ML20055A391

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for June 1982
ML20055A391
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 07/12/1982
From: Alden W
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20055A390 List:
References
NUDOCS 8207160247
Download: ML20055A391 (9)
v • d • e


Text

.

0 ,

s OPERATIBG DATA REPORT DOCKET 50. 50 - 277 DATE JULY 12, 1982 CORPLETED ST PHILADELPNIA ELECTRIC CORPANI 5.R.ALDEB ENGINEER-IN-CEARGE BUCLEAR SECTICB GEBERATION DITISION-BOCLEAR TELEPHOBE (215) 841-5022 OPEPATING STATUS

1. 0517 BARE: PEACN BOTTOR ONIT 2 i BOTES: UNIT 2 IS DOWS FOR 1 1 i
2. REPORTISG PERIOD: JOBE, 1982 l REPOELING ABD RalpTEB&BCE. l

............... . .... . g g

3. LICENSED TBERSAL P0928 (887): 3293 l OBIT 2 ST ARTOP OCCURRED l

===....... g g 4 WAREPLATE BATISG (GROSS RWE) : 1152 i OB JULT 2, 1982. 1

. . . . . . . . . . . . _ . g g

5. DESIGN ELECTRICAL B ATIBG (BET HrE): 1065 l l

....-. g l

6. RAIIMDB DEPENDABLE CAPACITT (GROSS AWE): 1098 l l

.. g g

7. R AIIROS DEPENDABLE CAPACITY (W ET B S E) : 1051 l l
8. IF C5&#GES OCCUB If CAPACITY RATIBGS (ITERS BOMBER 3 TER00GB 7) SIBCE LAST BEPORT, GITE BEASONS:
9. POWER LETEL TO WHICH RESTRICTED, IF ABT (5ET EWE)
10. RE45055 POR RESTRICTIONS. IF ART THIS B0375 TB-TO-DATE COB 3LATITE
11. 500R$ IN REPORTING PERIOD 720 4,343 70,031
12. NUR9ER OF B00PS REACTOR WAS CRITICAL 0 1,182.0 50,925.4

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

13. R EACTOR R ESERTE SBUTDOWN RODRS 0.0 0.0 0.0
14. 500R$ GENERATOR OB-LINE 0.0 1,167.1 49,623.6
15. UNIT RESERTE SMOTDJWE E0DRS 0.0 0.0 0.0
16. GPOSS THERK AL ENERGY GEN ER ATED (555) 0 3,143,292 144,366,608

.. ....... =_ .

17. GROSS ELECTRICAL EWERGT GENER ATED (595) 0 1,009,650 47,513.420
18. NET ELECTRIC AL ENERGY GEBER ATED (RTR)
  • 7,825 947,793 45,538,528
19. DaIT SERTICE FACTot 0.0 26.9 70.9

..==-

20. UNIT ATAILAarLITT FACTOR 0.0 26.9 70.9
21. OBIT CAPACITY FACTOR (USIs3 eDC 3ET) 0.0 20.8 61.9
22. UNIT CAPACITY FACTOR (OSIBG DER NET) O.0 20.5 61.1
23. UNIT FORCED DOTAGE BATE 0.0 2.7 8.0
24. SMOTDOWNS SCRESULED OTER BEIT 6 RORTRS (TYPE, DATE, AED DOR ATI0B 0F BACH):

RE?OELIBG/B AINTEN ABCE, ST ARTED 2/20/82, NINETEEN WEEKS

25. IF SRUTD0su AT EBD CF REPORT PERIOD, ESTIR ATED D ATE OF STARTUP: 7/02/82
26. UNITS IN TEST STATUS (Pa!OR TO COMBEPCI AL OPER ATIOB): FORECAST ACHIETED IRITIAL CRITICALITY ._

._- 3 IRITIAL ELECTRICITY __

COMMERCIAL OPERATION -

  • - NE3 ATITE T ALUE REPORTED FOR CONSISTENCY WITR FEDERAL ENERGY REGULATORT COSBISSION REPORTS.

8207160247 820712 PDR ADOCK 05000277 PDR p

e

, OPERATIE3 DAT& SEPORT DOCERT 50. 50 - 278 DATE JOLT 12, 1982 C05PLETED Bf PEILADELP5IA ELECTRIC COBPANT 9.E.ALDEN E NGI N E ER *I B-CB A R GE BDCLEAP SECTION GEN!EATION DITISICB-BUCLEAR TELEPROBE (215) 841-5022 OPERATIN3 STATUS

1. Du!T P&nt PEACs 80770s OpIt 3 I a0TES: OpIT 3 EIPERIEuCED l
g
2. REPORTIN3 PERIOD: J UN E , 1982 1 082 SCREDULED LOAD t

...... ................... g g

3. LICENSED TMER94L poser (MWT): 3293 i aEDDCTIOu.

l g g 4 N49EPLATE BATIB3 (GROSS RWE) : 1152 8 t

. ............ g  ;

5. DESIGN ELECTRICAL RATIp3 (NET REE): 1065 g l

......... g g

6. RAEIMD5 DEPENDABLE CAPACITY (GROSS 592): 1098 l l

.... g g

7. RAIIMOS DEPENDA9LE CAPACITT (BET Rf t) : 1035 l l

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

8. IP CH ANGES OCCUR IN CAP ACITT R ATINGS (ITE85 BORBER 3 TB300G5 7) SIBCE L&ST REPORT, CITE REASONS
9. Posta LETEL 70 usICs RESTRICTED, IP ANY (BET MUE):
10. REASONS FOR RESTRICT 10sS, IP ABf THIS RONTH TR*TO-DATE CUEDLATIVE
11. 500k5 IN REPORTING PERIOD 720 4,343 65,927
12. BOMSER OF N00SS BEACTOR WAS CRITICAL 720.0 4,025.3 49,512.7
13. REACTOR RESE3ft SEUTDOWN BODR$ 0.0 0.0 0.0 14 ROURS GES!RATOR OR-LINE 720.0 3,957.0 48,183.8
15. UNI? RESERVE 5507D035 BOURS 0.0 0.0 0.0
16. GROM TMERM AL ENEPGT GENER ATED (M rs) 2,332,080 12,667.859 13N359,381
17. GROSS ELECTRICAL ENERG7 GENERATED (RWM) 782,240 4,256,610 45,645,530
18. NET ELECTRICAL ENER37 GENER ATED (B55) 753,571 4,118,315 43,828,788
19. URIT SERVICE FACTOR 100.0 91.1 73.1
20. UNIT AT&ILABILITY FACTOR 100.0 91.1 73.1
21. UNIT CAPACITT FACTOR (OSING BDC EET) 101.1 91.6 64.2
22. U117 CAPACITY FACTOR (DSING DER NET) 98.3 89.0 62.4
23. UNIT FORCED OUTAGE RATE 0.0 8.9 8.0
24. $53TDOWNS SCHEDULED OVER BEIT 6 505753 (TTPE, DATE, AND DURATION OF EACE):
25. IF SMUTD0ff AT END OF REPot? PERIOD, ESTIM ATED D ATE OF ST&BTOP3
26. UNITS IN TEST $747D5 (PRIOR TO COBBERCI AL OPER ATION) : FORECAST ACHIETED INITIAL CRITICALITY INITIAL ELECTRICITT CO'f M ERCI AL OPER ATION

AVEhAGEDAILY UNIT POWER LEVEL

, i DOCKET No. 50 - 277 l UNIT PEACH BOTTOM UNIT 2 DATE JULY 12, 1982 COMPANY PHILADELPHIA ELECTRIC COMPANY W.H.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GEN, E RATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH JUNE 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET) (BWE-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 l

0 29 0 13 0 30 0 14 15 0

' 16 0

  • AVERAGE,DAI$Y UNIT POWE9 LEVEL DOCKET 's . 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE JULY 12, 1982 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH JUNE 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (M WE-N ET) (MWE-NET) 1 967 17 1061 2 1053 18 1061 3 1055 19 1052 4 1053 20 1058 5 877 21 1032 6 1052 22 1058 7 1062 23 1056 8 1062 24 1054 9 1065 25 1052 10 1066 26 1050 11 1060 27 1048 12 1059 28 1050 13 1063 29 1046 14 1061 30 1042 15 1061 16 1063

6 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCK ET No. 50 - 277

__________ - =__ _ =-_=____

UNIT N AME PEACH BOTTOM UNIT 2 DATE JULY 12, 1982 REPORT MONTH JUNE, 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 lSYSTEMICOMPONENTI CAUSE AND CORRECTIVE l [ TYPE lDUR ATION lRE ASON l SHUTTING DONNl EVENT l CODE l CO DE l ACTION TO NO.l DATE l (1) l (HOURS)l (2) l REACTOR (3) l REPORT 8 l (4) l (5) l PREVENT RECURRENCE

_______________==- = _ - _= -

_________ - _ _ _ _ _ _ _ - _==_______ _==__---

=-_

1 I I l t 1 l +1 1 3 1 820601 l S I 720.0 l C l 1 l NA l RC l FUELII l CONTINUING REFUELING OUTAGE.

I i 1 ----- 1 1 1 1 1 1 1 l I 720.0 l l t l l l (1) (2) (3) (4)

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

D - REGULATORY RESTRICTION 4 - OTHER (EIPLAIN) FILE (NO R EG-0161)

E - OPERATOR TR AINING + LICENSE EI ARINATION F - ADMINISTR ATIV E (5)

G - OPERATIONAL ERROR (EIPLAIN)

H - OTHER (EIPLAIN) IINIBIT I - SAME SOURCE e

UNIT SROTDOWNS AND PONER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE JULY 12, 1982 REPORT MONTH JUNE, 1982 COMPLETED BT PHILADELPHIA ELECTRIC COMPANY

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

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

I i l I i METHOD OF l LICENSEE ISYSTEMlCOMPONENTI CAUSE AND CORRECTIVE I ITYPElDURATIONIREASONISHDTTING DONNI EVENT l CODE I CODE I ACTION TO NO.l

---__ .==-

DATE l (1) l (N00RS)l (2) l REACTOR (3) l REPORT 8 I (4) l

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

(5) l PREYENT RECURRENCE

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

1 I l l l l l l l 10 l 820605 i S I 000.0 l H l 4 l NA l RC l ZZZZZZ l LOAD REDUCTION FOR THE ADJUST 8ENT OF THE l l l l l l l l l CONTROL ROD PATTERN.

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

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

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

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

G - OPERATIONAL ERROR (EIPLAIN)

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

V PEACH BOTTOM ATOMIC POWER STATION t NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE I June, 1982 .

UNIT 2 l

At the beginning of the report period, the fifth refueling outage was still in progress. Major activities during the period included:

1. Completion of reloading of the fuel into the reactor vessel.
2. Installation of the steam separator and dryer and tensioning of the pressure vessel head.
3. Completion of the hydrostatic test on June 12.

4 Overspeed test of the A & C reactor feed pumps.

5. Loss of power test on June 19 which caused ECCS initiation on Unit 3. The test was repeated successfully on June 21.

During the period, the Emergency Response Plan Drill was successfully conducted on June 16 with participation by Federal, State, and Local officials.

At 1649, on June 25, startup began and the reactor was critical at 1850, and remained at a low power level through the end of the reporting period while efforts to place the recombiner system in service continued. On June 28, reactor pressure was reduced to 450 psi to break condenser vacuum and start-up operations were interupted to permit the repairs of recombiner condenser internal baffles. Vacuum was restored on June 29. The unit was returned to service on July 2, 1982.

UNIT 3 The unit began the report period at 79% power increasing to full power after recovering from a May 28 controlled shutdown to investigate high drywell out-leakage.

On June 19 during the loss of power test on Unit 2, HPCI, RCIC and RHR were initiated on Unit 3. As a result of the cold water injection, APRM power increased, but did not reach the scram setpoint. The operator manually terminated the injection of HPCI & RCIC after verifying that there was no LOCA. No increase in offgas activity or change in water chemistry were noted. Load was decreased by 180 MWe on June 21 as a precaution in preparation for the Unit 2 loss of power test, and the test was performed satisfactorily. After the test, load level was increased to full power.

Docket No. 50-277

' Attcchm:nt to Monthly Oparating Report for June, 1982 REFUELING INFORMATION

1. Name of facility:

Peach Bottom Unit 2

2. Scheduled date for next refueling shutdown:

refueling began February 20, 1982

3. Scheduled date for restart following refueling:

July 2, 1982

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:

February 24, 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, 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 Attachm:nt to Monthly Operating Report for June, 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 recuire 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 i

(b) Fuel Pool - 934 Fuel Assemblies 1

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been reauested or is planned, in number of fuel assemblies:

l

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

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

l

( September, 1991

Retrieved from "https://kanterella.com/w/index.php?title=ML20055A391&oldid=2581366"