ML19241B285

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Monthly Operating Rept for June 1979
ML19241B285
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 07/10/1979
From: Alden W
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML19241B283 List:
References
MOR-790630, NUDOCS 7907130431
Download: ML19241B285 (8)
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Text

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE JULY 10, 1979 COMPANY PHILADLLPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLE AR .iECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022

-- - = - - _ = = = - _ _ _ _ _ _ _- - - -

MONTH JUNE 1979 DAY A*/ERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET) (MWE-NET) 1 1067 17 1048 2 1065 18 1065 3 1063 19 1064 4 1062 20 1061 5 1065 21 1063 6 1064 22 1065 7 1064 23 1069 ,

8 1045 24 1067 9 893 25 1065 10 1054 26 1066 11 1063 27 1068 12 1070 28 1063 13 1065 29 1066 14 1059 30 1065 15 1061 16 1064 g 3f 2_._

7907330 W /

OPE RATING DAT A REPORT DOCKET NO. 50 - 277 DATE JULY 10, 1979 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN

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

1. UNIT NAME3 PEACH BOTTOM UNIT 2 1 NOTES: THIS UNIT EXPERIENCED NO

_ _______-_-__ -- g l

2. REPORTING PERIOD 8 J UN E , 1979 l MAJOR POWER REDUCTION OR I l l
3. LICENSED 1HERMAL POWER (MWT): 3293 l OUTAGES THis MONTH l

__ -_____ g i

  • . NAMEPLATE RATING (GROSS MWEls 1152 l I

== - _ _

l l

5. DESIGN ELECTRICAL RATING (NET MWE): 1065 l 1

-_____-__ g l

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWEls 1098 l l

____ g l

7. M AXIMUM DEPE NO ABL E C AP ACITY (NET MWEls 1051 l l B. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THRDUGH 7) SINCE LAST REPORT, GIVE REASONS
9. POWER LEVEL TO WHICH RESTRICfED, IF ANY INET MWEla
10. REASONS FOR RESTRICTIONS, IF ANYt THIS MONTH YR-TO-DATE CUMUL A T IVE
11. HOURS IN REPORTING PERIOD 720 4,343 43,727

=

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720 4,001 33,421
13. REACTOR RESERVE SHU?DOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 720.0 3,977h 32,664.1
15. UNIT RE SERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) ,

2,351,309 12,756,231 92,977,188

17. GROSS ELECTRICAL ENERGY GENER ATED (MwH) 790,270 4,278,570 30,444,500
18. NE T ELECTRICAL ENERGY GENERATED (MWHI 761,197 4,13%,737 29,177,092
19. UNIT SERVICE FACTOR 100 0 93 6 74.7
20. UNIT AVAILABILITY FACTOR 100.0 91.6 74.7
21. UNIT r.APACITY FACTOR 1USING MDC NET) 100.6 90.6 63.5

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

22. UNIT CAPACITY FACTOR (USING DER NET) 99 3 89 4 62.7
23. UNIT FORCED OUTAGE RATE 0.0 0.8 7.0
24. SHUfDOWNS SCHEDULED OVER NEXT A MONTHS (TYPE D$TE,ANDDURATIOk0FEACHit
25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP 6/ 6/80
26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPER ATIDN): FORECAST ACHIEVED -

INITIAL CRITICALITY su INITIAL ELECTRICITY COMMERCIAL OPERATION

UNIT NAME PEACH BOTTOM UNIT 2 DATE JULY 10, 1979 g REPORT PONTH JUNE. 1979 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCL E A R SECTION GENERATION DIVISION-NUCLEAR Qy TELEPHONE (215) 841-5022 l l l l l METHOD OF l LICENSEE ISYSTEMICOMPONENTI CAUSE AND CORRECTIVE l lTYPEIDURATIONIREASONISHUTTING DOWN1 EVENT l CODE I CODE I ACTION TO NO.1 DATE I (111 (H00RSil (2) l REACTOR (3) l REPORT e 1 (4) l (5) l PREVENT RECURRENCE I i l l I I I I I i l - 1 I I I I I a,-A (1) (2) (3) (4) 4 r3p r&,.

i - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S - SCHEDULED A- EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA bN B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE hi[%

C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER) tmm 0 - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN) FILE (NUREG-0161) CQ E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5) %g G - OPERATIONAL ERROR (EXPLAIN) < *J us H - OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE CC C"D Q.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE JULY 10, 1979 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH JUNE 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET) (MWE-NET) 1 907 17 598 2 0 18 816 3 0 19 1007 4 0 20 1027 5 0 21 465 6 0 22 136 7 0 23 732 8 0 24 844 9 0 25 1032 10 0 26 967 11 15 27 1035 12 563 28 1037 13 558 29 1038 14 0 30 1038 15 0 16 34

& Y$

. OPERATING OATA REPOR1 DOCKET NO. 50 - 278 DATE JULY 10, 1979 COMPLETE 0 BY PHIL ADELPHI A ELECTRIC COMPANY h.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (2153 841-5022

__________ =_ __ -- - -

OPERATING STATUS l . UN I T NAME: PEACH BOTTOM UNIT 3 l NOTES: THIS UNIT EXPERIENCED NO I

_ g g

2. RE PORTING PE RIOD: JUNE, 1979 l MAJOR POWER REDUCTIONS AND l

__- ==--- =___-- ==_____ g l

3. LICENSED THERMAL POWERIMWT): 3293 l THREE OUTAGES THIS MONTH l l 1
4. NAMEPLATE RATING (GROSS MWE l s 1152 l 1 g g
5. DE SIGN ELECTRIC AL R ATING (NET MWE): 1065 l l

_________ g i

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

____ g  ;

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1035 l l
8. IF CHANGES OCCUR IN C APACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NE T MWE l:
10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH VR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720 4,343 39,623
12. NUMBER OF HOURS REACT 0A WAS CRITICAL 424 3,744 31,854
13. REACTOR RESERVE SHUTDOWN HOURS 00 0.0 00

______=--

14. HOURS GENER ATOR ON-LINE 388.6 3,600.3 31,030 2
15. UNIT RE SERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. TROSS THERMAL ENERGY GENERATED (MWHI 1,b78,003 10.964,913 85,839,049
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 347,400 3.620,670 27,848,780
16. NET ELECTRIC #t ENERGY GENERATED (MWHI 328 607 3,492,034 26,735,177 19 UNIT SERV 1CE FACTOR 54 0 82 9 78 3
20. UNIT AVAILABILily FACTOR 54.0 82.9 78 3
21. UNIT CAPACITY FACTOR (USING MDC NET) 44.1 77.7 65.2
22. UNIT C APACITY F ACTDR (USING DEE NET) 42 9 75 5 63 4
23. UNIT FORCED OUTAGE RATE 20.b 3.4 7.1 24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND OURATION OF EACHl:

9/8/79 TO 10/20/79 REFUELING OUTAGE

25. IF SHUTDOWN AT END OF REPORT PERIOD, E STIMATED DATE OF STARTUP: 10/20/79
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION -

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE JULY 10, 1979

{N, REPORT MONTH JUNE, 1979 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY kI)

{3 W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLE AR TELEPHONE (2151 841-5022

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

l l l l l METHOD OF l LICENSEE lSYSTEMICOMPONENTl CAUSE AND CORRECTIVE I ITYPE lDURATIONlRE A50NI SHUTTING DOWN1 EVENT l CODE I CODE I ACTION TO NO.l DATE I (111 (HOURSil (2) l REACTOR (3) l REPORT e 1 (41 l (5) l PREVENT RECURRENCE I I I I I I I I i 10 1 790602 i S l 230 5 l B l 1 1 NONE I MB l RECOMB 1 RECOM51NER CONDENSER MAINTENANCE I I i l 1 I I i 1 11 1 790613 l F l 75.4 1 A I 2 1 3-79-13/IP I CC l VALVE X l 'L' RELIEF VALVE FAILED OPEN I 1 l l i I I I I ,J 12 1 790621 1 F 25.5 A 2 NONE l MB RECOMB l 3A RECDMBINER MECHANICAL COMPRESSOR F A IL UR E gg,gs i I I 331.4 1 1 1 1 I I lEE3l mm.-as (mU U

IT$ae, C"3 (1) (2) (3) (4)

F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS C$

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$ - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PRcPARATION OF DATA

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B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE )

C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPDAT (LERI fi).-

D - REGULATORY RE S TR ICTION 4 - OTHER (EXPLAIN) FILE (NUREG-01611 E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE ($1 G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EXPLAINI EXHIBIT I - SAME SOURCE e

J Docket No. 50-277 Attachment to Monthly Operating Report REFUELI!10 3 ?IF0FJ1ATIO?J i

1. Nato of facility:

Peach Botto: Unit 2

2. Scheduled date for next refueling chutdown:

March 1, 1980

3. Scheduled date for restart following refueling:

May 17, 1980

h. k'ill refueling or resumption of operation thereaf ter require a technical cpecification change or other licence amendment?

Yec.

If answer is yes, what, in general, will these be?

Technical specification changes to accomodate reload fuel.

Modifications to reactor core operating limits are expected.

5. Scheduled date (c) for submitting proposed licencing action and supporting information:

February 8,1980

6. Important licenning connidera tions annociat ed with refueling, e.g. ,

new or different fuel design or cupplier, unresiewed design or perfommcc analyeic methods, significant changes in fuel design, new operating proceduren:

Initial utilization of General Elec tric pre-preccurized Puel Acuerblico 7 The nutber of fuel accc blies (a) in the core and (b) in the opent fuel storace pool:

i (a} Core - 76h Fuel Acceablies I (b) Fuel pool - 618 Irradiated Fuel Acsembliec l 8. The precent licenced cpent fuel pool storage capacity and the size of any increase in licenced storage capacity that has been requested or is planned, in number of fuel acceablien:

Criginal inctalled capacit3 in 1110 fuel asee:blies. An increase in capacity to 2816 fuel assemblies hac been licenced, providing capacit; for 1706 additional fuel acce bliec. Plant modificationa to be ccmpleted prior to next refueling.

9 The projected d,te of the laat refueling + hat can to diccharged to the spent fuel pool accusing the procent licenced capacity:

September, 1990.

& 3W

n . -

'I Attachment to Monthly Operating Report June, 1979 for i

FIRIELIMO I?,TCPRATION

1. Har.e of facility

- Peach Bottom Unit 3 I

2. Scheduled date for next refueling chutdown:

Septetter 8, 1979 3 Scheduled date for rectart following refueling:

1 October 20 , 1979

h. Will refueling or resumptien of operation thereaf ter require a technical opecification change or other licence amendment?

1

' Yen.

If annwer is yea, what, in general, will these be?

Technical opecification changen to accomodate reload fuel.

Modifications to reactor core operating limite are expected, j

i

5. Scheduled date (c) for nutmitting proroced licenoing action and

' cupporting infon::ation:

1 July 20, 1979

6. Important licencing conniderationo annociated 'eith refueling, e.g.,

new or different fuel denign or cupplier, unreviewed denign or perfo:r.ance analyci o me thodo , cignificant changco in fuel design, new operating procedureo:

h Initial utilization of General Electric pre-precourized Pael Acac=blies 7

The number of fuel acceablico (a) in the core and (b) in the opent

, 1 fuel otorace pool:

< a) Core - 76h Pael Assemblies b) Pac 1 pool -hh0 Irradiated Pael Assemblics i

8. The present licenced oprnt fuel pool ctorase capacity and the cize of any increase in licenced storace capacity that has been requested l

l or 10 planned, in number of fuel acnemblies:

l Original installed capacit, is 1110 fuel acee blies. An increase in capacity to 2816 fuel accembliec hac been licenced, providing capacity for 1706 additional fuel acceabliec. Plant modifications to be completed prior to next refueling.

l

- 9 The projected date of the lact refueling that can be diccharged to the crent fuel pool acce.ing the precent licenced capacity:

A Septc ber, 1991.

P h

Il

" NO N 3sy

NARRATIVE

SUMMARY

Of OPERATING EXPERIENCES PEACH BOTTOM UNITS 2 & 3 JUNE 1979 Unit 2 Unit 2 operated at rated power for the reporting period except for a load reduction to 800 MWe, from June 8 to June 10, to accommodate an adjustment to the control rod pattern. On June 21, the reactor water cleanup system was manually isolated after discovery of a leak on a suction pipe to the pumps. The system remains out of service while repairs are in progress. Reactor chemistry remains within limits, and is not expected to limit power.

Unit 3 Unit 3 operated at 975 MWe until June 1, at which time a unit shut down was initiated to accommodate maintenance on leaking feedwater heaters and to replace the recombiner condenser. The unit was returned to service on June 11, reaching 90% power by June 13 when a main stream line relief valve lif ted and would not reclose, thus requiring a manual scram. It was necessary to extend the outage a day to effect repairs to the reactor recirculation pump discharge valve, which had failed to open during the unit startup. Power operations were resumed on June 16, reaching full power on June 19 with the fif th feedwater heater valved out of service to maximize core reactivity.

The unit was removed from service on June 21, following a reduction in condenser vacumm resulting from loss of both recombiner mechanical compressors. The reactor was returned to service later that day. However, power ascension was delayed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to limit main off gas stack release rates. The unit was returned to service on June 22, reaching 857, of rated power by June 23. At this tice a load drop was initiated to adjust the control rod pattern. Full power was reached on June 25.

52 360 pg[$ ODIPD'M

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