ML20207P896

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Monthly Operating Repts for Dec 1986
ML20207P896
Person / Time
Site: Peach Bottom  
Issue date: 12/31/1986
From: Alden W, Middleton L
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8701200381
Download: ML20207P896 (13)
v • d • e


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e AVERAGE DAILY WIT PONER LEVEL DOCKET NO. 50 - 277 WIT PEACH BOTTON UNIT 2 DATE JANUARY 15,1987 COMPANY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION PAJCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 NONTH DECEPSER 1986 DAY AVERAGE DAILY poler LEVEL DAY AVERAGE DAILY PONER LEVEL (704E-NETI (P90E-NET 1 1

1074 17-1075 1

1078 18 1073 3

1074 19 1071 0

1075 20 761 5

1076 21 991 6

1072 22 1071 7

1076 23 1077 8

1076 24 1075 9

1077 15 1073 10 1075 26 1073 11 1076 27 1071 It 1075 28 1068 13 1070 29 1071 14 1069 30 1072 15 1074 31 1067 16 1070

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AVERAGE DAILY WIT PtBER LEVEL DOCKET No. 50 - 278 WIT PEACH BOTTOM LMIT 3 DATE JANUARY 15,1987 COMPANY PHILADELPHIA ELECTRIC COMPANY

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L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION MX; LEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 MONTH DECEleER 1986 DAY AVERAGE DAILY PONER LEVEL DAY AVERAGE DAILY PONER LEVEL 479tE-NET 1 IPME-NET 3 1

1068 17 MS 2

1073 18 829 s

3 1023 19 1038 4

M9 20 1052 5

1020 21 1047 6

1004 22 1000 7

1019 23 1030 8

1047 24 1033 9

'1051 25 1033 10 1038 26 741 11 1042 27 933 12 1021 28 80 13 85 29 0

14 0

30 0

15 743 31 0

16 1000 i

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OPERATING DATA REPORT-DOCKET No. 50 - 277 DATE JANUARY 15,1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 OPERATING STATUS

1. WIT NAME PEACH BOTTOM WIT 2 l NOTES: LMIT 2 EXPERIENCED ONE l

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2. REPORTING PERIOD DECEPSER, 1986 l

SCHEDULED LOAD REDUCTION.

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3. LICENSED THERMAL PONERIMT) 3293 l

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4. NAMEPLATE MATING (GROSS PME)8 1152 l

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5. DESIGN ELECTRICAL RATING INET PME):

1065 l

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- 6. MAXIPRM DEPENDA8LE CAPACITY IGROSS WE18 1098 l

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7. MAXIPRM DEPENDA8LE CAPACITY INET PME18 1051 l

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. O. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS PERSER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSI

9. PONER LEVEL TO NHICH RESTRICTED, IF ANY INET ME):
10. REASONS FOR RESTRICTIONS, IF ANY THIS MONTH YR-To-DATE CLMJLATIVE
11. HOURS IN REPORTING PERIOD 744 8,760 109,512
12. PARSER OF HOURS REACTOR NAS CPITICAL 744.0 7,272.8 72,467.0 t

~13. REACTCR RESERVE SHUTDopet HOURS 0.0 0.0 0.0

14. HOURS GENERATOR ON-LINE 744.0 7,014.0 70,142.8
15. LMIT RESERVE SHUTD0Det HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (PMH) 2,411,016 21,564,854 207,831,369
17. GROSS ELECTRICAL ENERGY GENERATED 1.9#1) 812,220 7,158,040 68,371,000
18. IET ELECTRICAL ENERGY GENERATED (PMH) 789,009 6,896,565 65,488,860 PAGE 1 OF 2 f

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' OPERATING DATA REPORT (CONTIMJED)

DOCKET NO. 50 - 277 C

DATE JAPAJARY 15,1987 THIS MONTH YR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 80.1 64.1
20. (A4IT 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 IUSING DER NET) 99.6 73.9 56.2

23. UNIT FORCED OUTAGE RATE-0.0 18.5' 13.6 i

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24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS tTYPE, DATE, AND DURATION OF EACH)

REFUELING OUTAGE FE8RUARY 7,1987 TO MAY 8,1987

25. IF SHUTD0>04 AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPt 04/18/87
26. UNITS IN TEST STATUS (PRIOR TO COPMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 COPMERCIAL OPERATION 07/05/74 i~

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DOCKET NO. 50 - 278 -

DATE JAP 4JARY 15,1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION PAJCLEAR SUPPORT DEPARTMENT TELEPHONE (2151841-6374 OPERATING STATUS

1. UNIT NAME8 PEACH BOTTON UNIT 3 l NOTES: UNIT 3 EXPERIENCE THREE l

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2. REPORTING PERIO0s DECEPBER, 1986 l

FORCE OUTAGES AND TNO I

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3. LICENSED THERMAL PONER(PMT):

3293 l

SCHEDULED LOAD REDUCTION.

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4. HANEPLATE RATING (GROSS PME ls 1152 l

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5. DESIGN ELECTRICAL RATING (NET PME):

1065 l

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6. MAXIMLH DEPENDABLE CAPACITY (GROSS PME)I 1098 l

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7. NAXIPRM DEPENDA8LE CAPACITY INET PME):

1035 l

l C. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS PAABER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSt

9. POM R LEVEL TO NHICH RESTRICTED, IF ANY (E T PME)
10. REASONS FOR RESTRICTIONS, IF ANY8 THIS MONTH YR-TO-DATE CUNULATIVE
11. HOURS IN REPORTING PERIDO 744 8,760 105,408
12. PAABER OF HOURS REACTOR NAS CRITICAL 744.0 5,919.3 74,532.5
13. REACTOR RESERVE SHUTD0bN HOURS 0.0 0.0 0.0

.14. HOURS GENERATOR ON-LINE 614.0 5.415.3 72,269.7

15. (MIT RESERVE SHUTDODM HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATEC (PMH) 1,878,072 15,512,989 210,519,653
17. GROSS ELECTRICAL ENERGY GENERATED (PMH) 616,342 5,062,202 69,055,872
18. NET ELECTRICAL ENERGY GENERATED (PMH) 598,033 4.849,352 66,242,093 PAGE 1 0F 2

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OPERATING DATA REPORT (CCNTINUED)

DCCKET No. 50 - 273 DATE JANUARY 15,1967 THIS MONTH YR-TO-DATE CUMULATIVE

19. LMIT SERVICE FACTOR 82.5 61.8 68.6
20. UNIT AVAILABILITY FACTOR 82.5 61.8 68.6
21. UNIT CAPACITY FACTOR (USING MDC NET) 77.7 53.5 60.7
22. LMIT CAPACITY FACTOR (USING DER NET) 75.5 52.0 59.0
23. LMIT FORCED OUTAGE RATE 16.0 19.9 8.2 ti. SHUTD0DNS SCHEDULED DVER NEXT 6 MONTHS ITYPE, DATE, AND DURATION OF EACHit
25. IF SHUTDOW AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPI 6/18/88
26. LMITS IN TEST STATUS (PRIOR TO CotMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 COPMERCIAL OPERATION 12/23/74 O

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WIT SHUTDOWS AND PONER REDUCTIONS DOCKET ND. 50 - 277 WIT NAME PEACH BOTTOM WIT 2 DATE JANUARY 15,1987 REPORT MONTH DECEPBER,1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 w....

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l l METHOD OF l LICENSEE lSYSTEMICOMPONENTI CAUSE AND CORRECTIVE I

ITYPEIDURATIONlREASONISHUTTING DOW I EVENT l CODE I CODE l ACTION TO DATE I (111 (HOURSll (2) l REACTOR (3) 1 REPORT S I (4) l (5) l PREVENT RECURRENCE l

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t (1)

(2)

(3)

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- FORCED REASON METHOD EXHIBIT C - INSTRUCTIONS

- SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MAMJAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MAMJAL SCRAM.

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

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (PAIREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)

G - OPERATIONAL ERROR (EXPLAIN) l H - OTHER(EXPLAIN)

EXHIBIT I - SAME SOURCE r

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UNIT SHUTD0 pets AND PONER REDUCTIONS DOCKET NO. 50 - 278' UNIT NAME PEACH BOTTOM UNIT 3 DATE JANUARY 15,1987 REPORT MONTH DECE!SER, 1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE I215) 841-6374 l

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l l NETH00 OF l LICENSEE ISYSTEMICOMPONENTl CAUSE AND CORRECTIVE I

lTYPElDURATIONIREASONISHUTTING D06911 EVENT l CODE I CODE l ACTION TO 31 DATE I (1)! EHOURS)l (2) l REACTOR (3) l REPORT S I (4) l (5) l PREVENT RECURRENCE 6.

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3.I 861203 l F l 000.0 l B l 4

l N/A l CE l VALVEX l LOAD REDUCTION TO 62% PCHER FOR REPLACEMENT OF l

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l HO-16 STEAM LINE ISOLATION VALVE PACKING.

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l N/A l HB l PIPEXX l TURBINE NAS MAPAJALLY NITH REACTOR P0HER l

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l l INLET FLANGE TO THE HIGH PRESSURE TURBINE.

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i LER-NA 1 HF 1 HTEXCH l LOAD REDUCTION TO 61% P0HER FOR LEAK TESTING l

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l l OF "C1" AND "C2" NATERB0XES, AND ColGROL, ROD l

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l N/A l rlF l LER-NA i LOAD REDUCTION TO 612 PME FOR CateENSER l

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l l MATERBOX TL3E LEAK INSPECTIONS IN THE B2 l

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l l NATERBOX, AND CONTROL R00 PATTERN ADJUSTMENT.

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1 N/A l HB 1 PIPEXX l MANUAL SHUTDODN FOR STEAM *.UK REPAIRS ON THE

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Peach Bottom Atomic Power Station Narrative Summary of Operating Experience December, 1986

-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

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control. rod-pattern adjustment and testing of main steam isolation valve 86-D.-

Load recovery.was completed on. December 12 1, and. full power was maintained-through the end of the report period.

UNIT 3

.The unit operated at full pow'er until December 3, when load was

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reduced tx) 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 pressure 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.

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Docket No. 50-277 Attachment to Monthly Operating.

Report.for-December, 1986-UNIT 2 REFUELING INFORMATION 1.

Name of facility:

Peach Bottom Unit 2 1

2.

Scheduled date for next refueling shutdown:

February 7, 1987 13.

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 J

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 was completed on November 15, 1986.

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-Docket No. 50-278

-Attachment ~ to

. Monthly Operating Report for October, 1986 UNIT 3 REFUELING INFORMATION i

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 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:

[

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 pool:

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

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Docket No. 50-278 Attachm3nt to i

Monthly Oparating R port for DacambDr,.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)

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 January 15, 1987 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 December, 1986, forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

Very rpl

yours, A,

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W. M. Alden Engineer-In-Charge Licensing Section Nuclear Support Department Attachment cc:

Dr. T.

E. Murley, NRC l

Mr. T.

P. Johnson, Resident Inspector l

Mr. Stan P. Mangi, Dept. of Envir. Resourtas i

Mr.

P. A.

Ross, NRC (2 copies) l Mr. R. J. Clark, NRC Project Manager Mr. Thomas Magette, Maryland Power Plant Siting INPO Records Center i

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