Text

Monthly Operating Repts for Feb 1986
	ML20154Q032
Person / Time
Site:	Peach Bottom
Issue date:	02/28/1986
From:	Alden W, Logue R; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	; NRC OFFICE OF ADMINISTRATION (ADM)
References
	NUDOCS 8603210010
	Download: ML20154Q032 (13)
	v • d • e

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Docket Nos. 50-277/50-278 1

Attachment to Monthly Operating Report for February, 1986 Peach Bottom Atomic Power Station Narrative Summary of Operating Experiences February, 1986 UNIT 2 The unit began the report period shutdown for a maintenance outage to repair the E-2 diesel generator, inspection of snubbers in the drywell and replacement of the 2B Residual Heat Removal (RHR) pump impeller and wear rings.

4 On February 6, the reactor was started, and the turbine-generator was synchronized later that day.

Full power operation was achievod on February 11.

On February 15, a load reduction to 760 MWE was taken to accommodate a control rod pattern adjustment.

The unit returned to full power later that day and maintained full power operation for the remainder of the month.

Unit 3 The unit began the report period shutdown for its sixth refueling and maintenance outage.

Return to service is scheduled for early March, 1986.

The Loss of Offsite Power Test was completed on February 7.

On February 12, the turbine oil system was placed into service with the turbine-generator on turning gear.

Condenser vacuum was established on February 14.

On February 16, a blown fuse, resulting from a short in a ribbon cable on the condenser vacuum recorder, caused the reject valves from the hotwell to the. condensate storage tank (CST) to fail open, thereby directing a portion of the operating condensate pump's flow to the CST.

As a result, the CST overflowed into the surrounding moat.

The water drained through two holes that had been left unsealed in the floor of the moat, entered a nearby yard sump, and was then pumped to the river via the storm drains.

~

The total release was estimated to be 36,00Q, gallons with a total activity of 0.37 curies.

This was within the allowable limits of Technical Specifications.

At a meeting on February 21 to discuss the. failure of the controller for the reject valve, the NRC requested that PECo repair the moat surrounding the CST prior to i

startup.

The repairs to the moat were completed on February 27.

On February 14, all work in the drywell was completed.

Checkoff lists for startup were completed on February 24.

l 9603210010 860228 f CI' PDR ADOCK 05000277 l

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X Docket Nos. 0-277/50-278 Operating Repoto Monthly Activities in pr February,rt for preparation for 1986 ogress Page 2 as of the startup included: end of the balanceRecirculation Syst report period in 3B

work, (LLRT),MO-lO-39A v lv em Motor-Generator (

RHR M-G) set a

and e repair LLRT and Local system AO-23-18 v lfor the High Pre Rate Test Leak ssure Coolant a ve.

Injection (HPCI)

LLM/vdw r

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Docket Nos. 50-277/50-278 Attachment to Monthly Operating Report for February, 1986 i

Page 2 Activities in progress as of the end of the report period in preparation for startup included:

3B Recirculation System Motor-Generator (M-G) set balance work, i

RHR MO-10-39A valve repair and Local Leak Rate Test (LLRT), and LLRT for the High Pressure Coolant Injection (HPCI) system AO-23-18 valve.

i 1

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Docket No. 50-277 o

Attachment to Monthly Operating Report for February, 1986 REFUELING INFORMATION 1.

Name of facility:

Peach Bottom Unit 2 2.

Scheduled date for next refueling shutdown:

January 31, 1987 3.

Scheduled date for restart following refueling:

May 1, 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 i

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

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were approved by the NRC on February 19, 1986 which increases the licensed fuel pool capacity to a total of 3819 l

fuel bundles in each fuel pool.

Docket No. 50-278 Attachment to Monthly Operating Report for February, 1986 REFUELING INFORMATION 1.

Name of facility:

Peach Bottom Unit 3 2.

Scheduled date for next refueling shutdown:

May 16, 1987 3.

Scheduled date for restart following refueling:

May 14, 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 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.

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1 AVERAGE DAILY UHIT POWER LEVEL i

DOCKET HO. 50 - 277

=_

LAIIT PEACH BOTTON UNIT 2

====- ----- -

DATE MARCH 14,1986 COMPANY PHILADELPHIA ELECTRIC COMPANY

=_

W.H. ALDEH t

ENGINEER-IN-CHARGE LICENSING SECTION HUCLEAR GENERI. TION DIVISION 1

TELEPHONE (215) 841-5022 i

,I N0HTH FEBRUARY 1986 T

s

+

DAY AVERAGE DAILY PCWER LEVEL DAY AVERAGE DAILY PCHER LEVEL (MNE-NET)

(HWE-NET) 1 0

17 1036 2

0 18 1038 I

j 3

0 19 1052 4

l 4

0 to 1071 I

j 5

0 21 1073 6

69 22 1073 i

7 425 23 1072 i

8 441 24 1074 l

9 736 25 1074 10 96 7 26 1074 i

i 11 1031 27 1074 l

12 1042 28 1072 i

l 13 1033 f

14 1037 i

15 950 I

16 1035 1

i r

c.

,.,,,.,_..n,..

..,,, - -..., - - - ~,,,.. -, -,,.,

.--.n,,--

AVERAGE DAILY UNIT POWER LEVEL DOCKET HO. 50 - 278

__ _=

UttIT PEACH BOTTON UNIT 3 DATE MARCH 14,1986 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGIllEER-IN-CHARGE LICENSIt!G SECTION tlUCLEAR GENERATION DIVISIGH TELEPHONE (215) 841-5022 NotlTH FEBRUARY 1986

= _ _

==...

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (iME-HETI (MWE-NETI 1

0 17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

14 0

15 0

16 0

OPERATItG DOTA REPORT DOCKET HO. 50 - 277

=-

DATE MARCH 14.1986

...=.

COMPLETED BY PHILADELPHIA ELECTRIC C0t1PANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSIttG SECTIC!i NUCLEAR GENERATI0H DIVISIDH TELEPHCHE (215) 841-5022

__== --

OPERATItG STATUS

=-

1. UNIT HAME: PEACH BOTT0t1 UNIT 2 l HOTES: UNIT 2 EXFERIEHCED ONE AUTO l

.......... - - =

l l

2. REPORTING PERIOD: FEERUARY, 1986 l

SCRAM, AND Ct1E SCHEDULED I

__===

[

l

3. LICENSED THERMAL POWER (MWT):

3293 l

LOAD REDUCTION.

l l

l

4. HAttEPLATE RATING (GROSS iME):

1152 l

l l

l

5. DESIGil ELECTRICAL RATING (HET MWE):

1065 l

l l

l

6. MAXIMUN DEPEllDABLE CAPACITY (GROSS MWE): 1098 l

l l

l

7. MAXIt1UN DEPENDABLE CAPACITY (HET fME):

1051 I

l

8. IF CHANGES CCCUR IN CAPACITY RATIl1GS (ITEttS HUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REA50ttS:

9. POWER LEVEL TD WHICH RESTRICTED, IF ANY (HET iME):

1

10. REASONS FOR RESTRICTI0t15. IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 672 1.416 102.168

12. HUMBER OF HOURS REACTOR WAS CRITICAL 547.2 985.7 66,179.9

83. REACTOR RESERVE SHUTDOWt1 HOURS 0.0 0.0 0.0

..==.

14. HOURS GENERATOR Oti-LINE 533.7 944.8 64.073.6

==_

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL EHERGY GENERATED (MWH) 1,628,671 2,670,312 188,936.827

_=_=_=.

.===

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 534,180 869.150 62,082.110

18. NET ELECTRICAL ENERGY GENERATED (MWH) 516.156 837.067 59,429,362

19. UNIT SERVICE FACTOR 79.4 66.7 62.7

-____==..

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20. UNIT AVAILABILITY FACTOR 79.4 66.7 62.7

21. EMIT CAPACITY FACTOR (USING MDC NET) 73.1 56.2 55.3

22. UNIT CAPACITY FACTOR (USING DER NET) 72.1 55.5 54.6

23. UNIT FORCED OUTAGE RATE 20.6 27.D 13.3

24. SHUTDOWS SCHEDULED OVER NEXT 6 MONTHS ITYPE DATE: AM DURATION OF EACH)*

25. IF SHUTDO W AT EtB OF REPORT PERIODe ESTIMATED DATE OF STARTUPt

26. UNITS IN TEST STATUS (PRIOR TO C0ft1ERCIAL OPERATION)

FORECAST ACHIEVED IHITIAL CRITICALITY A9tM1.73 INITIAL ELECTRICITY 12,f1_8]74 Cott1ERCIAL OPERATION A720.5]74

I UNIT SifUTDOWHS AND POWER REDUCTI0ftS DOCKET HO. 50 - 277 UNIT HAME PEACH BDTTOM UNIT 2

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

DATE MARCH 14,1986

__=-

REPORT MONTH FEERUARY, 1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M. A LDEN ENGINEER-IN-CHARGE LICE!!SIttG SECTI0tt HUCLEAR GENERATION DIVISICH TELEPHONE (215) 641-5022

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

__- =_________.... -_............__.....-_____........._______

l l

i METHOD OF l LICEttSEE ISYSTEMICOMPONErfTI CAUSE AllD CORRECTIVE l

lTYPElDURATI0tilREA50tilSHUTTItiG CCWfil EVEllT l CODE I CODE I ACTI0tl TO tt0.1 DATE I (1)l (HOURSil (2) l REACTOR f3) l REPCRT 8 i (4) I (5) l PREVENT RECURREttCE

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

I I

I 9 I 860201 1 F l 138.3 I A I 3

l 2-86-3 1 EE I ENGINE l DIESEL INOPERABLE. SCRAM FROM 96% PCWER DUE TO l

I l

l 1,

I I THE CLOSURE OF TWO MSIVS, COIttCIDENT WITH THE I

l I

l l

l l FAILURE OF THE E-2 DIESEL GENERATOR.

I I

l l

I I

I a0 1 850215 l Sl 0.0 1

D l 4

i H/A l RC l ZZZZZZ l LOAD REDUCTION TO 760 MWE FOR CONTROL ROD l

l l

l l PATTERH ADJUSTMENT.

I i

1 ----- 1 I

I I

l l

l 138.3 l l

l l

(1)

(2)

(3)

(4) 7 - FORCED REASON METHOD EXHIBIT G - INSTRUCTI0 tis 9 - SCHEDULED A - EQUIPMEffT FAILURE (EXPLAIH) 1 - MAffUAL FCR FREPARATICH OF DATA B - MAltITENANCE OR TEST 2 - MAllUAL SCRAM.

ENTRY SHEETS FCR LICENSEE C - REFUELIflG 3 - AUT0t1ATIC SCRAM.

EVENT REPORT ( LER)

D - REGULATCRY RESTRICTICN 4 - OTHER (EXPLAIH)

FILE (HUREG-0161)

E - OPERATOR TRAIllING + LICENSE EXAMIHATIDH F - ADMINISTRATIVE (5)

G - OPERATICHAL ERROR (EXPLAltil H - OTHER(EXPLAIN)

EXHIBIT I - SAME SOURCE l

20. UNIT AVAILAIILITY FACTOR 0.0 0.0 CO.2

21. UNIT CAPACITY FACTOR (USING HDC NET) 0.0 0.0 60.5

22. UNIT CAPACITY FACTOR (USING DER HET) 0.0 0.0 58.8

23. UNIT FORCED OUTAGE RATE 0.0 0.0 7.1

=_=.

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

SCHEDULED SHUTD0bt4 FOR REFUELING AND MAINTENANCE OUTAGE, STARTED 7/14/85

25. IF SHUTD0bil AT END OF REPORT PERICD. ESTINATED DATE OF STARTUP: 3/2/86

26. UNITS IN TEST STATUS (FRI TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY

...... 7 7 4 ggjg7 INITIAL ELECTRICITY 09/01/74 COMr1ERCIAL OPERATION

___/_2 3 /.7 4 12

=-

- HEGATIVE VALUE REFORTED FOR CCHSISTEHCY HITH FEDERAL ENERGY REGULATORY COHNISSION REPORTS.

OPERATING DATA REPORT DOCKET NO. 50 - 278 DATE MARCH 14,1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY

_ = _ -

W.M.ALDEN EttGIllEER-IN-CHARGE LICENSING SECTION HUCLEAR GENERATI0H DIVISION TELEPH0t46 (215) 841-5022 OPERATING STATUS

1. UtlIT HAME: PEACH BOTTON Ut(IT 3 l HOTES: UNIT 3 CONTINUED ITS SIXTH l

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

i l

2. REPORTItfG PERIOD: FEERUARY, 1986 l

REFUELING Ato NAINTEllAffCE I

___==

l l

3. LICENSED THERMAL POWER (t%IT):

3293 l

OUTAGE.

l

=__

___===

l l

4. HAMEPLATE RATING (GROSS t%lE):

1152 l

l

=-

__=_

l l

5. DESIGH ELECTRICAL RATIllG (IIET MWEl 1065 l

l l

l

6. MAXIMUM DEPEtOABLE CAPACITY (GROSS NWE): 1098 l

l l

l

7. MAXIMUN DEPENDABLE CAPACITY (HET MWEl:

1035 l

l G. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS tlUMBER 3 THROUGH 7) SINCE LAST REPCRT, GIVE REA50ftSt

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (HET iSIE):

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 672 1,416 98,064

==

12. HUNDER OF HOURS REACTCR WAS CRITICAL 0

0 68.613.2

13. REACTOR RESERVE SHUTDOWH HOURS 0.0 0.0 0.0

14. HCURS GENERATOR OH-LINE 0.0 0.0 66,854.4

__=======

_ _ __==.__

15. UNIT RESERVE SHUTD0tJH HOURS 0.0 0.0 0.0

16. GROSS THEPHAL ENERGY GEtlERATED (tSJH) 0 0

194.996.664

17. GROSS ELECTRICAL EHERGY GEllERATED (P5 ail 0

0 63.993.670

.= =_

_=.

18. NET ELECTRICAL ENERGY GENERATED (tSJH)

-4,141

-9.484 61.383.257

_====

10. UNIT SERVICE FACTOR 0.0 0.0 68.2 r

UNIT SHUTDOWPf3 AllD POWER REDUCTIONS DOCKET HO. 50 - 278

___=_===________..__.

UNIT HAME PEAct: BOTTCH UNIT 3 DATE MARCH 14,1986 REPORT MotiTH FEBRUARY, 1986 COMPLETED BY FHILADELFHIA ELECTRIC COMPANY W.H.ALDEH ENGIllEER-IN-CHARGE LICEllSIt!G SECTION HUCLEAR GENERATION DIVISIGH TE LEPH0t1E ( 215 ) 841-5022 o_____...._____

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

l l

l NETHOD OF l LICENSEE ISYSTEMICOMPCHEliTl CAUSE AllD CORRECTIVE I

l T Y PE l DUR AT IOH l R E ASOtl l EHUTT ING D OWti l EVENT l CODE l CODE l ACTICH TO NO.]

DATE l (1)l (HOURS)I (2) l REACTOR (3) l REPORT S l (4) l (5) l PREVENT RECURRENCE

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

1 1

I I

i 1 1 060201 1 S I 672.0 l C l 4

l H/A l RC 1 FUELXX l SHUTDOWN FOR SIXTH REFUELING AND HAINTENANCE I

I I

I I OUTAGE.

I I

I ----- 1 I

I I

l l

l 672.0 I l

l l

l I

Ill (2)

(3)

(4) 7 - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS 9 - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENAtiCE OR TEST 2 - HANUAL SCRAM.

ENTRY SHEETS FOR LICEllSEE C - REFUELIliG 3 - AUTOMATIC SCRAM.

EVENT REPORT ( LER)

D - REGULATORY RESTRICTION 4 - OTHER ( EXPLAIH)

FILE (NUREG-0161)

E - OPERATOR TRAINIlfG + LICENSE EXAMIllATION F - ADMINISTRATIVE (5)

G - OPERATICHAL ERROR (EXPLAIH)

H - OTHER(EXPLAINI EXHIBIT I - SAME SOURCE i

PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 March 14, 1986 PHILADELPHI A. PA.19101 12isi 84i-400o 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 February, 1986 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

Very truly yours, Y'

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 Mr.

P.

A.

Ross, NRC (2 copies)

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

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ML20154Q032

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