ML20083N357

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Monthly Operating Repts for Mar 1984
ML20083N357
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/31/1984
From: Alden W, Ullrich W
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8404190165
Download: ML20083N357 (10)
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OPERATING DATA REPORT DOCKET uO. 50 - 277 DATE APRIL 13, 1984 COBPLETED BY PHIL&DELPRIA ELECTRIC CORP &ET 4 5.5.4LDER BEGINEER-IN-CBARGE LICBBSIEG SBCTION GEBED&TIOS DITISIDE-50 CLEAR TELEPHOBE (215) 841-5022 OPER&TIgG STATUS

1. UNIT B&BE PEkCH BOTTOR UuIT 2 l EOTES: OBIT 2 REFERIESCED OBE l 1 I
2. REPORTING PERIOD: BARCH, 1984 l SCHEDULED LO&D REDUCTION l l 1
3. LICENSED THERBAL POWER (BET) : 3293 l FOR B&TER DOI IBSPECTION l 1 . I
4. B&BEPLATE R& TING (GROSS RWE): 1152 l AED REP &It AND COETROL ROD l l 1
5. DESIGN ELECTRICAL RATING (BET RWE): 1065 l PATTERE ADJBSTREST. l

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6. RAZIMOR DEPEEDABLE CAPACITY (GROSS 55E): 1098 l l l l
7. s&IInUn DEPENDABLE C&P& CITY (5ET B53): 1051 l l
8. IF CH&NGES DCCUB IN C&P& CITY RETIBGS (ITIES BURBER 3 THROUG5 7) SINCE L&ST REPORT, GITE REASOBS
9. POSER LETEL TO WHICH RESTRICTED, IF ABY (BET BSE):
10. REASopS FOR RESTRICTIONS, IF ABY:

I THIS BOETE TR-TO-DATE CUBULATITE

11. BOURS IE REPORTING PERIOD 744 2,184 85,392
12. BL5BER OF HOURS REACTOR WAS CRITICAL 744.0 1,931.9 61,630.8 4
13. REACTOR EESERTE SHUTD085 BOURS 0.0 0.0 0.0
14. BOURS GENERATOR 05-LINE 744.0 1,894.6 59,906.4
15. UNIT RESERTE 589?D085 BOERS 0.0 0.0 0.0

'16. GROSS THER8&L REERGY GREER&TED (535). 2,331,778 5,943,562 176,498,172 17.' GROSS ELECTRIC &L ENERGY GREERATED (BWB) ' 754,130 1,932,900 50,103,990

18. NET ELECTRIC &L ENERGY GEBER&TED (535) 731,249 1,873,943 55,710,373
19. UNIT SERVICE FICTOR 100.0 86.7 70.2
20. UNIT AVAILABILITT FACTOR 100.0 86.7 70.2
21. UNIT CAPACITY FACTOR (USIgG EDC NET) 93.5 - 81.6 62.1
22. REIT C&P& CITY F,&CTOR (USING DER NET) -92.3 30.6 &1.3
23. UNIT FORCED CBT&GE RATE 0.0 5.8 12.6 24.' SHUTDOWNS SCHEDULED OTER BRET 6 EONTES (TTPE, D&T2, AND BORATIO5 OF BACE) :
1. 'SBBTDOWE FOR REFUELING ABD PIPE REPLACEREBT FOR BBCIRCUL& TION AND RESIDUAL'EEAT RE80T&L (BBB) SY5TRES RESIRBIB6 4/27/94 ABD L&STIEG APPROIIBATELY 32-36 EEEKS.
25. IF SRUTDOWE AT EBD OF REPORT PERIOD, ESTIE&TED D&TB 0F STARTWP3-

' 26. UNITS IN TEST STATUS (PRIOR TO CORRERCIAL OPERATIO3): ' ' POBBC&BT ACRIETED IIITI&L CRITIC &LITY 191TIAL ELECTRICITY C08EERCIAL OPERATION-

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8404190165 840331 -

PDR ADOCK 05000277 ' -

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OPEE& TING DATA REPORT s

DDCKET 30. 50 - 278 D&TE APRIL 13, 1984 COMPLETED BT PHILADELPHIA ELECTRIC CORP &BT 3.5.ALDES ENGINEER-IB-C8&BGE LICEBSING SBCTION GREEBATION DITISIDE-BOCLE&B TELEP80EE (215) 841-5022 OP&RATIBG STATUS

1. UNIT BABE PEACH BOTT05 OSIT 3 l BOTES: DEIT 3 IIPERIENCED OBE t

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2. REPORTING PERIOD BARC5, 1984 l SCHEDOLED LOAD REDUCTION l

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3. LICENSED THERRAL POBER(suf): 3293 i FOR B-1 B&TER DOE REP &IR l

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4. B&MEPLATE RATING (GROSS EUE): 1152 l AED & CONTROL 300 PATTER 5 l l l
5. DESIGN ELECTRICAL BATIgG [ BET 55E): 1065 l &DJUSTBRET. l l 1
6. R&IIBUR DEPEED&BLE CAPACITY (GROSS BUE): 1098 l l l l
7. 84I1505 DEPEED&8LE CAPACITY (W ET RW E) : 1035 l l
8. IF C5&pCES OCCUR 15 CAPACITT RATINGS (ITERS BURBER 3 THROUGH 7) SIBCE LAST REPORT, GIVE RE& SONS:
9. poser LEVEL TO WHICE RESTRICTED, IF AST (BET BWE):
10. REASONS FOR RESTRICTIOUS, IF ABY THIS 80378 TR-TO-DATE CORDL&TIVE
11. ROURS 15 REPORTING PERIOD 744 2,184 81,288
12. 305BER OF E00R$ REACTOR WAS CRITIC &L 744.0 1,881.3 58,681.1 0.0 0.0 0.0
13. RE&CTOR RESERTE S5UTDONE BOURS
14. HOURS GE&ERATOR CB-LIBE 744.0 1,849.5 57,165.7
15. 0517 RESE, RTE SHOTDOWS BOURS 0.0 0.0 0.0
16. GROSS THERB&L REERGT GEBER&TED (BWB) 2,401,463 5,861,301 166,899,606
17. GROSS ELECTRIC &L ENERST GENERATED (BG B) -807,480 1,951,650 54,766,770 18.~EET EL&CTRIC&L EuBRGY GREER&TED (555) 785,881 1,896,799 52,560,584
19. OEIT SERVICE FACTOR 100.0 84.7 70.3
20. ORIT AT&IL&BILITY FACTOR 100.0 84.7 70.3
21. UBIT CAPACITY FACTOR (USING EDC NET) 102.1 83.9 62.5

, 22. OnIT CAPACITY FACTOR (OSING DER BET) 99.2 31.5 60.7

23. OBIT PORCED OUT&GE BATE 0.0 15.3 7.5
24. SHDTDOURS SCHEDULED OVER BRET 6 505T55 (TTPE, D&TE, 45D DORATIDE OF B&CE)

. 25. IF $50TDOWN &T END OF REPORT PERIOD, ESTIN&TED DATE OF STARTUP

26. UNITS IS TEST STATUS (PRIOR TO CDeREBCIAL OPERATIO3): FORIC&ST ACBIRTED IBITIAL CRITICALITY .

IEITIAL ELECTRICITY .

CORRERCIAL OPER& TION e

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. AVERAGE DAILY UNIT PONER LEVEL l l

DOCKET NO. 50 - 277 l UNIT PEACH BOTTOM UNIT 2 DATE APRIL 13, 1984 ,

COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 --

MONTH MARCH 1984 DAY AVERAGE DAILI POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MW E-N ET) (MWE-NET) 1 1039 17 998 2 1042 18 998 3 686 19 994 4 864 20 992 5 1028 21 990 6 1035 22 986 7 1030 23 979 8 1026 24 981 9 1012 25 971 10' 962 26 972 11 1024 27 969 12 1016 28 967

'13 1010 29 961-14 1008 30 959 15 1006 31 965-16 1002

AYERAGE DAILY UNIT PONER LEVEL DOCKET NO. 50 - 278 _ ___ .

UNIT PEACH BOTTOM UNIT 3 DATE APRIL 13, 1984 CORPANY PHILADELPHIA ELECTRIC COMPANY

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N.H.ALDEN EUGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022

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50 NTH HARCH 1984

_ _ _ _ _ _ _ _ _ _ =

DAY ATERAGE DAILY POWER LEVEL DAY ATERAGE DAILY PONER LEVEL (MN E-NET) (HNE-NET) 1 1078 17 736 2 1078 18 992 3 1085 19 1031 4 1078 20 1020 5 1076 21 981 6 1077 22 1068 7 1078 23 1067 8 1076 24 1067 9 1079 25 1075 10 1082 26 1075 11 1083 27 1076 12 1075 28 1074 13 1078 29 1075 14 1081 30 1077 15 1084 31: 1079 16 1062

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  • w UNIT SHUTDONES AND POWER REDUCTIONS DOCKET NO. 50 - 277 UNIT NARE PEACE BOTTOR UNIT 2 DATE APRIL 13, 1984 REPORT NONTH MARCH, 1984 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY N.n.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPEONE (215) 841-5022 - _=

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

l l l l l NETHOD OF I LICENSEE lSYSTERlCORPOWENTl CAUSE AND CORRECTIVE I lTYPElDURATIONIREASONISBUTTING DONN!' EVENT I CODE l CODE l ACTION TO NO.I DATE l (1) l (BOURS) l (2) i REACTOR (3) l REPORT 8 I (4) I (5) l PREYENT RECURRENCE I i 1 I I I I I I 4 I 840302 i S I 000.0 l E I 4 i NA l HC l zzzzzz l LOAD REDUCTION FOR NATER BOI INSPECTION I I l 1 l l l l l AND REPAIR AND CONTROL ROD PATTERN ADJUSTRENT.

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

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

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

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

G - OPERATIONAL ERROR (EIPLAIN)

H - OTHER (EIPLAIN) BIBIBIT I - SABE SOURCE 1

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A UNIT SHUTDOWNS AND POWER REDUCTIONS DOCERT NO. 50 - 278 UNIT NARE PEACH BOTTO8 UNIT 3 DATE APRIL 13, 1984 REPORT RONTE R&BCH, 1984 CORPLETED BY PHILADELPHIA ELECTRIC CORPANY N.H.ALDEN E3GINEER-IN-CHARGE LICENSING SECTION GENERATION DITISION-NUCLEAR TELEPEONE (215) 841-5022 l 1 I . I I BETHOD OF I LICENSEE ISYSTE5lCOMPONENTI CAUSE AND CORRECTITE I I TY PE I DU R ATION I RE AS ON I SHUTTIN G DOWN I ETENT l CODE l CODE I ACTION TO BO. I ' DATE I (1) l - (HOURS) I (2) i REACTOR (3) 1 REPORT 8 I (4) l (5) 1 FRETENT RECURRENCE I 1 1 I i i i I I 3l 840316 i S I 000.0 i B I 4 l N1 i HC 1 ZZZZZZ I LOAD REDUCTION FOR B-1 UATER BOI REPAIR I, I I I I I I I I AND A CONTROL ROD PATTERN ADJUSTRENT.

I I I- 1 I I i 1 1 I i 1 - 1 I 1 'l i I  !

1 I

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

F - FORCED REASON HETHOD RIEIBIT G - INSTRUCTIONS 9 - SCHEDULED 1 - EQUIPMENT FAILURE (EIPLAIN) 1 - MANUAL FOR PREPARATION OF D&TA B - MAINTENANCE OR TEST 2 - BANUAL SCR&B. ENTRY SEEETS FOR LICENSEE C - REFUELING 3 - AUTOS & TIC SCR&B. EVENT REPORT (LER)

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

E - OPERATOR TRAINING + LICENSE BIARINATION F - ADMINISTRATITE (5)

G - OPERATIONAL ERROR (EIPLAIN) n - OTHER (EIPLAIN) EIBIBIT I - SABE SOURCE I

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Docket No. 50-277 Attachment to Monthly Operating Report for March, 1984 REFUELING INFORMATION

1. Name of facility: )

Peach Bottom Unit 2

2. ' Scheduled date for next refueling shutdown:

April 27, 1984

3. Scheduled date for restart following refueling:

December 12, 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.

Technical specification changes associated with snubber reduction program.

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

September 12, 1984 for reload fuel

6. Important licensing considerations associated.with refueling, e.g., new or different fuel. design or supplier, unreviewed design or performance analysis methods, significant changes lin 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 - 764LFuel Acsemblies (b) Fuel Pool - 1170 Fuel Assemblies, 58 Fuel Rods

'8. The present licens'ed spent1fuel pool st.orage 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 ifor 2816 fuel assemblies.

79.. The projected date of the last refueling that'can'be-dischargedcto the spent fuel pooliassuming.the present

licensed capacity.- ' >

September.-1990 (March, 1986,Jwith reserve full-

- core discharge):

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Docket No. 50-278 Attachment to Monthly Operating Report for March, 1984 REFUELING INFORMATION

1. Name of facility:

Peach Bottom Unit 3

2. Scheduled date for next refueling shutdown:

March 30, 1995.

3. Scheduled date for restart.following refueling:

September 21, 1985.

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.

i Technical specification changes associated with snubber reduction program.

5 .1 Scheduled date(s) for submitting proposed licensing action and supporting information:

June 21, 1985 for reload fuel 64 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 1212 Fttel Assemblies, 6. Fuel Rods ..

'8. The?present licensed spent fuel pool storage capacity and the sizefof:any. increase =in licensed storage capacity that has been. requested orfis-planned, in number of' fuel assemblies:-

Theispent fuel pool storage capacity has been relicensed .

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for 2816 fuel-assemblies.

, ;9. 'Thel projected.date of the lastfrefueling that can be discharged to1the spent fuel. pool assuming;the present;

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'licansed' capacity.

. September, 1991-'(March, 1987, with reserve for' full: core-discharge)

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Docket Nos. 50-277/50-278  ;

Attachment to Monthly i

.. Operating Report for  !

March, 1984 l l

PEACH BOTTOM ATOMIC POWER STATION NARRATIVE

SUMMARY

OF OPERATING EXPERIENCES March, 1984 Unit 2 The unit began the month at full power with extended core flow.

Load was reduced on March 2 to 475 MWe for a control rod pattern adjustment and for condenser waterbox inspection and tube plugging. The unit attained full power on March 5. A power reduction was again taken on March 10 for condenser waterbox inspection and tube plugging. The unit returned to its maximum end-of-core coastdown capability on the same day. The end-of-core coastdown continued and the unit ended the month at 94%

- power.

On March 3, a Primary Containment Isolation System (PCIS) GE-HFA normally energized relay was replaced due to expected failure based on a higher than normal operating temperature.

Following discovery on March 9 of power cable conduit damage resulting from construction core boring, the E-3 diesel generator was taken out-of-service, the cable tested successfully, and the diesel generator tested satisfactorily and was returned to service. The Reactor Core Isolation Cooling System was taken out-of-service on March 12 for the replacement of a control relay for a motor-operated valve. The system was tested and returned to service later the same day.

Two normally energized relays, PCIS GE CR-120, failed: one on March 21, the other on March 23. They were replaced within hours and the logics successfully tested. Two oxygen analyzer solenoid

. valves also failed in the isolated condition during a surveillance test on March 23. These solenoid valves were

-repaired and tested successfully. On March 26, a leak was discovered on the "B" Residual Heat Removal. system heat l exchanger. .The High Pressure Service Water' side of the heat

(- exchanger has-been isolated and drained in preparation for repair of~the leak.

UNIT 3 The unit. began the month at. full power. Load was reduced to minimum reactor. recirculation flow on March 16 for inspection and-tube plugging of the. main condenser B-1 waterbox along with a

- control rod pattern adjustment. ~The unit was returned to.96%,

i restricted by' core thermal powa.r limits. On March 20,. load was reduced to 750 MWe for a further control rod pattern adjustment..

By' March:21, the unit hadf achieved essentially full-power. Load was. reduced on March 23 to 800 MWe for1another control rod

, pattern adjustment and attained full power-the same day. The' l ' unit. continued at full power for the remainder ~of the month..

L The "A" Core Spray-phap was taken out-of-service on March 19 for pump impeller l replacement due-to marginal pumping capacity. The L pump was tested and returned tx) service on March-21. On' Marc!.

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29,-failure of:a light socket-in the Core Spray. initiation logic resulted in blowing of :the -fuse feeding Lthe -B logic. The light

' socket /has been removed from.the circuit pending repairs.

1 PHILADELPHIA ELECTRIC COMPANY I 23O1 MARKET STREET P.O. BOX 8699 PHILADELPHIA PA.19101 (215)841-4000 April 13, 1984 Docket Nos. 50-277 50-278 Director Office of Inspection & Enforcement US Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Cc7 trol 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 March, 1984 forwarded pursuant to Technical Specification 6.9.1.C under the guidance of Regulatory Guide 10.1, Revision 4.

Very truly-yours, W.~T. Ullrich Superintendent 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 fb f

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