHILADELMtIA ELECTRIC COMPANY N.M. ALDEN I
ENGINEER-IN-CHARGE LICENSING SECTION BRACLEAR GENERATION DIVISION TELEPHONE (215) 841-5022 o.._
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l METHOD OF l LICENSEE ISYSTEMICOMPONENTl CAUSE AM CORRECTIVE l
lTYPElDWATIONlREASONISHLfrTINE D0leil EVENT l CODE I CODE l ACTION TO G.1 DATE l (1)I (HOWSil (2) l REACTOR (3) l REPORT # 1 (4) l (5) l PREVENT RECWRENCE 0
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1 3-86-16 l ED l CKTBRK l REACTOR SCRAM FROM 87% POWER ON NIEN NEUTWON l
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l l FLUX AS A RESULT OF THE TRIP OF THE 83 STARTUP l
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l l FEED BREAKER letICH CAUSED THE FAST CLDSWE OF l
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1 3-86-18 l HA l CKTBRK I REACTOR SCRAM FROM 86% POWER ON LOW REACTOR l
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l l HATER LEVEL AS A RESULT OF THE TRIP OF THE "A" l
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l l STATOR COOLANT Am 364 BYS BREAKERS te(ICN.
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l TRIPPED THE "A" As "C" REACTOR FEED PLMP 1
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(33 (4)
J= FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS p. SCHEDUu.
A E==nr FAI=E iExPuIN) 1 - MA-t
- - - AT10N OF DATA B - MAINTLNANCE OR TEST 2. MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LER)
D - REGULATORY RESTPICTION 4 - OTHER (EXPLAIN)
FILE ( M EG-0161)
E - OPERATOR TRAIL NG + LICENSE EXAMINATION t
F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
N - OTHER(EXPLAINI ENHIBIT I - SAME SOLRCE
PHILADELPHIA ELECTRIC COMPANY 23O1 MARKET STREET P.O. BOX 8699 PHILADELPHIA PA.19101 September 15, 1986 (2151841 4000 5,
i Docket Nos. 50-277 50-278 Director
'I s.
Office of Inspection & Enforcement US Nucleat Regulatory Commission Washington, DC 20555
^
Attention:
Document Control Desk e
SUBJECT:
Peach Bottom AtoElic. Power Station Monthly Operating Report Gentlemen:
Attached are twelve copies of the monthly ope. rating report for Peach Bottom Units 2 and 3 for the month of August, 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 5
Nuclear Generation Division Attachment cc:
Dr.
T.
E. Mdrley, NRC Mr. T.
P. Johnson, Resident Inspector Mr. Stan P. Mangi, Dept. of Envir. Resources Mr.
P. A. Ross, NRC (2 copies)
G.
E. Gears, NRC Project Manager Mr. Thomas Magette, Maryland Power Plant Siting INPO Records Center 4
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