ML20042A367

Monthly Operating Repts for Dec 1981

ML20042A367
Person / Time
Site:	Quad Cities
Issue date:	01/04/1982
From:	Weinfurter E COMMONWEALTH EDISON CO.
To:
Shared Package
ML20042A362	List: ML20042A361 ML20042A367
References
NUDOCS 8203230365
Download: ML20042A367 (26)

Text

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT DECEMBER 1981 .

COMMONWEALTH EDISON COMPANY .;

AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 1

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TABLE OF CONTENTS I. Introduction ,

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II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant of Procedure Changes, Tests, Experiments, 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 a VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossa ry e <

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r I e 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 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 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 1 and 2 respectively were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973 for Unit I and March 10, 1973 for Unit 2.

This report was compiled by Becky Brown and Robert Tubbs, telephone number 309-654-2241, extensions 127 and 174.

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1 II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One .

December 1-5: Unit One started the month of December holding load at ~

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815 MWe. On December 5 the Unit started dropping load'at 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> at 100 MWe/ hour.

December 6-11: On December 6, after reversing condenser flow and performing weekly Turbine tests, load was increased at 5 MWe/ hour to 815 MWe.

December 12-18: On December 12 Unit load was dropped at 200 MWe/ hour to 200 MWe to perform control rod hot scram timing. By 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, a 100 MWe/ hour load increase began to 500 MWe, then at 5 MWe/ hour until 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> on December 13 when the Unit picked up load at 8 MWe/ hour tc 813 MWe by 0840 December 14.

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December 19-26: At 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br /> the "A" Feedwater regulating valve went full open causing a Reactor water high level. Load was dropped to 720 MWe and the "B" Feedwater regulating valve was closed. Normal Reactor water level was restored by 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />. On December 20 load was --

decreased to 600 MWe to perform the weekly Turbine tests. At 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> '

a load increase was initiated at varying preconditioning rates. On a December 21 the load increase was stopped to allow for Xenon buildup.

Further load increases commenced until 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on December 21 at which time a maximum obtainable load of 820 MWe was achieved.

December 27-31: On December 27 load was dropped to 700 MWe to perform weekly Turbine tests. Load was increased to 822 MWe which was held to the end of December.

B. Unit Two December 1-25: The End of Cycle.Five Refueling Outage was still in p rog res s.

December 26-27: On December 26 the Reactor went critical at 0602 hours0.00697 days <br />0.167 hours <br />9.953704e-4 weeks <br />2.29061e-4 months <br /> and the generator was synchronized at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> with an output of 106 MWe. At 2331 hours0.027 days <br />0.648 hours <br />0.00385 weeks <br />8.869455e-4 months <br /> the Turbine was manually tripped due to high vibration. On December 27 the Unit was synchronized to the system at 1325 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.041625e-4 months <br /> with an output of 144 MWe. Load was increased at 50 MWe/ hour to 350 MWe.

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December 28-31: At 1249 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.752445e-4 months <br /> the generator was taken off line to perform the Turbine overspeed test. The Unit was then back on line by 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br />. The Unit dropped load at 50 MWe/ hour at 1535 hours0.0178 days <br />0.426 hours <br />0.00254 weeks <br />5.840675e-4 months <br /> and the Turbine was manually tripped to repair a steam leak on a sample tap. At 1650 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.27825e-4 months <br /> the Unit was synchronized to the system at 200 MWe and increased load at 100 MWe/ hour to 370 MWe. The 2B ^

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Recirculation MG Set was not operable, so the Unit was limited to 375 MWe through the end of December.

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III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Speci ficat ions There were no amendments to Facility License or Technical Specifications for the reporting period.

B. Facility or Proced 's 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 Experiments requiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the safety related maintenance performed on Unit One and Unit Two .

during the reporting period. The headings indicated in this summary include: Work Request Numbers, LER Numbers, .

Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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i UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN T0 flUMBER tlUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q13111 RCIC Trip Throttle The valve linkage was The valve could not be Cleaned trip valve Valve dirty & corroded. tripped remotely, linkage.

Ql5529 81-22/03L 1/2 Diesel Genera- Engine bearing #11 The Diesel was declared Replaced all bottom tor (1/2-6601) failed af ter being i nope rabl e . The Unit 2 shells and #11 upper contaminated with Diesel was crosstied to shell. Also, the diesel fuel oil, take the place of the 1/2 main bearing cap was Diesel Generator, re worked.

Ql5634 ESS fi-G Set The AC & DC motors The ESS bus was being Replaced broken (I-8100) would not operate. supplied by the reserve connections in the feed. overload trip circuit.

Q15951 ESS it-G Set AC drive motor will The ESS bus was being Adjusted f requency--

AC Motor Drive not stay on. The supplied by the reserve was set too low, frequency was set feed.

too low. -

Q15959 1C RHR Pump The valve 1imit The valve does not drive The 1imit switch cam Valve (1-1001-7C) switch was out of full open. RilR System was adjusted, adj us tmen t . was still operable.

Q14827 South Side SJAE Worn teflon rings The valve will not close Replaced teflon rings Suction Valve on the operator without assistance. & test stroked the (1-5401-B) shaft seals. valve.

Ql6075 1/2 Diesel Genera- Heater elements The heater did not work. Replaced the heater.

tor Emers ion were burned open. The Diesel was still Heater (1/2-6601) operable.

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UNIT Or!E MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q14826 South SJAE Suction Worn solenoid valve. The isolation function Replaced solenoid Valve (1-5401-A) was still operable. valve & tested valve.

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UlllT TWO HAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBEP. COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q13966 Drywell Sump Worn set screw on isolation function Installed new set isolation Valve limit switch striker was unaf fected. screw on striker arm; (2-2001-4) arm. adjusted limit switch and tested.

Ql5298 Diesel Generator The impeller wear The pump was operable The impeller and wear Cooling Water rings were worn but pump discharge rings were replaced.

Pump (2-3900 beyond tolerances. pressure was decreasing.

Q15596 81-23/03L Off Gas isola- The timer setting Tne Off Gas isolation Adjusted the timer to tion Timer drifted. signal occurred at 90% & locked the (2-2705-23) greater than the required setting down.

15 minutes.

Q15720 -

SDV Drain Valve The valve plug was The valve was leaking Disassembled valve &

(AO-2-302-22) worn. through. replaced plug; re-assembled.

Q15725 SDV Vent Valve The valve plug was The valve was leaking Disassembled valve &

(AO-2-302-21B) worn. through. replaced plug.

Q15726 SDV Vent Valve The valve plug was The valve was leaking Disassembled valve &

(AO-2-302-21A) worn. through. replaced plug.

Ql4795 RHR SDC Valve The stem was worn. Valve is normally closed. Installed new stem &

(M0-2-1001-43C) Valve would not close re-aligned operator.

from Control Room.

Ql5076 RHR Head Spray Sticky field RHRS was operabic. Cleaned,& lubricated Valve (2-1001-60) contactor in the the field contactor

, motor-starter. and adjusted springs.

Q11142 RHR Pump Suction The stem nut in the The valve could not Replaced stem nut;

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Valve (2-1001-7D) motor-operator was easily by cycled. adjusted yoke to

, worn. align with stem.

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l UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q15149 RHR Discharge to Broken limit switch The valve could not Aeplaced the cam shaft Radwaste Valve and cam shaft. be operated; normally and contact block.

(M0-2-1001-20) closed.

Q15390 Reactor Building Air leak found on The vacuum breaker was The solenoid valve was to Torus Vacuum solenoid valve. still operable. overhauled.

Breaker (AO 1601-20A)

Q14525 81-21/03L Main Steam Line Fire stop material The penetrations do Re-foamed four Penetrations was degraded. not contain combustible penetrations.

materials.

Q14694 81-21/03L B Feedwater Flush Penetration boot Secondary containment Replaced boot, re-foamed

. Pene t ra t ion was torn. capability was not installed sleeve, affected.

Q14991 81-21/03L Penetration MK-ll2 The penetration boot Secondary containment Replaced boot; re-foamed.

was torn. capability was not affected.

Q16273 81-26/03L 2A2 24V Battery Plates were Cell failed during Installed new cell.

Call #3 (2-8325)

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deteriorating in battery discharge the cell. test.

Q13777 #3 T;P Ball The valve operation The ball valve was still A new style ball valve Valve (2-730) , was very sluggish. operable, was installed.

Q15389 81-20/03L Drywell Purge The gaskets on the The valve was still Rebuilt the operator Valve (M0 air operator cylinder operable. & replac~ed solenoid

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1601-22) , were worn. valve.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMP 0NEMT MALFUNCTION SAFE OPERATION PREVENT REPETITION Ql5804 81-22/03L HPCI High Temper- Damaged high temper- The swtich appeared to Replaced swtich with ature Switch ature switch during be good prior to testing. new calibrated switch.

(2-2371A) testing.

Q15881 4 KV Switchgear A bent metal wire No af fect. The breaker Repaired wire cover &

23-1 Breaker 10 cover is inter- operated properly prior re positioned wires.

fering with breaker to maintenance.

closure.

Q16063 Reactor Water Broken wire was The break was causing a Repaired broken wire &

Clean up Recirc found in valve battery ground. replaced lug.

Shut-off (2- cable.

1201-5)

Q16332 Motor (2-1001- The motor will not The valve would not Replaced motor with 43C) operate. operate from the Control like.

Room. ,

Q16482 81-26/03L Cell 2A 24/48 VDC Cell plates had Cell failed during Replaced battery cell Battery Cell #4 deteriorated. battery discharge test. #4.

Ql6483 81-26/03L Cell 2A 24/48 VDC Cell plates had Cell failed during Replaced battery cell Battery Cell #6 deteriorated. battery discharge test. #6.

Q16489 RHR Pump Suction The pump stop logic The valve was still The open limit switch Valve (2-1001-7D) was not operating operable, was recalibrated.

properly.

Q12234 RHR Heat Exchanger Quad rims were bad. Valve breaker tripped Replaced the quad rings.

Bypass Valve (MO- while changing position.

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l IV. LICENSEE EVENT REPORTS The following is a tabular summa,ry of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting '

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period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.I. and 6.6.B.2. of the Technical Specifications.

UNIT ONE l

Licensee Event Report Number Date Type of Occurrence 81-23/03L 11-26-81 RCIC Drain Pot Steam l Leak 81-24/03L 12-09-81 Penetration opened

, loss of Secondary Containment UNIT TWO 81-25/03L 12-16-81 Standby Gas Treatment inoperable Design 4 Deficiency 81-26/03L 12-20-81 2A 24/48 VDC Battery Failure s

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V. DATA TABULATIONS i:

The following data. tabulations are presented in this report:

! A. Operating Data Report -

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4 B. . Average Daily Unit Power Level l C. Unit Shutdowns and Power Reductions 1

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OPERATINr c'T M U S 0h00 120101 7 c o L.; eing B e~r': o d : 2400 i23181 Gross bourn in~.'unortinq pa z od : 7'4

2. Current 1v a u t h :, r i z e d tower 1cvel (MWT): 2511 Max, Depend capacity 7674 De sign e l e c t r .i c c 1 r:c t i n g (MWe-Net). 789

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(MWe-Net)

3. Power level to which rettricted(if _any )(MWe- Ne t ) : NA

4. Reasons f or- restriction (if ano): a

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This Month Yr.to Date Cunulative S. !J u nb e r of hcurn reactor was critical _ 744,0 _

8392,8 6909o i ._

6. Ocactor reserve shutdown hours 0.0 0 . 0_ 3421,7 y2

7. Hour _ aencrotor on line . - - _ _ .744.0 . - . . - . .8247.7 66131.5 O. Unit reseruc chutdown h o u r ts . __ 0.0_ 0.0 909.?

9. C r c t, thernc1 u n t. c v entretcd(MWM) 1761327 18916271 13G055359

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o c2cnor a c t v i c. c :cc or 100.0 o r; . 8 O- '

actor

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.Z Reccior evcilubi ;1v '. 0 0 . 0 95.0 05.8

' /! Unit nervice f ac t or .00.0 94 2 / f; D

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. Uni- _ c :. t c i t y ? u t. t o r (U;inc_ Des Muc) 93.P 8 2 c' 6f .d

20. Unit forccd cutuge r u '. c 0.n P.2 _ _ _ , _

19 Shu t d ownss ct;ed uled' over nt x1 6 nun ths ( T v o ._ , D r. t e , u n d Durction of tach) L, 3

20. If t.h ; t d o w n at end of eport period cstinctet! date of :s t ar t ut ____,________] NA _

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flunbcr > 4' hebrn ,;e ac t o r ucs critica1 _

139 0 6049.0 64851.O~~

6. P,t a t t o r rcserve shutdoun acurs 0.0 0.0 2905.0 i

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P. Grow theren: encrav acncruted(M&) iP8630 12606675 127987 83

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60.7 81.1

, 4 Unit carcite Pactor ..' 68 . ti 74.a 1_9 . - U n t availubility Factor 34.2 6R . 't 75.7 s

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19. Shutdowns scheduled ever ncr1 6 ner.ths ( T y p e , D u t e , a n ti Duration of each)

20. II uhutdown ci and of report period.,catinuted date o f' _ t a r t u r .

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APPENDIX D QTP 300-S13 50-254 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.

March 1978 UNIT NAME . Quad-Cities Unit One COMPLETED BY E Weinfurter OAT January 4,1982 309-654-2241, REPORT MONTH DECEMBER 1981 TELEPHONE ext. 194 o

u 5 -

E hg E N' m @ LICENSEE g Co DURATION $

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" EVENT *8 g:8 ~

NO. DATE '-

(HOURS) yIy REPORT NO.

• 8 CORRECTIVE ACTIONS / COMMENTS R

31-31 811212 S 0.0 B 5 RB CONROD Load reduction to perform CRD scram timing 81-32 811220 S 0.0 B 5 -

RB CONR06 Reduced load for weekly Turbine tests, and to change the Control Rod Pattern (finai) m

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() 1 (3 'k APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO. 50-265 March 1978 UNIT NAME Quad-Cities Unit Two COMPLETED BY E Weinfurter DATE January 4, 198,' REPORT MONTH 309-654-2241' DECEMBER 1981 TELEPHONE ext 194 w $ p M h @ LICENSEE hg ag Co' DURATION $

in 3

• EVENT *8 g8 '

NO. DATE (HOURS) y3g REPORT NO.

• 3 CORRECTIVE ACTIONS / COMMENTS R

31-17 810907 5 606.03 C 4 RC FUELXX Continuation of End of Cycle Five Refueling

. Outage i

f (final) 9

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

• A A. MAIN STEAM RELIEF VALVE OPERATIONS Relief 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 2 12-26-81 2-203-3A I Manual Rx Press Post Mainte-2-203-3B 1 Manual 400 nance Survell-2-203-3C 1 Manual 1ance'T.S.

2-203-3D 1 Hanual 4.5.D.l.b 2-203-3E 1 Manual a

, C L,

- 9

B. CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO the basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of

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Technical. Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete sumesry of Units One and Two Control Rod Drive Scram Timing for the reporting period. All scram timing was performed with reactor pressure greater than 800 psig.

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RESULTS OF SCRAM TIMING MEASUREMENTS

, PERFORMED ON UNIT 1&2 CONTROL ROD DRIVES, FROM, 12-1 TO 12-31-81 l AVERAGE TIME IN SECONDS AT % Max. Time INSERTED FROM FULLY WITHDRAWN For 90%

Insertion DESCRIPTION NUMBER 5 20 50 90 Technical Specification 3.3.C.l &

DATE OF RODS 0.375 0.900 2.00 3.5 7 sec. 3.3.C.2 (Average Scram insertion Time) 12-12 89 0.285 0.659 1.428 2.514 3.04 (F-6) Unit 1 "B" Sequence Hot 12-20 177 0.26 0.50 0.98 1.72 1.85 (F-6, Unit 2 "A" & "B" Sequence, Cold K-9,J-8) Prior to Startup 12-27 177 0 30 0.69 1.49 2.58 3 30 (F-il: Unit 2 "A" & "B" Sequence Hot During Startup

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VII. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a Janua'ry 26, 1978, licensing memorandum (78-24) f rom 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-S32 Revision 1

• QUAD-CITIES REFUELING March 1978

[( - INFORMATION REQUEST h *

1. Unit: Reload: 6 Cycle: 7

( 1

2. Scheduled date for next refueling shutdown: 9-12-82 (Shutdown EOC61_,.

3 Scheduled date for restart following refueling: 12-5-82 (Startup BOC7)

4. Will refueling or resumption of operation thereaf ter require a technical f specification change or other license amendment: No, Plan 10CFR50 59 reloads for future cycles of quad Cities Unit 1. The review will be conducted in August, 1982.

5 Scheduled date(s) for submitting proposed Itcensing action and supporting

. Informa tion: August, 1982 for 10CFR50 59 related changes es 90 days prior to shutdown.

. 6. Important licensing u..csiderations 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: _

New fuel designs:

.2 7 The number of fuel assemblies.

a. Number of assemblies in core: 724

b. Nurier of assemblies in spent fuel pool: 820

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:

a. Licensed storage capacity for spent fuel: 1460

b. Planned increase in licensed storage: None 9 The prgjected date of the last refueling tha*. can be discharged to the  ;

spent fuel pool assuming the present Ilcensed capacity: September. 1985 (

(end of batch discharge capability)

(; X P P R O V E D_ <

APR 2 01978 C3. CL (). S. R.

L , ,

QTP 300-S32 R; vision 1

.. QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST

1. Unit: 2 Reload: 5 Cycle: 6

2. Scheduled date for next refueling shutdown: 8-30-81 (Shutdown EOC5)

, 3 Scheduled date for restart following refueling: 12-20-81 (Startuo BOC6)

- 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment: No, Plan 10CFR50 59 Reloads for future cycles of quad. Cities Unit 2. The review will be conducted by early August, 1981.

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

. Information: Early August, 1981 for 10CFR50.59 related changes a 90 days prior to shutdown.

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

' different fuel design or suppIIer, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

New Fuel Design: 1. Barrier Fuel .

2. Control Cell Core r -

7 The number of fuel a.ssemblies,

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 672

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:

a. Licensed storage capacity for spent fuel: 1460

b. Planned increase in licensed storage: None ,,

9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the pr'esent IIcensed capacity: September, 1984 i e, (End of batch discharge capability) I

. (3-4 PPROVED _,

APR 2 01973 .,

Q. c. O. S. R.

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

ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Cont ainment Atmospheric Monitoring ANSI -

American National Standards Institute APRM -

Average Power Range Monitor NfWS -

Anticipated Transient Without Scram BWR -

Boiling Water Reactor CRD -

Control Rod Drive EHC -

Electro-Hydraulic Control System EOF -

Emergency Operations Facility GSEP -

Generating Stations Emergency Plan HEPA -

High-Efficiency Particulate Filter HPCI -

High Pressure Coolant Injection System HRSS -

High Radiation Sampling System

• IPCLRT -

Int'egrated Primary Containment Leak Rate Test IRM -

Intermediate Range Monitor ISI -

Inservice Inspection LER -

Licensee Event Report ..

LLRT -

Local Leak Rate Test LPCI -

Low Pressure Coolant Injection Mode of RHRS .;

LPRM -

Local Power Range Monitor MAPLHGR -

Maximum Average Planar Linear Heat Generation Rate MCPR -

Minimum Critical Power Ratio MFLCPR - Maximum Fraction Limiting Critical Power Ratio MPC -

Maximum Permissible Concentration MSIV -

Main Steam Isolation Valve NIOSH -

National Institute for Occupational Safety and Health PCI -

Primary Containment Isolation PCIOMR -

Preconditioning Interim Operating Management Recommendations RBCCW -

Reactor Building Closed Cooling Water System RBM -

Rod Block Monitor RCIC -

Reactor Core Isolation Cooling System RHRS -

Residual Heat Removal System RPS -

Reactor Protection System RWM -

Rod Worth Minimizer SBGTS -

Standby Gas Treatment System SBLC -

Standby Liquid Control SDC -

Shutdown Cooling Mode of RHRS SDV -

Scram Discharge Volume SRM -

Source Range Monitor TBCCW -

Turbine Building Closed Cooling Water System TIP -

Traveling Incore Probe TSC -

Technical Support Center 9

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