ML20141D915

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Monthly Operating Repts for Jan 1986
ML20141D915
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 01/31/1986
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 8602240753
Download: ML20141D915 (14)
v • d • e


Text

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OPERATINS DATA REPORT DOCKET NO. 50 - 277 DATE FEBRUARY 14.1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION HUCLEAR GENERATION DIVISION TELEPHONE IE15) 841-5022 OPERATING STATUS

1. UNIT HAME: PEACH BOTTON LMIT 2 l HOTES UNIT 2 EXPERIENCED TWO AUTO l

l l

t. CEPORTIflG PERIDO:

JANUARYe 1966 l

SCRAMS SIX SCHEDULED LOAO l

l l

3. LICENLED THERMAL POWER (PSdTil 3293 l

REDUCTIONS AMI ONE SCHEDULED l l

l

4. HAMEPLATE NATING IGROSS PG4Eli 1152 l

SCHEDULED MINI-0UTA(et.

l l

l

5. DESIGN ELECTRICAL RATING INET MWEle 1065 l

l l

l

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWElf 1098 l

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7. MAXIMUM DEPEHDABLE CAPACITY (HET MWEls 1051 l

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8. IF CHANGES OCCUR IN CAPACITY NAT! HGS IITEMS HUMBER 3 THROUGH 7) SINCE LAST REPORTe SIVE REASONSI l
9. POWER LEVEL 70 lef!CH RESTRICTEDe IF ANY INET NWElf
10. REASONS FOR RESTRICTIONS IF ANTI THIS MONTH YR.TO-DATE CUMULATIVE
11. hDURS IN REPORTING PERIDO 744 744 101.496
12. HUMBER OF HOURS REACTDR WAS CRITICAL 438.5 434.5 45,632.7
13. CEACTOR RESERVE SHUTDOWN HOURS 9.0 0.0 0.0
13. HOURS GENERATOR DN-LINE 411.1 411.1 63.539.9
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. BROSS THERMAL ENERGY StHERAf tD (MWHI 1 041,441 1.041,641 187.304 156
17. GROSS ELECTRICAL ENERGY StHERAf t0 (MWHI 334,970 354,970 61.547.930
18. HET ELECTRICAL ENERST SENERATED (MWH) 320,911 320.911 54.913.204
19. UNIT SERVICE FACTOR 55.3 55.3 62.6 v'

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t 9602240753 8

PDR ADOCK 7

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m

29. L20!T AVAILABILITT FACTOR 55.3 55.3

- 62.6

21. LRIIT CAPACITT FACTOR (USINS NBC NET) 41.0 41.0 55.2
22. 1942T CAPACITY FACTOR (USINS DER NET) 44.5 40.5 54.5
23. LMIT FORCED OUTAGE RATE 33.9 33.9 13.2
24. SHUTD0l#45 SCHEDULED OVER NEXT 6 HONTHS ITTPE, DATE, APG DURATION OF EACHit s
25. IF SHUTD0bei AT Ele OF REPORT PERIOD, ESTIHATED DATE OF STARTUPt 5/12/87
26. UNITS IN TEST STATUS (PRIOR TO Cort 1ERCIAL OPERATIONit FORECAST ACHIEVED INITIAL CRITICALITT
0. 9./.16../.73 INITIAL ELECTRICITY
0. 2./.18../.74 CorttERCIAL OPERATICH
0. 7./.05../.74 1

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OPERATING DATA REPORT DOCKET NO. 50 - 278 DATE FEBRUARY 14.1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION DAJCLEAR GENERATION DIVISION TELEPHONE I2151 841-5022 OPERATING STATUS

1. UNIT NAME PEACH BOTTOM UNIT 3 l NOTES: UNIT 3 CONTINUED ITS SIXTH l

l l

E. CEPORTING PERIODI JANUARY, 1986 l

REFUELING APS MAINTENANCE l

l l

3. LICENSED THERMAL POWERtitiTII 3293 l

CUTAGE.

l l

l

4. NAMEPLATE RATItG (GROSS PedEls 1152 l

l l

I

5. DESIGN ELECTRICAL RATING (HET PS4 Ell 1965 l

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l

6. MAXIMUM DEPEFEA8LE CAPACITY (GROSS tedElt 9

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7. MAXIMUM DEPEteABLE CAPACITY (HET MWElf 1035 l

l

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUPEER 3 THROUGH 7) SINCE LAST REPORT, SIVE REASONSI
9. POWER LEVEL 70 bMICH RESTRICTED. IF ANY (HET MWEla
10. CEASONS FOR RESTRICTIDHS, IF ANY THIS MONTH TW.TO-DATE CUPtJLATIVE
11. HOURS IN REPORTING PERIOD 744 744 97,392
12. NUr1BER OF HOURS REACTOR WAS CRITICAL 0

0 68.613.2

13. CEACTOR RESERVE SHUTD06et HOURS 0.0 0.0 0.0
14. HOURS GENERATOR OH.LINE 0.0 0.0 66,854.4
15. UNIT RESERVE SHUTD064t HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWHI O

9 194,996.664

17. GROSS ELECTRICAL ENERGY GENERATED (MWHI O

O 63.993.670

18. NET ELECTRICAL ENERGY GENERATED titell a

'-5.343

-5 343 61.387 398

19. UNIT SERVICE FACTOR 0.0 0.0 48.6
20. WIT AVAILABILITT FACTOR 0.0 0.0 68.6 Ek. WIT CAPACITT FACTOR (USING f9C NET) 0.0 0.0 60.9
22. WIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 59.2
23. WIT FORCED OUTAGE RATE 0.0 0.0 7.I
24. SHUTDOWHS SCHEDULED OVER NEXT 6 MONTHS (TTPEe DATE. Ate DURATION OF EACHit SCHEDULED SHUTDO W FOR REFUELING APO MAINTENANCE OUTAGE, STARTED 7/14/85
25. IF SHUTDOW AT Ele OF REPORT PERIOD. ESTIMATED DATE OF STARTUPt 2/28/86
26. WITS IN TEST STATUS (PRIOR TO Cort 1ERCIAL OPERATION)

FORECAST ACHIEVED INITIAL CRITICALITT

..__/_0 7_/.74 08 INITIAL ELECTRICITT

..../.01/ 74 09 COMMERCIAL UPERATIM 12./.23/.74

  1. - NEGATIVE VALUE REPORTED FOR CONSISTENCT WITH FEDERAL ENERGT REGULATORT CorttISSION REPORTS.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277 UNIT PEACH BOTTort UNIT 2 DATE FEBRUARY 14.1986 COMPANY PHILADELPHIA ELECTRIC COMPANY W.H.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION NUCLEAR GENERATION DIVISION TELEPHONE t215) 841-5022 MONTH JANUARY 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL tit 4E-NET)

(Pt4E-NET )

1 767 17 0

2 2

18 0

3 603 19 6

4 894 20 531 5

656 21 757 6

706 22 862 7

892 23 978 8

885 24 246 9

936 25 0

10 861 26 0

11 651 27 0

12 655 28 0

13 715 29 0

14 867 30

'O 15 0

31 0

16 e

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AVERAGE DAILY LMIT POWER LEVEL 3

DOCKET ND. 278 UNIT PEACH BOTTOM UNIT 3 DATE FEBRUARY 14.1986 COMPANY PHILADELP; IIA ELECTRIC COMPANY d

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

MONTH JANUARY 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL t redE-NET)

(te4E-NET )

1 0

17 0

2 0

18 0

3 0

19 0

i 0

0 20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

0 0

25 0

1 10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

C 10 0

30 0

15 0

31 0

10 0

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tRtIT SHUTD0bo45 Ale PCMER REDUCTIONS DOOLET HD. 50 - 277 194IT NAME PEACH BOTTOM UNIT t DATE FEBRUARY 14.1986 REPORT MONTH JAltJARY,19M COMPLETED BT PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION HUCLEAR GENERATION DIVISION TELEPHONE (215) a41-5o22

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(1)

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(3)

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- FORCED REASON ffETH00 EXHIBIT 5 - INSTRUCTIONS

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

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

EVENT REPORT (LER)

D - REGULATORT RESTRICTION 4 - OTHER (EX88 LAIN)

FILE (HUREG-o161)

{

E. OPERATOR TRAINING + LICENSE EXAMINATION l

UNIT SHUTDole4S AW POWER REDUCTIONS DOCKET NO. 50 - 278 l

UNIT NAME PEACH BOTTON UNIT 3 DATE FEBRUARY 14.1986 REPORT N0HTH JAWARY. 1986 COMPLETED BY PHILADELPHIA ELECTRIC CONPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION NUCLEAR GENERATION DIVISION TELEPHONE (215) 641-5022 w........

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1 1 860101 i S l 744.0 1 C I 4

l N/A l RC l FUELXX l SHUT 00544 FOR SIXTH REFUELING AM) MAINTENANCE I

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[-FORCED REASON NETH00 EXHIBIT G - INSTRUCTIONS J - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1. MANUAL FOR PREPARATION OF DATA B. MAINTENANCE OR TEST 2 - MANUAL SCRAN.

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

EVENT REPORT tLERI C - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (WREG-0161)

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

G - OPERATIONAL ERROR (EXPLAIN)

H - OTHERIEXPLAIN)

FXHIBIT I - SAME SOURCE

Docks t : No. 50- 277 Atttchment to Monthly-Oparcting Report for January,.1986 7 3-REFUELING INFORMATION 1.

Name of facility:

i-Peach Bottom Unit.2 2.

Scheduled date for next refueling sh'utdown:

January 31, 1987 3.

Scheduled date for restart following refueling:

4 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 ' fu'el.

Modifications to reactor core. operating limits.

1 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:

+

i None expected.

7. - The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

i (a)

Core - 764 Fuel Assemblies (b)

Fuel Pool - 146 2 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.

i requested or is planned, in number of; fuel assemblies:

The spent fuel pool storage capacity.has been relicensed for' 2816 fuel assemblies.

A request for approval of replacement higher density - fuel. racks was 1 submitted to the.NRC on June' i

[

13,-1985 which will' increase the fuel pool capacity to a total of 3819 fuel-bundles ~in each fuel pool.

~

l 9.

The projected date of the last refueling ' that can be ' discharged-to

~

the spent fuel pool. assuming'the present licensed capacity..

4 t

March,- ~ 1991 - (September,.1986, with reserve - full core discharge) i

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'Dockat'No.'50 278' 4

Attrchment '~ to Monthly Operating.

Report'for January, 1986 REFUELING INFORMATION 1.

Name of facility:

Peach Bottom Unit 13 2.

Scheduled date for next refueling shutdown:

1 July 14, 1965 3.

Scheduled date for restart following refueling:

February 28, 1986 4.

Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?

i 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:

J MAPLHGR Linits Submitted January 7, 1985 Additional Core Limit Information - April 11, 1985-Importantlicerhingconsiderationsassociatedwithrefueling, 6.

i e.g., new or ditferent fuel design or. supplier, unreviewed design or performance Dnalysis methods, significant changes.in fuel design, new o. !j:ating procedures:

None expeched.

l 7.

The number of fiel assemblies (a) in the core and (b) in the spent-fuel. storage poa1:

(a)

Core -$ 764 Fuel Assemblies (b)

Fuel Pool - 1490 Fuel Assemblies, 6 Fuel Rods i

S.

The preser.i licensed spent fuel pool storage capacity and the size of any inc ease in licensed storage capacity that has been reques ted ir is planned, in number of fuel assemblies:

The spent fuel pool storage capacity has been relicensed for 2816 fuel assemblies.

A request.for approval of replacement-higher density fuel racks was submitted to the NRC on June 13, 1985 which will increase the fuel pool capacity to a total of 3819 fuel bundles in each fuel pool.

l I

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present-licensed capacity.

March, ' 1992 -(March,1987 with reserve for full core discharge)

=

~

Dockot N:o. 50-277/50-278 AttEchmentoto Monthly.

Operating Report for i

+

January, 1986 Peach Bottom Atomic Power Station Narrative Summary of Operating Experiences.

January, 1986 4

UNIT 2 I

l The unit began the report period operating at 85% power.

On January 1, the turbine tripped due to high water level in the

'B' moisture separator, resulting in a scram of the reactor from 931 power.

The high level occurred.as a. result of an incorrect adjustment to the dump valve controller, causing the dump valve to close and the water level to rise to the high level trip point.

Further inspection revealed that an air supply line had broken, causing the normal drain valve to fail closed.

Repairs j

were made to the air supply line, the

'B' moisture. separator drain tank level controllers were adjusted, and the drain and 4

dump valves were checked for proper operation.

On January 2, the unit was returned to service.

From January 4 to January 7, load was reduced to accommodate condenser water box inspections and tube leak repairs.

Load reductions occurred again-from January 8 through January 13 for additional condenser water box inspections and tube leak repairs; however, water chemistry problems due to high conductivity persisted.

The unit was removed from service from January 14 through January 19 to correct inability to completely close C1 z.

water box inlet valve in order to gain access to the tube sheet for tube repair work.

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DockOt Nso. 50-277/50-278 Atttchment to Monthly Operating Report for January, 1986 Page 2 Other repairs performed during this outage were:

I 1.

'B' recirculation pump motor-generator (MG) set controls.

2.

Repair of the

'B' torus vacuum breaker.

On January 24, the reactor scrammed from 964 power due to the closure of two main steam isolation valves.

The valve closures were the result of simultaneous failures of AC and backup DC solenoid valve coils.

The AC coils lost their power when the E-2 diesel generator failed.

Under normal conditions, the diesel generator does not carry this load; however, it was supplying the load to E-22 and E-23 emergency buses in preparation for the Loss of Off-site Power Test on Unit 3.

The DC solenoid coil is believed to have failed because of coil degradation due to high temperature caused by continuous energization and its environment.

Investigation into the cause of the E-2 diesel generator failure revealed. damage to its air blower and turbocharger.

The unit remained shutdown as of January 31 to repair the E-2 diesel generator and to replace the 2B residual heat removal (RHR) pump impeller and wear rings.

DockOt Non. 50-277/50-278 Atttchment to Monthly Operating Report for January, 1986 Page 3 UNIT 3 The unit began the report period shutdown for its sixth refueling and maintenance outage.

Return.to service is scheduled for February 28, 1986.

Reactor hydrostatic pressure testing began on January 5; however, the test was delayed af ter leaks were discovered at the head spray piping vessel flange, the Reactor Core Isolation Cooling (RCIC) inboard isolation valve, the

'C' Reactor Feed Pump (RFP) turbine high pressure steam piping. supply valve, and at three main steam line piping valves.

The head spray flange was tightened, the leaking valves were repaired, and the vessel hydro was resumed on January 11.

Hydrostatic pressure testing of the reactor vessel was completed on January 15.

The containment integrated leak rate test (ILRT) was successfully conducted from January 21 to January 22.

Activities in progress at the end of _ the report period included repair of the

'B' recirculation pump seal and RHR heat exchanger valve repair.

/LLM

/

1 PHILADELPHIA ELECTRIC COMPANY 23O1 MARKET STREET P.O. BOX 8699 PHILADELPHIA PA.19101 1215)841-4000 February 14, 1986 Docket Nos. 50-277 50-278 Director Office of Inspection & Enforcement US Nuclear Regulatory Commission hashington, 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 Botton Units 2 and 3 for the month of January, 1986 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

Ver truly yours

/

f tw.

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 l

' I l

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