Text

Monthly Operating Repts for Apr 1986
	ML20205P495
Person / Time
Site:	Peach Bottom
Issue date:	04/30/1986
From:	Alden W, Logue R; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	NUDOCS 8605210432
	Download: ML20205P495 (17)
	v • d • e

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Docket Nos. 50-277/50-278 Attachment to Monthly Operating Report for April, 1986 Page 1 Peach Bottom Atomic Power Station Narrative Summary of Operating Experience April, 1986 UNIT 2 The unit operated at 100% power until April 5, when load was reduced to 75% power with control rod 06-35 blocked in the full-in position to replace the nitrogen accumulator block valve on the hydraulic control unit.

Repairs were completed and full power was restored that same day.

On April 13, load was reduced to 65% to accommodate condenser tube leak inspections.

Two leaks were repaired in the B-1 waterbox, and the unit was returned to full power.

The same day, an explosion occurred in the "A" phase of the #1 Transformer in the North Substation, causing a fire which resulted in damage to the "B" phase transformer and to control cables for some breakers in the substation, resulting in the loss of the Unit 3 startup feed.

In response to the loss of the Unit 3 startup feed, the E-2 diesel generator was started to supply some of the load normally supplied by the Unit 3 startup bus.

While operating at rated speed, a speed switch failed, requiring the E-2 diesel generator to be manually tripped.

Continued operation of the plant was permissible provided the emergency core cooling system remained operable.

On April 14, load was reduced to 600 MWe at the load dispatcher's request in order to maintain transmission stability until the North Substation repairs could be completed.

On April 16, a controlled shutdown was initiated when the "A" core spray pump was declared inoperable due to the failure of the "A" minimum flow valve during surveillance testing coincident with the inoperability of the E-2 diesel generator.

The valve was repaired the same day and the'"A" core spray pump was declared operable.

The speed switch was replaced and the E-2 diesel generator was returned to service on April 16.

Shutdown was terminated at 980 MWe, and load recovery began the same day.

Full power was achieved on April 17.

On April 23, an automatic scram from 100% power occurred as a result of combined intermediate valve (CIV) #1 closure while testing CIV #2, causing generator lockout.

The closure of the #1 CIV was caused by air trapped in a hydraulic control line between the disc dump and the solenoid valve.

The air pocket allowed a 8605210432 860430 PDR ADOCK 05000277 R

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Attcchment to Monthly Operating Report for April, 1986 Page 2 hydraulic transient to occur during the testing of the #2 CIV, causing reduction of electro-hydraulic control oil pressure which was sufficient to cause the closure of the #1 CIV.

EHC oil pressure was subsequently restored.

The unit remained shutdown to repair the reactor feed pump (RFP) minimum flow valves.

Reactor startup began on April 26, and the turbine-generator was returned to service April 27.

Full load was achieved on April 29.

The unit ended the report period with load reduced for a control rod pattern adjustment.

Unit 3 The unit began the report period increasing in power following the return of the 3B recirculation pump motor-generator (M-G) set to service.

On April 2, load was reduced to 600 MWe for condenser waterbox inspections and control rod pattern adjustment.

Two leaks in the C-1 waterbox were found and repaired.

The unit returned to full power on April 8.

On April 9, load was reduced to 700 MWe for condenser tube leak inspections.

Leaks were found and repaired in the A-2 and B-1 waterboxes.

On April 11, the unit was shutdown for a mini-outage to repair the three reactor feed pump minimum flow valves.

An automatic scram on low reactor water level occurred with the unit in hot shutdown, due to the inability of the Reactor Core Isolation Cooling (RCIC) system to maiptain level during water level fluctuations which occurred while shutting down.

The RCIC system had been placed into service for level control after the last reactor feedpump was removed from service, due to the lack of minimum flow protection on the feedpumps.

While the unit was shutdown, the #1 transformer in the North Substation exploded and the associated oil fire resulted in the loss of Unit 3 startup feed and North Substation operability.

Work associated with the RFP minimum flow valve repairs was completed on April 14.

Unit 3 was returned to service on April 23.

Due to the extent of the damage to the #1 transformer, plans are being evaluated whether to repair or to replace the transformer.

Another transformer was installed prior to the explosion during the Unit 3 refueling outage.

At the time of the explosion, it was being used to supply the Unit 3 startup feed, which was

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Attachmsnt to Monthly Operating Report for April, 1986 Page 3 previously supplied by the #1 transformer.

It will continue to be used as the Unit 3 startup source.

On April 26, a reactor scram from 80% power occurred as a result of a turbine trip caused by testing of the #65 breaker in the North Substation.

Reactor startup began on-April 27 and the turbine generator was returned to service on April 28.

Unit 3 ended the report period operating at full power.

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Docket No. 50-277 Attachment to Monthly Operating Report for April, 1986 REFUELING INFORMATION 1.

Name of facility:

Peach Bottom Unit 2 2.

Scheduled date for next refueling shutdown:

February 28, 1987 3.

Scheduled date for restart following refueling:

May 29, 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 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 i

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.

I

DockGt No. 50-277 Attcchm2nt to Monthly Operating Report for April, 1986 Page 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, 1995 (March, 1998, with reserve full core discharge)

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i Docket No. 50-278 4'

Attachment to Monthly Operating Report for April, 1986 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.

l If answer is yes, what, in general, will these be?

Technical Specifications to accommodate reload fuel.

Modifications to reactor core operating limits.

1 5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

j Reload 7 License Amendment to be submitted January 7, 1988 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design l

or performance analysis methods, significant changes in fuel i

design, new operating procedures:

i i

None expected.

7.

The number of fuel assemblies (a) in the core and (b) in the 1

spent fuel storage pool:

(a) Core - 764 Fuel Assemblies (b) Fuel Pool - 1496 Fuel Assemblies, 6 Fuel Rods i

2 1

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Dockst No. 50-278 AttcchE3nt to Monthly Operating Report for April, 1986 I

Page 2 REFUELING INFORMATION (Continued) h 8.

The present licensed spent fuel pool storage capacity and the i

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 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) i l

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AVEIAGE DAILY UNIT POWEJ LEVEL DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE MAY 15.1986 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CNARGE LICENSING SECTION NUCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022 MONTH APRIL 1946 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1t04E-NETI (MWE-NETI 1

1078 17 1043 2

1078 18 1952 3

1073 19 1067 4

1074 20 1075 5

1024 21 1074 6

1969 22 1077 7

1073 23 944 8

1071 24 0

9 1071 25 0

10 1071 26 0

11 1973 27 422 12 1070 28 918 13 801 29 1955 14 7%

30 1037 15 690 16 995

7 AVERAGE DAILY WIT POWER LEVEL DOCKET HO. 50 276 UNIT PEACH BOTTOM WIT 3 DATE MAY 15.1966 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTIOH NUCLEAR GENERATI0H DIVISIDH TELEPHONE I215) 841-5022 MONTH APRIL 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL iISIE-NET )

ENWE. NET) 1 803 17 0

t 914 16 0

3 608 19 0

4 649 20 0

5 726 21 0

6 855 22 0

1 7

949 23 0

6 1032 24 64 9

873 25 663 10 664 26 293 11 573 27 0

12 0

28 559 13 0

29 831 14 0

30 2003 15 0

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1. LMIT HAME: PEACH BOTTOM UNIT 2 i NOTES 8 UNIT 2 EXPERIENCED ONE AUTO l

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2. REPORTING PERIODI APRIL 1966 l

SCRAM TWO FORCED LOAO l

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3. LICENSED THERMAL FCHER(tedTit 3E93 l

REDUCTIONS APG THREE l

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4. HAMEPLATE RATING (GROSS PG4Elt 1152 l

SCHEDULED LOAO REDUCTIONS.

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5. DESIGN ELECTRICAL RATING (HET IS4Els 1965 l

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6. MAXIPRJM DEPEteA8LE CAPACITY IGROSS 994Elt 1998 l

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7. MAXIMUM DEPEtWA8LE CAPACITY (HET 194Elt 1951 l

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8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS HUteER 3 THROUCH 7) SINCE LAST REPORT. GIVE REASON 58

9. POWER LEVEL TO 64(ICH RESTRICTEDe IF ANY (HET PG4Eli

10. CEASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH VR-TO-DATE CLMULATIVE 1

11. HOURS IN REPORTING PERIOD 719 2.879 103.631

11. HUPRER OF HOURC REACTOR HAS CRITICAL 652.6 2.337.7 67.531.9

13. REACTOR RESERVE SHUTD06H HOURS 0.0 0.0 0.0

14. HOURS GENERATOR ON-LINE 642.7 2.272.2 65,401.0

15. UNIT RESERVE SHUTD0684 HOURS 0.0 0.0

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16. GROSS THERMAL ENERGY GENERATED (1980 1.972.992 6e731.174 192.997.649

17. GROSS ELECTRICAL ENERGY GENERATED (PteH 664.640 2.226.820 63.439 780

18. NET ELECTRICAL ENERGY GENERATED (PteH 643.562 2.153.055 60.745 350

19. (MIT SERVICE FACTOR 89.4 78.9 63.1

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20. WIT AVAILASILITT FACTOR 89.4 78.9 63.1

21. WIT CAPACITY FACTOR (USING 99C iTT) 85.2 71.2 55.8

22. UNIT CAPACITY FACTOR IUSINS DER NET) 84.0 70.2 55.0

23. WIT FORCEO OUTAGE RATE 10.6 17.6 13.2

24. SHUTD06845 SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AhD DURATION OF EACHit

25. IF SHUTD0 led AT Ele OF REPORT PERIOD, ESTIMATED DATE OF STARTUP8

26. UNITS IN TEST STATUS (PRIOR TO CotttERCIAL OPERATIONil FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 COMMERCIAL OPERATIN 07/05/84 O

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DOCMET NO. 50 - 278 DATE MAY 15 1986 i

COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION NUCLEAR GENERATION DIVISION TELEPHONE I215) 841-5022 j

i OPERATING STATUS i

1. WIT HAMEt PEACH BOTTOM WIT 3 l NOTES WIT 3 EXPERIENCED TWO l

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NEDUCTIONS.

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5. DESIGN ELECTRICAL RATING INET PS4Elt 1965 l

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9. POWER LEVEL 70 leIICH RESTRICTED IF ANY INET PS4Els J

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THIS MONTH TR-TO-DATE CL#tJLATIVE i

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11. H0tAIS IN REPORTING PERIOD 719 te879 99.547 i

1E. SAJPRER OF HOURS REACTOR WAS CRITICAL 404.1 1.025.9 69.639.1 4

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13. REACTOR RESERVE SHUTD0604 HOLAtS 0.0 0.0 0.0

14. NOURS SENERATOR ON-LINE 374.7 769.3 67.683.7 1

15. WIT RESERVE SHUTD0bei HOURS 0.8 0.0 0.0 l

16. GROSS THERMAL ENERST SENERATED 19901) 942,936 1,535.765 196.532,429 1

17. GROSS ELECTRICAL ENERGY SENERATED It001) t99e720 464e950 64e454e620 i

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14. NET ELECTRICAL ENER6Y SENERATED (Pteil 187.811 433,399 61.446.100

19. WIT StRVICE FACTOR 52.1 26.7 67.9 1

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20. tR41T AVAILABILITY FACTOR 53.8 27.1 68.0

21. LMIT CAPACITY FACTOR (USING PmC NET) 38.7 14.5 60.0 i

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22. UNIT CAPACITY FACTOR (USING DER HET) 37.6 14.1 56.3

23. UNIT FORCED OUTAGE RATE 11.3 14.4 7.2

24. SHUTD00445 SCHEDULED OVER HEXT 6 MONTHS ITYPE. DATE. ape DURATION OF EACHit o

25. IF SHUTD0644 AT EM OF REPORT PERIOD, ESTIHATED DATE OF STARTUP

26. UNITS IN TEST STATUS (PRIOR TO COPMERCIAL OPERATIONil FORECAST ACHIEVED J

INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 COPMERCIAL OPERATION 12/23/74 i

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6 UNIT SHUTD06#45 AND POWER REDUCTIONS DOCMCT HO. 50 277 LMIT NAME PEACH BOTTOM WIT 2 DATE MAY 15.19M REPORT MONTH APRILe 19 %

COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION HUCLEAR GEHERATION DIVISIDH TELEPHONE (215) 841-50E2 c................................................................................................

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I O2 l 660430 i Sl 0.0 l

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O - FORCED REASON METHOU EXHIBIT G. IHSTRUCTIONS S - SCHEDULED A - EQUIPMENT FAILURE (EXPLA!HI 1 - MANUAL FOR PREPARATI0H 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 (EXPLAINI FILE (HUREG-0161)

E. OPERATOR TRAINING + LICENSE EXAMIHATION F - ADMINISTRATIVE (5) i G - OPERATIONAL ERROR (EXPLAIH)

H - OTHER(EXPLAIH)

EXHIBIT I - SAME SOURCE b

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(MIT SNUTD06MS AM POWER REDUCTIONS DOCKET NO. 50 - E76 1

UNIT NAME PEACH BOTTOM UNIT 3 OATE MAT 15 1966 REPORT MONTH APRIL, 19M COMPLETED BY PHILAOELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE

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LICENSING SECTIDH HUCLEAR GENERATION DIVISIM4 TELEPHONE (E15) 641-50EE i

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1 3-64-10 l CH I VALVEX l AUTOMATIC REACTOR SCRAM SIGNAL RECEIVED OURING l

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B - MAINTENANCE OR TEST E. MANUAL SCRAM.

ENTRT SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT ILERI D - RESULATORT RESTRICTION 4 - OTHER ttXPLAINI FILE INURES-Stell E - OPERATOR TRAINN5 6 LICENSE EXAMINATION F - ADMINISTRATIVE (5)

S - OPERATIONAL ERR 04 (EXPLAINI N - OTHERIEXPLAINI EXHIBIT I - SAME SOURCE

L PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA, PA.19101 May 15, 1986 12151841-4000 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 April, 1986, forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

Very truly pours,

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R.

H. Logue Superintendent Nuclear Services Attachment cc:

Dr. T.

E. Murley, NRC Mr. T. P. Johnson, Resident Inspector Mr. Stan P. Mangi, Dept. of Envir. Resources Mt. P. A. Ross, NRC (2 copies)

Mr. Thomas Magette, Maryland Power Plant Siting INPO Records Center i

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ML20205P495

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