ML20101Q572

Monthly Operating Repts for June 1992 for Quad Cities Units 1 & 2

ML20101Q572
Person / Time
Site:	Quad Cities
Issue date:	06/30/1992
From:	Michael Benson, Tietz G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GCT-92-29, NUDOCS 9207150013
Download: ML20101Q572 (22)

Text

{{#Wiki_filter:.- E,, Commonwealth E%.1 o-Ou'd Cities Nuct;st Pow:r St: tion 22710 206 Avenue North Corcova, Illinois 61242 Telephone 309/0$4 2241 GCT-92-29 July 2, 1992 L I U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report HRC_RochcLNoL30-25LanL10-265 Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the L month of June 1992. Respectfully, COMMONHEALTH EDISON COMPANY p QUAD-CITIES NUCLEAR POWER STATION CmA C 7L F Gerald'C.-Tietz ( Technical Superintendent GCT/HB/dak~ I Enclosure cci 'A. B. Davis, Regional Administrator I T. Taylor, Senior Resident Inspector-f R PDR

~ li d4 t t 'i n QUAD-CITIES NUCLEAR POWER STATION f UNITS 1 AND 2 HONTHLY PERFORMANCE REPORT ') ^76 JUNE 1992 COHHONHEALTH EDISON COMPANY AND IDHA-ILLIN0IS GASL& ELECTRIC COMPANY 4 ' NRC DOCKET N05. 50-254 AND 50-265-LICENSE NOS. DPR-29 AND DPR-30 s 6 1914

. _. ~ - _ _ .1 0 T/.BLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. 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 Reports V. Data Tabulations A. Operating Data Report B. Average Dal2y Unit Power Level C. Unit Shutdowns and Power Reductions VI.- Unique Reporting Requirements A. Main Steam Relief Valve Operations B.. Con'crol Rod Drive Scram Timing Data VII. l Refueling Information VIII. Glossary-

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I. INIRQDUC110N 4 Quad-Cities Nuclear Power Station is composed of two Loiling 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 Siwam Supply Systems are General Electric Company Boiling Hater 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 Hatt Benson and Debra Kelley, telephone number 309-654-2241, extensions 2995 and 2240. TS t4

II. SUMt1AILLOLDEERAIINGRP_IRIENCE A. Unit _Qat Quad Cities Unit One began the month of June in a maintenance outage for tube repair on the main condenser. The Unit was brought back on line on the 2nd of June. Another maintenance outage, occurred from June 13 through June 15, for additional condenser tube repair. Full power for the Unit One declined over the month due to the unit being in coast down for the upcoming refuel outage. The significant load reductions ordered by Chicago Load Dispatch occurred on; June 5 to 630 MWe, June 7 to 600 MWe, June 8 to 700 MWe, and June 9 to 500 MWe. B. Unli_Iwo Quad Cities Unit Two performed a load drop per Chicago Load Dispatch on 1 June 4 to 500 MWe. On June 6, Unit Two reduced power to 450 MWe and held due to increased off gas flow. Power, on June 6, was returned to full and reduced a second time to 450 MWe due to increasing condenser L back pressure. Unit Two's power remained between 450 MWe to as low as 180 MWe, due to low condenser back pressure and high off gas flow, untti condenser leak repairs were complete on June 14. Chicago Load Dispatch requested the following additional loc.d drops for Unit Two for the nonth of June; Dale Load 06-18-92 468 MWe 06-19-92 550 MWe 06-20-92 700 MWe 06-21-92 250:MWe 06-23-92 650 MWe 06-25-92' 700'MWe 06-28 550 MWe 06-29-921 700 MWe On June 27_ Uni t Two generat< kitput was red' iced to-700 MPe for a turbine surveillance.- l L ' 4 14 ,n, n e--

III. ELANLOR PROCEDURE _ CHANGE 1._lESIlmEXEERIliEMIS. AND_SAELILRELAIED_lBIRIEtt& lice A. Amendments to Fac11(tL11CEDiLor_Itchnical Sancff_itationi There were no Amendments to the Facility License or Technical Specifications for the reporting period. D. EAC111ty_oL2rocedure_. Change.i_ Requiring NRC Appron1 There were no facility or Procedure changes requiring NRC approval for the reporting period. C. Tests and ExoerimentLRe.nutring_NRC_Appron1 There were no Tests or Experiments requiring NRC approval for the reporting period. D. CorttctiVe Maintenancs_oLSaf.e.tLRelAteLEaulpment The following represents a tat,ular summary of the. major safety related maintenance performed on Units One and Two during the reporting period. This summary includes the following: Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Halfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition. I 18 14 - i

~ UNIT'1 MAINTENANCE

SUMMARY

HORK REOUEST SYSTEM EID DESCRIPTIQM HORK PERFORMED QO1006-2406 Repair Oxygen-Hydrogen recorder As Found: Recorder pegged high when turned on. failed.up-scale. As left: The recorder read in normal range after -being turned on for 1 1/2 hours. Solution was sufficient time to stabilize after energizing record panel. Q01180 1705 MSL rad monitor down scale As Found: Bypassed the 1 Rx Bldg vent monitor and reactor building fuel pool vent MSL downscale alarm came.up with no indication cn rad monitor calibration. bypass monitors. As Left: Suspected short between leads. switch trouble. required lifting and jumping various leads to isolate. No short found. Problem disappeared with no MSL down scale alarm w/ process rad monitor in bypass. Q01274 0312 SCRAM inlet valve leaking water, As Found: Valve packing was leaking. As Left: repair / repack.- Installed new packing and set seating pressure and spring tension. 7 i-TS 15 .1 w

m UNIT 2 MAINTENANCE hfMMARY HORK REOUEST SYSTEM EID DESGIPTION HORK PERFORMEQ Q01292 -2499 Maintenance for valve cam check As Found: Valve cover appeared to not be on all which failed LLRT. the way. As Left: Gasket had been installed wrong. New gasket installed and cover tightened. I l 1 TS 15 i

5 g ? IV, LICENSEE EVINLREEQRIS 4 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 reportablo occurrence reporting requirements a:, ::et forth in sections 6,6.B.! and 6.6.B.2 of the Technical Specifications. UHLL1 h, Licensee Event- "d* RenotLNumber Date Ittle_of_Quurrenca 92-013 06-09-92 Logic deficiency in the SBGT Logic. 92-016 06-26-92 Missed Tech Spec Surveillance un Fire Valve. ) URLL2 92-018 05-29-92 Manual Isolation of HPCI System. 97 '9 06-06-92 Hi Rad Area door lock malfunction (Hotwell Door). 92-020 06-12-92 "R" Gate Found Open. 92-021 06-23-92 Offgas Isolation. 7 s l ' Ta 14

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g. W V, DAIA_TABULAT10ti$ ' The-following. data-. tabulations are-presented in this report: L A.- _ Operating Data _ Report' 3 B. Average Daily Unit Power Level - C, Unit Shutdowns and Power Reductions '? h 0 1 ~e t, t L \\ t t i 9 1 '.? R E l '7.. 1 ':yj c\\: rVs', :~-k ' ' ^ ([@'_% fi s [_ in g :. t .'-~ l:i.R' 3 p S,m;. --o +, --,;: #.s,. _ ,,l l::I-.b;[ll; & ' ; ,i -j ;. r la t ti ,. 3 ',l

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y, c -APPENDIX C ~ ~ OPERATING DATA REPORT DOCKET "o 5A-154 UNn ov.. DATE July 2 1922 COMPLETED BY tlaiLRenion TELEPHONE D091 65f-2241 OPERATING STATl;S 0000 060192 -1. REPORTING PERIOD: 2.4.00 -_Q&399L GROSS HOURS IN REPORTING PERIOD: 220

2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511 HAX. DEPEND. CAPACITY: 769 DESIGN ELECTRICAL RATING (HWe-Net): IB9

3. POWER LEVEL TO Wii!CH RESTRICTED (if

• ."Y) (HWe-Net N/A

4. PFASONS FOR RESTRICTION (IF ANY):-

THIS HONTH YR TO DATE CUHULATIVE

S. NUMBER OF HOURS REACTOR WAS CRITICAL...........

644.lQ 3971.69 _,,, L4Q4&hZQ .6. REACTOR RESERVE SHUT!CWU "OURS.................. 0.0 0.0_ 3421.L

7. HOURS GENERATOR ON LINE........................

_622dQ 3931.20 136162.30 .v

8. UNIT RESERVE SHUTDOWN HOURS.....................

0.0_ 00 909.2 2

9. GROSS THERHAL ENERGY GENERATED (HWH).............

1421217.60 9437121.60 293504144.fA

10. GROSS ELECTRICAL ENERGY GENERATED (HWH)..........

450504.0 3062333.0-95136669.0 11; NET ELECTRICAL ENERGY GENERATED ("MH)........... 428921.0 2954096.0 89664264.0

12. REACTOR SERVICF. FACT 0R.............

89.45 90.95 79.26 13'. REACTOR AVAILABILITY FACTOR..................,.. ,_ JLA6 90.95 81.19

14. WIT SERE CE FACTOR............................

86.4Q-90.02 -76.82

15. UNIT AVAILABILITY FACTOR........................

86.40 9hDZ 77 3.4

16. UNIT CAPACITY FACTOR:(Using HDC)................

77.47 87.99 65.79 -17. UNIT CAPACITY FACTOR (Using Design HWe)... i... 75.50 85d6 64.11 --18.'UNITLFORCED OUT GE RATE-.................'......... -13JQ. 10.0Q 5.85 ~19. SHUTDOWNS SCHEDULED OVER NEXT 6'HONTHS (TYPE. DATE. AND DURATION OF EACH):

20.'IF_ SHUTDOWN _AT END OF REPORT PERIOD.'EST! HATED DATE OF STARTUP

';+

21. UNIT $ IN TEST STATUS (PP.IUR TO COMMERCIAL-OPERATION):

g FORECAST ACHIEVED I NITIAL CRITICALITY I

~ INITIAL ELECTRICITY. ~ ~COHHERCIAL OPERATION c -L Ts W 1.16-9 A m__.__

APPENDIX C 0 PIRATING DAVA REPORT DOCKET NO 50-265 )_ -UNIT Inn DATF.htly 2.1992 COMPLETED BY Ma.tLitepson IELEPHONE 1302L6541241 2 OPERATING STATVS 0000 060192 1.; REPORTING PERIOD: _2ARO 06309L GROSS HOURS IN REPORTING PERIOD: _Z20

2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511 HAX. DEPEND. CAPACITY: 769 DESIGN ELECTRICAL RATING (HL'e-Net): 789..,_

3. POWER LEVEL TO WHICH RLbTRICTED (IF ANY) (tMe-Net): N/A

-44 REASONS FOR RESTRICTION (IF ANY): THIS HONTH YR TO DATE CUMULATIVE '5. NUMBER OF HOURS REACTOR WAS CRITICAL............ 720.00 _ 1275_J5. 134758.2h

6. REACTOR RESERVE SHUTDOWN HOURS.................

0.0 0.D_ 2985.8

7. HOURS GENERATOR ON LINE.........................

720.0Q 120AJS 131224.45-

8. UNIT RESERVE SHUTDOWN H0VR$'.....................

0.0 0.0 - 702JL 9.' GROSS THERHAL ENERGY GENERATED (HWH)............. J3Z1112A 2181116 30-1824E5D02 E - 10. GROSS ELECTRICAL ENERGY GENERATED (HWH).......... 445726 & 765827.QQ _9D696017.0Q ' ll.: NET ELECTRICAL ENERGY GENERATED (HWH)............ __.124231.0D 2.q611LDD _85840316 2 12.~ REACTOR SEbrICE FACT 0R........................... 100.00_ '29.21 76.71 li, REACTOR AVAILABILITY FACIOR.,................... 100.00_ 29.21 _Jbal 4

14. UNIT SERVICE FACTOR.......;....................

100.00 27.58- '74.70

15. UNIT AVAILABILITY FACTOR.......................

100.00 21.58 _ _ZL1R

16. UNIT CAPACITY FACTOR (Using HDC)................

76.62 21.03 ~ 63_d4 hs

17. UNIT CAPACITY FACTOR _(Using Design HWe).........

766fL-20.49 61,93 '- 18. UNIT FORCED OUTAGE RATC......................... 0.0 0.0 6.02 4

19. SHUTDOWNSTSCHEDULED OVER NEXT 6 PONTHS (TYPE, DATE, AND DURATION OF EACH):

20._IF SHUTDOWN AT END OF REPORT PERIOD.' ESTIMATEU DATE OF STARTUP;

21. UNITS ~IN TEST STATUS (PRIOR TO COHHERCIAL_0PERATION):

FORECAST: ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY $ C08tfERCIAL OPERATION - 1.16-9 T81417 +

e e APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCK'tT NO 50-254 UNIT One DATE July 2.1192 COMPLETED BY Hatt Benson TELEPHONE (309) 654-2241 -HONTH JuDe 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net) (HWe-Net) 1. -8 17. 744 g- ?. 101 18, 736 3. 647 19, 731 4, 764 20. 734 .5. '729 21. 727-

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-768 22. 709 7, 726-2a. 707 8. 749' 24. 701 9.- 695 25. 705 l 10, 7561, 26. 700 . c. 11. 744 27. 652

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695 28. 657 13 s 7-29. 679 '14;

8 30.

651 15, 39 '31. 16. ~62; . INSTRUCTIONS -On this-form,-ilist the average daily unit-pot?r level in MWe-Net for each' day, inithe reporting month. Compute -to the tieara.t whole megawatt. .These figures will_ be.used to plot'a graph for each reporting month. Note that_when maximum dependable capacity is used for the net electrical-rating of _the Unit,-there may be occasions when'the daily average power level exceeds the 1007.111ne'(or che restri_r.ted power level lino). In such cases, the-c . average dailyiunit power output sheet should-be footnoted to explain the ap' parent anomaly.- _1.16-8 Tm - n. -Y- .1 -{',

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APPENDIX 8 AVERAGE DAILY UNIT PUHER LEVEL 00CKEI NO 50-1E5 a UNIT Lwq DATE July 2. 1932 COMPLETED BY Matt Bensen TELEPHONE 1301L151-2241 MONTH Jne_J992 i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAlli iM ER LEVEL y~ ~ (HWe-Net) (MWe-Net) 1. 784 17. 777 2.- 785 18. 701 ~3. 771 19. 726 4. 66L 20. 735 _S. 776 21. 539 1 -6. 465 22, 718 7. '367 2 3 '. 761 ' 81 - 310 24. 776 i; t f 9. 270 25. 754 6 10.- 330 26. 179 W 'll, 153

27. _

742 21 2. 38 28, 717 13. '102 79. 755. 14. 1121 30, 780 15. 642 31. -16. 771 INSTRUCTIONS-h this form, list the average daily unit power level in MRa-Net for each day Lin t;;e repo-ting month. Compute to the nearest whole megawatt. These__ figures willibe used to plot a graph for each reporting month. Note , i that-when tr.aximum: dependable capacity is used for the net elettrical rating of Lthe. unit,:there nny be occasions when tne daily average power level exceeds T, the 1001,line (or the' restricted power level line). In s.uch cases, the. s average daily unit-power output sheet should be footnoted to explain the-s . apparent anomaly,

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33_3 g 9 =c s. 4 e APPENDIX D UNITJSHUTDOWNS AND POWER REDUCTIONS + ' DOCKET NO. 50-254 " UNIT NAME' Unit 0ne' COMPLETED BY Matthew Benson ~

DATE'

. July 2, 1992 2 REPORT HONTH Ju;.e, 1992 TELEPPONE 309-654-2241 A i g Do$ ' co x zo x w sal O Q NW-Z ta3 g @. j j ' LICENSEE i' DURATION 7 EVENT 'o V g g- 'NO. . DATE. '(HOURS) u REPORT NO. CORRECTIVE ACTIONS / COMMENTS o . l o 92-23 6-1-92 'F-3516' .B -4 Continued Cond. Tube Repair 92-24 6-5-92.- 'S 4.5 -F; 5 Load Nop per Chicago Load Dispatcher 92-25 6-7-92 5 4.6 F .5 Lead Drop per Chicago Load Dispatcher 92-26 6-8-82 S 2.8 F- -5 Load Drop per Chicago Load Dispatcher 92-27 6-9-92 S 5.9 F 5 Load Drop per Chicago Load Dispatcher 92-28 6-13-92 F 62.3 .B 2 Cond. Tube Repair . (final)

":J.a. / y ~- v7 ~ e9 ~ m. ..v n 3 1Y i ~ .APPEFDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS- <-DOCKET NO. 50-265' UNIT'NAME' Unit Two ' COMPLETED BY Matthew Benson

DATE July 2,.1992 REPORT MONTH Jt. ne, 1992 TELEPHONE 309-654-2241 n

b e t;.. M m x .W o Q w <:. m. w x 93 c:3 hi ta3 'g $ $L gym LICENSEE. M@_ . g., DURATION M' gMg. EVENT U o" NO. DATE (HOURS). REPORT NO. COPJtECTIVE ACTIONS / COMMENTS g 92 6-04-92 S 17.1 F 5 Load Drop per Chicago Load Dispatcher ' 9 2-06 '. 6-06-92 F 8.6 D 5 Increased Off Cas/Cond Leak 92-07 6-06-92 P' 202.0 D 5 Increased Off Gas /Cond Leak 92-08 6-18-92 S '6.9 F~ .5 - Load Drop per Chicago Load Dispatcher 92-09 6-19-92 S. 4' 8 F 5 Load Drop per Chicago Load Dispatcher 92 26-92 S 6.6 F 5 1-Load Drop per Chicago Load Dispatcher 92 '6-21-92 S 35.0 F 5 Lord Drop per Chicago Load Dispatcher 92-12 6-23-92 .S '2.9 F 5 Load Drop per Chicago Load Dispatcher 92-13 6-25-92 S 5.0 F 'S Load Drop per Chicago Load Dispatcher 92-14 6-27-92 5' 7.6 B .5 Turbine Weekly Test 92 6-28-92 S 6.3-F 5 Load Drop per Chicago Load Dispatcher 92-?6 6-29-92 S-4.3 F 5 Load Drop per Chicago Load Dispatcher ! (final)

s f VI. URIQUEJEPORTING REQUIREMEtil$ The following. items are included in this report based on prior commitments to-the commission: A. Stin1tenLRellef Valte_Qaerallom There were no Main Steam Relief Valve Operations for the reporting period. B. ControLROLDrive 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 Technical Specifications 4.3.C.1 and 4.3.C.2. The following table is a complete summary of Units One and Two Control %d Drive Scram Timing for the reporting period. All scram timing was performed with-teactor pressure greater than 800 PSIG. I C 't. 22=_ _ _. _- _ +_ __ __

~ e J RESilLTS OF SCRWTfMING HEASURENENTS ~ . PERFORMED ON UNIT 1 & 2 CONTROL- _' ROD DRIVES, FROM 1-92 TO'12-31-92 y 1 AVERAGE. TIME IN SECONDS AT.1 . MAX. TIME .l ~~ INSERTED-FROM FULLY HITHDRAWN FOR 901 INSERTION DESCRIPTION NUMBER 5 20 50 90 Technical Specification 3.3.C.1 & DATE' OF RODS 0.375 0.900' 2.00 3.5 7 sec. 3.3.C.2 (Averace Scram Insertion Time) 2-19-921 2-0.28 0.67l 1.43 2.48 J Drive Replacement (J-2), Scrau Valve N-7 2.55 2-20-92 1 0.32I 0.69 1.45 2.45 -N-5 Scram Valve Work N-5 2.45 '5-12-9?' 177 0.31 0.69 1.47 2.58 L-13 Start-up Scram Timing Unit Two 3.43 6-02-92 1 0.31 '0.65 11.37 2.35 N-5 Scram Valve Work 2.35 6-26-92 2 0.27-0.62 1.32 2.32 C-13 ACCUM C-13, N-7 2.26 TS 75 I' .c

A t ^ VII. REFUELIBG INFORjMIJDN The following information about future rcloads 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. 2 (I A TS 14 i I:-- '. f-

QTP 300-S32 Revision 2 QUA0 CITIES REFUELING Oc hher 1989 INFORMATION REQUEST 1. Unit: Q1 Reload: 11 Cycle: 12 2. Scheduled date for next refueling shutdown: 9-5-92 3. Scheduled date for restart following reftvling: 12-5-92 4. Will refuciing or resumption of operation thereefter require a Technical Specifica.tlon change or other license amendment: 1. Modification to HPCI turbine exhaust steam line. S. Scheduled date(s) fo. submitting proposed licensing action and supporting information: 1. 06/30/92 6. Important licensing considerations associated with refceling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel destgn, new operating procedures: NONE AT PRESENT TIME, M 7. The number of fuel assemblies. 6-a. Number of assemblies in core: 724 g d-b. -Number of assemblies in spent fuel pool: 1405 -8. The present licensed spent fuel pool stnrage 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: 3657 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 APPROVED 14/0395t -l OCT 3 01989 )l O.C.O.S.R.

~ w ^ QTP 300-532= t Revision 2-QUAD CITIES REFUELING October 1989 'INFORMATION REQUEST '1. -Unit: - Q2-Reload: _ 11 12-Cycle: -2. Scheduled date:-for next refueling shutdown: 03/06/93 3. -- -Scheduled date for restart. following refueling: 06/05/93

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Will refueling or resumption of operation thereaf tcr require a Technical Specif_lcation change or other license amendment

y NOT-AS YET DETERMlNED. 75 Scheduled'date(s) for submitting proposed licensing action and , supporting:information: NOT AS YET DETERMINED.- 6. Important -.11 censing: considerations asso;1ated with refuel 1ng, e.g... new . or-different fuel' design or supplier,'unroviewed design or performance . analysis methods, significant changes-in fuel 6 sign,-new operating . procedures: _ NONE AT PRESENT TIME.- 7. The' number of fuel. assemblies.

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, Number of' assemblies In-core: 724 ' b.- Number of assemblies in spent-fuel pool: 2439 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:. c

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Licensed storage capacity for spent fuel: 3897 b.. Plannad increaro in licerded storage: 0 9. The' projected date of;the lastirefueling that can be_ discharged to the spent fuelfpool-assuming' the present 1icensed capacity: "2009 ~ m APPROVED w' (final)- 00T 3 01989-414/0395t-G.C.O.S.R. a w -w -t t 4 3 M ~ 9 Ea--l M ey T

l3 x pr: VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below: ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI - Araerican National Standards Institute APRM - Average Power Range Monitor ATHS- - Anticipated Transient Without Scram BHR- - Boiling Hater Reactor CRD- - Coniti Rod Drive .EHC - Electro-Hydraulic Control System EOF- - Emergency Operations Fac'.lity GSEP - Generating Stations Emergency Plan HEPA - High-Efficiency Particulate Filter HPCI - High Pressure Coolant Injection System HRSS - High Raoiation 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 Dlanar Linear Heat G0neration Rate MCPR - Minimum Critical Power Ratio MFLCPR- - Haximum Fr.iction Limiting Critical Power Ratio MPC- - Maximum Permissible Concentration MSIV ~- Main Steam Isolation Valve .MIOSH - National Institute for Occupational Safety and Health-PCI- - Primary Containment Isolation PCIOMR - Preconditioning Interim Operating Management Recommendations-RBCCH. - Reactor Building Closed Cooling Hater. System RBM - Rod Block Monitor RCIC --Reactor = Corr Isolation Cooling System RHRS - Residual Heat Removal System 'RPS- - Reactor Protection System RHM ,- Rod Horth Minimizer SBGYS ' - Standby Gas Treatment System SBLC - Standby Liquid: Control SDC. - Shutdorin Cooling ModeHof RHRS SDV_ - Scran. Discharge _ Volume - 4SRM-Source Range konitor TBCCH .- Turbiacc Building Closed Cooling Hater Systen

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