ML20044C925

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Monthly Operating Repts for Apr 1993 for Quad-Cities Nuclear Station Units 1 & 2.W/930503 Ltr
ML20044C925
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 04/30/1993
From: Michael Benson, Walsh R
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RJW-93-15, NUDOCS 9305140091
Download: ML20044C925 (24)
v • d • e


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O-Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Corcova, Illinois 61242 Telephone 309/654-2241 RJW-93-15 May 3, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 l

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC Docket Nos. 50-254 and 50-265 l

l Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of April 1993.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION Robert J. Walsh Tech Staff Supervisor RJW/MB/dak Enclosure cc: A. B. Davis, 2egional Administrator T. Taylor, Senior Resident Inspector r

TECHOPFNRCMONTHLY.RPT l j/

93o514oo91 93o43o .nnn4 I PDR ADOCK 0500o254 GUUU4 v R PDR c_ _ _ _ _ _ - _ - _ _

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT . .f APRIL 1993 1

1 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 TECHOP3WRC.MONT)(LY.RPT

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l TABLE OF CONTENTS .j l

I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant or Procedure Changes, Tests, Experiments, and Safety Related i

Faintenance l

A. Amendments to Pacility 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 i

IV. Licensee Event Reports V. Data Tabulations i

A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary TECHOP3WRCMONDILY.Rrf -

I. 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 Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license numbers 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 One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for unit Two.

This report was compiled by Matt Benson and Debra Kelley, telephone number 309-654-2241, extensions 2995 and 2240.

TEcHOPISRC, MON"mLY.RW

l II.

SUMMARY

OF OPERATING EXPERIENCE l l

l A. p_ nit One Quad Cities Unit One began the month at full power and remained on line f

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for the entire month of April 1993. Numerous load drops were performed l on orders from bulk power operations. None of these load drops caused the daily average net power generation to drop below 20% of full load.

3 B. Unit Two Quad Cities Unit Two was in its twelfth refuel outage during the entire month of April 1993. The unit entered the outage on March 6, 1993 and is scheduled to start up again on May 28, 1993.

r TECHOP3 NRC'. MONTHLY.RIT

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III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS,  !

AND SAFETY RELATED MAINTENANCE j A. Amendments to Facility License or Technical Specifications  !

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

i B. Facility or Procedure Chances Recuirino NRC Acoroval t There were no Facility or Procedure changes requiring NRC approval for i the reporting period.  !

' Revision O.L. to the Offsite Dose Calculation Manual (ODCM) was Onsite  ;

Reviewed and accepted on April 14, 1993. The revision changed the name of environmental monitoring location Q-06 from "Hanson's Boat Landing" to "Fairbanks" in table 11-1 of the ODCM. The change ef fected only ODCM ,

pages 11-1 and 11-1 and is documented in Onsite Review Report Number 93-

21.  ;

i C. Tests and Experiments Recuirina NRC ADDroval  !

There were no Tests or Experiments requiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Esuicment i

The following represents a tabular summary of the major safety related maintenance performed on Units one and Two during the reporting period.

2 This summary includes the following: Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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TECHOP3.NPc. MONTHLY.RFT i

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4 UNIT 1 MAINTENANCE

SUMMARY

WORK REQUEST SYSTEM WORK REQUESTED WORK PERFORMED -

s QO3286 640 Repair door latch on vessel Installed new door latch.

level recorder 1-0640-26.

Q04809 756 Repair LPRM 16-41A. Investigated card and found no problem. Detector determined to be bad. Will be replaced in a future outage.

Q05428 756 Investigate and repair LPRM Ran I/V curve. Readings40-09A spiking problem, stabilized.

Q05499 590 Repair 1AB1 and 1AB2 reserve Tightened loose connections and electric protection replaced capacitors.

assemblies.

Q05774 2400 Repair CAM system radiation Found clutch for red pen recorder 1-2420-A. slipping. Cleaned, adjusted, and calibrated both pens. .

Q05895 2400 Investigate and repair Found both hydrogen and oxygen hydrogen / oxygen analyzer 1- indication would not span.

2446B. Replaced the oxygen reagent gas regulator.

Q06202 7800 Repair auxiliary contacts on Replaced one auxiliary contact l MCC 19-4, cubicle A4. and applied a thin coat of l

grease. Inspected and cleaned both left and right contactors.

Q06350 6700 Repair 4kV breaker 1/2-6700- Sent breaker to General Electric 034. A broken weld was for repair.

found on the striker plate.

Q06453 6600 U-1/2 diesel generator air Found air lines were switched.

start motor failed to crank Re-installed air lines engine. correctly. l

Q06465 1000 Repair 1A RHR service water Found outboard bearing housing primary pump outboard damaged and bearings destroyed.

bearing. High vibrations Machined shaft sleeve and nuts .

. detected. to tolerance, replaced bearings, balanced shaft, and aligned pump to motor.

Q06809 7300 Replace broken screws on Replaced broken screws. '

right side of breaker 1/2-7300-S0B1.

Q98185 7300 Repair bent pin and broken Found one of the secondary terminal strip on 480V tie contacts stuck and the terminal breaker for bus 28 to 29. block chipped off in that area.

Replaced bullet pin and top of terminal block.

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4 UNIT 2 MAINTENANCE

SUMMARY

WORK REQUEST SYSTEM WORK REQUESTED WORK PERFORMED -

Q01060 756 Repair LPRM 16-49B. Failed Determined detector to be bad.

downscale. Will be replace during U2 ,

outage.

Q01670 7800 Replace cracked coil in MCC Replaced coil on motor starter ,

29-1 cubicle A2, standby with a new coil and put a new +

liquid control tank heater. screw in the control transformer  ;

to replace one that was missing.

001846 6600 Repair broken diesel Replaced the 3/4 straight generator turbo oil pump sealtite fittings with 3/4 90 sealtite. degreee sealtite fittings. ,

002035 2300 Repair large leak on HPCI Injece.ed Furmanite. Leakage discharge header inboard reduced 80%. Discontinued stop valve 2-2301-18. injection due to time / load  ;

demands.

QO2501 20 Inspect and repair 2B RHR Found door had a broken latch room watertight door. handle on the torus side. Weld repaired latch handle and reinstalled.

003199 5700 Reverse fan flow on diesel Reversed the motor leads from generator cooling water pump the normal power feed.

room cooler.

Q04016 6700 Replace bulb broken off in Replaced socket.

socket of bus 24 cubicle 14.

Q05924 3900 Replace pump and internals Installed new pump.

for diesel generator cooling water pump 2-3903.

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. I Q06132 1100 Repair heater element on 2A Found heater loose. Reattached standby liquid control pump bracket to heater.

2-1102A. .

.Q06255 7800 Replace overload relay in Replaced relay with a new one.

breaker, MCC 28-1A-1 cubicle Installed old heater in the new C4. relay.

Q06264 4600 Repair service air supply to Cleaned valve internals, drywell check valve 2-4699- installed a new gasket and

47. Failed LLRT. reassembled valve.

Q06602 6600 Replace diesel generator low Replace with new switch and oil temperature switch. calibrated.

Q06769 8300 Repair broken terminal block Removed terminal block from MCC on MCC 2A cubicle F02. 1B cubicle R01 and installed in MCC 2A cubicle F02.

Q06788 6600 Remount diesel generator Remounted current transformer to current transformer. the bracket.

Q06835 7800 Replace spaded lug on MCC Replaced bad lug with a new lug.  ;

28-1A-1 cubicle D4.

007011 902-63 Replace defective lug in the Installed new lug on termin: ',

63C panel. wire #435.

Q82826 5200 Repair diesel generator day Found level switches reversta tank level switch. and improperly set. Removed c switches, rewired, and l

reinstalled them. l Q83863 6700. Repair closed indication Found light socket grounded out.

l light on bus 24-1 cubicle 10 Replaced socket.

j bus tie to bus 14-1.

! 096555 6700 Investigate / repair bus 24 Found mechanical linkage out of cubicle 15 well water pump tolerance. Adjusted travel of

  1. 5 breaker racking screw interlock shaft.

problem.

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Q97359 902-4 Replace broken insulator on Installed new terminal block.

902-4 panel terminal block.

, Q97708 6700 Replace broken secondary Replaced secondary disconnects

. disconnects on bus 23 with new ones.

cubicle 3, 2A circ water Pump.

Q97962 1400 Repair check valve to ECCS Disassembled , cleaned, and fill to 2A core spray. reassembled valve.

Q98921 261 Replace gaskets on EQ Found gaskets missing from ,

junction box 2TB-28. covers. Replaced gaskets and missing screws on all four boxes.

C99318 6700 Repair racking screw shutter Repositioned alignment pins and on bus 23 cubicle 6, 2A reassembled the front cover.

condensate booster pump. Also lubricated the shutter linkage.

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IV. LICENSEE EVENT REPORTS '

l 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 occ2rrence reporting requirements as set forth in sections 6.6.B.1 and ,

6.6.B.2 of the Technical Specifications. l UNIT 1  ;

Licensee Event Report Nu2rber Date Title of Occurr.ence  ;93-005 03-31-93 Control Room Vent Toxic Gas Analyzer  ;

INOP Ammonia Analyzer.

THIS LER WAS DOWNGRADED 4-20-93.93-006 04-20-93 Inadvertent start of the Unit 1 Diesel Generator.

UNIT 2 Licensee Event [

Report Nurber Date Title of Occurence t

93-008 04-02-93 Crack on 2" equalizing 2-0209B-2".93-009 04-08-93 Missed Rx Vent Sample.93-010 04-22-93 1/2 Diesel ' Generator Closed Cooling [

Water Pump failure to start.  ;

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1 V. D___A_ _TA TABULATIONS ,

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The following data tabulations are presented in this report:  ;

A. Operating Data Report B. Average Daily Unit Power Level  !

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C. Unit Shutdowns and Power Reductions ,

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APPENDIX C ,

OPERATING DATA REPORT DOCKET NO. 50-254 i

UNIT One DATE May 1.1993  ;

i COMPLETED BY Matt benson  ;

TELEPHONE (309) 654-2241 f

OPERATING STATUS I h

0000 040193 '

l. REPORTING PERIOD: 2400 043093 GROSS HOURS IN REPORTING PERIOD. 719 f
2. CURRENTLY AUTHORIZED PORTR LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789

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3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY):  ;

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL 719.0 2824.30 145585.20 f I
6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

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7. HOURS GENERATOR ON LINE 719.00 2803.10 141194.70
8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00  %'.20

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9. GROSS THERM AL ENERGY GENERATED (MWH) 1733023.20 6766094.40 304347918.20
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 567095.00 2203881.00 98622971.00
11. NET ELECTRICAL ENERGY GENERATED StWH) 548623.00 21187I8.00 92994230.00
12. REACTOR SERVICE FACTOR 100.00 98.10 78.89
13. REACTOR AVAILABILITY FACTOR 100.00 98.10 80.75
14. UNIT SERVICE FACTOR 100.00 97.36 76.51  ;
15. UNIT AVAILABILITY FACTOR 100.00 97.36 77.01 i
16. UNTT CAPACITY FACTOR (Using MDC) 99.22 95.70 65.53 .

!?. UNTT CAPACITY FACTOR (Using Design MWe) 96.71 93.27 63.87 I

'l8. UNIT FORCED OUTAGE RATE 0.00 2.64 5.76 +

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19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): t t
20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):  ;

i FORECAST ACHIEVED INTTIAL CRITICA1JTY INITIAL ELECTRICTTY ' ,

COMMERCIAL OPERATION 1.169 i TIIHOP3WRCMON7HLY.RPT

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OPERATING DATA REPORT DOCKET NO. 50-265 UNIT Two  !

DATE May 1,1993 i COMPLETFD BY Matt Bennon 5 TELEPHONE (3091 654-2241 -)

OPERATING STATUS _j 0000 040193

1. REPORTING PERIOD: 2400 043093 GROSS HOURS IN REPORTING PalOD: 719 .
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 71V [

DESIGN ELECTRICAL RATING (MWe-NET): 789  !

3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWeNet): N/A
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4. REASONS FOR RESTR]CTION (IF ANY): i I

THIS MONTH YR TO DATE CUMULATIVE {

5. NUMBER OF HOURS REACTOR WAS CRITICAL 0.00 1391.60 140566.85 T

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6. REACTOR RESERVE SHUTDOWN HOURS 0.00 010 2985.80
7. HOURS GENERATOR ON LINE 0.00 1356.80 136998.25 j
8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90 ,
9. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 3310351.20 295973760.40  ;
10. GROSS ELECTRICAL ENERGY GENERATED (MWH1 0.00 1084961.00 95110222.00 ,
11. NET ELFITR] CAL ENERGY GENERATED (MWH; 0.00 1033782.00 - 90064525.00 ,
12. REACTOR SERVICE FACTOR 0.00 4834 76.82

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13. REACTOR AVAILABILITY FACTOR 0.00 48.34 78.46 l
14. UNIT SERVICE FACTOR 0.00 47.13 74.87 i
15. UNIT AVAILABILITY FACTOR 0.00 47.13 75.26
16. UNIT CAPACITY FACTOR (Using MDC) 0.00 46.69 64.01 l f
17. UNTT CAPACITY FACTOR (Using Design MWr) 0 110 45.51 62.39 i
18. UNTT FORCED OUTAGE RATE 0.00 13.05 7.84
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):  ;

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20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 05-29-93 l
21. UNTTS IN TEST STATUS (PR]OR TO COMMERCIAL OPERATION):  ;

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INTTIAL CRIT]CALITY t INITIAL LIIETv.lCTTY l i

COMME ' 'AL OPERATION j 1.m  ;

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i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL i

r DOCKET NO 50-254 UN1T One  !

DATE May 1. 1993 f COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH April 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

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1. 789 17. 795
2. 790 18. 766 L
3. 790 19. 741 [

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4. 792 20. 791 ft
5. 792 21. 749 f

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6. 793 22, 738 -)

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7. 790 23. 720 -l

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8. 742 24. 746 l 1

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9. 782 25. 755
10. 708 26. 750 .t
11. 761 27. 741 ~ f
12. 767 2 8 .- 735 -t i
13. 785 29. 750 .l
14. 770- 30, 704 <j i

- 15. 767 31. ;i i

16. 780 I 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 Note that when - maximum '-

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be used.tc plot a graph ; for each reporting month.

dependable capacity is used for the net electrical rating of the uniti 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.

1.16-8 f TEOf0P3&RcMONELY.RPT 'l  !

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AVERAGE DAILY UNIT POWER LEVEL {

l DOCITT NO 50-265 l I

UNIT Two DATE May 1. 1993 }

COMPLETED BY Matt Benson (

TELEPHONE (309) 654-2241 '!

MONTH ADril 1993 i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j (MWe-Net) (MWe-Net) i i

1. -8 17. - -8  !

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2. -8 18. -8 j
3. -8 19. -8 l I

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4. -8 20. -8 .i t
5. -8 21. -8  !

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6. -8 22. -8 l

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7. -8 23. -8 l l
8. -8 24. -8 ,

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9. -8 25. -8 i
10. -8 26. -8 l
11. -8 27. -8  !
12. -8 28. -8  ;
13. -8 29. -8 I
14. -8 30; -;
15. 31.
16. -8' 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 _l be used to plot a graph for each reporting month. Note that- when maximum 1 dependable capacity is used for the net electrical rating of the unit, there may l be occasions when the daily average power level exceeds.the 100% line (or the i restricted power level line) . In such cases, the average daily unit power _ output -

-sheet should be-footnoted to explain the apparent anomaly.

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i, VI. UNIOUE REPORTING REOUIREPENTS . i, The following items are included in this report based on prior commitments to the  !

commission-  !

A. Main Steam Relief Valve Operations There were no Main Steam Relief Valve Operations for the reporting period.  ;

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B. Control Rod Drive 6 cram Timino Data for Units One and Two ,

There was no Control Rod Drive scram timing data for Units One and Two for ,

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3 VII. REFUELING INFORMATION f i

I The following information about future reloads at Quad-Cities Station was  !

.l 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 j for Refueling Information", dated Januat'f 18, 1978.  !

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QTP 300-532-  !

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Revision 2  !

QUAD CITIES REFUELING ' October 1989  !

INFORMATION REQUEST I

1. Unit: Q1 Reload: 12 I3 I Cycle: 1
2. Scheduled date for next refueling shutdown: 3-14-94
3. Scheduled date for restart following refueling: 6-13-94

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4.  !

Will refueling or resumption of operation thereafter require a Technical  !

Specification change or other license amendment: i NOT As YET DETERMINED I

5. Scheduled date(s) for submitting proposed licensing action and I supporting information.  ;

l NOT AS YET DETERMINED ,

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6.  !

Important licensing considerations associated with refueling, e.g., new l' or different fuel design or supplier, unreviewed design or performance  :

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

NONE AT PRESENT TIME.

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7. The number of fuel assemblies. i
a. Number of assemblies in core: 724
b. Number of assemblies in spent fuel pool: 1557
8. The present licensed spent fuel pool storage-capacity and the size of i

any. increase in licensed storage capacity that has been requested or is  !

planned in number of fuel assemblies: -!

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a. Licensed storage capacity for-spent fuel: 3657  !
b. Planned increase in licensed storage:- 0  ;
9. l The projected date of.the last refueling that can be discharged to the j spent fuel pool assuming the present licensed capacity: 2009- j i

i APPROVED (final) 14/0395t DCT 3 01989 i 1

Q.C.O.S.R. '

1 QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: 02 12 Reload: Cycle: 12
2. Scheduled date for next refueling shutdown: 03/06/93
3. i Scheduled date for restart following refueling: 05/29/93 4.

Will refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment:

NO i

S.

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

NO SUEMITTALS REQUIRED.

e 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 AT 12RECENT TIME.

7. The number of fLel assemolies.
a. Number of assemblies in core: 724
b. Number of assemblies in spent fuel pool: 2583
8. i The present licensed spent fuel pool storage capacity and the size of '

any increase in licensed storage capacity that hts been requested or is planned in number of fuel assemblies:  ;

a. Licensed storage capacity for spent fuel: 3897
b. Planned increase in licensed storage: 0 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2009 i

i APPROVED 14/0395t ' ' " l_l ) OCT 3 01989 C).C.O.S.R.  !

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I VIII. GLOSSARY  ;

I The fol.owing abbreviations which may have been used in the Monthly Report, are '

defined below: .

ACAD/ CAM - Atmospheric Containment Atmospheric I Dilution / Containment Atmospheric Monitoring ANSI - American National Standards Institute APRM - Average oower Range Monitor ATWS - Anticipated Transient Without Scram .!

BWR - Boiling Water Reactor l

CRD - Control Rod Drive l EHC - Electro-Hydraulic Control System l EOF - Emergency Operations Facility i GSEP - Generating Stations Emergency Plan  ;

.HEPA - High-Efficiency Particulate Filter ]

HPCI - High Pressure Coolant Injection System  !

HRSS - High Radiation Sampling System l IPCLRT - Integrated Primary Containment Leak Rate Test j IRM - Intermediate Range Monitor  :

ISI LER Inservice Inspection Licensee Event Report j

MAPLHGR - Maximum Average Planar Linear Heat Generation Rate  !

MCPR - Minimum Critical Power Ratio i MFLCPR - Maximum Fraction Limiting Critical Power Ratio {

MPC - Maximum Permissible Concentration i MSIV - Main Steam Isolation Valve  ;

NIOSH  !

- National Institute for Occupational Safety.and Health PCI - Primary Containment Isolation l PCIOMR - Praconditioning Interim Operating Management Recommendations j RBCCW - Reactor Building Closed Cooling Water System  !

RBM - Rod Block Monitor -I RCIC - Reactor Core Isolation Cooling System 5 RHRS - Residual Heat Removal System .i RPS - Reactor Protection System RWM - Rod W:.ath Minimizer SBGTS - Standby Gas Treatment System ,

SBLC - Standby Liquid Control l SDC - Shutdown. Cooling Mode of-RHRS  !

SDV - Scram Discharge Volume .i SRM - Source Range Monitor l

- Turbine' Building Closed Cooling Water System TBCCW .l TIP - Traversing Incore Probe -!

TSC - Technical Support Center I

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_l ncMoP3 NRcMONTHLY.RPT

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