ML20076H051

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Monthly Operating Repts for Apr 1983
ML20076H051
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 05/09/1983
From: Alden W, Cooney M
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
References
NUDOCS 8306160379
Download: ML20076H051 (10)


Text

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 (21588414000 May 12, 1983 Docket Nos. 50-277 50-278 Director Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

2055 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 April, 1983, forwarded pursuant to Technical Specification 6.9.1.C under the guidance of Regulatory Guide 10.1, Revision 4.

Very truly yours,

, f sf M. J. Cooney Superintendent Nuclear Generation Division GB:vdw Attachments cc:

Mr.

J. M. Allan, NRC Mr. A. R. Blough, NRC Site Inspector Mr. Stan P. Mangi, Dept. of Envir. Resources GNOpt M g f(3 Mr.

P. A.

Ross, NRC INPO Records Center 1GN gS D

Cedge&

B306160379 830512 PDR ADDCK 05000277 ffM

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DOCKET N3. 50 - 277

==

DATE 51Y 9, 1983

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COMPLETED BY PHILADELPHIA ELECTRIC COMPANY

.-----.==

N.B.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DITISION-NUCLEAR TELEPHONE (215) 841-5022

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OPERATING STATUS

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1. UNIT N ABE: PEACH BOYTOR UNIT 2 i NOTES: UNIT 2 EIPERIENCED TWO l

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2. REPORTING PERIOD:

APRIL, 1983 l

SCHEDULED LOAD REDUCTION.

l g

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3. LICENSED THERBAL POWER (BWV) :

3293 l

1 g

l

4. NAMEPLATE RATING (GROS 3 RWE) :

1152 l

l g

i

5. DESIGN ELECTRICAL RATING (NET REE):

1065 l

l l

l

6. BAYIBUR DEPENDABLE CAPACITY (GROSS REE): 1098 l

1 g

l l

7. RAIINU5 DEPENDABLE CAPACITY (NET BWE):

1051 l

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===

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8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITERS MURBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET 55E) :
10. REASONS FOR RESTRICTIONS, IF ANY:

THIS BONTH YR-TO-DATE CU5ULATITE

11. BOURS IN REPORTING PERIOD 719 2,879 77,327

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_ ---_=

12. NUBBER OF HOURS REACTOR WAS CRITICAL 719.0 2,677.9 57,767.6

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13. REACTOR RESERTE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 7 19.0 2,638.4 56,187.3
15. UNIT RESERVE SHUTDOWN BOURS 0.0 0.0 0.0
16. GROSS THERHAL ENERGY GENERATED (BWH) 2,331 610 8,444,266 164,953,238

=-

==...--

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 773,810 2,797,620 54,318,130
18. NET ELECTRICAL ENERGY GENERATED (BWH) 751,181 2,700,018 52,085,167
19. UNIT SERVICE FACTOR 100.0 91.6 72.7

=_

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20. UNIT AVAILABILITY FACTOR 100.0 91.6 72.7 j
21. UNIT CAPACITY FACTOR (USING RDC NET) 99.4 89.2 64.1
22. UNIT CAPACITY FACTOR (USING DER NET) 98.1 88.1 63.2 0.0 0.9 7.4
23. UNIT FORCED OUTAGE RATE

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24. SHUTDOWNS SCHEDULED OTER NEXT 6 50NTHS (TYPE, DATE, AND DURATION OF EACH) :

I REFUELING-BAINTENANCE OUTAGE BEGINNING 10/15/83 FOR 13 UEEKS.

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIBATED DATE OF STARTUP:
26. UNITS IN TEST STATUS (PRIOR TO COMBERCIAL OPERATION) :

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY

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C055ERCIAL OPERATION

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CPERATING DATA REPORT DOCKET NO. 50 - 278

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DATE RAY 9, 1983 COBPLETED BY PHILADELPHIA ELECTRIC COMPANY

_-=---

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

1. UNIT NAME: PEACH BOTTOR UNIT 3 I NOTES: UNIT 3 CONTINUED SCHEDUL D l

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2. REPORTING PERIOD:

APRIL, 1983 i

SHUTDOWN FOR REFUELING.

I g

l

_-_.==

3. LICENSED THERB AL POWER (BWT) :

3293 l

l g

g

4. NAMEPLATE RATING (GROSS EWE) :

1152 l

l g

g

5. DESIGN ELECTRICAL RATING (NET BWE) :

1065 l

l l

1

6. 511I505 DEPENDABLE CAPACITY (GROSS RWE): 1098 l

1 g

i

7. BAIIMUM DEPENDABLE CAPACITY (NET MBE):

1035 l

l

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITERS NU5BER 3 THR06Gk 7) kINCE LAST REPbdT, GIYb kEASONS
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET RUE) :
10. REASONS FOR RESTRICTIONS, IF ANY:

THI3 RONTH YR-TO-DATE CUMULATIVE

11. BOURS IN REPORTING PERIOD 719 2,879 73,223
12. NUMBER OF HOURS REACTOR WAS CRITICAL 0

1,039.3 54,969.0

.13. REACTOR RESERTE SHUTDouN HOURS 0.0 0.0 0.0 0.0 1,026.3 53,627.1 14 HOURS GENERATOR ON-LINE

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THER5AL ENERGY GENERATED (sWB) 0 2,742,355 155,957,983
17. GROSS ELECTRICAL ENERGY GENERATED (MBH) 0 894,560 51,136,090

=---

-3,664 837,790 49,080,582

18. NET ELECTRICAL ENERGY GENERATED.(BWH) 0.0 35.6 73.2
19. UNIT SERVICE FACTOR 0.0 35.6 73.2
20. UNIT AVAILABILITY FACTOR
21. UNIT CAPACITY FACTOR (USING HDC NET) 0.0 28.1 64.8
22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 27.3 62.9 0.0 2.6 7.3
23. UNIT FORCED OUTAGE R ATE
24. SHUTDOWNS SCHEDULED OVER NEIT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

SCHEDULED SHUTDOWN FOR REFUELING AND MAINTEN ANCE, STARTED 2/13/83. OUTAGE CONTINUING TO FIRST HALF OF JUNE.

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUF:
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION) :

FORECAST ACHIEYED INITIAL CRITICALITY INITIAL ELECTRICITY COM5ERCIAL OPERATION

4

(

8 DOCKET NO. 50 - 277 UNIT SHUTDOWNS AND POdER REDUCTIONS

)

UNIT R&HE PEACH BOTTOR DNIT 2 e

DATE BAY 9, 1983 COBPLETED BY PHILADELPHIA ELECTRIC COMPANY REPORT NONTH APRIL, 1983 N.n.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPuONE (215) 841-5022 l

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l l METHOD OF l LICENSEE ISTSTEElC05PONENTl CAUSE AND CORRECTIVE EVENT l CODE l CODE l ACTION TO I

ITYPEl DURATION l REASON l SHUTTING DOWNl NO.)

DATE l (1) l (HOURS)l (2) l REACTOR (3) l REPORT 8 I (4) l (5) l PRETENT RECURRENCE l

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l NA l RC l ZZZZ11 l LOAD REDUCTION FOR CONTROL ROD PATTERM I

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EIMIBIT G - INSTRUCTIONS METHOD 1 - NANUAL FOR PREPARATION OF DATA F - FORCED REASON

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S - SCHEDULED

& - EQUIPMENT FAILURE (EIPLAIN) 2 - MANUAL SCB&5.

ENTRY SHEETS FOR LICENSEE B - M AINTEN ANCE OR TEST 3 - AUTon& TIC SCRAM.

EVENT REPORT (LER) 4 - OTHER (EIPLAIN)

FILE (NUREG-0161)

C - REFUELING

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D - REGULATORY RESTRICTION E - OPER ATOR TR AINING + LICENSE EI&MINATION (5)

F - ADMINISTRATIVE I)

G - OPERATIONAL ERROR (EXPL&IN)

EINIBIT I - S&ME SOURCE H - OTHER (EIPLAIN)

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=J UNIT SHUTDONES AND PONER REDUCTIONS DOCKET NO. 50 - 278 UNIT MAME PEACH BOTTOR UNIT 3 up DATE MAY 9, 1983

=7 BEFORT MONTE APRIL, 1983 CONPLETED BY PHILADELPHIA ELECTRIC COMPANY W.H.4LDEN ENGINEER-IN-CHARGE

%d LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 d

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l l METHOD OF l LICENSEE ISYSTEMICORPONENTI CAUSE AND CORRECTITE l

l TYPE l DURATION lBEASONISHUTTING DONNI EVENT l CODE I CODE l ACTION TO NO.l DATE I (1) { (HOURS)I (2) l REACTOR (3) i REPORT 8 l (4) l (5) l PREVENT RECURRENCE I

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F - FORCED REASON METHOD EIHIBIT G - INSTRUCTIONS S - SCHEDULED 1 - EQUIPMENT FAILURE (EIPLAIN) 1 - M&MUAL FOR PREPARATION OF DATA 8 - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

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

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (N U REG-0161)

E - OPERATOR TRAINING + LICENSE EIANINATION (5)

F - ADMINISTRATIVE G - OPERATIONAL ERROR (EIPLAIN)

EIHIBIT I - SAME SOURCE H - OTHER (EIPL&IN)

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AYERAGE DAILY UNIT POWER LEYEL

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DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE HAY 9, 1983 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 HONTH APRIL 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MW E-NET)

(M WE-NET) 1 1033 17 1067 2

760 18 1060 3

999 19 1057 4

1055 20 1055 5

1052 21 1057 6

1055 22 1044 7

1053 23 1032 i

8 1052 24 1020 l

9 1058 25 1064 10 1050 26 1058 11 1056 27 1065 12 1061 28 1066 13 1063 29 1065 14 1057 30 1063 15 1055 l

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16 1056 l

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AYERAGE DAILY UNIT POWER LEYEL DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE MAY 9, 1983 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR IELEPHONE (215) 841-5022 MONTH APRIL 1983 DAY AYERAGE DAILY POWER LEVEL DAY AYERAGE DAILY POWER LEYEL fiJ (MWE-NET)

(MW E-NET) 1 0

17 0

2 0

18 0

19 0

3 0

4 0

20 0

21 0

5 0

6 0

22 0

7 0

23 0

24 0

8 0

25 0

9 0

10 0

26 0

27 0

11 0

t 28 0

12 0

29 0

13 0

30 0

14 0

15 0

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Attcchm:nt to Monthly J

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Operating RSport For Month of April,1983 i

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 fuel.

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 pool:

(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) t

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'g Op3rcting Raport For Month of April,1983 1

REFUELING INFORMATION 1.

Name of Facility:

Peach Bottom Unit 3 2.

Scheduled date for next refueling shutdown:

February 13, 1983 3.

Scheduled date for restart following refueling:

First Half of June 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(s) for submitting proposed licensing action and supporting information:

Submitted December 30, 1982 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 and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

t l

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:

September, 1990 (March,1986 with reserve for fuel core discharge)

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PEACH BOTTOM ATOMIC POWER STATION NARRATIVE

SUMMARY

OF OPERATING EXPERIENCES 1

APRIL, 1483 Unit 2 The unit began the month at full power.

Load was reduced on April 2.for control rod pattern adjustment.

The unit was returned to full power on April 3.

On April 22, load was reduced to 850 MWe for control rod pattern adjustment.

The unit returned to full power on April 23rd and remained at full power for the remainder of the month.

The March report should have included a brief outage of the E-2 Diesel Generator on March 28 to repair a small leak on a jacket coolant vent line.

Unit 3 The unit continues in its fif th refueling outage.

Power range neutron detector reolacement was completed.

The in-vessel ISI of the core spray spargers was performed.

Induction Heating Stress Improvement and ISI of Reactor

. Recirculation and RHR piping continued.

Crack indications were found on several jet oump risers.

The reactor water cleanup system was chemically decontaminated to allow repairs to a non-regenerative heat exchanger.

Fuel movement continued throughout the month as conditions oermitted.

The Unit 3 reload license amendment has been received from the NRC.