ML20092D005

Monthly Operating Repts for Jan 1992 for Braidwood Nuclear Power Station Units 1 & 2

ML20092D005
Person / Time
Site:	Braidwood
Issue date:	01/31/1992
From:	Kofron K, Pershey C COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BW-92-0080, BW-92-80, NUDOCS 9202120244
Download: ML20092D005 (20)

Text

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j Braldwood Nuclear Power Station 4

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'3 ' Route A't Box 84

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/ Braceville. lilinois 60407 -

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Telephone 815/458-2801 February 10,1992 4

BW/92-0080 Director, Office of Resource Management Unitod States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the Monthly Performance Report covering Braidwood Nuclear Power Station for the period January 1 through January 31,1992.

Very truly yours, K, L. Kofront'2-Station Manager Braidwood Nuclear Station KLK/JUdla (227/ZD85G).

Attachments cc:

A. B. Davis, NRC, Region 111 NRC Resident inspector Braldwood 111. Dept. of Nuclear Safety -

M. J. Wallace E. D. Eenigenburg T.J.Kovach Nuclear Fuel Services, PWR Plant Support INPO Records Center Performance Monitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station R. Pulsifer - USNRC T. W. Simpkin -

D. R. Eggett -' Nuclear Engineering Department

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9202120244 920131 PDR - ADOCK 0500o456 y

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-BRAIDWOOD NUCLEAR POWER STATION UNIT 1 AND UNIT 2 HONTHLY PERFORMANCE REPORT COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-456, LICENSE NO NPF-72 NRC DOCKET NO. 050-457, LICENSE i10 WF-77

4 I.

Montbly Report'for Braidwood Unit 1 A.

SamarLoLQaenting_fapertanct Braidwood Unit I entered the month of January, 1992, at approximately 94% reactor power.

The unit operated routinely during the month wtth no significant outages or power

-reductions.

i l.

i (227/ZD85G)3

B.

• DEifLAIIRG_DAIA_REORI-DOCKET NO.:

50-456 UNIT:

Braidwood 1 DATE: _02/10/92.

COMPILED BY:

C. E. Pershey TELEPHONE:- (815)458-2801 ext. 2173 OPERATING STATUS 1.

Reporting Period:

January, 1992 Gross Hours:

744 2.

Currently Authorized Power level (MWt):

3411 Design Electrical Rating (MWe-gross):

1175 Design Electrical Rating (MWe-net):

1120 Max Dependable Capacity (MWe-gross):

1175 Max Dependable Capacity (MWe-net):

1120 3.

Power level to which restricted (If Any):

None 4.

Reasons for restriction (If Any):

None IRIS _110 RTE YR TO DATI _CURQL611VL.

5.

Report: period Hours:

744.0 744.0 3D253__

6.-

Hours Reactor-Critical:

744.0 744.0-2302412-7.-

RX Reserve Shutdown Hours:

' 0_a0 0.0 O0 t

8.

Hours Generator on Line:

7AA,D 744.0 ____22516.0 9.

Unit Reserve' Shutdown Hours:

0.0 __

0.0 0 <0 10.

Gross Thermal Energy (MWH):

_23A1169__. _2A42250__ _61127276 11.

Gross Elec. Energy (MWH):

839770

__839770 23161961__-

12._

. Net.Elec. Energy _(MWH):

809197._

__803132__ _22_111121 13..

Reactor Service Factor:

100.0 100.0 74,3_

14,

. Reactor Availability factor:

10A,0 190.0_

74.9 15.

-Unit Service-Factor:

-100.0-100,0-7314 16.

Unit Availability Factor:

190.0-100.0 73.4 17.

Unit Capacity Factor (MDC-net):

97.1 97,1

- 64.2 -

18.

Unit Capacity Factor (DER net):

97 l-97.1 64,2_

t 19.

Unit Forced Outage Rate:

0.0 0.0 12.3 20.

Unit Forced Outage Hours:

0.0 0.0 2151.3 21.

Shutdowns Scheduled Over-Next 6 Months:

None 22.

If Shutdown at End of Report Period, Estimated Date of Startup:

(227/ZD85G)4 L

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AVERAG EDALLLUH11JiELP014ER_L EVELLQG DOCKET NO.:

50-456 UNIT:

Braidwood 1 DATE:

02/10/92 COMPILED BY:

C. E. Pershey TELEPHONE:

(815)458-2801 ext. 2173 MONTH:

January, 1992 1.

1010 17, 1117 2.

1062 18, 1088 3.

1088 19.

0091 4,

1102

20. ___

1014 5.

1029

-21, 1102 6.

1019 22, 1107 7,

1112 23.

1045 8.

1101 24, 1096 9.

1112 25, 1015 10.

1103 26, 10a8 11, 1094 27.

1Q60 12, 1078 28, 1085 13, 1096 29, 1109 14.

1101~

30.

1_Q98_

15.

1107 31.

J.QE3 16.

1120 INSTRUCTIONS On this form list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

These figures will be-used to plot a graph for each reporting month.

Note that when maximum dependable capacity is used for the net electrical

~

rating of the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line).

In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

c.

L Due to condenser efficiency.

l-(227/ZD85G)5 l

a.

2D

- 1LNIT-SHUTDOWNS / REDUCTIONS ;

DOCKET NO.: 50-456,...

tJNIT: Braidwood 1-

'DATE:;02/10/92~

' COMPILED BY: C. E. Pershey -

'l TELEPHONE: (815)458-2801 ext. 2173

~

REPORT PERIOD: January,"1992

_N_Q_

Qalf 11P_E HOURS REASON. METHOD LER NUMBER. SYSTEM 'COMPONENI CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE None 4

SUMMARY

TYPE REASON METHOD SYSTEM & COMPONENT F-Forced A-Equipment Failure 1 - Manual Exhibit F & H S-Scheduled B-Maint or Test 2 - Manual Scram Instructions for Preparation of C-Refueling 3 - Auto Scram Data Entry Sheet D-Regulatory Restriction 4 - Continued Licensee Event Report E-Operator Training & License Examination 5 - Reduced Load (LER) File (N'JREG-Ol61)

F-Administration 9 - Other G-Oper Error H-Other (227/ZD85G)6

j^'.

E.

-UNIOUE ' REPORTING REOUIREMENTS - Unt't 'l 1.

' Safety / Relief valve operations.

VALVES NO & TYPE PLANT DESCRIPTION QATI ACTUATED.

ACTUATION CONDITION OF EVENT

-. None si

'l 2.

Licensee generated changes to ODCH.

See attached.

(227/ZD85G)7 L

.n.

e,

4 F.

LICENSEE: EVENT REPORTS - UNIL1

-The following-is a-tabular. summary of alll Licensee Event Reports submitted during.the reporting period, January 1 through January 31, 1992:.

This information is provided pursuant to the reportable occurrence

< reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Report RenotLHumber_

Rate Iltle_oLCtccumace None-1 I.

I (227/ZD85G)8 i

I, Monthly Report for Braidwood Unit 2 A.

Sumary_oL0penting.lxnertene Braidwood "..it 2 entered the month of January, 1992, at approximately 96% reactor-power.

The unit operated routinely during the month until January 26, 1992, when load was reduced to perform scheduled maintenance on the

. Heater Drains system.

The unit operated routinely through the end of the month following this maintenance.

l (227/ZD85G)9 L

~

D.-

OfEfBIlliG DATA __ REEORI DOCKET NO.:

50-457 UNIT:

Braidwood 2 DATE:

02/10/92

1 COMPILED BY:

C. E. Pershey l

TELEPHONE:

(815)458-2801 ext. 2173 J

OPERATING STATUS 1.

Reporting' Period:

January, 1992 Gross Hours:

744 2.

Currently Authorized Power Level (MWt):

3411 Design Electrical Rating (MWe-gross):

1175 Design Electrical Rating (MWe-net):

1120 Max Dependable Capacity (MWe-gross):

1175 Max Dependable Capacity (MWe-net):

1120 3.

Power level to which restricted (If Any):

None 4.

Reasons for restriction (If Any):

None THIS MONI11 YR TO DALE _ CUhulallyE 5.

Report period Hours:

14 L

.____]_4 L _ _2B835_

6.

Hours Reactor Critical:

7_4 L 744_ __23El016 7.

RX Resarve Shutdown Hours:

0.0 OJ OJ 8.

Hours Generator on Line:

144_ ___144_

_232BA10 9.

Unit Reserve Shutdown Hours:

01.0 OJ QJ 10.

Gross Thermal Energy.'(MWH):

_2422213__.._2422213 _ Sllll82 L 11.

Gross Elec. Energy (MWH):

._B36260_ _ a36260_ 211M10A_

12.

Net Elec. Energy.(MWH):

_BME62_._ _E05962 22168151_

13..

Reactor Service factor:

100 100_

BL5 14.

Reactor Availability factor:

100 100 BL.5 15.

Unit Service Factor:

100 100 80J 16.

Unit Availability Factor:

100

_100 _

80.7-17.

Unit Capacity Factor (MDC net):

96.1

_96,7

_68.6 18.

Unit Capactty Factor (DER net):

96.7 9.6J 6fL.6 19.

Unit Forced Outage Rate:

0.0 OJ

_3.9 20.

Unit Forced Outage Hours:

0.0 0.0 _.94118 21.

Shutdowns Scheduled Over Next 6 Months:

None 22.

If Shutdown at End.cf Report Period, Estimated Date of Startup:

(227/ZD85G)10

C.

AVIRAGE_DAILLU1P LNELE0liEfLLEYEL_ LOG DOCKET N0.:

50-457 UNI 1:

Braidwood 2 DATE:

02/10/92 COMPILED BY:

C. E. Pershey TELEPHONE:

(815)458-2801 ext. 2173-HONTH:

January, 1992 1.

1065 17, 1047 2.

106S 18, 1997 3,

1078 19.

1D89 4,

1103 20, 1098 5.

1099 21.

1103 6,

1095 22, 1105 7,

1115 23, 1087 8.

1118 24, 1092 9.

• 1127 25.

1058 10 -

1119_

26, 683 11.

1095 27.

1087 12, 1075 28, 1120 13.

1093 29.

1111 14.

1109 30, 1093 15.

1114 31.

IDB9 16.

112D INSTRUCTIONS On this form _ list the average daily unit power level in HWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month.

Note-that when maximum dependable capacity is used for the net electrical rating _of the unit there may be occasions when the daily average power level exceeds the 100%-line (or the restricted power level line).

In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

l-

• Due to condenser. efficiency.

L (227/ZD85G)11

D.

1) NIT SHUTDOHNS/ REDUCTIONS

' DOCKET NO.:.50-457.

UNIT: Braidwood 2 DATE: 02/10/92-COMPILED BY: C. E. Pershey-TELEPHONE: (815)458-2801' ext. 2173 REPORT PERIOD: January, 1992' No DAIE TY_PE HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE' 1

920126 S 19,3 8

5 N/A SI

'STR Load reduction taken to perform a scheduled Heater Drain pump strainer flush. Pump was returned to service prior to power ascension.

1 o***.....**

SUMMARY

o.***..*******...

TYPE REASON METHOD SYSTEM & CCNPONENT F-Forced A-Equipment Failure 1 - Manual Exhibit F & H S-Scheduled B-Maint or Test 2 - Manual Scram Instructions for Preparation of C-Refueling 3 - Auto Scram Data Entry Sheet D-Regulatory Restriction 4 - Continued Licensee Event Report' E-Operator Training & License Examination 5 - Reduced Load (LER) File (NUREG-0161)

F-Administration 9 - Other G-Oper Error H-Other (227/ZD85G)12

E.

.UNIOUE REPORTING REOUIREMENTS - UNIT 2 1.

_ Safety / Relief. valve operations.

VALVES.

NO & TYPE.'

PLANT-DESCRIPTION QAJE ACTUATED ACTUATION CONDITIOR.

OF EVEhT A

None 2.

Licensee generated changes to ODCH.

See attached.

t

)

(227/ZD85G)13

- - - ~ _..

F.

LICENSELEVENLREEORIS - UNILZ-The following'is a tabular summary of all Licensee Event Reports submitted during the reporting period, January 1 through January 31, 1992.

This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Report Reno.tLHumhe.r Date Ilt1e of Oc.cattence 91-006 01-13-92 Generator trip caused by spurious actuation of neutral ground relay.

1 l

(

i (227/ZD85G)l4 L

1 CHA'<OES TO THE OFFSITE DOSE CALCULATION MANUAL Changes to the Offsite Dose Calculation Manual (ODCM) are reportable to the Nuclear Regulatory Commission (NRC)in accordance with station Technical Specifications.

Part I of Revision O.F. to the Braidwood Annes, identifies a new dairy for milk sampling, BD-26, Gaddis Farm, replacing BD-18, Biros Dairy Farm.

This revision does not reduce the accuracy or' reliability of dose calculations or setpoint determinations, and has been reviewed and found acceptable by the Onsite Review and Investigative Ftmetion.

020592 48/ZCGEN

lawAP 1205-371 Revision 4 Braidwood On-site Review and Investigation Report

.OSR Numb 2rt 91' 00'l.,_

Date: _l' Z $ $'{

Subject Review:,Idsd bv bd'* d**^ M ^ud (W A). dt

.T 4f Rev or v

Q ts d a <4 II

• VI J (6- > W n. d whi. 4 A. a n Requested by:

Nik b '0% C C Disciplines Required! RA Nuclear Power Plant Technology BB Reactor Operationo DC Reactor Engineering DD Chemistry NE Radration Protection

'O r Instrumentation and Control 2G Hechanical and Electrien1 Systems

Participants:

R f S

,~,r.

_oE y

TSS Er u..s.

^=

OSR Membership Approved k

l N' Technical Staff Supervisor

/

Date 10CFR50.59Screeningand/orSafetyEvaluationisRequired?---Y/h N

If yes,-attach completed documentation in accordance with DwAP 1205-6.

Concurrence Required by Offsite Review? (per Section C.6) - - - Y /h b

Findings and Recommendations:

f)Maled 42 tdent C, o nN d a. gj E, mitic h a' h 6

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/leenria Mr t '. h

• T /t 1 in u _i - W d it n he d P /ttwnrv s e n M (1 Dorob.\\ -

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On-Site Review Committee Signature indicates concurrence with Tindings ard Recommendationr. and 10CFR50.59 Safety Evaluation.

Lonstures 0.11giglint11)

DAtt fw b bb ll~2bil-1/,, dd.L

~ APPROVED c

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'IUL 0 91991

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/mn BR AIDWOOD ON st?E RE view

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Approved by:

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STATION MANAGER DATE 130(070991) 1 of 2 ZWBWAP

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BwAP 1205-371~

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Revision 4

'-e-BRAIDWOOD OH-SITE hEVIEW AND INVESTIGATION REPORT OSR Ho*.

• • n*********** enenene*******e**=>****e*******

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This checklist-ic'provided as-guidance for OSR 1*

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• preparation and review.

Items should be completed as appropriate.

• • • • • • • nn******e *******eoe********ee***** n**n****

Preparer Apo. N/A I.-

SYNOPSIS TORMAT

'X'

- Purpose jeu Ab N A m b M hmM Xl

--Executive Summarf of _ Findings and Recommendations

's '

- References ~

- Bases of TindingsTand Recommendations

,,l Contingency Actions Recommended _._

u

.II., DOCUMENTATION ! REVIEWED : -(List Applicable Sections in Synopsis) 1;

- UTSAR

= Tech Specs. 2a 6~~a>

Nm-

- Admin Tech-Requirements

,e,

- Safety Evaluation Report

- Tire Protection Report.

.l

,l

- Prior 10CTR50.59 Safety Evals

- NRC Commitments f,

/

- Vendor-Documentation ll

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- Special Permits / Licenses _

s'

- Station: Procedures l

- Environmental Qualification

--Desion Basis Docunentation ll

,/(;

l/

- Drawings

- Mnint. Hi;, tory (TJM).

--NPRDS>

'/ '

.:PRA-Info.

l l/ l

- Prior NED OE:40.1 operability Evaluations 4.

- III, PLANT CONDITIOttS

'(Discuss Applicable Items in Synopsis)

)

J'

- Applicable - Modes.

l/l

- Nork:In-Procress/ Planned

- Temporary Alteration Installed

- Out-of-Service; f,

- Degt:kded -- Equipment Log-

- AbnoTmalEValve Lineups

/.-

- Effect on Opposite Train.-

- Effect on Other Unit

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- Effect'on Other Station-

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--Training Required IV.

OTHER 'UNSIDERATIONS:

. Discuss Applicable _ Items-in Synopsis)

(

'X; JC

--Consistency-(dates,1 document no.s, values, EID's-etc.)

- Grammar- (Continuity, spellin" flow, etc.)-

i

[/] - Engineering Review of-A/C Calc,ulations and Assumptions-Adequately Documented

/,'

- Reportability (10CTR21, 10CTR72, etc) l'

-Prepared by:

eUh APPROVED '

l (Final) l

'130(070991).

2 of 2

.lUL 0 9 li'91 ZWBWAP 2RAnnvooo

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• I

BRAIDWOOD REVISION 0.F DECEMBER-1991 BRAIDWOOD ANNEX INDEX PAGE REVISION l

CilAPTER 11 11-1 0.F 11411 0.A 11-111 0.A 11-iv

'O.A 11-1 0

11-2 0

11-3 0

11-4 0

11-5 0

11-6 0.D 11-7 0.F

'11-8 0

11-9 0.A 11-10 0.A 11-11 0

11-12 0.A 11-13 0

11-14 0

11-15 0-11 '6 0

11 _7 0.F a

11-i

7.

REVISION 0.F BRAIDH000 DECEMBER 1991:

e 3.

Waterborne (Cont'd)

' Gross beta anal'ysis d.

Coolina Water -BD-08, Intake Pipe No.'3, 5.0.mi E (8.0 km E) Heekly 60-09. Discharge Pipe No. 4, 5.0 mi.E (8.0 km E) e.

Shoreline 80-10. Kankakee River downstream of Semiannually Gamma isotopic' analysis on each -

Sediments discharge, 5.0 mi ENE (8.0 km D) sample.

4.

Incestion' Semimonthly: May to October Gamma _ isotopic and l

a.

Hilk Indicators Monthly: November to April I-131 analysis on each l

sample.

BD-11, Morris / Hack Farm 2.4 mi E (3.9 km E) l 8D-17. Halpin's Dairy, 5.5 mi SSH (8.8 km K)

BD-26. Gaddis Farm, 11.0 mi ESE (17.6 km F)

Controls 80-18, Biros Farm, 10.5 ml N (16.9 km N) b.

Fish BD-07. Kankakee River upstream of discharge, Three times a year (spring, Gamma isotopic 5.4 mi E (8.7'km E) summer, and fall) analysis on edible portions.

j 80-10, Kankakee River downstream of discharge, 5.0 mi ENE (8.0 km D) c.

Veaetables 80-14, Pinnick Farm, 1.8 mi N (2.9 km A)

Annually Gamma isotopic analysis on edible BD-15, Girot Farm, 1.4 mi N (2.2 km A) portions.

80-16. Clark Farm 3.3 mi ENE (5.5 km D) 11-7 4

is,

l REVISION 0.f DECEMBER 1991 22 *

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ankakee K

River Braicwood

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Location it.

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'J i om.u:ioa Station u

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Braceville w

County Line Rd, e

d Gardner i

Essex Aice Rd 7

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0FFSITE DOSE CALCULATION MANUAL 4

BRAIDWOOD STATION FIGURE 113 INGESTION AND WATERBORNE EXPOSURE PATHWAY SAMPLE LOCATIONS

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VaW-m 11-17

_ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ - _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _