ML20207C418

Monthly Operating Repts for June 1986

ML20207C418
Person / Time
Site:	Peach Bottom
Issue date:	06/30/1986
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 8607210366
Download: ML20207C418 (15)

Text

,

. f-Peach Bottom Atomic Power Station

, Narrative Summary of Operating Experience

• June, 1986 UNIT 2 The Unit 2 began the report period at 25% power in single loop operation, with repairs in progress to return the 2B recirculation pump M-G set to service, following a fire in the M-G set exciter which caused damage to the collector rings and brushboxes. On June 2, the 2B recirculation pump M-G set was returned to service and the 2A M-G set was removed from service to replace its exciter brushes. Repairs were completed and load recovery was initiated on June 3.

Load recovery was halted on June 3 at 0700 MWe to inspect the A-1 and A-2 condenser waterboxes for tube leaks. No leaks were detected, and load recovery was continued. Full power was achieved on June 5.

Daily load reductions ranging from 50 to 250 MWe were taken between June 6 and June 17 due to main transformer high oil and winding temperature. On June 6, load was further reduced to 650 MWe to accommodate a control rod pattern adjustment.

On June 18, the reactor was manually scrammed upon the discovery of a leak in the emergency service water (ESW) supply piping to the 2A Residual Heat Removal (RHR) room cooler. Repairs were made to the piping and verified by hydrostatic pressure testing.

While shutdown for ESW pipe repair, repairs were also made to the B, C, D, and E intermediate range monitors (IRMs). These repairs were completed on June 24 and startup was initiated. The turbine generator was placed on line on June 25.

On June 28, a load reduction to 650 MWe was taken for a control rod pattern adjustment. Load recovery began the same day. Unit 2 ended the report period at 99.5% power, limited by the maximum fraction of limiting power density.

Unit 3 Unit 3 began the report period at 100% power. On June 1, load was reduced by 150 MWe due to main transformer high oil temperatures. Several load reductions were taken during the month for main transformer high oil temperature, ranging between 50 and 300 MWe.

On June 2, load was reduced to 917 MWe due to degredation of the main condenser vacuum. Inspection revealed that a steam supply relief valve to the "A" steam jet air ejector opened prematurely, thereby reducing the efficiency of the air ejector. The valve was adjusted, the unit was returned to full power on June 4.

On June 17, load was reduced to 800 MWe as a result of an increase in reactor water conductivity, due to a resin injection while placing the 3G condensate demineralizer into service. Full ,

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8607210366 860630 PDR ADOCK 05000277 \\

R PDR

. Attachment to Monthly Operating Report for i June, 1986

- Page 2 load was achieved on June 18. Load was again reduced to 800 MWe on June 20 as a result of another increase in reactor water conductivity, caused by a resin injection while placing the 3H condensate demineralizer into service. Full load was restored on June 22.

On June 27, a load reduction of 550 MWe was taken to accommodate a control rod pattern adjustment, and for primary containment isolation system (PCIS) and main steam isolation valve (MSIV) testing. Load recovery was completed the same day.

Unit 3 ended the report period at 100% power.

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Docket No. 50-277 Attachment to Monthly Operating Report for June, 1986 UNIT 2 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 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.

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• Docket No. 50-277 Attachment to Monthly Operating Report for June, 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, 1995 (March, 1998, with reserve full core discharge) i l

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Docket No. 50-278 Attachment to Monthly Operating Report for June, 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 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 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 t

Docket No. 50-278 Attachment to Monthly Operating Report for June, 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 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) t

• AVEIAGE DAILY UNIT POWE2 LE' VEL DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2

.........- =_ ---__ ____.

DATE JULY 15.1986

.................. __ = = =

COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION NUCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022

= ===..==______.......

N014TH JUNE 1986

=____.....

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET) (MWE-NET) 1 308 17 1017 2 297 18 395 3 683 19 0 4 979 20 0 5 982 21 0 6 970 22 0 7 1029 23 0 8 988 24 0 9 1021 25 16 10 1035 26 560 11 981 27 929 12 1049 28 997 13 1054 29 838 14 1020 30 1044 15 %7 16 986 i

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• AVERAGE DAILY UNIT POWEQ LEVEL

. DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3

............:___ =.......

DATE JULY 15.1986 COMPANY PHILADELPHIA ELECTRIC COMPANY

- _____-- ==_=-_.............

W.M. ALDEN ENGINEER-IN-CHARGE LICENSING SECTION NUCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022

........_ ___==.............

MONTH JLA1E 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

! !'WE-NE T ) (MWE-NET) 1 986 17 993 2 998 18 1001 3 988 19 1021 4 1044 20 860 5 997 21 826 6 985 22 1020 7 373 23 1009 0 901 24 1037 9 964 25 1048 10 1010 26 1045 A1 960 27 1027 12 1009 28 86 3 13 1016 29 981 14 1018 30 1044 15 1026 16 1044

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. OPERATING DATA REPORT DOCKET NO. 50 - 277

....====- = __===__ _==..

DATE JULY 15.1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION NUCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022 OPERATING STATUS

__..._____ ..__._=__--_ =_=_=______ __........

1. UNIT NAME: PEACH BOTTON UNIT 2 l NOTES: UNIT 2 EXPERIENCED TWO I l l

2. REPORTING PERIOD: JUNE, 1986 l FORCED LOAD REDUCTIONS, 1 I

.....___.. ...__ __ - ___. l l

3. LICENSED THEPMAL POWER (MWT): 3293 l AND NO SCHEDULED LOAD l l l

4. NAMEPLATE RATING (GROSS MWE): 1152 l REDUCTIONS. l

======_

l l

5. DESIGN ELECTRICAL RATING (HET MWE): 1065 l l l l

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098 l l l l'

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1051 l l

__.... _......__.- =- __ ___=== ________

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS HUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):

10. REASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720 4, 34 3 105:095

=..___ .=====__

12. NUMBER OF HOURS REACTOR WAS CRITICAL 575.0 3.656.7 68.850.9

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

14. HOURS GENERATOR OH-LINE 542.5 3,558.7 66,687.5 '

=____ _== ..__== _.. .... ...

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15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

13. GROSS THERMAL ENERGY GENERATED (MWH) 1.533.264 10.637.534 196.904.049

____=-- -= ...___...... ............

17. GROSS ELECTRICAL ENERGY GENERATED IMWH) 504.600 3.526 200 64.739.160

10. NET ELECTRICAL ENERGY GENERATED (MWH) 481.554 3.400.934 61,993.229 l l

19. UNIT SERVICE FACTOR 75.3 81.9 63.5 l l

. 20. UHIT AVA%LABIL8TY FACTOR 75.3 81.9 63.5

- 21. UNIT CAPAC2VY FACTOR (USING MDC HET) 63.6 74.5 56.I 2?. U"It C/FACITY FACTCR (USING CER NET) 62.8 73.5 55.4

23. UNIT FORCED OUTAGE RATE 24.7 15.7 13.2 5

24. SHUTDCWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE. DATE. AND DURATIDH OF EACHl -

25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUPt i l 1 1

26. UNITS IN TEST STATUS (PRIDR TO COMMERCIAL OPERATION): FORECAST ACHIEVED 1 i

INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 COMMERCIAL OPERATIDH

......... -07/05/74 d

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- l CPERATING DATA CEPORT l

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, DOCKET NO. 50 - 278 DATE JULY 15.1986 CONPLETED BY PHILADELPHIA ELECTRIC CONPANY W.N.ALDEN ENGINEER.IN-CHARGE LICENSING SECTION NUCLEAR GENERATION DIVISION w

TELEPHONE (215) 841-5022 OPERATING STATUS

....___......... ========= _==--- _ .=-- ..........

1. UNIT HANE: PEACH BOTTON UNIT 3 l NOTES: UNIT 3 EXPERIENCED ONE l

=-____________....=_

l l

2. REPORTING PERIOD: JUNE, 1966 l FORCED LOAD REDUCTION l

... __..= -__- __- _..... l l

3. LICENSED THERNAL POWER (NWT): 3293 l AND NO SCHEDULED LOAD l

...- =___ _ ____ l l

4. HAMEPLATE RATING (GROSS NWE): 1152 i REDUCTIONS. l

. -_ ._.... l l

5. DESIGN ELECTRICAL RATING (HET NWE): 1065 l l

......... l l

6. NAXIMUN DEPENDABLE CAPACITY (GROSS NWE): 1098 l l l l

7. NAXIMUN DEPENDABLE CAPACITY (HET NWE): 1035 l l

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:

9. POWER LEVEL TO WHICH RESTRICTED. IF ANY (NET NWE):

10. REASONS FOR RESTRICTIONS. IF ANY:

THIS NONTH YR-TO-DATE CUNULATIVE

11. HOURS IN REPORTING PERIOD 720 4.343 100,991 I2. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 2.489.9 71.103.1

=- _ __.... .......... . ......... ..

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

14. HOURS GENERATOR CH-LINE 720.0 2.233.3 69.087.7

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERNAL ENERGY GENERATED (NWH) 2.198.616 5.905.061 200.901,725

............ .===_ _=.. ............

17. GPOSS ELECTRICAL ENERGY GENERATED (NWH) 727.350 1.905.230 65 898.900

19. NET ELECTRICAL ENERGY GENERATED (NWH) 698.265 1.817.392 63.210.133

............ ==== =__==. ....__...__.

19. UNIT SERVICE FACTOR 100.0 51.4 68.4

, 80. UMT AVOILABILITY FACTOA 100.0 51.0 68.0

21. UNIT CAPACITY FACTOR (USING POC NET) 93.7 40.0 60.5

22. UNIT CAPACITY FACTOR (USING DER NET) 91.1 39.3 58.8

23. UNIT FORCED OUTAGE RATE 0.0 5.1 7.1

...-........ --- _-=.... ............

24. SHUTDCWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE, AND DURATION OF EACH):

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 C0ft1ERCIAL OPERATION 12/23/74 i

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UNIT SHUTDOWNS AND POWER REDUC IONS DOCKET NO. 50 - 277 UNIT NAME PEACH BOTTON UNIT 2

..__. ...._ _== __.... __..

DATE JULY 15,1986 REPORT NONTH JUNE 1986 CONPLETED BY PHILADELPHIA ELECTRIC CONPANY

_ ___-___..... ...........==- _______....._

W.H.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION NUCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022

,.........__........................... _=- ____.... ....................... . ........... __-__ =- =....................

l l l l l NETH00 CF l LICENSEE lSYSTEHlCONPONENTI CAUSE AND CORRECTIVE I ITYPElDURATIONIREASONISHUTTING DOWNl EVENT l CODE I CODE I ACTION TO

' 7.1 DATE l till (HCURSil 121 1 REACTOR 13) l REPORT 8 l 14) l (5) l PREVENT RECURRENCE

=_ . . ......... .............

I I l l I I I l I

') l G60601 1 Fl 0.0 l A l 4 l N/A l CB l GENERA l LOAD REDUCTION TO 25% POWER DUE TO RICIRCULA.

l l l l l l l l l TION NG SET DRIVE NOTOR TRIP, CAUSED BY WOPN l l l l l l l l l BRUSHES IN THE EXCITER. LIMITED TO SINGLE LOOP l l l l l l l l l OPERATIONS.

I I I I I I I I I YI G60618 l F l 177.6 I A l 1 l 2-86-18 I WB l PIPEXX l NANUAL SHUTDOWN DUE TO A LEAK IN ENERGENCY I l l l l l l l l SERVICE WATER (ESW) SUPPLY PIPING TO THE RHR l l l l l l l l l ROON COOLER. (REQUIRED BY TECHNICAL SPECIFICA-l l l l l l l l l TIONS.

I I l ----- 1 I I I I I l l l 177.6 l l l l l l (1) (2) (3) (4)

- F09CED REASLN NETH00 EXHIBIT G - INSTRUCTIONS

- SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTONATIC SCRAN. EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAINI FILE (NUREG-0161)

E - CPERATOR TRAINING + LICENSE EXAMINATION F - ADNINISTRATIVE (5)

G - OPERATIONAL ERROR (EXPLAINI H - OTHERIEXPLAIN) EXHIBIT I - SANE SOURCE i f

o UNIT SHUTDOWHS Ate POWER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTON UNIT 3 DATE JULY 15.1986 REPORT MONTH JUNE, 1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE

, LICENSING SECTICH HUCLEAR GENERATION DIVISION TELEPHONE (215) 841-50 2

......__ .............................. ...........................= _ --- ............ ...=== ==____ ___=.................

l l l l l METHOD OF l LICENSEE lSYSTEMICOMPONENTl CAUSE AND CORRECTIVE l I T Y PE I D UR ATION I R E ASON I SHUTTING DOWH I EVENT l CODE l CODE l ACTIDH TO Q.l DATE l (1)! (HOURS)l (2) l REACTOR ( 3) l REPORT S l 14) l (5) l PREVENT RECURRENCE

_==...---- _____ _..- _ _-_...........

I I I I I I I I 1

) l 860607 l Fl 0.0 l B l 4 l N/A l CB l ELECON l LOAD REDUCTION TO 276MW FOR REPLACEMENT OF l l l l l l l l l RECIRCULATION MG SET EXCITER BRUSHES.

I 1 l ----- 1 I I I I I I I I - 1 I I I l l (1) (2) (3) (4)

- F09CEO REASON METHOD EXHIBIT 6 - INSTRUCTIONS

- SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATI0H OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAN. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAN. EVENT REPORT ( LER)

D - REGULATORY RESTRICTIDH 4 - OTHER (EXPLAIN) FILE INUREG-0161)

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

G - OPERATIONAL ERROR (EXPLAIH)

N - OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE

r j PHILADELPHIA ELECTRIC COMPANY 23O1 MARKET STREET l

P.O. BOX 8699 PHILADELPHIA. PA.19101 July 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 June, 1986, forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

Very truly yours,

/

R. H. Logue Superintendent Nuclear Services Attachment i

cc: Dr. T. E. Murley, 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 i

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