ML20027B554

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Monthly Operating Repts for Aug 1982
ML20027B554
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 09/13/1982
From: Alden W
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20027B551 List:
References
NUDOCS 8209210241
Download: ML20027B554 (9)
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Text

.

  • - OPERATING DATA REPORT DOCKET No. 50 - 277 DATE SEPTEMBER 13, 1982 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER *IN-CHARGE NUCLEAR SECTION GENER ATION DIVISION-NUCLEAR TELEPH ON E (215) 841-5022

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

07ERATING STATUS

. ________ _ _= _______________ ______________________ .

1. UNIT NAME: PEACH BOTTOM UNIT 2 l NOTES: UNIT 2 EXPERIENCED ONE l

_ _ _ _ . . . . . . _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ . - g g

2. REPORTING PERIOD: AUGUST, 1982 l SCHEDULED LOAD REDUCTION l g  ;
3. LICENSED THERM AL POWER (MWT) : 3293 l AND ONE SCHEDULED SHUT- l

..._- =_...... g  ;

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

.=- ____ g  ;

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

_.=_

l l

6. MAIIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098 l l

.... g g

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) : 1051 l l
8. I? CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 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 744 5,831 71,519
12. NUMBER OF HOURS REACTOR WAS CRITICAL 617.8 2,668.8 52,412.2
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

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

14. HOURS GEN ERATOR ON-LINE 589.5 2,471.3 50,927.8

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

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERM AL ENERGY GENERATED (BWH) 1,795,430 6,980,268 148,203,584
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 590,750 2,265,570 48,769,340
18. NET ELECTRICAL ENERGY GENERATED (MWH) 566,289 2,153,050 46,743,785

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

19. UNIT SERVICE FACTOR 79.2 42.4 71.2

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

20. UNIT AVAILABILITY FACTOR 79.2 42.4 71.2
21. UNIT CAPACITY FACTOR (USING MDC NET) 72.4 35.1 62.2
22. UNIT CAPACITY FACTOR (USING DER NET) 71.5 -~34.7 61.4
23. UNIT FORCED OUTAGE RATE 0.0 1.3 7.8
24. SHUTDOWNS SCHEDULED OYER NEIT 6 MONTHS (TY PE, DATE, AND DUR ATION OF EACH) :
25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPER ATION) : FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPERATION R20921oa91

OPE 2ATING DATA REPORT DOCKET NO. 50 - 278

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

DATE SEPTEMBER 13, 1982

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

COMPLETED BY PHILADELPHIA ELECTRIC COMPANY

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

N.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GEMERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 OPERATING STATUS

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

1. UNIT NAME: PEACH BOTTOM UNIT 3 l NOTES: UNIT 3 EXPERIENCED l

. ----...... --.. - = . g i

2. REPORTING PERIOD: AUGUST, 1982 l ONE FORCED LOAD l

-- ....--_.--. - ------- g g

3. LICENSED THERM AL POWER (MUT) : 3293 l REDUCTIONS. l

__- __ =-- --- g i

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

-=- g g

5. DESIGN ELECTRICAL RATING (NET MWE) : 1065 I l

. g g

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

.... g l

7. MAIIMUM DEPENDABLE CAPACITY (RET MWE): 1035 l 1

=----

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

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE 1&ST REPORT, GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (WET MWE):
10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE I

11. HOURS IN REPORTING PERIOD 744 5,831 67,415
12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 5,513.3 51,000.7
13. R2 ACTOR RESERVE SHUTD0m' 0URS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 744.0 5,445.0 49,671.8 a --.---..-... .-...--.---- ...--- =
15. UNIT RESERVE SMUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENER ATED (MWH) 2,418,245 17,442,278 144,133,800
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 803,240 5,837,740 47,226,660

-- ====-...

18. NET ELECTRICAL ENERGY GENERATED (MWR) 772,802 5,639,968 45,350,441
19. UNIT SERVICE FACTOR 100.0 93.4 73.7

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

l

20. UNIT AVAILABILITY FACTOR 100.0 93.4 73.7

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

21. UNIT C APACITY FACTOR (USING MDC NET) 100.4 93.5 65.0

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

22. UNIT CAPACITY FACTO R (USING DER NET) 97.5 -

90.8 63.2-

=- __ = _ -

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

d

23. UNIT FORCED OUTAGE RATE 0.0 6.6 7.8
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (?YPE, DATE, AND DURATION OF EACH):

J

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPER ATION) : FORECAST ACHIEVED INITIAL CRITICALITY

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

INITIAL ELECTRICITY COMMERCIAL OPERATION

.y. ,% ,_ - - - _ - - - - - -

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 277 UNIT NAME PEACH BOTTOM UNIT 2 DATE SEPTEMBER 13, 1982 REPORT MONTH AUGUST, 1982 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY

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

W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 l l l l l METHOD OF l LICENSEE l SYSTEM l COMPONENT l CAUSE AND CORRECTIVE l l TYPE l DURATION l REASON l SHUTTING DOWNl EVENT l CODE l CODE l ACTION TO NO.l DATE l (1)l (HOURS)l (2) l REACTOR (3) l REPORT 8 l

__- =- ..... --

(4) l (5) l FREVENT RECURRENCE I l l l l l 1 I l 6 l 820806 l S l 154.5 l B l 1 i NA l CB l PUMPII l SHUT DOWN FOR REPLACEMENT OF THE '21' l l l l l l l l l AND '2B' RECIRCULATION PUMP SEALS. ,

l l l l l l l l l 7l 820821 l 5 l 00.0 l H l 4 l NA l RC l ZZZZZZ l LOAD REDUCTION FOR THE ADJUSTMENT OF THE l l l l l l l l l CONTROL ROD PA TTERN.

I l l - - - - - l i l l l l I I i 154.5 l l l l l l (1) (2) (3) (4)

F - FORCED REASON METHOD EIHIBIT G - INSTRUCTIONS S - SCHEDULED A - EQUIPMENT FAILURE (EIPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER)

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

E - OPERATOR TRAINING + LICENSE EIAMINATION F - ADMINISTR ATIVE (5)

G - OPERATIONAL ERROR (EIPLAIN)

H - OTHER (EIPLAIN) EIHIBIT I - SAME SOURCE I

l

UNIT SHUTDONNS AND PONER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3

___ ==-

DATE SEPTEMBER 13, 1982

.. = -___ -- ..

REPORT MONTH AUGUST, 1982 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY

== ____.-

_ _ _ = - - - - - ___

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

- - - - _ = -

- _ = _=__ --

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

l l l l l METHOD OF -l LICENSEE lSISTEMICOMPONENTI CAUSB AND CORRECTIVE I l TYPE l DURATION l REASON l SHUTTING DONNl EVENT l CODE l CODE l ACTION TO N3.l DATE I (1)l (HOURS) l (2) l REACTOR (3) l REPORT 8 l (4) l (5) l PREVENT RECURRENCE i I l l l l 1 1 l

13 I 820812 l F l 00.0 l A l 4 l WA l HG l DEMINI l MAIN STEAM LINE RADIATION MONITOR SPIKED l l l l l l l l l UPSCALE, DUE TO TRANSIENT INCURRED NHILE l l l l l l l l l PLACING '3J' CONDENSATE DEMINERALIZER

  • I I l 1 1 I I l l IN SERVICE.

I l 1 ----- l 1 l l l l 1 I l - 1 I l l l 1 -

(1) (2) (3) (4)

F - FORCED REASON M ETHOD EIHIBIT G - INSTRUCTIONS S - SCHEDULED A - EQUIPMENT FAILURE (EIPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - M AINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER)

D - R EGULATORY RESTRICTION 4 - OTHER (EIPLAIN) FILE (NU R EG-0161)

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

G - OPERATIONAL ERROR (EIPLAIN)

H - OTHER (EIPLAIN) EIHIBIT I - SAME SOURCE

. . AVERAGE JAILY UNIT PO.WSR L'EVEL DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE SEPTEMBER 13, 1982 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION .,

GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 o MONTH AUGUST 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (M WE-N ET) (MWE-NET) 1 - 1045 17 842 2 1044 18 1042 3 1047 19 1045

{ 4 1046 20 1043 5 1043 21 705 6 1047 ,

22 923 7 24 23 1038 8 0 24 1041 9 0 25 1046 I 10 0 26 1046 J

11 0 27 1049 12 0 28 1052

13 138 29 1051 14 786 30 1052 15 705 31 1054 16 707 1

, AVEdAGE DAILY 'J N IT PO91t LEVEL I

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

DATE SEPTEMBER 13, 1982 COMPANY PHILADELPHIA ELECTRIC COMPANY -

W.M.ALDEN ENGINEER-IN-CHARGE

. NUCLEAR SECTION '

GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH AUGUST 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (M WE-NET) (MWE-NET) 1 1023 17 1046 2 1043 18 1047 i 3 1039 19 1051 4 1035 20 1051 5 1035 21 1051 l 6 1034 22 1050 l 7 993 23 1049 i

8 1045 24 1047

}

9 1049 25 1047 10 1049 26 1045 11 1046 27 1043 12 1013 28 1043 13 959 29 1041 1 14 1052 30 1040 l

l 15 1052 31 1033 16 1050 0

PEACH BOTTOM ATOMIC POWER STATION NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AUGUST 1982 Unit 2 The unit began the month at full power. The unit shutdown on August 6 to replace the shaft seals on both recirculation pumps, and returned to power on August 13. Load was reduced on August 21 to adjust the control rod pattern. The unit returned to full power on August 22.

The E-1 Diesel Generator was out of service for approximately eight hours on August 25 due to a grounded overspeed trip switch. The switch was repaired and the diesel generator returned to service. On August 27, the E-1 Diesel Generator was removed from service to install a new overspeed trip switch.

Unit 3 The unit began the month at full power. Late on August 12, load was reduced due to a Main Steam Line Radiation Monitor spike incurred while placing the 3J Condensate Demineralizer in service. The unit returned to full power the following day.

On August 30, the failure of both 24 volt D.C. power supplies in one ECCS initiation system logic caused a very brief inadvertent RCIC injection to the reactor vessel and erratic operation of ECCS initiation relays. The RCIC injection resulted in a slight reactor power increase from 100% to approximately 104%. Upon verification of proper reactor water level, the RCIC system was tripped. Both ECCS power supplies were replaced within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and the ECCS initiation system was returned to normal.

. Docket No. 50-277 Attcchmant to l Monthly Opercting '

Rnport for August, 1982 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:

October 29, 1983

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:

July 29, 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 - 1216 Fuel Assemblies

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.

September, 1990

Docket No. 50-278 Attcchmant to Monthly Operating Report for August, 1982 REFUELING INFORMATION

1. Name of facility:

Peach Bottom Unit 3

2. Scheduled date for next refueling shutdown:

February 12, 1983

3. Scheduled date for restart following refueling:

April 8, 1983

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:

December 17, 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 - 934 Fuel Assemblies

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.

September, 1991

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