ML20215H318
| ML20215H318 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/31/1987 |
| From: | Alden W, Middleton L PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8704200260 | |
| Download: ML20215H318 (15) | |
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Peach Bottom Atomic Power Station Narrative Summary of Operating Experience March, 1987 UNIT 2 Unit 2 began the report period operating at 85% limited by the inoperability of the
'A' feedwater heater string.
On March 13, Unit 2 was shutdown for its seventh refueling outage.
The outage is scheduled for completion on May 23, 1987.
UNIT 3 Unit 3 operated at 100% power until March 5, when a shutdown was initiated as a result of a hydrogen leak from the main generator.
Investigation revealed that a sample valve was the source of the hydrogen leak.
Repairs were completed and startup commenced on March 10 and the turbine-generator was synchronized to the bus on March 11.
On March 14, load was reduced to 600 MWe for control rod pattern adjustment.
Full load was recovered on March 16.
Later the same 4
day, a tube leak was identified in the 'C2' feedwater heater.
The
'C' feedwater heater string was removed from service and load was limited to 85% power.
On March 17, an autouatic reactor scram occurred on high neutron flux.
Investigations did not immediately reveal the cause of the scram; however, the main turbine electrohydraulic control (EHC) system was suspected of malfunctioning since the pre-scram plant parameter oscillations were accompanied by fluctuations of reactor pressure and steam flow.
While EHC system investigation continued, repairs were performed on the 'C2' feedwater heater.
No problems were identified with the EHC and startup commenced on March 21 with plans to hold power at it to perform dynamic troubleshooting on th9 EHC system if the problem reappeared.
4 Later on March 21, startup was suspended when turbine bypass valve oscillations concurrent with reactor pressure and level fluctuations were observed.
A defective EHC system steam pressure regulator was determined to be the cause of the oscillations.
Startup was resumed on March 24 and recurrence of the il turbine bypass valve oscillations were observed.
Reactor power was held at it while dynamic troubleshooting of the EHC system was in progress.
On March 25, an autcmatic reactor scram on low level occurred as a result of lifting leads in the EHC control cabinet while troubleshooting the cause of the turbine bypass valve oscillations.
After further investigation, it was determined that defective cabinet cooling fans caused the electronic components in the EHC system to malfunction which in turn resulted in erratic EHC pressure control system operation.
The five defective fans were replaced with the intention of qY)g 8704200260 B70331 j
I PDR ADOCK 03000277 g
PDR L
Attachm2nt to Monthly Operating Report for March, 1987 Page 2 replacing the other control cabinet fans during the upcoming refuel outage.
Startup was resumed and the turbine-generator was synchronized to the bus on March 27.
Full load was restored on March 31.
Common On March 31, the NRC issued orders for an immediate plant shutdown based on allegations that control room operators had been observed sleeping while on duty and were otherwise inattentive to their license obligations.
Unit 3 achieved cold shutdown on April 1; meanwhile, Unit 2 was in shutdown since March 13, 1987 for refueling.
Both units will remain shutdown until a comprehensive plan and schedule to accomplish the plan is submitted to the NRC for its approval, to assure that the facility will safety operate and comply with all requirements including station procedures.
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DockGt No. 50-277 Attachment to Monthly Operating Report for March, 1987 UNIT 2 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 2 2.
Scheduled date for next refueling shutdown:
March 13, 1987 3.
Scheduled date for restart following refueling:
May 23, 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 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 pools (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.
l' Docket No. 50-277 l
Attcchm3nt to l
Monthly Operating Report for March, 1987 Page 2 l
l UNIT 2 REFUELING INFORMATION (Continued)
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9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present 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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Docket No. 50-278 Attachment to Monthly Operating Report for March, 1987 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:
June 17, 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.
S.
Scheduled date(s) for submitting proposed licensing action and supporting information:
Reload 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 pools (a) Core - 764 Fuel Assemblies (b) Fuel Pool - 1496 Fuel Assemblies, 6 Fuel Rods w
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Dockot No. 50-278 Attachment to Monthly Operating Report for March, 1987 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 began on February 20, 1987 and should be completed in mid July, 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)
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AVERAGE DAILY WIT POMER LEVEL DOCKET NO. 50 - 277 WIT PEACH BOTTOM WIT 2 DATE APRIL 15,1987 COMPANY FMILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION PAJCLEAR SUPPORT DEPARTMENT TELEPHONE I215) 841-6374 MONTH MARCH 1987 DAY AVERAGE DAILY PCHER LEVEL DAY AVERAGE DAILY P0HER LEVEL IPME-NETI
( 794E-NET I 1
896 17 0
2 892 18 0
3 892 19 0
4 889 20 0
5 894 21 0
6 885 22 0
7 881 23 0
8 882 24 0
9 890 25 0
10 885 26 0
11 895 27 0
12 892 28 0
15 619 29 0
14 0
30 0
15 0
31 0
16 0
AVERAGE DAILY WIT PONER LEVEL
/
DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE APRIL 15,1987 COMPANY PHILADELPHIA ELECTRIC CCHPANY
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L. L. MIDDLETON
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TECHNICAL ASSISTANT s
LICENSING SECTION NUCLEAR SUPPORT DEPARTHEhT TELEPHONE 1215) 841-6374 4-HONTH MARCH 1987
- DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY P0HER LEVEL (P9tE-NET)
( t94E-NET )
1 1069 17 98 2
1070 18 0
5 1072 19 0
4 1071 20 0
5 758 21 0
6 0
22 0
7 0
23 0
8 0
24 0
1.
9 0
25 0
10 0
26 0
11 112 27 150 12 714 28 591 13 993 29 687 14 722 30 932 15 908 31 595 16 1010
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OPERATING DATA REPORT DOCKET No. 50 - 277 DATE APRIL 15,1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 OPERATING STATUS
/.
- 1. LMIT NAMEt PEACH BOTTON LNIT 2 1 NOTESt UNIT 2 BEGAN l
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- 2. REPORTING PERIOct MARCH, 1987 l
REFUELING ON l
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- 3. LICENSED THERMAL PONER(tMT):
3293 l
HARCH 13, 1987.
l l
l
- 4. NAEPLATE RATING (GROSS tMEls 1152 l
l 1
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- 5. DESIGN ELECTRICAL RATING I E T PME):
1065 l
l l
- 6. MAXIPRJM DEPENDABLE CAPACITY tGROSS PNE II 1098 l
l l,
i
- 7. MAXIttJH DEPENDABLE CAPACITY INET INE)*
1051 l
l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS IITEMS NUteER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSI
- 9. P0HER LEVEL TO NHICH RESTRICTED, IF ANY (NET tWEls
- 10. REASONS FOR RESTRICTIONS, IF ANY h THIS MONTH VR-TO-DATE CUMULATIVE i
t.
744 2,160 111,672
- 11. HOURS IN REPORTING PERIOD i
12.14ASER OF HOURS REACTOR NAS CRITICAL 313.8 1,729.8 74,1 %.8
- 13. REACTOR RESERVE SHUTDODN HOURS 0.0 0.0 0.0 1% HOURS GENERATOR ON-LINE 308.0 1,724.0 71,866.8
- 15. LMIT RESERVE SHUTDatN HOURS 0.0 0.0 0.0 4,979,376 212,810,745
- 16. GROSS THERMAL ENERGY GENERATED ttNH) 848,928
- 17. GROSS ELECTRICAL ENERGY GENERATED tlWHI 279,470 1,648,230 70,019,230
- 18. ET ELECTRICAL ENERGY GENERATED IPMH) 267,400 1,599,912 67,088,772 PAGE 1 0F 2
OPERATING DATA REPORT (CONTIPAJEDI DOCKET No. 50 277
+
)
. I' DATE APRIL 15,1987 THIS MONTH YR-TO-DATE CLHJLATIVE
- 19. WIT SERVICE FACTOR 41.4 79.8 64.4
- 20. WIT AVAILABILITY FACTOR 41.4 79.8 64.4
- 21. WIT CAPACITY FACTCR IUSING MDC NET) 34.2 70.5 57.2
- 22. WIT CAPACITY FACTOR tuSING DER NET) 33.7 69.5 56.4
- 23. UNIT FORCED OUTAGE RATE 0.0 0.0 13.3 2). SHUTCortaS SCHEDULED DVER NEXT 6 MotiTHS ITYPE, DATE, AND DURATION OF EACHis s
REFUELIN) OUTAGE MARCH IL,1987 To MAY 23,1987
- 25. IF SHUltMe4 AT Etl0 0F REPORT PERIOD, ESTINATED DATE '3F STARTUP8 INDETERMINATE UNTIL NRC ORDER IS SATISFIED.
- 26. WITX7FTEST STATUS IPRIOR TO CormERCIAL OPERATIOF
- FORECAST ACHIEVED 3
INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 CDPMERCIAL OPERATION 07/05/74
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OPERATING DATA REPORT DOCKET NO. 50 - 278 DATE APRIL 15,1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION MJCLEAR SUPPORT DEPARTMENT TELEPHONE t215) 841-6374 OPERATING STATUS
- 1. WIT NAE t PEACH BOTTOM WIT 3 l NOTES: WIT 3 EXPERIENCE THREE l
l l
- 2. REPORTING PERIOD MARCH, 1987 l
FORCED SHUTD0694S.
l l
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- 3. LICENSED THERMAL P0HERIM(T):
3293 l
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- 4. NAMEPLATE RATING IGROSS NtE38 1152 l
l l
l
- 5. DESIGN ELECTRICAL RATING I E T NtElt 1065 l
l l
l
- 6. MAXItt#1 DEPENDABLE CAPACITY tGROSS 194E) 1098 l
l l
l
- 7. MAXIMJM DEPENDABLE CAPACITY IET 99tE18 1035 l
l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUPSER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSI
- 9. PONER LEVEL TO NHICH RESTRICTED, IF ANY INET 994Elt
- 10. REASONS FOR RESTRICTIONS, IF ANY THIS MONTH YR-TO-DATE CLMULATIVE
- 11. HOURS IN REPORTING PERIOD 744 2,160 107,568
- 12. MASER OF HOURS REACTOR NAS CRITICAL 505.4 1,823.2 76,355.7
- 13. REACTOR RESERVE SHUTD0604 HOURS 0.0 0.0 0.0
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- 14. HOURS GENERATOR ON-LINE 353.8 1,659.6 73,929.3
- 15. WIT RESERVE SHUTD0694 HOURS 0.0 0.0 0.0 I
l
- 16. GROSS THERMAL ENERGY GENERATED El94H) 997,704 4,759,248 215 278,901
- 17. GROSS ELECTRICAL ENERGY GENERATED tt94H) 310,610 1,555,560 70,611,432
- 18. NET ELECTRICAL ENERGY GENERATED tl94H) 297.610 1,507,719 67,749,812 PAGE 1 0F 2
_... _ _. ~. _ _ _ - _,.. -
_ _.,. ~ -.. _. - --
- ~.
e OPERATING DATA REPORT (CONTIPAJED)
DOCKET NO. 50 - 278 DATE APRIL 15,I987 THIS HONTH YR-TO-DATE CUHULATIVE
- 19. UNIT SERVICE FACTOR 47.6 76.8 68.7
- 20. WIT AVAILABILITY FACTOR 47.6 76.8 68.7
- 21. WIT CAPACITY FACTOR (UGING MDC NET) 38.6 67.4 60.9
- 22. WIT CAPACITY FACTOR (USING DER NET) 37.6 65.5 59.1
- 23. WIT FORCED OUTAGE RATE 52.4 23.2 8.6
- 24. SHUTDom S SCHEDULED OVER NEXT 6 MONTHS iTYPE, DATE, AND DURATION OF EACH)
INDETERMINATE IMTIL HRC ORDER IS SATISFIED.
-25. IF SHUTDO W AT END OF REPORT PERIDO, ESTIMATED DATE OF STARTUP 23.~ WITS IN TEST STATUS (PRIOR TO C0tt1ERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 Cott1ERCIAL OPERATION 12/23/74 PAGE 2 0F 2
e UNIT SHUTDOPO4S AND PONER REDUCTIONS DOCKET NO. 50 - 277
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UNIT NAME PEACH BOTTOM UNIT 2 DATE APRIL 15,1987 REPORT MONTH MARCH, 1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE I215) 841-6374
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(4) 7 - FORCED REASON METH00 EXHIBIT G - INSTRUCTIONS B - SCHEDULED A - EQUIPtENT FAILURE IEXPLAIN) 1 - MANUAL 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 (EXPLAIN)
FILE (PAJREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE I51 G - OPERATIONAL ERROR (EXPLAIN)
H - OTHERIEXPLAIN)
EXHIBIT I - SAME SOURCE N
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LMIT SHUTDo m s AND P0HER REDUCTIONS DOCKET No. 50 - 278 LMIT NAME PEACH BOTTOM UNIT 3 DATE APRIL 15,1987 REPORT MONTH MARCH, 1987 COMPLETED BY PHILADELPHIA ELECTRIC COW ANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 1
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ITYPEIDURATIONIREASONISHUTTING DOW l EVENT l CODE l CODE I ACTION TO I
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[-FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS
) - SCHEDULED A - EQUIPMENT FAILURE IEXPLAIN) 1 - MAPAJAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT ILER) 0 - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)
FILE INUREC-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
H - OTHERIEXPLAIN)
EXHIBIT I - SAME SOURCE
PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA PA.19101 April 15, 1987 (215)0414000 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 March, 1987, 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 LLM:vdw Attachment cc:
Mr. James M. Allan, Acting Administrator, Region I, USNRC Mr. T. P. Johnson, Resident Inspector Mr. Stan P. Mangi, Dept. of Envir. Resources Mr.
P. A. Ross, NRC (2 copies)
Mr. R. J. Clark, NRC Project Manager Mr. Thomas Magette, Maryland Power Plant Siting INPO Records Center oi
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