ML20003B068

Monthly Operating Repts for Jan 1981

ML20003B068
Person / Time
Site:	Quad Cities
Issue date:	02/02/1981
From:	Tubbs R COMMONWEALTH EDISON CO.
To:
Shared Package
ML20003B066	List: ML20003B065 ML20003B068
References
QTP-300-S13, NUDOCS 8102100303
Download: ML20003B068 (22)

Text

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it 1 -QUAD-CITIES' NUCLEAR POWER STATION' UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT-JANUARY 1981 i

e- COMM0tNEALTH EDISON COMPANY AND-10WA-ILLIN0ls GAS t, ELECTRIC COMPANY - .

NRC DOCKET NOS. 50-254 A'JD-50-265' LICENSE NOS. DPR-29 AND DPR-30 f

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i TABLE OF CONTENTS 1

i. Introduction

11. Summary of Operating Experience A. Unit One B. Unit Two

' lit. _ Plant or Procedure Changes, Tests, Experiments, 'and Safety Related Maintenance l A. Amendments to Facility License sr 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 i

V. Data Tabulations

$ VI. Unique Reporting Requirements 3

A. Main Steam Relief Valve Operations B. Control Rod. Drive Scram Timing Data.

Vll. Refueling Information

, . Vill- Glossary ..

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l. INTRODUCTION 4

i quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MVe net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and lowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The 1

Architect / Engineer was Sargent & Lundy, incorporated and the primary construction contractor was United Engineers & Constructors. The con-3 denser cooling method is a closed-cycle spray canal, and the Mississippi River is the condenser cooling water source. The plant is subject to i

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. Lommercial generation of power began on February 18, 1973 for Unit I and f. rch 10, 1973 for Uni t 2.

• This report was compiled by Becky Brown and Robert Tubbs, telephone.

number 309-654-2241, extensions 245 and 174.

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11.

SUMMARY

OF OPERATING EXPERIENCE A. UNIT ONE January 1-6: Unit One began the reporting, period at 600 MWe, increasing at 5 MWe/ hour. Load was held at 65C MUe at 1045 and was maintained at that level until 1530 on January 6, Lxcept for a short load reduction due to vacuum problem. At 1530 load was again increased at a rate of 5 MWe/ hour.

Jar.uary 7-10: Load was increased, at 5 MWe/ hour, until a load of 777 i MWe was reached at 1200. This load was held until 2100 on January 9 when load was reduced in preparation for shutdown. On January 10, at 0214, the generator was tripped off-line for a maintenance outage.

Work performed was mostly limited to valve repairs.

January 11-15: On January 11, at 1959, the reactor was brought critical and the turbine put on line at 0757 on January 12. Power was increased at various rates and hold times untl1 a load of 770 MWe was reached and held at 1410,<n January 15 January 16-21: Over this six day period load was~ held at an average of 769 MWe. The only deviations were'a-short drop on January 18 for turbine tests, and a small increase on January 21 when the D1 heaters was restored to service.

.lanuary 22-27: At 0200, on January 22, during routine CRD exercise, a control rod over-traveled. As a result, the control rod was fully

• inserted and electrically de-energized with a resulting load drop to 752 MWe. At 2200 load was dropped to 425 MWe while the rod was re-coupled and wi thdrawn. Power was then increased at various rates until load was held at 825 MWe on January 25 On January 26 and 27 load was depressed by a xenon transient until a load of 824 MWe was reached on January 27 January 28-31: During this four day period an average load of 825 MWe was held. Unit One ended the reporting period holding a load of 820 MWe.

-. B. UNIT TWO Januar/ l-16: Unit .Two began the reporting period at a load of 732 L MWe, increasing at 5 MWe/ hour. At.1500 load was held at 800_MWe.

During the remainder of this sixteen day period, load was held at ani average of 783 MWe. The only exceptions were load drops fo'r turbine weekly surveillance on January 4 and 11.

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t January 17-20: On January 17, load was dropped'to 200 MWe to perform a control rod sequence change. Load was then increased at various rates until January 20. On that day, at 1500, load was held at 770 MWe.

January 21-23: Over this three day period load was held at an average of 765 MWe.

January 24-27: On January 24, load was droppen to.425 MWe to adjust ,

j- the control rod pattern per the Nuclear Engineer's ' direction. Load ~ -

was then increased at 5 MWe/ hour until a load of-795 MWe was held at

- 0550 on January 27 January 28-31; An average load of 784 MWe was held on January 28 and 29 On January 30 load was dropped in preparation for a maintenance outage. The turbine was tripped off-line at 2216, and the unit remained shutdown for the remainder of the reporting period.

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i lit. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED hAINTENANCE A. Amendments to Facility License or Technical Specifications

- There were no amendments to Facility License or Technical Speci fications 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 or experiments requiring NRC approval for the reporting period.

l D. Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the safety .

j' 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 Mal functions, Results and Effects or. Safe' 0peration, and Action Taken to Prevent Repetition.

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UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS OF ON ACTION TAKEN TO W.R. LER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION NUMBER NUMBER CRD 46-43 Flange bolts were Drive had a minor Retorqued CRD to 350 Q09482 loose. - flange leak, discovered ft.-lbs.

l during test. Unit was shutdown.

CRD 34-35 Flange bolts were Drive had a minor Retorqued CRD to 350 Q09 33 loose. i flange leak, discovered ft.-lbs.

during test. Unit was shutdown.

CRD 18-39 Flange bolts were Drive had a minor Retorqued CRD to 350 Q09481 loose, flange leak, discovered ft.-lbs.

during test. Unit was shutdown.

1A Core Spray Cracks in elbows. Replace 105 cibow in 105 bend replaced in Q07820- 80-25/0lT Line SEE LER. line located between lA Core Spray Line; reactor vessel and tested.

manual isolation valve.

81-1/03L 1/2B Standby Faulty auxiliary 1/2B train discharge Replaced auxiliary Q010205 Gas Treatment contacts, damper won't close. contacts in starter circuit; tested.

1/2-7507B Q09942 CRD Module Worn accumulator Received numerous high Removed old accumulator piston seals. water alarms. Scram and installed new one; 38-59 capability not affected. tested.

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Q010091 CRD 26-43 Worn accumulator Accumulator water level Installed new

- piston seals, alarm came up. Scram accumulator, capability not affected.

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'l UNIT ONE , MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS LER OF ON ACTION TAKEN TO W.R.

NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION NUMBER' Q07821 8C-25/0lT la Core Spray Cracks in elbows. Replace 105o elbow in IB 105o radius bend Line (1-1404- SEE LER. .

Core Spray Line located installed in "B" Core i

i 10"B) between reactor vessel Spray loop in l and manual isolation accordance with Work valve 1-1402-6B. Request package.

Seal ring required Valve seal ring leak in Disassembled valve, QO10005 RCIC Check MSIV room; RCIC cleaned, and replaced Valve (1-1301- replacing.

50) operability not affected. seal ring.

Q010286 Feedwater Check Seal ring leakage. Caused small leak of Replaced seal ring.

Valve (1-220- feedwater.

62A)LPRM 08-33D The detector was LPRM was reading down- Replaced detector Q00872

' faulty. scale. APRM operability during refuel outage.

was not affected.

24/48V IB2 Voltage regulator Voltage fluctuated Replaced regulator QO10633 Dattery Charger defective. erratically. System was card.

Et e' l-8325 operable.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS Od ACTION TAKEN To LER OF W.R. MALFUNCTION SAFE OPEFATION PREVENT REPETITION t- - NUMBER NUMBER COMPONENT Valve operator trips Valve normally open. Replaced torque switch

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Q09435 RHR (2-1001-7C)' in limitorque valve when valve reaches LPCI was operable.

Faulty operator. Valve fullclosed{h.

torque switc operability & interlocks checked.

Switch failed. Switch inoperable. Replaced mercury switch.

QO10634 HPCI (LS-2-2365)

HPCl was operabic.

Drywell Equipment Various parts out of Valve took longer than Lengthened stroke one Q010131 80-35/03L required 20 seconds to turn on connector nut; Drain Pump Valve adjustment.

close. Inboard isolation adjusted packing gland, (2-2001-16) reset limit switches.

valve A0-2-2001-15 was closed.

RHR Valve.to Faulty auxiliary Valve will not open Replaced auxiliary lq010158 80-39/03L contact on closed Torus (2-1001- contact. from 902-3 control 34A) switch. contactor.

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l IV. LICENSEE EVENT REPORTS The following is a tabular summary of all license 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.l. and 6.6.B.2. of the Technical Specifications.

UNIT ONE License Event Report Number Date Title of Description 81-1/03L 01-05-81 Made 1/2B Standby Gas Treatment inope rable to repair discharge damper.

81-2/03L 01-07-81 Failure of Humber 1 Diesel Generator to run after' monthly inspection.-

81-3/03L 01-14-81 High Drywell pressure switch PS-1-1001-90D

- instrument drift. - .

81-4/03L 01-16-81 LS-1-263-57A low-Low Reactor Vater Level instrument drift.

UNIT TWO 81-1/03L 01-16-81 High'Drywell pressure switch PS-2-1001-88D instrument drift.

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! 81-2/03L 01-16-81 Electromatic Relief valve controller drif t i PC-2-203-3B.

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V.- DATA TABULATIONS I

I The following data tabulations are presented in this report:

i l A. Operating Data Report I B. Average Daily Unit Power Level C. Unit Shutdown and Power Reductions i

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AVE 2 AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 DATE ichrua . 2, 1981 COMPLETED BY R C Tubbs

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MONTH Jonoorv 1981 .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) _ _ _ _

(MWe-Net)

1. 601.6 17, 742.5

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3. 619.0 19, 728.4 4, 621.8 20. 738.7 y n.

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22. 713.4

7. 728.5 23. 533.0

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9. 680.4 25. 774.0

10. .8 26. 76?.9 i~i .~ ~ ~~~~~~~~ ~~ -~ ri 1797 ~ ~ ~ ~~ ~ -~~ ~ ~ ~ ~~ 2 7 7 ~ ~ ~ ~~ ~~ ~ 77i, 3

12. 240'.3 28. 778.6 ~

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13. 442.7 29. : -771.1

. . _ . _ . . 768 i~ ~ ~

g9 LS. 711.6 31.. 769.5-16, 733.9 ,

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INSTRUCTIONS ~

On this f arn, list the estrege daily snit ;twer' level in Se-Net for each hy in the repartir.g scath.Cespite to the r.ecrest cele neccestt.

. Dese fiMes will be vsed to plot a graph fer each re; rtleg asnth. Note thet whts actinta deper.hbic cc::tity is  ? '~~ ~ ~ ~ ~

.osta isrithe net electrical rating of the sait there a1y be ettesiens d.en the daily everge pswer level excetts tht illi lire ter the restricted power level line) la sich cases,the average daily init power estput sheet shesid be

. f antacted ta explain the apparent onently.-

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.._--__ ~' APPENDIX B

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7 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265

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. DATE_ February 2, 1981 COMPLETED BY R C Tubbs

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~ TELEPHONE- 309-65-42241 rext .-174-110 NTH . Jonoor v 1981 . . . --_ . .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) .

(HWe-Net)

i. 715.4 17, 371.7

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3. 730.1 19. 622.8 4, 730.9 20. _ 696.3

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6. 736.0 22. 713.2

7. 737.6 23. 708.4 B.

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9. 726.4 25. 551.8

10. 734.3 26, 651.1

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731.9 -

28. 730.9

13. 722 i 29. 752.5 __

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720'.i '30.. ~~618 '. 8" L5. 714.0 ,

31. -9.6' L6. -686.3

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INSTRUCTIONS . -

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. r.cerest whole, list negowet t. the overagt daily unit power level in liile-Net for each day in the reporting nonth. Compete to the

- These figures will be used to plot a grcph for each reporting nonth. Note that when notinen dependable capacity is -

tsed for the met elettricel rating of the sait there may be ecccstens when the daily everage power level exceeds the" -

illI line (or the restricted power level line)'In sich cases,the average daily enit power outpet sheet shecid be :

_fsstnoted to esplein the opptrent on.nly -

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r OPERATING DATA REPORT

' DOCKET NO C '50-254~ ~'- -~

UNIT _ _ ONE DATE_ February 2,1981 w me w+ -

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' COMPLETED BYER C~Tubbs OPERATING STATUS TELEPHONE _309-654-2241, ext. 1)

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1. ~ rep or tIhg 'peFi'o d i240 -0000 0 010181 013181

2. Gr o s~s ~ h o~u r s i n ~r e p o r t i n g'~p e~F fo d ^

(MWe-Net): Currently authorized power level(MWt):

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769* Design electrical rating '(MWe--Ne t)i ~7892511 Max. Depe ~ ~ ' ~ ~ '

3. Power.

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level to_.whi.ch_ restri.cted(if any)(MWe-Net):th Reasons for restriction (if any): _ _ _ _ _ _ _ _

5. This Month' Yr , t o Dote ' ' CuriiilotTve Nunber, of hours _ reactor was critical

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742.6__ _ 742,6_

Reactor reserve shutdown hours 61448.9

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0.0 0 . _0_ 3421.9 H o ur~s ' Ten e Fli~tF o n Tfrie'

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UDil.yeserve shutdown hours. _ ~~~742.3" Y 5862'Q 9 _

0.0 0._0 Gross thernal energy generated (MWH) 909.2_

10, 1503625 _

1503625 Gross elec'trical '~nergy~generot'ed(MWH) e _ 1117745713

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492600

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T37871507' N e t . e l e c t r_i c a l_ e n e r_g y _ g e_n c r o t e d ( M W H )

, . _ _ 467867 467867

12. Reactor service factor 1

_ 35325146_

13. _

99.8 99.8 Reac t or a vaillitiffi fy~ foEt or '

_ 80,3

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__14. Unit service factor

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L5. Unit ovallobility factor 99.8 99.8~ 76.6 L6. Unit ~

99.'8 99.8 77.8 capacity fiEi'o'r'(Using t Des.HWe) j.

T~ 81 I8 l ~ i 81.8'

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! Unit _ capacity factor _(Using MDC) 60.0 79 2 ._

-18. Unit forced outage rote 79.7 ___ _' 4 1.

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19.' Shutdowns scheduled __

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-20. If shutdown at over nextl6'nonths (Ty'pe,Dute>ond Duratidn'lof coE h') :

end~of report. period,estinated date of stortup-ire MC nay be lower than 769 We during periods of hi h ,

_[_NA _ _ , , ,

ts the thernal perfernana of the spray tenal. g anblant tenperatsre due.

OPERATING DATA REPORT DOCKET NO."~~50-265

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UNIT TWO DATE February 2,1981

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~~ ~ ~ ~" COMPLETED BY R~C T6bbs" TELEPHONE 309-654-2241, ext. 174

- OPERATING STATUS 0000 010181

~ 4. . ' R e p o r t in g 'p e r i o~di24 0 0 ' 013181_ GrWs s ' ti o'u r s in~7Ep 6Ft in g ~ fir ~iid i ~ 744~

2. 7urrently authorized power leu' . (MWt): 2511 Mox. Depend capacity - ~ ~ ~ ~ ~ ~ ~ ~ ^ ~ ' ' ~ ~ ~ ~

~~ ~~(MWe 'le t ) i 769* De+ign elec tricci eating (MWe-Net)i~789

3. P o w e. r- level to which restr hted(if any)(MWe-Net): NA

4. Reasons for restriction (if any):

~

This Month 'Yr .'ti Diite ~Cunulit1Ve

5. Number of hours reactor was critical 702.7_ 702.7 59535.5

6. Reactor reserve shutdown hours 0.0 0.0 ~2985.8

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8. Unit reserve shutdown hours. 0.0_ 0.0 702.9

9. Gross thernal energy generated (MWH) 1658047 1650047 116858455

1. 0 . Gross electrical energy generated (MWH) 527635. 527635 37249186 l .

! 11. Het electrical energy _ generated (MWH) 489926_ 489926 34846878

12. Reactor service factor 94.4_ 94.4 78.8 8 2'7_ ;

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~ E'474T~~~~~ F4T4 92.8 92.8. -

175.4

14. Unit service factor l- 15. Unit availability factor 92.8. 92.8' 76.3

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17. Unit. capacity factor (Usin_g MDC) - 83.5- 83.5 58.4-i _

t 0.0 0 . 0_ 9.i 1.0. Unit forced outoge rate t

19. Shutdowns schedu' led over_next 6 nonths (Type, Dote,and Durdtion o'f each)T ~

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20. If shutdown at end o f rep or t L p eri od , e st inat ed dote o.f st ar t_up__2-2-81.

-*De RC nay be lower _ thsm 769 MWe dering perleds of high c2iont tenperatere due -

'to the thernal perforsonce af the spray canol.'

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'5 p -h APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO, 50-265

. March 1978 UNIT NAME @AD-CITIES UNIT WO COMPLETED BY R C Tubbs e uary 2, 1981 DATE REPORT MONTH JANUARY 1981 TELEPHONE 309-654-2241, ext. 174 e 5 -

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po' DURATION $

p t; E EVENT *8 g8 '

NO. DATE (HOURS) y5g REPORT NO. 8 CORRECTIVE ACTIONS / COMMENTS R

81-1 810117 5 0.0 H 5 RC ZZZZZZ Load reduction to change control rod pattern.

81-2 810124 S 0.0 'H 5 RC ZZZZZZ Load reduction to change control rod pattern.

81-3 810131 S 1.4 8 1 ZZ ZZZZZZ Maintenance Outage to work on various valves, and check for condenser tube leaks.

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VI. UNIQUE REPORTING REQUIREMEllTS 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 during the reporting period.

B. Control Rod Drive Scram Timing Data for Units One and Two There were no Control Rod Drive Scram Timings for the reporting period.

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Vll. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26,19/8, licensing memorandum (78-24) from D.E.

O' Brien to C. Reed, et. al . , t i t led "Dresden, Quad-Ci t ies , and Zion Station--

NRC Request for Refueling infornation" dated January 18, 1978.

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QTP 300-532 Revision 1 QUAD-CITIES REFUELitlG tiarch 1978

-(-- lilFORMATIO!! REQUEST

1. Unit: 1 Reload: 6 Cycle: 7

2. Scheduled date for next refueling shutdown: 9-12-82 (Shutdown E006) 12-5-82 (Startup BOC7) 3 Scheduled date for restart following refueling:

4. Will refueling or resumption of operation thereafter requirc a technical specification change or other license amendment: tio, 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 licensing action and supporting Information: August, 1982 for 10CFR50 59 related changes ~ 90 days prior to shutdown.

r

6. Important licensing considerations asqoc ated with refueling, e.g., new or

' dif ferent fuel design or :,upplier, unreviewed design or performance analysis methods, significant changes in fuci design, new operating procedures: ,

flew fuel designs:

.T .: -

7 The number of fuel assemblies.

tiumber of assemblies in core: 724 a.

Plumber of assemblics in spent fuel pool: 820 I

b.

I 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: ,

Licensed storage capacity for spent fuel: 1460 .

a.

Planned increase in licensed storage: None b.

9 The projected date of the last refuelinD that can be discharged to the spent fuel pool assuming the present licensed capacity: September, 1985 (end of batch discharge capability)

/-

.X P P R O V E D APR 2 01973 Q. c. O. S. R.

b

QTP 300-s32 r

R: vision 1 QUAD-C! TIES REFUELING March 1978

(--.

lHFORMATION REQUEST Reload: Cycle: 6

1. Unity 2 5

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

Scheduled date for restart following refueling: 12-20-81 (Startup BOC6) -

3

4. Will refueling or resumption of operation thereaf ter 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. ,

8 5 Scheduled date(s) for submitting proposed licensing action and supporting

. Informa tion: Early August,1981 for 10CFR50 59 related changes a90 days l

prior to shutdown. -

L

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

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

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

New Fuel Design: 1. Barrier Fuel

2. Control Cell Core 7 The number of fuel a,ssemblies.

f

a. Number of assemblies in core: _

724 I b. Number of assemblies in spent fuct pool: 672 f

I 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 l

f in number of fuel assemblies: .

a. Licensed storage capacity for spent fuel: 1460 Planned increase in licensed storage: None

b. ,

9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September, 1984 (End of batch discharge capability)

L l {Ty

.'PPROVED A

APR 2 01978 Q.C.O.S.R.

[ e_. . . au- e y

Vill. CLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined ociow:

CRD -

Control Rod Drive System SBLC -

Standby Liquid Control System MSIV -

Main Steam Isolation Valve RHRS - Residual Heat Removal System RCIC - Reactor Core Isolation Cooling System HPCI -

High Pressure Coolant injection System SRM -

Source Range Monitor IRM -

Intermediate Range Monitor LPRM -

Local Power Range Monitor APRM -

Average Power Range Monitor TIP -

Traveling incore Probe RBCCW -

Reactor Building Closed Cooling Water Systen TBCCW -

Turbine Building Closed Cooling Water System RWM -

Rod Worth Minimizer SBGTS -

Standby Gas Treatment System HEPA -

High-Efficiency Particulate Filter RPS - Reactor Protection System IPCLRT -

Integrated Primary Containment Leak Rate Test LPCI ' " -

Low Pressure Coolant injection Mode of RHRS RBM -

' Rod Block Monitor BWR -

Boiling Water Reactor ISI -

In-Service inspection MPC -

Maximum Permissible Concentration .

PCI -

Primary Containment isolation SDC -

Shutdcwn Cooling Mode of RHRS LLRT -

Local Leak Rate Testing MAPLGHR -

Maximum Average Planar Linear Heat Generation Rate RO -

Reportable Occurrence DW -

Drywell RX -

Reactor EHC -

Electro-Hydraulic Control System HCPR -

Minimum Critical Powcr Ratio PCl0MR -

Preconditioning interim Operating Management Recommendations LER -

Licensee Event Report ANSI -

American National Standards Institute NIOSH - National Institute for Occupational Safety and Health ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ATWS -

Anticipated Transient Without Scram SDV -

Scram Discharge Volume TSC -

Technical Support Center EOF -

Emergency Operations Facility HRSS -

High Radiation Sampling System GSEP -

Generating Stations Emergency Plan