ML20134F877
| ML20134F877 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/31/1985 |
| From: | Alden W, Logue R PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| NUDOCS 8508210296 | |
| Download: ML20134F877 (11) | |
Text
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OPERATING DATA REPORT l
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00CKET N0. 54 277 OATE AUGUST 15.1945 I
COMPLETED ST PHILADEL*. fIA CLECTRIC COMPANT j
W.M. ALD EA l
ENGINEER.IN. CHARGE
)
LICENSING SECTION
{
SDtERATION CIVISION. NUCLEAR j
T!LEPHONE (!153 441 5022
=
OPERATING STATUS i
I. UNIT MANEt PEACM 30TTOM UNIT t l NOTESI UNIT t STARTUP BEGAN ON l
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- 2. REPORTING PERIGOI JULY. 1945 1
7/13/65. LMIT 2 INCL 2 RED l
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- 3. LICENSED THERMAL PONER(reif ts 3293 i TNO SCHEDULE 0 3rlUT00te45.
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- 4. MAMEPLATE RATING (GROSS PG4E18 1152 l TWO FORCEO LOA 0 REOUCTIONS.
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- 5. DESIGN ELECTRICAL RATING (NET leet):
1965 l Ate ONE SCHEDULED LOAD l
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- 6. ItAXIttM DEPOSABLE CAPACITT E69055 todEll 1994 l REOUCTIDH.
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- 7. MAXIraes OEPEleASLE CAPACITY (NET lt4 Ele 1951 1 I
- 4. IF CHANGES OCCLst IN CAPACITY RATINGS IITDis NUMBER 3 TNFOUGH 7) SINCE LAST REPORT. SIVE REASONS 8 I
- 9. POWER LEVEL 70 letICM RESTRICTED. IF ANT (NET IS4 Ele
- 10. REASONS FOR RESTRICTIONS. IF ANY8 THIS MONTH TR.TO-CATE
'CL# M TIVE I
- 11. NouRS IN REPORTING PERIOD 744 5.087 97.879 l
l
- 12. 8499ER OF Notas REACTOR lAAS CRITICAL 534.4 534.4 68.414.0 l
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- 13. REACTOR RESERVE sNuT00ies hours e.e e.e e.e l
- 14. NOLa3 GENERATOR ON.LINE 324.1 324.1 60.844.7 l
- 15. WIT RESERVE SMUT 00 bel N0Las 0.0 8.0 0.0 l
- 16. GROSS THERMAL ENERGY SENERATED (1941) 775.824 775 224 179.195 tES l
1
- 17. EROSS ELECTRICAL ENERGY SENERATE0 0944) 212.150 212.150 54.934.410
- 14. NET ELECTRICAL ENERGY SENERATED Heell 194.921 145 764 54.444.118
- 19. WIT SERVICE FACTolt 43.6 6.4 62.7 4
- 10. WIT AVAILASILITT FACTOR 43.6 6.4 62.7
- 21. WIT CAPACITT FACTOR (USING teC NETI 24.4 1.7 55.3 h
St. WIT CAPACITT FACTOR (USING DER NET) 24.5 8.7 54.6
.nm b
- 23. WIT 70RCEO OUTAsE RATE 0.9 0.0 12.4 2
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- 14. SNUT00 tees SCHE 00 LEO OVER NEXT 6 MONTHS ITTPE. DATE. Abe DURATION OF EACNil S W.
Oc as. It SMUT 00ies AT De OP RtPORT PERICO. ESTInATE0 DATE Or sTARTuP M4
- 26. WITS IN TEST STATUS (PRIOR TO COP 91ERCIAL OPERATIONil FontCAST ACHIEVED 0 0*
IO Q INITIAL CRITICALITY ma.x y' a j 1HITIAL ELECTRICITT CoretERCIAL OPERATION
OPEROTINS DATO REPORT g
e DOCMET NO. 50 - 278 Daft AUGUST 15.1965 COMPLETt0 ST PHILADELPNIA ELECTRIC COMPANT N.M.ALDEN ENGIHttR-IN-CHARGE LICENSING SECTION SENERATION CIVISION-tAJCLEAR TELEPHONE (115I 841-5022 OPERATIts STATUS
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- 1. WIT MAMtt PEACH OOTTOM WIT 3 l NOTESt UNIT 3 INCURRED ONE FORCt0 l
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- t. REPORTING PERICOs JJLTe 1965 l
LOA 0 REDUCTION. WIT SHUT l
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- 3. LICENSES THERMAL POWERtreffit 3893 I DOWN ON 7/14/85 FOR REFUEL l
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- 4. NAMEPLATE RATING (69055 ledf al 1152 l Ale MAINTENANCE OUTAGE 06.
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- 5. OfSIEN ELECTRICAL RATINS INET tedtil 1965 l l
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- 6. MAXINUM DEPtteAatt CAPACITT (GROSS pestle 199e l l
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- 7. NAXIMun DEPENDABLE CAPACITT INtf testat 1935 l l
- 4. IF CHANGES DCCUR IN CAPACITT RATINGS IITEMS DERetR 3 THROUGH 78 SINCE LAST REPORT. SIVE REASONSI
- 9. POWER LEVEL 70 leIICH RESTRICT 10.1F ANT (NET ledt38 St. REASONS F0at RESTRICTIONS IF ANT 8 THIS MONTH TR TO-DATE CLRtJLATIVE
- 11. 900URS IN REPORTING PtRICO 744 Sete?
9te975 St. MRetR OF NOLAS Rf ACTOR WAS CRITICAL 351.0 4.055.7 64.613.t
- 13. REACTOR RESERVE SHUT 00bteit0L81S 0.0 0.0 0.0
- 14. 800LNt3 SENERATOR ON-LINE 336.0 3.949.3 66.484.4
- 18. IMIT RittRVE ONUTDelet 100URS 0.0 0.0 0.0
- 16. eROSS TmRMAL ENERGT SENERATED 09413 779.856 10.796.056 194.996.664
- 17. GROSS ELECTRICAL ENERef stHERAff0 (7900 236,530 3e446e130 63.993e670
.~.
1s. NET ELICTRICAL INERST SEMEAft0 titell 216,816 3.320.641 61.434.143
- 19. 18417 SERVICE FACTOR 45.2 74.6 71.9 St. tedIT AVAILASILITY FACTOR 49.2 74.4 71.9
- 21. LAIT CAPACITT FACTOR (USING teC NETI 20.1 63.1 63.8 St. UNIT CAPACITT FACTOR (USINS OtR NETI 17.3 61.3 62.0
- 33. WTT FORCta CUTAtt Raft 0.0 0.8 T.1
- 24. SNUTD0lefS SCNEt'ULla CytR latXT 6 teNTNS (TTPf e DAf t. Ape DURATION OF EACHis SCHt0ULEO BN'ITDelet FOR REFUELING Ape MAINTtHANCE OUTAGte STARTto 7/14/45
- 25. IF SNillDClet AT EMI 0F REPORT PERIODe ISTIMAff0 oaf t O' !TARTUPt 10/17/65 l
- 26. WITS IN TEST STATUS (PRION TO COP 99tRCIAL OPERATIONis FORECAST ACHIEVIO INITIAL CRITICALITT INITIAL ELECTRICITT COP 9tERCIAL OPERATION
- - - ~
AVERAGE DAYLY UNIT POWER LEVEL DOCKET No. 50 - 277 UNIT PEACH 80TTON UNIT 2 DATE AUGUST 15:1985 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISIDH-HUCLEAR TELEPHONE (215) 841-5022 HONTH JULY 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (P54E-NET)
(MWE-NET) 1 0
17 601 2
0 18 169 3
0 19 0
0 0
20 32 5
0 21 493 1
6 0
22 476 i
7 0
23 0
8 0
24 0
9 0
25 476 10 0
26 805 4
11 0
27 738 12 0
to 728 4
j 13 0
29 956 10 234 30 981 l
15 237 31 909 16 494 j
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AVERAGE DAILY UNIT' POWER LEVEL DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE AUGUST 15.1985 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTIDH GENERATION DIVIS!0H-NUCLEAR TELEPHONE (215) 841-5022 MONTH JULY 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-HET) 1 707 17 0
2 703 18 0
3 701 19 0
4 697 20 0
5 692 21 0
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6 690 22 0
7 684 23 0
8 680 24 0
9 641 25
,0 10 691 26 0
11 678 27 0
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12 670 28 0
13 673 29 0
10 332 30 0
15 0
31 0
16
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UNIT SHUTDOWHS AtB POWER REDUCTIDHS DOCKET NO. 50 - 277 UNIT NAME PEACH 80TTOM UNIT 2 DATE AUGUST 15.1985 REPORT N0HTH JULY, 1985 COMPLETED BY PHILADELPHIA ELECTRIC ConPANY W.M. A LDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215') 841-5022
............................................................................................................................c I
l l
l l NETH00 0F l LICENSEE (SYSTEMICOMPCHEHTl CAUSE AND CORRECTIVE l
lTYPElDURATIONIREASOHISHUTTING DOWHI EVENT l CODE l CODE I ACTIDH TO NO.1 OATE I (1li (HCURSil (2) l REACTOR (3) l REPORT 4 I (4) l (5) l PREVENT RECURRENCE
........................................................--............................................................c I
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1 l 850701 l 5 1 310.0 l C l 1
l WA l RC i FUELXX l SHUIDOWN FOR SIXTH REFUELING MAINTENANCEe l
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l l AND MAJOR MODIFICATIDH OUTAGE.
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l t-85 01 1 HA i TURBIH I SHUTD0644 TO BALANCE TURBINE DUE TO HIGH I
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I I VIBRATIONS.
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I 3 l 850722 l S I 057.5 l A l 1
l 2 85-02 l CH I PIPEXX l CORRECT INSTRUMENT TEST TAP LEAK ON C FEED 1
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l l PUMP DISCHARGE LINE.
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l l-1 4 1 450727 l 8 1 000.0 l B l 4
l WA 1 RC l ZZZZZZ l LOAO REDUCTION FOR R00 PATTERN AOJUSTNENT.
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l l
1 1
I 5 l 850730 l F l 000.0 1 0 l 4
i WA l MC l ZZZZZZ l LOAD REDUCTION DUE TO MA!H STEAM LINE HIGH l
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l 1 RA0!ATION DUE 70 RESIN INJECTION.
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I 6 l 450731 l F l 000.0 l A l 4
l WA l CH l PUNPXX l LOAD REDUCTIDH DUE TO A REACTOR FEED PLR1P l
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l l EXHAUST RUPTURE DISC LEAK.
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(1)
(2)
(3)
(4) 1 F. FORCEO REASON METHOD EXHIBIT S. INSTRUCT 10HS jS. SCHEDULED A. EQUIPMENT FAILURE (EXPLAIH) 1. MANUAL FOR PREPARATI0H OF DATA B. MAINTEHANCE OR TEST t. MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C. REFUELING 3. AUTOMATIC SCRAM.
EVENT REPORT (LER)
)
D. REGULATORY RESTRICTICH 4
OTHER (EXPLAIN)
FILE (HUREG.0161)
E. OPERATOR TRAINING + LICENSE EXAMINATIDH F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
H. OTHER(EXPLAINI EXHIBIT I. SAME SOURCE L_
UNIT SHUTDOWHS AND POWER REDUCTIDHS DOCKET HO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE AUGUST 15.1985 REPORT MONTH JULYe 1985 COMPLETED BY PHILADELPHIA ELECTetIC CONPANY W.M.ALDEN ENGINEER-IN-CalARGE LICENSING SECTION GENERATI0H DIVISIDH HUCLEAR TELEPHONE (215) 841-5022 l
l l
l l METHOD OF l LICENSEE lSYSTEMICONP0HENT! CAUSE AND CORRECTIVE l
lTYPElDURATIONIREASOHISHUTTING DOWH1 EVENT l CODE l CODE l ACTION TO HO.I DATE I (1)I (HOURSil (2) l REACTOR (3) l REPORT # l (4) l (5) l PREVENT RECURRENCE I
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12 1 650709 l F l 000.0 l A l 4
i H/A l EG l ZZZZZZ l LOAD REDUCTION DUE TO LOSS OF VACUUM CAUSED I
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l l BY XFMR BREAKER TRIP DUE TO GROUND FAULT.
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i 13 l 850714 1 5 1 408.0 l C i 1
i N/A l RC l REFUEL i SHUTDOWN FOR SIXTH REFUELING / MAINTENANCE I
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1 1
1 1
I l OUTAGE.
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I 408.0 l l
1 l
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(1)
(2)
(3)
(4)
F - FORCED REA50H METH00 E)0lIBIT G = INSTRUCTIDHS S - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B
MA!HTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT ILER)
D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIH)
FILE (NUREG-0161)
E - OPERATOR TRA!HING + LICENSE EXAMINATIDH f. ADMINISTRATIVE (5)
E - OPERATIONAL ERROR (EXPLAIN)
H - OTHER(EXPLAINI EXHIBIT I. SAME SOURCE i
i l
2 i
Docket No. 50-277 Attcchmsnt to Monthly Oparcting Report for July, 1985 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 2 2.
Scheduled date for next refueling shutdown:
October 11, 1986 3.
Scheduled date for restart following refueling:
December 27, 1986 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.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
Reload 7 license amendment to be submitted September 26, 1986.
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 - 1464 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.
September, 1990 (March,1986, with reserve full core discharge)
Dockat No. 50-278 Attachm0nt to Monthly Operating Report for July, 1985 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 3 2.
Scheduled date for next refueling shutdown:
July 14, 1985 3.
Scheduled date for restart following refueling:
October 17, 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.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
MAPLHGR Limits Submitted January 7, 1985 Additional Core Limit Information - April 12, 1985 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 pools (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:
l The spent fuel pool storage capacity has been relicensed for l
2816 fuel assemblies.
9.
The projected date of the last refueling that can be discharged to l
the spent fuel pool assuming the present licensed capacity.
March, 1992 (January, 1987 with reserve for full core discharge)
Dockot Nos. 50-277/50-278 Attcchm:nt to Monthly Operating Report for July, 1985 Peach Bottom Atomic Power Station Narrative Summary of Operating Experiences July, 1985 UNIT 2 Reactor startup began on July 6.
The turbine generator returned to service on July 13.
On July 18, the unit was shutdown to balance the generator and turbine in order to correct a vibration problem.
The unit returned to service on July 20.
On July 22, the unit was shutdown to repair an instrument test tap leak on the "C" reactor feedpump flow transmitter sensing line.
The unit returned to service on July 25.
Load was reduced on July 27 to 738 MWe for a control rod pattern adjustment.
Upon completion of the control pattern adjustment, the unit returned to full power on July 30.
On July 30, load was reduced to 860 MWe after the main steam line radiation levels increased as a result of an apparent resin 1
injection into the reactor vessel when placing the "G" filter demineralizer in service.
The unit returned to full power on i
July 31.
I r
(
On July 31, a loud reduction to 791 MWe was initiated in order to
{
remove the "A" reactor feedpump from service for repair of the feedpump turbine exhaust rupture disc.
After removing the "A"
reactor feedpump from service, load was held at 791 MWe in order I
to regenerate several condensate filter demineralizers.
The unit
r Attachment to Monthly Op3 rating Report for July 1985 Page 2 ended the report period operating at 934 MWe.
UNIT 3 The unit began the month at 73% power in extended core flow coastdown operation.
On July 9, a personnel accident associated with the cooling tower transformer caused an initiation of one of two automatic logic f
signals for the Group II and III containment isolation in both units, and loss of various electrical loads, including the Unit 3 recombiner compresser and air ejector.
On July 14, Unit 3 was shutdown for its sixth refueling outage.
The scheduled return date is October 17, 1985.
The vessel head, steam dryer, and moisture separator have been removed.
Local leak rate testing (LLRT) of the eight (8) main steam isolation valves (MSIV) has been completed; two (2) need attention.
By the end of July, the aug.mented T 1ervice Inspection program to p
4 satisfy Generic Letter 84-11 inspect.on requirements has resulted 9
i in confirmed crack indications in three welds in previously uncracked Induction Heating Stress Improvement (IHSI) treated
~
Residual Heat Removal (RHR) system welds.
Two of the three welds will be weld overlay repaired.
Based on fatigue crack growth analysis, a decision on the third weld is pending.
e a,
_g PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET GTREET P.O. BOX 8699 PHILADELPHIA, PA.19101 1215)8414000 August 15, 1985 Docket Nos. 50-277 50-278 Director Office of Inspection & Enforcement US Nuclear Regulatory Commission Washington, DC 20555 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 July, 1985 forwarded pursuant to Technical Specification 6.9.1.C under the guidance of Regulatory Guide 10.1, Revision 4.
Very truly yours,,
R.
H. Logue Superintendent Nuclear Services Attachment cc:
Dr. T.
E. Murley, NRC Mr. T.
P. Johnson, Resident Inspector Mr. Stan P. Mangi, Dept. of Envir. Resources Mr.
P. A.
Ross, NRC (2 copies)
Mr. Thomas Magette, Maryland Power Plant Siting INPO Records Center rExy W
.