ML20087F707

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Monthly Operating Repts for Feb 1984
ML20087F707
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 02/29/1984
From: Alden W, Ullrich W
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF ADMINISTRATION (ADM)
References
NUDOCS 8403190198
Download: ML20087F707 (10)
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C05PL5T5D SI 753L&DBLP534 ELSCTRIC C0eFAET 5.5.434 55 55635BBS-35-CSA365 LIC558156 SECTIOS SBBBB&TIOS BETIS100-55C15&A TELEP3055 (215) 841-5022 I

QPER& TING STATUS

1. UNIT NARE: P5&cN BOTTOs OBIT 2 l 50T858 551T 2 COEPLBTSD ITS PB871005 I g

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2. REPORTIuu TEh10D: FEBRUART, 1984 1

OST&GB 151TI& TBS 95 1/28/84, l g

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3. LICENSED THEuRAL POWas taWT):

3293 l

33P53155CBD 055 sCESDSLED 3

g 4 N&R8 PLATE 84 TING (GOOSS SWE):

1152 l

855fD055 TO TBST 881T'S ABD l

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5. DESIGu ELECTA 1 CAL SAT 1gG (5ET RUB) 1065 i

FEEDW ATER CNBCE VALVES, 550 l

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6. N&I15UR DEPENDASLE CAP &CITT (GROSS ROR): 1998 i

Oss SCNBOOL50 LOAD 35DUCTI05 I g

7. nazInun psPEnD&DLE CAPACITT tusT sus):

1951 l

FOR COUTBOL 500 ADJOSTREET.

I S. IF CHANGE 3 OCCUR IB CAPACITT BATINGS (ITERS EUNDER 3 Tut 05Gs 7) SINCE L&st 5570a7, CITE kBASonS:

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9. POWER LETRL TO UNICM RESTRICTBD, IF 45T (EST 5W5):
10. REASONS FOR RESTRICT 1095, IF &ETs TMIS 505?M IB-TO-D&T5 C550LATITE
11. HOURS IN 35 PORT 15G PERIOD 696 1,440 04.548
12. NunuEN OF HOUk3 R44CTOR W AS CRITICAL 495.1 1,147.9 6 0,8 86. a
13. REACTOR k3 SERV 5 SHUTDQUE HobA5 0.0 0.0 0.0
14. HOUus GENERATOR OW-L1st 441.3 1,150 6 59,162.4
15. UNIT WESEk:E SHUTDoup Nuuks 0.0 0.0 0.0
16. Ghos5 THERA &L EbERGT GENET &TBD (mun) 1,467,302 3,611,784 174,166,394
17. GkOS5 ELECTRICAL EutaGT GBWERATED (RUN) 462,430 1,178,770 57,349,860
18. NET ELECTR104L ENERGT GEuts&TED (NUN) 447,367 1,142,694 54,979,124
19. UNIT SERTICE P&CTOR 69.2 79.9 69.9
20. UNIT AT&IL&BILITT FACTOR 69.2 79.9 69.9
21. UNIT CAPACITT FACTOR (WSIBG BDC EST) 61.2 75.5 61.8
22. OsIT CAPACITT FACTOR (USIpu DES NET) 60.4 74.5 61.0
23. 9517 PORCSD OSTAGB BATS 8.0 9.2 12.8 2e. SuuTDovus sCHEDULs0 of an asst 6 nostus (TTPs, c4TE, auD pus &TJ0s or s&Cu):
1. SNUTDOWu FOR esPUBLING AuD FIPS 33PLACEMBut FOR BBCISCUL& TION AND BESIDUAL ME&T REROTSL (RNR) SYSTEMS BEGINNING 4/27/95 Asp LANTING APPRu18A&TELT 32-Jb WE555.

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25. IF SMUTbOWN AT 359 0F 3870*T PERIOD, B8TIEATED D&TE OF START 5Ps
26. UNITS IN TEST STATUS (Pu1ON 70 CORNNNCIAL OPENATION):

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4. 8samtPLATE RATIIeG (GROS $ Mutt s 1153 1

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7. MAAIMuM utPtNDebLk SAPAC11V (Nt1 MWtis 103b I

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40. kk A&DNb FGk At$1klC110hbe IF A8evs th!5 800selh in-10-0Al t CuseUL A13 Vt II. nuunb IN REPO411NG PtR100 696 le440 4u,544
82. Numuth De enouMb ktaciuk es Ab LulllLAL 677.4 1,137.3 67ev37.1
13. ht ACICR RE btRVE &MU100WN teJuR6 0.0 0.0 0.0 84 eiuukh GthkRA10R Ufe-LINT 461.4 le105.5 56,421.7 lb. uNil kkhtkyt 5HulO0mN H0ukh 9.0 0.0 0.0
19. Ghubb INkkMAL ENEkGT GtNthAltD IMeshi 2,079e002 3e4b9e336 164,497.c*3
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19. UNil St4VICE PAC 104 99.0 76.8 70 1
40. UNIT AVAILAg!LIIT PAClun 95.0 76.8 79 8
24. UNI) CAPAC11Y FAC10M IU58Mb MDC sekil 93.8 14.5 62.5 4 2. 08 11 CAPAC41V FAC10R tuliseG DER sekil 90.5 72 4 6u.4 da. UNil FOACEO Ou1 AGE nalt 5.0 23.2 7.6
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277

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UN11 PEACH BOTTOM UNIT 2 DATE MARCH 13, 1984 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SEC110N GENERATION DIVISION-NUCLEAR lELEPHONE (215) 841-5022 MON 1H FhBRUARY 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NhT)

(MWE-NET) 1 0

17 995 2

50 18 5

3 637 19 0

4 781 20 0

5 797 21 0

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1019 22 0

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7 1063 23 0

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1069 24 0

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1066 25 296 l

10 1060 26 893 11 1062 27 663 12 1067 28 891 i

j 13 1061 29 1032 14 1057 l

15 1063 16 1059

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AYERAGE DAILY UNIT PONER LEfBL DOCKET No. 50 - 278 UNIT PEACH BOTTOR UNIT 3 DATE 84RCH 13, 1984 COMPANY PHILADELPHIA ELECTRIC COMPANY W.R.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH FEBRUARY 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(RNE-NET) 1 1073 17 1071 2

1076 18 1068 3

1082 19 1067 4

1094 20 1067 5

1064 21 1074 6

1059 22 1075 7

1096 23 1076 8

1010 24 1076-9 792 25 1080 10 0

26 1081 11-303 27 1079 12 404 28 107f 13 787 29 1084 14 1024 15 1054 16 1053

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WNIT SHOTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 277

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UNIT NAME PEACH BOTTon UNIT 2

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DATE BARCH 13, 1984 L:

.l REPORT BONTE FEBRUARY, 1984 COMPLETED BY PHILADP1PRIA ELECTRIC C05PANY 5.5.ALDEN ENGINEER-IE-CBABGE

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LICENSING SECTION GENERATION DIVISIO5-50 CLEAR TELEPHONE (215) 841-5022 1

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ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAR.

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EIPLAIN)

FILE (NDREG-0161)

Z - OPEBATOR TRAINING + LICENSE EIAMINaIION i

F - AD5INISTRATIVE (5)

G - OPER ATION AL ERROR (EXPLAIN)

H - OTHER (EXPLAIN)

EIBIBIT I - SATE SOURCE 9e n _

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UN11 NAME PE ACH SDTIDM UN11 3 l

f' DATE MARCH 13, 1984 l

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REPOR1 MON 1h Febkuaky, 1984 cDMPLeigD sy PHILADELPHIA kLEC1RIC LOMPAN1 W.M.ALDeN i

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ENTRY SHEk15 FOR LICENSEE C - REFbELING 3 - AUTDMAllt SCR AM.

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D - REGULA1DRV RE51RICTibN 4 - 01hER (EXPLAINI FILE INukEG-Olet)

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Monthly OperaB8ng

. RIport fer.FCbrunty, 1984-REFUELING INFORMATION 1.

Name of facility:

Peach Bottom Unit 2

. = -

2.-

Scheduled date for-next refueling shutdown:

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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

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

Technical ~ Specifications to accommodate reload fuel.

9 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 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 - 1170 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.

4 September, 1990 (March,1986, with reserve full core discharge)

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Dockct No. 50-278 i

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Attcchasnt to Monthly Operating Report for February, 1984 REFUELING INFORMATION 1.: 'Name,of facility:

Peach Bottom Unit 3 2.:

Scheduled date for next refueling shutdown:

March 30, 1985.

'3.

Scheduled date for restart following refueling:

. September 21, 1985.-

Will refueling or resumption of operation thereafter require

4.. a technical specification change or other license amendment?

Yes.

e 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:

June 21, 1985 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 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 - 1212 Fuel Assemblies, 6 Fuel Rods 8.

The present libensed 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 (March,1987, with reserve for full core discharge)

Docket Nos. 50-277 50-278

. ~

Attschmsnt to Monthly Operating Report'for February, 1984 PEACH BOTTOM ATOMIC POWER STATION NARRATIVE

SUMMARY

OF OPERATING EXPERIENCES February, 1984 Unit 2-Startup. began.on February 2 after repair of a packing leak on the RCIC' testable check. valve and a leak in the drywell airlock inner

~

. gasket.

A power reduction was taken on February 4 to permit

. final. control' rod pattern adjustment.

'OnLFebruary.6, in response to Bulletin 84-01, a Drywell_to Torus

Bypass Area Test was performed satisfactorily.

On February 18, the' unit-was removed from service for Main Steam Isolation Valve

-(MSIV) and'Feedwater Check Valve testing in compliance with NRC 10 CFR 50, ' Appendix J. requirements.

One MSIV failed to meet the leak rate requirements, was repaired and successfully retested.

The Feedwater Check Valves tested satisfactorily.

During this outage, an inspection of the Torus Vent Header was conducted.

An isolated defect in the workmanship, associated with previous itorus modifications, has been identified and repaired.

~

The unit returned to service on February 25.

On February 27, T

reactor power was reduced to 426 MWe for a control rod pattern adjustment. -The. unit had reached 97% power at the end of the month..

UNIT 3'-

The; unit began the operating period at full power.

On February 6,~in. response.to Bulletin _84-01, a Drywell to Torus Bypass Area Test was performed satisfactorily.

fl On' February 9, the unit shutdown due to a high' flux scram.

The scram occurred-following a trip of the

'B' reactor feedwater pump l~

due to high. vibration.' Loss of the feedpump initiated runback of recirculation pumps and main turbine.

Turbine runback did not p

automatically terminate as designed, resulting in a reactor

pressure transient that caused the~high flux spike.

-The unit returned to service on February 10.

On February 11, reactor: power.was reduced-to 600 MWe for a control' rod pattern i.

' adjustment.

i.

L On February 12, the unit was reduced to 400 MWe to permit

repacking of a reactor'feedpump coupling and to plug condenser o 3 tubeLleaks; After repairing a condenser water box leak, the unit achieved

' full power on February 14.

On February 16, power was reduced L

90:MWeLto replace a solenoid operated valve on the fifth h

~feedwater heater extraction steam line.

Later in the day, an L

additi~onal 50 MWe reduction occurred when a feedwater heater extraction valve closed-in-the

'C' feedwater loop.

The valve was

- -re-opened'and'the unit attained full power on February 17, and

operated at full power for the remainder of the month.

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET

' ~

P.O. BOX 8699 PHILADELPHI A. PA.19101 (215184t 4ooo March 13, 1984 Docket Nos. 50-277 50-278 Director Office of Inspection &, Enforcement US Nuclear Regulatory Commission Washington, DC 20555 Attention:

Document Control Desk j

SUBJECT:

' Peach Bottom Atomic Power Station Monthly Operating Report Gentlemen:

l Attached are_ twelve copies of the monthly operating I

report for Peach Bottom Units 2 and 3 for the month of February, 1984 forwarded pursuant to Technical Specification 6.9.1.C under the guidance of Regulatory Guide 10.1, Revision 4.

Very truly yours, M,Wd,Y 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 f'b 1

7

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