ML20076M691

Monthly Operating Repts for June 1983

ML20076M691
Person / Time
Site:	Peach Bottom
Issue date:	07/14/1983
From:	Alden W, Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8307210045
Download: ML20076M691 (11)

Text

._

OPER172NG DATA REPORT DOCKET No. 50 - 277 DATE JULT 13, 1983 COEPLETED BY PHILADELPHIA ELECTRIC COBPANY

______e._

W.R.ALDEN.

ENGINEER-IN-CHadGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 OPERATING STATUS

1. UNIT NAME: PEACH BUTT 05 UNIT'.2.

NOTES: UNIT 2 EXPERIER*ED ONE l

l 1

2. REPORTING PERIOD:

JUNE, 1983 l

FORCED LORD REDUCTION

.l g

g

3. LICENSED THERMAL POWER (MUT) :.

3293 l

AND ONE SCHEDULED LOAD l

g

4. NAMEPLATE RATING (GROSS BWE) :

1152 l

REDUCTION.

l g

g

5. DESIGN ELECTRICAL RETING (NET RWE):

1065 l

l g

._l t

6. 512I505 DEPENDABLE CAPACITY (GROSS MWE): 1098 i

l l

.g

'l

7. 511IM05 DEPENDABLE CAPACITY (BET BWE) :

1051 l

8. IF CHANGES OCCUR IN CAPACIT! RATINGS (ITEMS N05BER 3 THROUGH 7) SINCE LAST REPORT,.GIVE REASONS:

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

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS SGNTH YR-TO-DATE CUBULATIVE

11. HOURS IN REPORTING PERIOD 720 4,343 78,791

12. NUEBER OF HOURS REACTOR WAS CRITICAL 720.0 3,824.8 58,914.5

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

14. HOURS GENER ATOR ON-LINE 720.0 3,743.8 57,292.7

15. UNIT RESERVE SHUTDOWN BOURS 0.0 0.0 0.0

16. GROSS THER51L INERGY GENERATED (555) 2,326,630 11,912,451 168,421,423

17. GROSS ELECTRICAL ENERGY GENERATED (595) 769,140 3,932,330 55,452,840

18. NET ELECTRICAL ENERGY GENERATED (BWH) 742,485 3,792,982 53,178,131

19. UNIT SERVICE FACTOR 100.0 86.2 72.7

20. UNIT AY1ILABILITY FACTOR 100.0 86.2 72.7

==-

21. UNIT CAPACITY FACTOR (USING BDC NET) 98.1 83.1 64.2

22. UNIT CAPACITY FACTOR (USING DER NET) 96.8 82.0 63.4

23. UNIT FORCED OUTAG; RATE 0.0 9.3 7.8

24. SHUTDOWNS SCHEDULED OVER NEIT 6 50NTHS (TYPE, DATE, AND DURATION OF E1CH):

REFUELING-MAINTEN ANCE OUTAGE BEGINNING 10/15/83 FOR 13 WEEKS.

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTI51TED DATE OF STARTUP:

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

FOREr1ST ACHIEYED INITIAL CRITIC 1LITT INITIAL ELECTRICITY C055ERCIAL OPERATION 8307210045 830714 PDR ADOCK 05000277 R

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DOCKET 30. 50 - 278 1

i DATE JULY 13, 1983 CosPLETED BY PHILADELPHIA ELECTRIC C05PANY N.B.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 OPERATING STATUS

1. UNIT NABE: PEACE 30ff05 UNIT 3 l NOTES: UNIT 3 CONTINUED SCHEDULED l

g g

2. REPORTING PERIOD:

JUNE, 1983 i

SHUTDn5N FOR REFUELING.

1 g

3. LICENSED THERRAL POWER (RWT) :

3293 l

l g

g

4. NAREPLATE RATING (GROSS BWE) :

1152 l

l g

5. DESIGN ELECTRICAL. RATING (NET EWE):

1065 l

l g

l

6. 54II505 DEPENDABLE CAPACITY (GROSS 55E) : 1098 l

l g

g.,

7. BAIIBUR DEPENDABLE CAPACITY (NET ENIO:

1035 l

l

8. IF CHANGES OCCUR IN CAPACITY BATINGS (ITEMS NURSER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

9. POWER LEVEL TO NEICE RESTRICTED, IF ANY '(NET ENE1

10. RE ASONS FOR RESTRICTIONS, IF ANY:

THIS 50NTS YR-TO-DATE CURULATIVE

11. ROURS IN REPORTING PERIOD 720 4,343 74,687

12. NUMBER OF HOURS REACTOR WAS CRITICAL 0

1,039.3 54,969.0

13. REACTOR RESERVE $5DTDOWN E0035 0.0 0.0 0.0

--...-=

14. BOURS GENERATOR ON-LINE 0.0 1,026.3 53,627.1

15. UNIT RESERVE $5DTDOWN BOURS 0.0 0.0 0.0

16. GROSS THER5 AL ENERGY GENES &TED (5NE) 0 2,742,355 155,957,983

17. GROSS ELECTRICAL ENERGY GENERATED (555) 0 894,560 51,135,090

--- =

18. NET ELECTRICAL ENERGY GENERATED (555)

-6,374 825,998 49,068,790

19. UNIT SERVICE FACTOR 0.0 23.6 71.8

20. UNIT AVAILABILITY FACTOR

' 0.0 23.6 71.8

21. UNIT CAPACITY FACTOR (OSIN, RDO NET) 0.0 18.4 63.5 22.' UNIT CAPACITY FACTOR (USikJ : DER NET) __

0. 0.._

.17.9_

61.7

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23. UNIT 'FORCID OUTAGE B ATE 0.0 2.6 7.3

24. SHUTDOWNS SCREDULED OVER NEIT 6 50NTHS (TYPE, D ATE, AND DUR ATION OF E&CE) :

SCREDULED SEUTDOWN FOR REFUELING AND BAINTENANCE, STARTED 2/13/83.

25. IF SEUTDOWN AT END OF REPORT PERIOD, BSTIn&TED DATE OF STARTUP: 8/15/83

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY C055ERCIAL OPERATION

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AVERAGE' DAILY UNIT POWER LEVEL o.

s DOCKET NO. 50 - 277 j

UNIT PEACH BOTTOM ONIT 2 DATE JULY 13, 1983 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 k

MONTH JUNE 1983 C4

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DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 3

(M NE-NET)

(M WE-N ET) 1 1047 17 1016 f'

2 1053 18 994 3

1053 19 846 2 4 1050 20 1032 1044 21 1044 6

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE JULY 13, 1983 CONPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH JUNE 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 0

17 0

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18 0

3 0

19 0

4 0

20 0

5 0

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8 0

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9 0

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Docket No. 50-277 Attachment to Monthly Operating Report for June, 1983 REFUELING INFORMATION 1.

Name of facility:

Peach Bottom Unit 2 2.

Scheduled date for next refueling shutdown:

October 15, 1983 3.

Scheduled date for restart following refueling:

January 14, 1984 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 fue' Modifications to reactor core operating limits are expected.-

5.

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

September 30, 1983 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 pools (a)

Core - 764 Fuel Assemblies (b)

Fuel Pool - 1170 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 2816 fuel assemblies.

9.

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

March, 1990 (September, 1985 with reserve for full core discharge)

Docket No. 50-274 Attachment to Monthly operating Report for June, 1993 REFUELING INFORMATION 1.

Name of facility:

Peach nottom Unit 3 2.

Scheduled date for next refueling shutdown:

February 13, 1993 3.

Scheduled date for restart following refueling:

August 15, 1993 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 are expected.

5.

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

Submi tted on Decon'>er 30, 1992, amended by MnC on klay 4,

1993 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, now 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 - 1212 Fuel Assemblies, 6 Fuel Rods 8.

The present licensed spent fuel pool storage capacity ar.d 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 2816 fuel assemblies.

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

Sentember, 1990 (March, 1996 with reserve for fuel core discharge)

i Peach Bottom Atomic Power Station Narrative Summary of Operating Experiences June, 1983 Unit 2 The unit began the month at full power.

On June 10, a Reactor Protection System instrument power supply was replaced when high ripple voltage was detected during routine Surveillance Tests.

On June 11 the Reactor Water Cleanup System Inlet Inboard Isolation Valve failed to close during Surveillance Test.

The valve was declared operable on June 13 after the problem was identified to be auxilliary switch contacts at the motor contactor, and a method was employed to ensure that the contacts would be verified each time the valve was opened. Shortly after the

'G' Condensate Demineralizer was put in service on June 15, the main steam line radiation increased to 150% of full power background.

The demineralizer was removed from service and reactor power reduced to 810 MWe to stabilize main steam line radiation leveln.

The unit returned to full power operation early on June 16.

Reactor power was reduced to 700 MWe on June 18 for a control rod adjustment.

The unit was returned to full power on June 20.

On the evening of June 20, it was discovered that the relief device on one phase of a start up source transformer had failed.

This startup source was de energized until this relief device was repaired early on June 21.

On June 24, during Surveillance Testing, the High Pressure Coolant Injection System failed to operate.

The cause of the failure was found to be a failed electronic component which was replaced and the system tested satisfactorily.

On June 28, the annual Emergency Plan Graded Exercise was conducted.

Results were satisfactory, with minor deficiencies noted.

The unit ended the month at full power.

Unit 3 Unit 3's Fifth Refueling Outage continued throughout the month.

Reactor refueling was completed on June 20.

Major activities ongoing throughout the month included clad overlay repair to Reactor Recirculation System Piping and Shutdown Cooling

Piping, maint'enance and testing of various Primary Containment System Valves, and mud removal from the Service Water

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o Summary of 10CFR50.59 Review for Temporary On-Site Storage of Radioactive Material A storage area will be' established on the second floor of the former Unit 1 auxiliary building for the temporary storage of radioactive material utilized at the Peach Bottom Unit 2-3 facility.

The safety evaluation, performed in accordance with Generic Letter 81-38, concluded that storage in the designated area.as specified in the evaluation meets the regulatory require-raents and does not constitute an unreviewed safety question. The amount of radioactive material present will be controlled based on the total volume and measured dose rate limitations specified in the safety evaluation.

Only dry material in metal containers will be stored.at the storage facility.

Ten percent of the total storage volume (720 cubic feet) may have contact dose rates up to.50 mrem /hr.

The remainder of the material (6480 cubic feet) will have an average contact dose rate per container of less than 10 mrem /hr.

The dose assessment indicates that the storage facility is within the regulatory limitations of 40CFR190 and 10CFR20.

A chain link fence surrounds the former Unit 1 facility with access under the control of the Peach Bottom security organization. This information is being provided as requested in a June 12, 1980 letter (R.W. Reid, NRC to E.G.

Bauer, Jr., PECO) i b

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O'. BOX 8699 PHILADELPHIA. PA.19101 1215)841-4000 July 14, 1983 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 twe?.ve copies of the monthly operating report for Peach Bottom Units 2 and 3 for the month of June, 1993 forwarded pursuant to Technical Specification 6.9.1.C under the guidance of Requiatory Guide 10.1, Revision 4.

uly yours, Y

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M. J Cooney t

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_rintendent Nuclear Generation Division Attachment cc:

Dr. T. E. Murley, NRC-Mr. A.

R. Blough, NRC Site Inspector Mr. Stan P. Mangi, Dept. of Envir. Resources Mr.

P. A. Ross, NRC INPO Records Center t