ML20077N493

Monthly Operating Repts for Jul 1991 for Quad-Cities Nuclear Power Station,Units 1 & 2

ML20077N493
Person / Time
Site:	Quad Cities
Issue date:	07/31/1991
From:	Losekshort C, Robey R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RAR-91-33, NUDOCS 9108140339
Download: ML20077N493 (22)

Text

{{#Wiki_filter:. - _ _.. - _ _ _ _ _.. -..-. -{, 4 RAR-91-33 August 1, 1991 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington. D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Honthly Performance Report NRLDocke.LNo.sm50-254_anL50-165 Enclosed for your informatinn is the Monthly Performance Report covering the operation of Quad-Cities h/ lear Power Station, Units One and Two, during the month of July 1991. Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION 7 R. A. Robey Technical Superintendent RAR/CALS/dak Enclosure cc: A. D. Davis, Regional Administrator T. Taylor, Senior Resident Inspector e pDR ADtEK 050092['4 PU" R f$$f- 'It

. _. _ _ _ _. _ _ _ _ _ _. ~... _. _______m QUAD-Cli!ES NUCLEAR POWER STATION UNITS 1 AND 2 e HONTHLY PERf0RMANCE REPORT JULY 1991 COMMONNEALTH EDISON COMPANY AND 10HA-ILLIN0!S GAS & ELECTRIC C if NRC DOCKET NOS. 50-254 AND 50-265 i LICENSE NOS. OPR-29 AND DPR-30 i.l. t l . TS 14

l TABLE OF CONTENTS 1. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two 111. Plant or 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 Rcports V. Data Tabulations A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. Unique Reporting Regitirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information Vill. Glossary TS 14

I. IlllRODUC110li Quao-Cities Nuclear Power Station is composed of two Boiling Hater i Reactors, eacv with a Maximum Dependable Capacity of 769 MHe 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 Hater Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary I 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 Cynthia A. Losek-Short and Debra Kelley, telephone number 309-654-2241, extensions 2938 and 2240. j TS 14

II. SUti!%RY_0LDEE RAll tiG_EXEE RI Uf C L A. Unit _0ne Unit One began the month of July operating on a load drop which was requested by Chicago Load Dispatch. The load drops that occurred within the month were requested by Chicago Load Dispatch and for a drywell entry. The load drops that were requested by Chicago Load Dispatch occurred July 1, 4, 5, 7,10, 11, 13, 14, 15, 16, 18, 19, 24, 25, 26, 28, 30, and 31. The load drop to 200 MHE for drywell entry occurred July 20th. B. URLt_Jwo Unit Two began the month of July operating in Economic Generation Control (EGC). The unit was taken out of EGC on the 3, 4, 5, 6, 9, 11, 12, 20, 21, 22, 23, 28 and 30 per Chicago load Dispatch requests. The unit was also taken out of EGC on July 10 for a Drywell entry. The reactor was scrammed on Juiy 13 at 1239 hours for an entry to the Drywell to work on equipment. Reactor became critical again on July 15 at 2300 hours. TS 14

- -. _ = III. ELA!(LOR.2ROCEDURLCHANGES _JESIS...EXEERIMENIS. AND_SMULRELAILDlalttIENANCE A. kaend me nt s_to_f ac1111y_Ltc ens tor _le c hnic a LS p e t inc ations There were no Amendments to the facility License or Technical Specifications for the reporting period. B. Eac1Lity_rrJIoc ed ure_Ch an g e sJes u irlnglRClp atoyal There were no facility or Procedure changes requiring NRC approval for the reporting period. C. Jests _and_ExperlaienisJequirJng_RRC_ Approval There were no Tests or Experiments requiring NRC approval for the reporting period. D. Corre c tlyeJaj nt en an c e_oLS Afe tLRelat e LEq u ipine n t i The following represents a tabular summary of the major safety related maintenance performed on Units One and Two during the reporting period. This summary includes the following: Hork Request Numbers, Licensee Event Report Numbers, Components, Cause of Halfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition. f i I L f-TS 14

i ^ UNIT 1 MAINTENANCE

SUMMARY

HORK REOUEST SYSTEM .EID DESCRIPTION WORK PERFORMEQ Q87815 0912 Repair broken lug on white As Found: Found wire from Cable 31143 taped and conductor of Cable 1143. laying at the bottom of 912-2 panel. As Left: Installed #14515 wire, window splice, and lug properly in 912-2 panel and taaed wire with 33T tape. Q89084 3102 Body to bonnet gasket needs As Fcund: Fitting for bonnet gasket was damaged replacement please repair. and some metal on the bolt icread interfered with the upper bonnet half (causing gasket not to seal). As left: Removed old bonnet and replaced with new bonnet and gasket. Q43320 1002 Inspect and repair as needed the As Found: Windings were found burnt and motor bearinos for IB RHR pump grounded. The rotor was also bowed on the motor. motor. As Left: Installed new motor under WR #Q43490. Q93802 1641 Category I - Torus Level As Found: Found transmitter reading 0.6 MA low Indication 12.9' too low, over the whole range. As left: Ferformed locp calibrate and repair indications calibration on xmitter. Indicator and recorder as needed. using Std #033164Q and #1271310 Documented on QIS #54-54. Replace 0-Rings for E.Q. Q91291 8300 Investigate broken glass on 24/28 As Found: Found broken glass on relay cover. As VDC overvoltage relay in large Left: Replaced glass on cover (Use 1/8" battery charger room. (Replace plexiglass). cover). TS 15

UNIT 2 MAINTENAM E

SUMMARY

WORK REQUEST SYSTEM ELD _DJSCRIPTION KP.K PE3f_OFFJD 093788 3127 Investigate and repair U2 HCV As Found: Stem was rubbing on two sides 180* 58-23 Rod R-6 drifted in from 48 apart from top and bottoc. The valve seat was to 00 and beyond (suspect leaking worn, ball check was marked up, there was slight scram valve). rust internal to the sleeve is scored from stem rubbing, and the disk has uneven seat mark but was l seating 360*. As Left: Installed new stem and adjusted HCV bracket so operator was Tevel, new j packing ball check was also installed. Q92918 0750 Repair IRM 12 which is spiking As Found: Chassis reading was to be 15 units. As High High causing 1/2 scrams. Left: IRM was indicating 15 on chassis. All the l tests that were done looked normal. Removed High voltage power supply checked and cleaned connector under pot. Reinstalled High voltage power supply. l Q88898 0756 Investigate and repair APRM #1 As Found: Found APRM #1 to be bypassed. As which spiked downscale inoperable Left: Inspected all connections on page bus, causing 1/2 scram anti released everything looked normal. Inspected and cleared increasing 12-4. (Refer to WR all page cor.nectors. Found Pin 14 on connector J39 to be recessed a little rid pushed it back to

1. 87391).

its original position. Performed function test ST-3-2 on APRM Ch. I tested normal, also performed QIS 3-1. 093954 1201 For QOS 1200-1 repair 2-1201-2 As Found: Valve was 3/8" off of backseat. As valve whose stroke timed at 30.6 Left: Adjusted 1 4 limits one turn CCH to give seconds which exceeds its maximum 9/?6" off of backseat stroked valve three time. T.S. of 30 seconds. and timed it at 28.76 seconds and 29.06 seconds. TS 15

IV. LICENSELEVENLRERORIS t 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 tequirements as set forth in sections 6.6.B.1 and 6.6.B.2 of the Technical Specifications. UNIL1 Licensee Event F Repor.tJumber Datte litle_oL0ccurrence 91-010* 06-14-91 1/2 Scram on Loss of A 24/48 VDC (near Miss). 91-010 06-14-91 Closure of S/D Cooling Valves during Surveillance. Last month LER 91-010' was reported with the wrong Title of Occurrence the title should have been Closure of 5/D Cooling Valves during Surveillance. There were no licensee event reports for Unit I for this reporting period, UNIL2 91-07 07-13-91 Low Hater-Level Scram. 91-08 07-23-91 Rectre Sample Valve 2-220-45 Closure, i i l TS 14 __._..__,.._.___.._._._.___.___-____._____.__...__m_._

i i + - i i V. MTAJABULMIONS l The following data tabulations are presented in this report: l t A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions i i t .i 5 -TS 14

ArttNOIK C OPER ATING DATA REPORT DOCKET No. 50-254 UNIT Une DATE ^"P""t 1 1991 liina I m k-Sliort COMPLETED BY l TELEPHONE 'U"~h64-224I OPER ATING STATUS 50000 070191 52400 073141 700

1. REPORTiwS PSR100:

GROS 8 HOUR $ lN REPORTINQ Piml00 2511 764

2. CURRENTtY AUTHORitt0 POWER LEVtt lWWti.

W AE. otPt No. CAP ACITY IWWe46ml. DESIGN SLECTRICAL RATING inned: M9

3. PowtR LEVEL TO WHICJ4 RtSTRICTED llP ANYI 1%Neil:

4. REASONS POM RESTRICTION llP ANYli THilWONTH YM TO OATE CUWVLATIVE 744.0 1523.0 111004.4

5. NVuetR OP HOURS REACTOR WAS CRITICAL 0.0 0.0_

3421.4

4. R CACTOR R ESERVE SHUTOOWN HOURS................

744.0 1146.1_ 128765.6

7. HOURS O EN E R ATOR ON UN E...................

0.0 0.0 409.?

8. UNIT MillRVE SHUTDOWN HOUR 8 1695427.0 3085818.0 275817?78.0

9. GROSS THERWAL ENERQY OtNER Af tO lWWHI 545749.0 990151.0 89184005.0

10. CROS8 ELECTRICAL ENERQY CLNER ATt0 IWWHI...

52837I.0 930215.0 M 104 Wi. 0

11. Ntf SLECTRICAL ENERGY GENERATED (WWH) 100.0 29.9 78.6

12. r E ACTOR 5t RVIC E P ACTOR................,.

IOU *U 24*9 .6

13. All ACTOR AV AILAtlLITY P ACTOR................

100.0 ?7.4 76.1

14. UNIT S E RVIC E P ACT OR.......................

. _ 00.0 77,4 76.6 ] 19 UNIT AV AIL AllLITY P ACTOR........................ 6' 92.( 73,s

18. UNIT CAP ACITY F ACTOR IUmng WDC) 21*2

17. UNif CAP ACITY P ACTOR IUwag Osme WWWI.............

0.0 192.6 1%.3

18. UNIT PORCED OUTACE RATE,......

19. 5 HUT 00WNS SCHEDULt0 0VER Nt xt 6 uoNTH8 ITYPE DAf t. AN0 0VRAtl0N CF E ACHit

20. IP SHUT 00WN AT EN0 0P REPORT PERIOD.ESTlMATto DATE OP STARTUP;

21. UNITS IN TEST ST ATUS IPalOR TO COMMERCI AL OPER AT10NI; PORECAST ACHIEVED INitt AL CRITICALITY INITI AL ELECTRICITY COWMERCIAL OPERATION l.16 9 l

c

.~ -. 4 g APPENDlX C OPERATING DATA REPORT DOCKET NO, 50-265 VNIT Two Aueust 3. 1991 DATE ,OMPLETE O ggy Cythina Losek-Short l 309-654-2241 TELEPHONE ONRATING STATUS 50000 070191 52WO 073191

1. R8PORTIN0 PORl00:

GROSS HOURS IN RtPORTl40 PtRi00r 744 25II M AX. ORPt NO. CAP ACITY (MnNesth 769

2. CURRtNYtY AUTHOR 1880 PowtR LEVEL IMwth 08810N OLtCTRICAL RATING IWwe Neil 789

3. POW 9R LIVIL TO WHICH ResTRICTSO llP ANY) (Ww,Neth

4. RtASONE POR M88tRILTION UP ANYl THIS MONTN YR TO Daft CUMULAfivt 68e.6 4 '> 7 ?. 6 130261.8

5. NUMSGM OP HOURS REACTOR WAS CRITICAL...............

0.0 0.0 2985.8

8. REACTOR RSSSRVE SHt87DOWN HOURS...................

668.3 4524.8 126811.8

7. HOUR 8 GINERATOR ON LINE............

0.0_ 0.0 702.9

8. UNIT RESORVE SHUT 00wN HOUms,.....................

9. GROSS THERMAL INERGY QENERAf tD (WWHI............ 1513058.0 10507158.0 27373

10. GROS 8 ELECTRICAL ENEROY QENER ATIO (WwH)........,,,

483328.0 340200hD 87863216.0 ,467183.0 3291221.0 83121773.0

11. htT ttICTRICAL ENEROY GINER Af tD IWWHs,......,...

92.2 89.9 77_7

12. P E ACTOR $t RVICS P AC(OR....................,.

9 *2 9*9 79 5--

13. R E ACTOR AV All.A tlLITY P ACTOR.....................

09*8 88 9 75.6

14. UNIT stRVIC E P ACTOR..............................

89.8 88.9 76.1

19. U N IT AV AI L A t l LI T Y P ACTOR..........................,

81.7 84.1 64.s l

18. UNIT CAPACITY P ACTOM aVeng MDC) 79.6 82.0,

67.8

17. UNIT CAP ACITY P ACTCM lusing Dee.e MWel.................

j'

18. UNIT PORCE D OUT A0 8 RATE..........................

1.0 77.9 85.8

19. 5HUTDOWN$ SCHEDULIO OvtM NEXT S MONTHS LTYPE. DATE. AND DURATION OP (ACHh

20. IP SHUT DowN AT (NO OF REPORT PERIOD. ESTIMATED DATE OP STARTUP:

21. UNIT 5 IN TEST ST ATUS IPR 104 TO COMMERCI AL OFIRAT10Nh PORICAST ACHEVED INITI AL CRITICALITY INITIAL ELECTalCITY COMMERCIAL OPSRATION 1.16 9 n

. g,

APPENDlX B AVERAGE DAILY UNIT POWER 12 VEL 50-254 DOCKET NO. UNIT 0"* DATE Aucust 3 1991 COMPLETED BY cytidna g-stion TELEPHONE 309-654-2241 MONTH 3"1" 1991 DAY AVERAGE DAILY MWER LEVEL DAY AVERAGE DAILY POWER IEVEL (MWe+ et) (MWe-Net) bb2 731 9 gy 776 2 gg 73g 746 724 3 g, 561 398 4 g 607 5 21 677 777 758 ,3 y 725 7 ,3 7gy 727 8 754 24 9 774 28 7?6 749 701 10 3 727 746 gg 37 775 674 12 739 769 13 h 664 687 14 30 708 6RI 18 33 723 16 INSTRUCTIONS On this form,lat the awray Jaily unit power newn in MWe. Net for each day m the reporting month, Compute to the neascal whole megawalt. These figures will be used to plot a path for ca h reporung month, Nute that when truximum dependable capacity is used for the net clestncal rating of the umt, there may be owasions wiien the daily average power level exceeds the 100A line (or the rntricted power Ictel line). In such cases, the average d.uly unit power output sheet should be j footnoted to captain the apparent anomaly. l.16 8

APPENDIX 4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. so-26s UNIT T* i DATE Ato un t 3, 1991 j COMPLETED BY Cvthina Lasek-short TELEPHONE 209-654-224 1 l MONTH J"1V 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILYp)WER LEVEL (MWe-Net) (MWe-19et 755 1 g 651 775-3 744 gg 775 3 678 gg bb3 709 .4 n 661 720 3 724 761 8 22 Il0 736 y gg 774 740 g 24 679 733 g 576 740 10 N 739 699 gg g7 700 729 12 as 32 743 13 29 -7 729 14 30 ~0 69h 13 -- 31 50 16 L INSTRUCTIONS On this form, hat the aversgs daily unit power level in MWe&t for each day m the reporting month. Compute to the nessest whole megawatt, These figures will be used to plut a paph for cash reportans month. Nute that when enexamum dependable capacity is used for the net etteincal ratmg ut the unit, there may be ossuions when the daily average power level exceeds the 107A Ime (or the rntricted powet Icsel hnc) in such cases. the average duly urut power output sheet should be foutnoted to caplaus the apparent anumaly. l.16 4 l

? ? !ii, I <F i;it 5 t lrii(. D!?!!!, h t? p Li !!lr i', i t r - o h s 1 ke 4 s 2 S o 2 T L N 4 E 5 9 A 6 P O a 9 C i 0 / y h 3 S r t A' t n D n y I E C TC l l A e YB E w V yr D E I E N T D T O C r E H E o L P R f P E R r L O p 0 E C o 0 T r D d ao L S .NO IT C U w8" D { o" 1 E 9 R 9 1 R ,l E ) 'DW t l O s w8" a XP u n I g rgm$ i DD u = f NN A EA .l f P 1 PS E O AN H E N W T ST O N NNT D O EER T M CVO U I EP N T L E S R R O T P I E conugE a N R 5 oz ~ {i" t iS wo o zoQE B N) OS 4 I R TU 2 AO 1 RH U( 1 9 D 9 1 o$% s 1 S ug 4 1 t 5 s 2 t u i g 0 E 0 n u 2 5 U A T 7 A 0 D 1 9 O g N M A T N 3 E O 0 K T E N 1 C 1 TA 9 O fB D D I 1 i4i!'

E E i A 4 \\ s g h ~1 x ? 2 a S h F 2 8 C i A E o TYPE m F OR S G n a m3 5 = b wx 5 REASON METHOD OF SHVITING g DOW REACTOR R 3 tn g i tut N g g 3 i h m 1

a. R mm m

ir 58 SYSTEM a 8 CODE E NM 0 c' a i e s COMPONENT B i C CODE O i E 5 ?? RX a n M 8 9 e R 4 ?! 2 F F f, t Q a y ~ A = C h Y si a g ax w x 0 o T ? l }i k h f+ I

e e t VI. UNIOVLREPORTINGJEQUIREMERIS The following items are included in this report based on prior commitments to the commission: A. tia11LS i e anLReite LYalyL0p eration s There were no Main Steam Relief Valve Operations for the reporting period. B. ControLRod_Ditve_ScranLillRinLData for_UnLts_One_and..Iwo The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2. The following table is a complete summary of Units One and Two Control Rod Drive Scram Timing for the reporting period. All scram timir.g was performed with reactor pressure greater than 800 PSIG. l TS 14 L i L

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 1-1-91 TO 12/31/91 AVERAGE TIME IN SECONDS AT % MAX. TIME INSERTED FROM FULLY WITHDRAWN FOR 90% INSERTION DESCRIPTION ' NUMBER l 5 20 1 50 90 Technical Specification 3.3.C.1 & DATE OF RODS 0.375 0.900 1 2.00 1 3.5 7 sec. 3.3.C.2 (Averace Scram Insertion Tire) 1-30-91 1 0.28 0.63 1.37 2.45 H-7 U2 scram tir ing for accumulator replacer:ent (2.45) on H-7 1-30-91 1 0.30 0.72 1.53 2.67 F-6 U2 scram timing for accumulator replacement (2.67) on F-6 4-30-91 22/177 0.29 0.67 1.46 2.57 H-11 U1, Hot Scram Timing during Start Up (3.0) Sequence A&B, Cycle 12 (Paritial) 5-2-91 177 0.29 0.67 1.44 2.55 R 10 U1 Start Up Scram Timing Begin Cycle 12 (3.27) 5-5-91 89 0.31 0.68 1.43 2.51 B-4 U2 Scram Timing For Sequence A (2.84) 5-6-91 1 0.26 0.62 1.40 2.52 E-12 UI Scram Timing for IR on Scram Light 1 (2.52) 7-12-91 4 0.27 0.62 1.35 2.38 N-12 UI Wort Requests for Accumulator Replacement (2.42) 7-17-91 1 0.28 0.62 1.32 2.32 R-6 U2 Scram Outlet Failure (2.32) l scrmtim

___._.._.__..___.____m a VII. REfuELIK_.INf0RHA110H 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. I l l l ' TS 14

OTP 300-532 .!evision 2 00AD CITIES REFUEL.ING October 1989 INFORMATION REQUEST i 1. Unit: 01 -Reload:- 11 Cycle: 12

2.

Scheduled date for nest refueling shutdown: v-5-92 3. Scheduled date for restart following rafueling: 12-5-92 4 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment: FOT AS YET DETED!INED. 5. ' Scheduled date(r) for submitting proposed licensing action and supporting information: NOT AS YET DETEMIINED. 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 PRESENT TIME. 7. The number of fuel assemblics, a. Number of assemblies in core: 724 b. Number of assemblies in spent fuel pool:- 1405 8. The present lice 03ed spent fuel pool storage capacity and the size of 4 any increase tra licensed storage capacity that has been requested or is planned in number of fuel.issemblies: a. Licensed storage capacity for spent fuel: 3657 b. ~ Planned increase in licensed storage: 0 9. The projected date of the last refueling that c3n be discharged to the spent fuel pool assuming the present-_Ilcensed capacity: 2009 APPROVED (final) OCT 3 01989 14/0395t O.C.O.S.R.

4 QTP 300-532 Revision 2 QUAD CITIES' REFUELING October 1989 INFORMATION REQUEST 1. Unit' g2 Relcad: 10 Cycit: 11 2. Scheduled date for next refueling shutdown: 12-28-91 3. Scheduled date for restart following refueling: 3-7-92 4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment: NOT AS YET DETERMINED. 5. Scheduled date(s) for submitting proposed licensing action and supporting information: NGI AS YET DETERMINED. 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or suppiter, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: NONE AT PRESENT TIME. 7. The number of fuel assemblies, a. -Number of assemblies in core: 724 b. Number of assemblies in spent fuel pool: 2287 s- - 8. - The'brcsent-licensed spent fuel pool storage capacity and the size of any trerease in licensed storage capacity that has 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 prcjected date of the last refueling that can be discharged to the spent fuel pool assuming tne present licensed capacity: 2009 APPROVED i (final) 00T 3 01969 14/0395t Q.C.O.S.R.

c l l VIII. GLOSSARY 1 I The following abbreviations which may have been used in the Monthly Report, are defined below: ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring tNSI - American National Standards Institute APRM - Average Power Range Monitor ATHS - Anticipated Transient Hit:out Scram BHR - 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 l HPCI - High Pressure Coolant Injection System HRSS - High Radiation-Sampling System IPCLRT - Integrated 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 Permissibic Concentration MSIV - Main St]am Isolation Valve NIOSH - National Institute for Occupational Safety and Health PCI - Primary Containment Isolation PCIOMR --Preconditioning Interim Operating Management Recommendations _ i RBCCH - Reactor Building Closed Cooling Water System l RBM - Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal System RPS - Reactor Protection Systea RHM - Rod Horth Minimizer SBGTS - Standby Gas Treatment System l SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV - Scram Discharge Volume SRM - Source Range Monitor 'TBCCH - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center TS 14 L -}}