ML20063P420

Monthly Operating Repts for Sept 1982

ML20063P420
Person / Time
Site:	Quad Cities
Issue date:	10/04/1982
From:	Buss R COMMONWEALTH EDISON CO.
To:
Shared Package
ML20063P417	List: ML20063P416 ML20063P420
References
NUDOCS 8210130390
Download: ML20063P420 (13)

Text

..

TABLE OF CONTENTS

.I.

Introduction i

II.

Summary of Operating Experience A.

Unit.One B.

Unit Two III.

Plant or Procedure Changes, Tests, Experimente, and Safety Related Maintenance A.

Amendments to Facility License or Technical Specifications B.

. Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval D.

Corrective Maintenance of Safety Related Equipment IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions VI, Unique Reporting Requirements A.

Main Stem Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary i

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' INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe net, located in Cordova, Illinois.

The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Comoany. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construc. ion contractor was United Engineers & Constructors. The condenser.

cooling method is a closed cycle spray canal, and the Mississippi River is the condenser cooling water source. The plant is subject to license nuabers DPR-29 and DPR-30, ' issued October 1,1971, and March 21, 1972, respectively, pursuant to Docket Numbers 50-254 and 50-265. The date of initial reactor criticalities for Units 1 l.

and 2 respectively were October 18, 1971, and April 26, 1972.

Commercial generation? of power began on Fabruary 18, 1973 for Unit l'

I and March 10, 1973 for Unit 2.

l This report was compiled by Becky Brown and Randall Buss, i

l telephone number 309-654-2241, extensions 127 and 181.

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'II..

SUMMARY

OF OPERATING EXPERIENCE r

[A.

Unit One-2 September 1-30: ' Unit: One began the month holding load at approximately

.400 MWe.

The unit is derated -due to end of cycle fuel depletion /

coastdown. ~ 0n' four occasions.the Load' Dispatcher requested a load '

' reduction of 200 MWe due to. low system demand. At.2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br />, on

. September 5, the unit began ' decreasing load at 100. HWe/ hour.

On September 6,Jat 0014 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />, the main Turbine Generator was taken off line, and' at 00421 hours the' unit was manually scrammed by placing the

+

mode switch to SHUTDOWN to' begin.the-Cycle Six Refueling.0utage.

- B.-

Unit Two September 1-10: Unit Two started the month holding' load at:

approximately 745 MWe.. The-unit.is.still'derated 40'MWe due to high-vibration in the 2A' Recirculation. Pump Motor-Generator Set. On September 4, the unit ~ dropped load to 700 MWe for weekly Turbine tests.

i On two occasions, load was ' dropped due to Iow system demand at the request of the Load Dispatcher.

September 11-23: On September 11, at Midnight, Unit Tvnt reduced. load to 400 MWe for control rod pattern' adjustment, q 0n September 16, the i.

Ioad was dropped to 700 MWe for maintenance on the 2E Condensate i'

Demineralizer. The unit otherwise. maintained an average load of approximately-760 MWe.

i September 24-30: At 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br />, on September.24, the tx11t began decreasing load to 430 MWe fo'r maintenance on the 2A Recirculation -

Pump Motor-Generator Set in an attempt to resolve the high vibration

~

p roblem..The unit increased load to 746 MWe.by September 26 and l

to 783 MWe on September'27, where it was held through the end of the' month.

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E.

A j-b._.,,_---_.-.-,.._--

-~.,.,_ _ __ -. _. _-

III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS,- AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications' There were no Amendments to Facility License or Technical Specifications for the reporting period.

B.

Facility or Procedure Changes Requiring NRC Approval -

There were no Facility or Procedure Changes Requiring NRC Approval for the reporting period.

C.

Tests and Experiments Requiring NRC Approval There were no Tests and Experiements requiring NRC approval for the reporting period.

D.

Corrective Maintenance of Safety Relate i Equipment The following represents a tabular summary of the safety related maintenance performed on'~ Unit,0ne and Unit Two

- during the reporting period. The hea61ngs in Jcated in this summary include: Work Request Numbers, mER Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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UNIT ONE MAINTENANCE

SUMMARY

~

CAUSE RESULTS & EFFECTS W.R.

LER-OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q17385 SJAE Suction Valve The solenoid valve The valve operated The solenoid valve A0-1-5401-B Internals were worn.

sluggishly, was replaced.

Q20874 82-21/03L ID RHR Service A broken pipe nipple Water was leaking Replaced the nipple Pump l-1001-65D was found on the low from the nipple.

on the pump vent pressure pump casing line.

vent line.

Q20960 1/2A SBGT System The filters were The heater output Changed filters.

Prefilter

-suspected of causing differential 1/2A-7510 a flow channeling temperature varied, problem.

4 9

=

UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & E' r ECTS

~

W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q20488 Core Spray A leaky gasket was Limitorque valve ~

Replaced the gasket injection Valve found in the valve operator casing is and tested the valve.

1-1402-25A operator. casing.

leaking oil. The valve was still operable.

Q21599 Refuel Bridge Sheared bolts; Left Bridge control Installed right hand (833) causing panel panel on mast panel console; wrote Q21603

damage, bolts were sheared to repair console off when mast dropped, and install on Unit 2 crane.

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IV.

LICENSEE EVENT REPOP.TS The following is a tabular summary 'of. all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period. pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications.

UNI T ONE Licensee Event Number Date Title of Occurrence -

82-20/03L 9-20 & 21-82 RCIC Area High Temperature Switches (3) 82-25/03L-9-7-82 1/2A Standby Gas Treatment Heater Tripped 82-26/03L 9-6-82 Local Leak Rate' Tests 82-27/03L 9-2-82 Administrative Controls-ERV 82-28/03L 7-19-82 Reactor Pressure Setpoint Drift 82-29/01T 9-16-82 Reactor Water Clean-up t.

Line Cracks 82-30/03L 9-5-82 ID RHR Service Water Pump inoperable - Burned Packing I

UNIT TWO l

i There were no Licensee Event Reports for the reporting period.

yy

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-V.

DATA ' TABUIATIONS i

The following' data tabulations are presented in this report:

A.

Operating Data Report i

B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions 4

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1 LOPERATING DATA ~ REPORT-

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DOCKET-NO.

50-254

UNIT ONE -

_ 2

_.m

_. = _

DATE0ctober 4.1982

- _ _ _ _ _ ~..

COMPLETED BYRando11='D Buss

.. - _. _ _. _ u. TELEPHONE 309-654-2241x181

.m.

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0PERATING STATUS 0 0 0 0 -0 9 0182 y-_.-_

L. Rep orting f period 2400 0.93082 Gross hours in reporting' periods

'720-

" i.-Currently;outhorized: power-level-(MWt):22511-Max. Depend-capacity-2 (MWe-Net): 769* Design electrical rating -(MWe-Net): 789 i 3.-Power 71e vel-t o-which.cestrit ted (if - any ) (MWe-Ne t ) i nNA --

. - = -. _

restriction (if-ony):"

~4.

Reasons - f orc

.This-Month Yr.to Date Cunulative

-5.-Numbar of--hours-reactor-was critical

_i20.7 -

5833.i'_

74932.2 A r

6. Reactor: reserve shutdown" hours-0.0' 0.0 3421.9. ;-

7. Hours generator on line 120.2 5777.1

-71908.6 p- - - 8.- Un i t-- rese r ve-sh u td own-h o ur s.:

"-0.0

-- - 0. 0.

=909.2 -

9. Gross thernal energy generated (MWH).

142142 iin00483.

146058842'-

.=...,-....-:.-

~ _ :_-:- _._.

=

~-.

10. Gross electrical energy generated (MWH) 43586 3533210 47062143 Li - Ne t-elec t r ical-energy-generated (MWH)--- - 22527-- -3207872-

.43791956 m

12.. Reactor service factor-

-16.8

'89.0 82.3

.__m

_ n ;_._.

J.

13. Reactor avo11ob111ty factor 16.8 89.0 86.0.

--14.-.Un i t--ser a lce - f ac t or 16.7 -

- 88. 2 --

7 84._ _

'15.-Unitiovo11ob111ty. factor

-16'7 88.2' 79.9s

~ _ _ _ _ _..

_ ~._

16. Unit cop'ocity factor'-(Using MDC) 4.1 63.7 62.5

-17.2-Un it 2 cop ac i t y-f ac t o r (Using -- De s. HWe )- --- = 4. 0 - - - - - 6 2.1 ---

6 0, 9--

0.0 1.5

6~7

~18. : Unit - f orced. o u t.oge rat e

~

r.__-__._.

19. Shutdowns scheduled-over next 6 months (Type,Date,and Duration of each):

20. If...sh u t d own-atz e nd...of-rep or.t-p eriod,ast inat ed dat e o f._ s tar t up

___?_________ _.,

$The 100 not be lower then 769 Ilie dering perleds of high emblent tenseretere die

.-te the thernal perfernance ef-the sprey cenel L H

i SWIDFFICIAL CSFAllY IAREERS ARE USED Ill THIS REPRT

_m-OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATE0ctober 4 1982 CbMPLETED BYRandall D Bthss

---. TELEPHONE 309-654-2241x181- _ -

OPERATING STATUS 0000 090182 - -

L. Repc.' ting period 2400 093082 Groes hours in reporting period 720 2e Currently authorized-power level-(MWt) 2511-Max. Depend. capacity _

(N'Je-Net): 769* Design electrical rating (MWe-Net): 789

-3.

Power--le vel -t o which restric ted(if-any )(MWe-Ne t ) :. NA -

4.

Reasons for restriction (if any):

This Month Yr.to Date Cunulative-

--5. Number of ho urs-reac t or - was-critico.'. - -

720.0~

5391.0 _..

70242.8__._

6.

Reactor reserve shutdown hours 0.0 0.0 2985.8

.~.

7.

Hours generator on line 720.0 5349.9 67591.1

8. Unit reser ve-shu td own h o urs.- - --- - - -

0,0.-_

0. 0_ -

702.9 _--

9. Gross thernal energy generated (MWH) 165830i 12198756 140085839

10. Gross electrical energy generated (MWH) 526044 3880193 4'4586433

- ii.--Net elec trical-energy-generated (HWH)-- -

-502253

-3695782~

41820366_._

12. Reactor service factor 100.0 82.3 77.9

13. Reactor avo11ob111ty factor 100.0_

82.3 81.2

14. Unit-service factor 100.0 81.7 _

7 5. 0 -. __.

15. Unit avo11obillsy factor 100.0 81,7 75.7 L6. Unit capacity factor (Using MDC) 90.7 73.4 60.3

- - t7. Unit capacity factor-(Using-Des.MWe)-

88.4 71.5-

--- - 58. 8 -

10. Unit forced outage rate 0.0 17.6 9.2

19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each):

- - 20.-. If-shu t d own-at end~of-repart-period,estinated date of startup

___"_A

$The MDC nay be lower than 769 MWe diring perleds of high ambient temperatsre die

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~ts.t!.e thernal perfernence ef the spray canal.

$UN0FFICIAL COMPANY NUMERS ARE USEP IN THIS REPORT m

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APPENDIX D AVERAGE DAILY UNIT POWER LEVEL

[

l DOCKET NO.

50-254 UNIT ONE DATE0ctober 4-1982 Cul1PLETED BYR_pndr211 D Buss TELEPHONE 309-654-2241xi8i

-HONTH-September 1982---

h DAY. AVERAGE DAILY POWER LEVEL' DAY AVERAGE DAILY POWER LEVEL

.(MWe-Net)-

- (MWe-Ne t )

1.

331.4.

17.

-31.7

_ _ -_~.._ _. __ ~._..

2.

344.5 18.

-29.6

--3.

321.4

- 19.

-27.5~

4.

305.8 20.

-23.0 S.

267.0 21.

-24.3 6.-

-33.6

22..

-22.5-7.

-31.6 23.

-10.0 8.

-29.3 24.

-20.0 9.

-29.0-

- 25. ---

-15.i-10.

-29.5 26.

-17.7 ti.

-29.5 27.

-18.5 12.

-30.2

-28.

-17.3 6.3.

-29.9 29.

-19.6 14.

-32.7 30.

-21.6 15.-

-29.3 16.

-28.6 INSTRUCTIONS On this forn, list the average daily snit powr level in IWe-Net for each day in the reporting nanth Conpute to the startst 6Aelt negawatt.

These flgeres will be ssed to plot a graph for each reporting month.' Hete that when no inen denendable copocits is

~

used for the net electrical rating of the snit there ney be occasions when the dolly coerege power level excetes the 1H111ne (or the restricted pwr.r level line).,In such cases,the neerage daily enit power estpst sheet should be

_ _ festnoted to erphin the apparut oaenoly

t AVERAGE DAILY UNIT POWER LEVEL.

. ' APPENDIX B

.:.- -- +.--

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DOCKET NO.

50-265 UNIT TWO

...a D ATE 0c t ob e r-4 -19821------

TELEPHONE 309-654-2241xi81

--MbHTH - -Seo tember J19 8 2 - - - -- -- " -

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--~

DAY ~ AVERAGE DAILY POWER LEVEL DAY AVER AGE-DAILY POWER' LEVEL ~

- uu-. ~ --

-( MWe -Ne t )

r

---_ =-~--..a-n=_. ( HWe -Ne t )- -

1.

701.9 17, 716.7.

711.5-

?2.

709.0

.18. -

_ _. _.- _ 3, _ __ -... __ ; _ _ 7 19, 3 _.

_.___ _ __a_19, _ _ _ _. - - - 718. 51-- --- -

4.

711.0 20.

725.5

-5.

721.8

'21.

735.7 4

u

--.--720.6 - -

=

-6.

171'i. 51-

"- -- -- ~ 2 2. y 7.-

709.9

~23.

728.5-

._...~.. _ ____._ _ _ _ _

..___.m.__,_.

8.

637.i

' 24. -

725.8-

--- --25..

. = o 56i.3-_

.. _.. p. -

--728.31

=-

2-10.

-697.7 26' 697.5

_.. _ _ _. _., _ _ ~ _ -. _ _., __

. ii.

492.3

' 27.

728.7

. _ Lia,_

592.9, 28 e

'729.5' 13.

683.5 29.

741.4

'i4.

698.9 30.-

750.0

- 15. - -

- - 714, i - ---

706.8

-_' i 6.-

INSTRUCTIONS-neerest uhele, list the enrege delly snit power leul in Illit-liet for each day in the reporting nonth.Conpete to (ki this forn ne tt..

~~"These figeres vi 1 he used te plet a graph for each reporting nenth; liete that uhen mIinen dependeble copecitv-is ' -

- ~ -

esed for the ut electrical rating of the snit there ney be eccetions when the delly everage peuer leul exceeds the

- iH1 line (or the restricted power leul line),.In such cows,the enregt delly enit pesar setpet sheet should be

_,-_feetnote_d_.to__ explain the apparent onenely

._..___-.m___

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ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.

050-254 August 1982.

UNIT NAME Quad-Cities Unit I COMPLETED BY R. Buss, ext. 131 DATE October 4, 182 REPORT HONTH SEPTEftBER 1932 TELEPHONE 309-654-2241

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LICENSEE m@

O H w DURATION EVENT gu o

u NO.

DATE (Il0URS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS ca 32-00 020901 S

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 02-81 820903 S

0.0 F

5 EA ZZZZZZ 02-82 820904 S

0.0 F

5 EA ZZZZZZ 02-83 820905 S

0.0 F

5 EA ZZZZZZ 82-34 G20905 S

0.0 11 5

ZZ ZZZZZZ Load reduced in preparation of End of Lycle Refuel Outage 32-85 820906 S

599.8 C

2 RC FUELXX Unit shutdown for End of Cycle Six Refueling Outage APPROVED AUG 1 G 1982 (final) ygggg

M M

M F'"*1 M

M M

M M

M M

M M

P"P'1 t"""1 M

M ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.

050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY R. Buss, ext. 181 DATE October 4, 1982 REPORT HONTH SEPTEftBER 1982 TELEPilONE 309-654-2241 N

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LICENSEE m@

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DURATION EVENT gu o

FO.

DATE (HOURS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS ct 82-67 820904 S

0.0 B

5 IIA XXXXXX Reduced load to perform weekly Turbine

~

tests 82-68 820905 S

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand J?-69 820908 S

0.0 F

5 EA ZZZZZZ 82-70 820911 F

0.0 B

5 RB C0tlROD

' Reduced load to adj ust control rod pattern 82-71 820916 F

0.0 B

5 WC DEttifiX Reduced load due to Condensate Demineralizer problems 82-72 820924 F

0.0 B

5 CB ttECFUll Load reduced for maintenance on the 2A Recirculation P' ump flotor-Generator Set APPROVED AUG 101982 (final) ygg3g

VI.. UNIQUE REPORTING REQUIREMENTS The' following items are included in -this report based on prior commitnents to the commission:

14.

MAIN STEAM RELIEF VALVE OPERATIONS ReIIef valve operations' during the' reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting'in its actuation.

VALVES NO. & TYPE PLANT DESCRIPTION Unit Date ACTUATED ACTUATIONS CONDITIONS OF EVENTS 1

9-06-82 1-203-3A 1 Manual RX PRESS Surveillance 1-203-3B 1 Manual 1002

'T.S. 4.5.D.1.b-1-203-3C 1 Hanual 1-203-3D 1 Manual 1-203-3E 1 Manual B.

CONTROL R0D DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There were no Control Rod Drive Scram Timing Data for the reporting period.

e

t VII. REFUELING INFORMATION The following information about future. reloads at Quad-Cities

' Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E. O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion-Station--NRC Request for Refueling Information",

dated January 18, 1978.

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QTP 300-532

{

Revision 1 QUAD-CITIES REFUELING March 1978 4

INFORMATION REQUEST u'~

1.

Unit:

1 Reload:

6 Cycle:

7 m

2.

Scheduled date for next refueling shutdown:

Sept 12, 1982 u

3 Scheduled date for restart following refueling:

Dec 4, 1982 4.

Will refueling or resumption of operation thereafter require a ter.hnical specification change or other license amendment:

7 YES 5.

Scheduled date(s) for submitting proposed IIcensing _ action and supporting F

Information:

' JULY 26, 1982 L

6.

Important licensing considerations associated with refueling, e.g., new or

~

' different fuel design or supplier, unreviewed design or performance analysis a[

methods, significant changes in fuel design, new operating procedures:

?

'litPLEltENTATION OF TH'E ODYN TRANSIENT ANALYSIS CODE AND RESULTS (MCPR SCRAM TlHE DEPENDENCE) 1 T

.f 9--

a

=

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The number of fuel assemblies.

a.

Number of assemblies in core:

224 new/724 total 4

after the i

b.

Number of assemblies in spent fuel pool: outage-1940 g

8.

The present licensed spent fuel pool storage capacity and the size of any Increase in IIcensed storage capacity that has been requested or is planned

[

h in number of fuel assemblies:

1:

P a.

Licensed storage capacity for spent fuel:

2920 f

b.

Planned increase in licensed storage:

4636 new/7556 total l

9.

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

H-LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/34 A' ' P P R O V E D h

LOSS OF RELOAD CORE. DISCHARGE CAPABILITY - 2/86 y_ APR 2.01978 Q.C.O.S.R.

I.s

_,.. _ _ _ _.., - - -. _ ~ -

, _ _ _ _ - ~ - - - _ - - - - - -

l, 2

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QTP 300-S32 Revision 1 L,

QUAD-CITIES REFUELING March 1978 2

INFORMATION REQUEST l ~ ~ ~

1.

Unit:

2 Reload:

6 Cycle:

7 V

n 2.

Scheduled date for next refueling shutdown:

Feb 27, 1983 b

i l

3 Scheduled date for restart following refueling:

April 23, 1983 n

l :

4.

Will refueling or resumption of operation thereafter require a technical specification change or other IIcense amendment:

19 N0 d

(

5 Scheduled date(s) for submitting proposed !! censing. action and supporting I

Information:

~ NONE

["

6.

Important licensing considerations associated with refusiing, e.g., new or

' different fuel design or supplier, unreviewed design or performance analysis

./

methods, significant changes in fuel design, new operating procedures:

NONE c

7-W 7

The number of fuel assemblies.

a.

Number of assemblies in core:

192 new/724 total l

b.

Number of assemblies in spent fuel pool: outage 2132 r-b 8.

The present !! censed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in num'er of fuel assemblies:

o a.

Licensed storage capacity for spent fuel:

2920 l

b.

Planned increase in licensed storage:

4636 new/7556 total

^

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

^

LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/84 WppROVED V

LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 APR 2 01978 Q.C.O.S.R.

I;

f ee VIII, GLOSSARY The following abbreviations which may have been used in the Monthly-Report, are defined below:

Atmospheric Containment Atmospheric Dilution / Containment ACAD/ CAM Atmospheric Monitoring American National Standards Institute ANSI Average Power Range Monitor APRM ATWS Anticipated Transient Without Scram Boiling Water Reactor BWR-Control Rod Drive CRD

-EHC Electro-Hydraulic Control System Baergency Operations Facility EOF Generating Stations Emergency Plan GS EP High-Ef ficiency Particulate Filter HEPA HPCI High Pressure Coolant Injection System High Radiation Sampling System HRSS Integrated Primary Containment Leak Rate Test IPCLRT Intermediate Range Monitor IRM Inservice Inspection ISI LER-Licensee Event Report Local Leak Rate Test LLRT Low Pressure Coolant Injection Mode of RHRS LPCI-Local Power Range Monitor LPRM Maximum Average Planar Linear Heat Generation Rate MAPLHGR Minimum Critical Power Ratio MCPR Maximum Fraction Limiting Critical Power Ratic MFLCPR.

Maximum Permissible Concentration l

MFC Main Steam Isolation Valve MSIV National Institute for occupational Safety and Health NIOSH Primary Containment Isolation l-PCI PCIOMR

- ' Preconditioning Interim,0perating Management Recommendations RBCCW Reactor Building Closed Cooling Water System-

~

Rod Block Monitor RBM Reactor Core Isolation Cooling System RCIC Residual-Heat Removal System RHRS-Reactor Protection System RPS RWM ~

Rod Worth Minimizer Standby Gas Treatment System SBCES-Standby Liquid Control SBLC Shutdown Cooling Mode of RHRS -

SDC Scram Discharge Volume

-SDV Source Range Monitor SRM Turbine Building' Closed Cooling Water System TBCCW Traveling Incore Probe TIP Technical Support Center TSC

?

l l

-