ML20064H686

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Monthly Oper Rept for Nov 1978
ML20064H686
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/12/1978
From: Alden W
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20064H684 List:
References
NUDOCS 7812220064
Download: ML20064H686 (9)
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Text

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AVERAGE DAILY UNIl POWER LEVEL DOCrli NO. 50 - 177 UNIT PEACH BOT 1CM UNIT 2 DATE DECEMBER 12i1978

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COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN E NG I NEER -IN-CH A RGE NUCLEAR SECT ION GENERATION DIVISION-NUCLE AR 1ELEPHONE (215) 841-5022 MCNih NOVEMBER 1976 DAY AVERAGE DAILY PCWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MdE-NET)

(MWE-NET) 96E 17 1055 1

319 18 2

1054 977 19 3

1051 1047 20 k

1052 4

21 1054 1051 5

22 1023 1050 6

705 23 7

1048 i

724 24 8

1046 935 25 1049 9

351 26 10 104a 27 912 ILb7 11 28 1050 12 1061 29 1029 look 13 -

1042 20 181 14 690 15 952 16 781222006f l

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OpteatlNG DATA LLPORT i

OCLatt

  • C. ?O = 211 n..

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Calf G&tialta 11 1976 Com*LEik0 ST FMIL ADt LPMla ELEC1RIC CLM* ANT u.a.AL0th

&NGINEEk-1N-CMA4GI NoCLEAR 5ttilCN GENtRallCN Olvl510N-90CitAR ftLEPMONk 4215) a = 1%012 8

LPE RA11NG 51 A195 i N014 5 1N is Lasti IIPitithCEO 08st 1

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8. Uhli NAME: Pl&C> 60110m 17 11 2 l
2. REPOR11NG PtRICO Novkm&ER. 1973 i

PowEn RLOuLTION AND THREE I

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3293 3

5>UT 00mh5 1H15 m0N1H.

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3. LICIN510 INEAmAL PCmLRINulls l

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4 NamfC Aft RATING IGaC15 Natis 1152 3

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I S. CESIGN ELECTRICAL RA11NG LNE1 muti 1065 I

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a. mallmum C1PENDAbLL CAP ACITY IGR055 mutts 1098 I

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7. maximum DLitN0 AbLE CAP AC11Y (NET mwils 1053 I
6. IF CHANGli OCCUR IN CAPAC11Y RA?!NG5 (11 Ems pas btR 3 InnouGM 71 SINCE L*51 REP a

ANT int 1 Muti PostR LkytL 10 WHICH RL51RIC1LD. IP 9

IC. RfA5045 FCR Rt51RIC110N5. 1F ANY:

IH15 MONTH T R-10-O AT E CumuLAT1vt 720 9,514 36 460

11. hours IN RtPCRT ING PERICO s!3 t,tv$

24.68S

11. NbhbER OF Hoba5 AEALTOR was CRITICAL 0.0 6.C 0.0
13. EkACTCR RE5fRVE SHuf00was HCURL e78.5 6.577.3 27.562.3
n. % R5 CENERA1CR CN-LINE 0.0 00 0.0 13.

4 11 REstRvt SHUTOCNN HOUR 5 2 110.256 14,333.370 77.920.984 as. GAc55 1HERmAL thtRGY CENERATED tmmal 481 430 6.304 340 25.357.494

17. GRC15 ELECTRICAL ENERGY GENERA 1k0 (numt 603 530 6.051e%21 24.299.441
18. NET ELECTRICAL ENtRGY GENERATED Imuni h.2 82.1 72.4 1%. UNIT SLRvitt F AC1CR 72.4 94.2 02.1
20. uself AvalLAblLITY F ACICR 87.7 71.5

$9.8

21. usa ti C AP AC11Y F AC104 tu11NG mOC peETI St.$

70.9 99.0

22. Ute11 CAPACITY FACTOR tu11NG DER NET)

S.8 3.5 s.O

23. uself FCRCEO Cu1 AGt R ATE I

OF EACHis SHuTOOuMS SCHEDULEG Ovik Nt K1 6 PONTH5 (TYPE. Dait. A8eo OURATION 24 1

25. IF 5HuTocuss at Efe0 0F REPOR1 PtR100. 15T1M&110 Daft OF staptura en/a 1

FORECAST ACHIEvt0 1111 5141us (P61CR 10 C0puntRCI AL OPERal10mla it. uN!IS Ife INITI AL CRITICALITY

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INITIAL ELECTRICITY CCMatRCIAL QPERATICN

-i 00(#t1 NO. $O - 277 bNil 5HulbumNS AND POWLR REDUCI!0NS UN!! NAML PLACH boff 0M UNil 2 DAIL OtCLMbER 12.1978

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REPbR1 MONTH NOWLMbtR, 1978 COMPLEILO bV PHILADtLPHIA ELEC1RIC COMPANY

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W.M.ALDEN j

ENGINEER-!N-CHAMGL l

NDCLIAR 5LCilDN g

GLNLRAI!bh Olvl51DN-hACLLAR ILLEPHONE (21SI 841-5022

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EVENI l COOL i CODE I ACIl0N 10

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No.1 DATE I till ! HOUR $ll (28 i REACIOR 838 i REPOR) #

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($8 l PREViNI RLCURRENCE h

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LNIRV $HLL15 70R LICLN5LL 3 - AUICHAllC SCRAM.

LVENI RLPORT ALLRI C - kEFULLING 4 - DIHLR (EXPLAIN)

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AVERAGE DAILY UNIT POWE1 LEVEL DOCKET NO. 50 278 UNIT PE ACH BOTTOM UNIT 3 DATE DECEMBER 12,1978 COMP ANY PHIL ACELPHI A ELECTRIC COMPAN i

g W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERAT10N DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH NO\\LM6ER 1976 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY PCWER LEVEL (MWE-NET)

(MWE-NET) 17 1039 1045 1

1033 la 2

1043 1040 19 3

1044 1G40 20 1041 4

1037 21 5

1044 22 1040 507 6

23 1039 83 7

1039 24 582 8

25 1039 895 9

1041 26 989 10 27 1036 11 705 1042 28 922 12 1041 29 1002 13 30 1039 897 14 1044 15 1032 16 1

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CPEmallNG DATA REPCRT 00CRif 4. 50 - 274 Daft OkCEm4Ek 12 1976 CCMPtt1ED BT PalLACELPm1A LLECTRIC CCmPANY N.M.ALOEN E NGINEE A-IN-CHARGE NUCLEAR SEC11Cm GENERATICN Olvl510N-NuCLLAR TELEPMCNE 12151 041-5022 OPtR AtlNG STATUS l NCTES: 1M15 UNIT EXPERIENCED CNA l

3

1. L* elf Naatt Pt ACH B0110m uMIT 3 g

POuth REQuCTION Asso A Shut i

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atPOR11NC PtR1002 Novtabkm. 1978 3

i DOum This MONTM.

3293 1

1

3. LICtN5LO 1>tamAL Postalamils l

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i NAmtPLATE RailmG IGR055 m=Els i

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t. Ok11GN LLEC1RICAL RATING (NL1 nulls --

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mAAlmum OLPtNCABLE CAPACITY ( GROSS en g l 1998 l

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7. mAAlaum OtPtNDA6LL CAPACITY lNL1 mutts 1035 l

3 THROUGM Tl !!4CE LA51 REPORT, G1Wh REA5CN58

t. IF CHANGE 5 DCCLR IN CAPAC11Y RAllNGS tlTimi NumblR INE T MwE l s POWER Ltytt TC wMICM RESTRICTED,17 ANY RE ASCNS FCA RE51RIC110NS, IF ANY:

TH15 mCPette TR '10-0&TE CumutATIVk 720 E,016 34 536

1. hCURS IN REPOR11NG PERICO 704 6,766 27.36S Ncubik 0F tour 5 REACTOR ua5 CRITICAL

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C.0 G.0 0.0

.3. RE ACitA RE5ERVE SMul00mm MotA5 497.5 4.670.9 26,685.9 4 HOUR $ GENERA 10R 04-L IN E 0.0 0.0 0.0

.S. LMIT RtitRvt SMb100mm HobR$

GRC&& THERMAL ENERGY GENERATED tmwMI

2. L,4,64 4 19,460,755 h e*AteS30 66 711,420 te4S9,0%Q 23,429,730
17. GROS $ ELECTRICAL ENERGY GENsapILO imWM) 682,101 6.196.205 22,473.204
18. NE1 ELLCTRICAL ENERGY GENERATED inwMI 96.9 8 4. '

V7.3

19. UN11 SE RVICE P ACTOR 96.9 83.2 77.3

.0. UNIT AVAILA6tLITT FACTOR 91.5 74 62.9

21. UN1' CAP ACITY P AC10A tuSING MDC NETI 89.0 72.6 61.1

.2. bM11 CAPAC11Y PAC 104 (U51NG DEk NEll 3.1 2.1 13

.3. UN11 PORCED Ou1 AGE Raf t OP EACHis SHU100mM5 SCHtouLt0 04th NkR1 6 MONTH 5 t TYPt. D ATE, AND OuRATION 14 N/A END OF REPCRT PER100. ESTIMATED DATE OF STARTUP

25. IP SMuf 00 wee AT FORECAST ACHIEvt0
26. Ese115 1N TkST STATUS IPR 10R TO CommtRCI AL QPERATIONis INITIAL CRITICA&lTY INITIAL ELECTRICITY ConseERCIAL OPERATION

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50 - 278 UNB1 5Hul00mNS ANO POwtR REDuCilbN5 ONll NAME PEACH B013CM DN11 3 DAIL DECEMbfR 82,1578 j

REPhki MON 1H NuvtMbER, 1978 00MPLE110 bY PHILADtLPHIA L LECIkl0 COMPANY W.M.ALDEN E NG INE E R- !N-Cid R GL NDCLLAR SECllbN e

GLNLR AllbN OlVISIDH-NUCLL AR ILLLPHONE (2158 841-5022 e.

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Harrative Su= mary of Operating Experiences Feach Bottom Units 2 and 3 l

Jovember. 1978 peach Botton Station E

Unit 2 Unit 2 continued operating at rated power until November 8 when a reactor feedpump control malfunction caused a 200 W e power reduction by way of a recirculation pump runback. On November th, the reactor i

experienced a hi;h flux scram as a result of another reactor t

I feedpump control malfunction. The Unit was returned to service and reached approximately 86% power on Ifovember 15, when a load reduction to 600 We was taken to acco=modate control rod pattern adjustments.

Rated power was reached on November 17 via a preconditioning ra=p.

At 10 pm on the same day a reactor low water level scram resulted from a high vibration trip of a reactor feedpump turbine. The Unit was returted to service on November 18 and was brought to full power November 19 Oa : ovember 22, a load reduction was taken to accommodate adjustmen3 of the control rod pattern and the Unit reached full power l

cn Nove h r 26 via a fuel preconditioning ramp and power reduction i

to allow setting of the shallow control rods. A spurious operation of the power / load unbalance relay caused a rew: tor scrax early in the day l

of November E6. The Unit was returned to service late on the day of i

November 28. A brief load reduction of 30 We was experienced en November 29, as a result of diffic% ty in completing service testing of the No.1 intermediate stop valve.

Unit 1 4

Unit 3 centinued operating at rated power until November 6, when an-I electronic component failure in tN master feedwater controller caused a reactor scram and a Group I Isclation. Correction of improper per-l formance of HPCI following the Group I isloation and a scram due to IPli j

si.gnil noise delayed returning the Unit to service until November 7 The Unit reached 10h0 Ee via a preconditioning ramp on November 10c The Unit reached 1050 We on November 13 following a load reduction to adjust the control rod pattern.

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. Docket No. 50-277 4

Attachment to Monthly C;:erating Report r N vember 1978 l

REFUELD;G DTiORMATION _

1 1.

Name of facilityi Peach Botton Unit 2 2.

Scheduled date for next refueling chutdown:

March 22, 1980 3.

Scheduled date for restart following refueling:'

f l

May 2, 1980.

14 Will refueling or resumption of operation thereafter require a technical specification change or other license amend =ent?

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

l Technical specification changes to accomodate reload fuel.

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Modifications to reacter core operating limits are expected, i

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5.

Scheduled date (s) for submitting proposed licensing action and-t supporting information:

e February 1, 1980 t

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:

Initial utilization of General Electric 8x8 Pre-Pressurized Fuel Assemblies.

i

'7 The number of fuel assemblies (a) in the-core and' (b) in the spent -

[

fuel storage pool.

(a) Core - 764 Fuel Assemblies t

(b) Fuel pool - 618 Ir adiated Fuel Assemblies r

6.

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:

)

4 i

Present capacity is 1110 fuel assemblies. An increase in licensed capacity to 2816 fuel assemblies has been given. New high density racks to be installed.

9 "he projected date of the last refueling that can be discharged to L

the stent fuol pool assuming the present licensed capacity-

.hrch, 1992 i

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Dcchet No.

50-278 Attach =ent to Monthly Operating Rnpert REFUELING IITF0FJ4ATION 1.

Name of facility Peach Bottc Unit 3 2.

Scheduled date for next refueling shutdown:

September 8,1979 3

Scheduled date for rectart following refueling:

October 27, 1979 h.

Will refueling or resu=ption of operation thereafter require a technical specification change or other license amend =ent?

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

Technical specification changes to acec=odate reload fuel.

Modifications to reactor core operating limits are expected.

5.

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

July 25, i979 6.

I=portant licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unraviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

Initial utilization of General Electric 8x8 Pre-Pressuri::ed Fuel Asse blies.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

a) Fuel pool - hho irradiated fuel assemblies Core -

76h fuel assemblies b) 3.

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 uu=ber of fuel assemblies:

Present capacity is 1110 fuel assemblies. An increase in licensed capacity to 2816 fuel assemblies has been given. New high density racks to be installed.

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

August, 1991

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