View source for SVP-98-249, Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2

{{Adams
| number = ML20236P368
| issue date = 06/30/1998
| title = Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2
| author name = Dimmette J, Hamilton L
| author affiliation = COMMONWEALTH EDISON CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000254, 05000265
| license number = 
| contact person = 
| document report number = SVP-98-249, NUDOCS 9807160283
| document type = MONTHLY OPERATING ANALYSIS REPORT, TEXT-SAFETY REPORT
| page count = 20
}}

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* Ownmonwealth Edi on Company Quad Otics Generating Station
  . _ ,'- Q' *#        22710 2(Kith Avenue North
  /                    G>rdova, IL 612 42-9740 Tei .w>6s 4-2m SVP-98-249 July 10,1998 U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention:         Document Control Desk

==Subject:==
Quad Cities Nuclear Power Station Units 1 and 2 Monthly Performance Report NRC Docket Numbers 50-254 and 50-265 Facility Operating License Numbers DPR-29 and DPR-30 Enclosed for your information is the Monthly Performance Report covering the operation of Quad Cities Nuclear Power Station, Units One and Two, during the month of June 1998.
1 If you have any questions or comments concerning this letter, please refer them to                                                  j Mr. Charles Peterson, Regulatory Affairs Manager, at (309) 654-2241, ext. 3609.
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Si erely, ,
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J$el P. Dimmette, Jr S(te Vice President                                                                                                                 j Quad Cities Station

==Attachment:==
 " Monthly Performance Repon" cc:        C. J. Paperiello, Acting Regional Administrator, Region 111 R. M. Pulsifer, Project Manager, NRR C. G. Miller, Senior Resident Inspector, Quad Cities                                                                     l W. D. Leech, MidAmerican Energy Company                                                                                  {
D. C. Tubbs, MidAmerican Energy Company Office of Nuclear Facility Safety, IDNS INPO Records Center l                                                                                                                                                 f i                                                       .-                                                                                      !
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d 9007160283 900630 i                 PDR      ADOCK 05000254 l                  R                         PM A Unimm Company N__________--_.

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_ QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JUNE 1998 COMMONWEALTH EDISON COMPANY AND MIDAMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 i
LICENSE NOS. DPR-29 AND DPR-30 l'
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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 IVi           Licensee Event Reports V.            Data Tabulations A.                     Average Daily Unit Power Level
      ,                              B.                     Operating Data Report -
CJ                      Unit Shutdowns and Power Reductions VI.           Unique Reporting Requirements L,                                 'A.                       Main Steani Relief Valve Operations B.                      Control Rod Drive Scram Timing Data i
l-                     VII.          Refueling Information Vill. Glossary l.
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I. INTRODUCTION Quad Cities Nuclear Power Station is composed of two Boiling Water Reactors and Steam Turbine / Generators, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and MidAmerican Energy Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1,1971, and March 21,1972, respectively; pursuant to Docket Numbers 50-254 and 50-265. The date ofinitial Reactor criticalities for Units One and Two, respectively were October 18,1971, and April 26,1972. Commercial generation of power began on                             I February 18,1973 for Unit One and March 10,1973 for unit Two.
This report was compiled by Lynne llamilton and Debra Kelley, telephone number 309-654-2241, extensions 3114 and 2240, respectively.
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==SUMMARY==
OF OPERATING EXPERIENCE A.             Unit One Quad Cities Unit One began the month of June 1998 with the reactor critical. On June 1,1998, at 9:20 p.m., Unit One was synchronized to the grid. On June 2,1998, at 4:45 a.m., a level control valve began to cycle erratically causing a hydraulic transient in which three pipe supports were broken and insulation was shaken off of the piping to the Moisture Separator Drain Tank. On June 4,1998, at 9:15 a.m., the generator was taken off-line. Unit One remained at 25% thermal power while welding repairs were made on the inlet and outlet pipes of the Moisture Separator Drain Tank. On June 5, 1998, at 3:48 a.m., Unit One was synchronized to the grid. On June 27, at 5:11 p.m., an automatic scram occurred on Unit One due to a malfunction of one of the Scram Discharge Volume switches. The switch was replaced. Start-up activities commenced on June 29. The reactor went critical at 12:15 p.m. on June 29,1998, and Unit One was synchronized to the grid at 2:50 p.m. on June 30,1998.
B.            .lJnit Two Quad Cities Unit Two began the month of June,1998 operating at full power. On June 5,1998 at 9:25 p.m., Unit Two was taken off-line to repair a faulty solenoid on the No. 2 Combined Intercept Valve. On June 6,1998, at 10:40 a.m., Unit Two was synchronized to the grid. On June 14,1998, at 3:30 a.m., Unit Two was taken off-line due to a leak discovered on the Main Turbine #3 Control Valve EHC line. The leak was repaired, and on June 14,1998 at 10:35 p.m., Unit Two was synchronized to the grid.
Unit Two was brought to full power. On June 28,1998, at 2:23 a.m., an automatic scram occurred when severe lightning caused a generator differential trip due to a downed pilot wire on offsite high voltage lines. Start-up activities commenced on June 30,1998, and the reactor went critical at 8:54 a.m.
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III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.
AND SAFETY RELATED MAINTENANCE A.         Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period. However, the following changes to the Technical Specification Bases were received:
May 26,1998 - Bases Section 3/4.5.A,"ECCS [ Emergency Core Cooling System]-
Operating". The second sentence in the seventh paragraph states,"The HPCI pump is designed to deliver greater than or equal to 5000 gpm ut steam supply pressures between 1150 and 150 psig." The number 1150 was changed to 1120 to reflect the correct pressure.
June 11,1998 - Bases Section 3/4.4.A," Standby Liquid Control System" erroneously stated, "A net quantity of 3245 gallons of solution..." The net quantity of solution was changed in error from 3254 to 3245 gallons when TS Bases page B 3/4.4 1 was last issued.
June 17,1998 - Bases Section 3/4.5.C, " Suppression Chamber" requires in MODE (s) 4 and 5 that the water level in the suppression chamber can be less than 7 foot above the bottom of the suppression chamber provided that among other limitations the condensate storage tank (CST) contains > 140,000 available gallons of water. The Core Spray and Residual Heat Removal system suction standpipe was lowered in the CST to ensure this quantity of water can be available. Comed performed an evaluation pursuant to 10 CFR 50.59.
I B.         Facility or Procedure Chances Reauirine NRC Anomval There were no Facility or Procedure changes requiring NRC approval for the reporting period.
C.         Tests and Experiments Reauirine NRC Annroval There were no Tests or Experiments requiring NRC approval for the reporting period.
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   'b IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two submitted during the reporting period.
UNIT 1 Licensee Event                Submission Renon Number                  Date                               Title of Occurrence There were no Unit 1 LER's sent out during the month of June,1998.
UNIT 2 Licensee Event                Submission Renort Number                 Date                               Title of Occurrence 98-02                         6/26/98                             On June 9,1997, Hydrogen Samples Were Not Collected in Accordance with Technical Specification (TS)
Surveillance Requirements Due to a Misinterpretation of the TS Requirement.
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i r-V. DATA TABULATIONS
: The following data tabulations are presented in this report:
A. Average Daily Unit Power Level B. Operating Data Report i
!-                                  C. Unit Shutdowns and Power Reductions l
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    'O APPENDIX B
                                                            .                      AVERAGE DAILY UNIT POWER LEVEL                                                                                                 j DOCKET NO.:  50-254                      i UNIT: ONE DATE: July 10,1998
                                                                                                                                                                     . COMPLETED BY: Lynne Hamilton TELEPHONE:  (309)654-2241 MONTH: June 1998                                -
DAY AVERAGE DAIL.Y POWER LEVEL                                                                                DAY AVERAGE DAILY POWER LEVEL (Mwe-Net)                                                                                              (Mwe-Net)
: 1.                                       0                                                                           17.                   771
: 2.                                    106                                                                             18.                   770
: 3.                                    101                                                                             19.                   770
: 4.                                      32                                                                            20.                   769
: 5.                                    175                                                                             21.                   752
: 6.                                   487                                                                              22.                   768
: 7.                                   602                                                                              23.                   768
: 8.                                   719                                                                              24                    766
: 9.                                   773                                                                              25.                   765 10,                                  768                                                                              26.                   762
: 11.                                  774                                                                              27.                   538
: 12.                                 774                                                                              28.                   -13 13,                                  714                                                                              29.                   -12
: 14.                                  769                                                                              30.                    16
: 15.                                  775                                                                              31.
: 16.                                  772 l
l                                    INSTRUCTIONS: On this form, list the average daily unit power level in MWe-Net for each day in the reporting i                                    month. Compute to the nearest 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 100% line (or the restricted power level line). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.
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!                                                                                                                                        APPENDIX B
                                                                                                           .                    AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:   50-265 UNIT:  TWO
;                                                                                                                                                                  DATE:   July 10,1998 l-                                                                                                                                                         COMPLETED BY:   Lynne Hamilton TELEPHONE:   (309)654-2241 MONTH: June 1998 l
l L                                                                          , DAY AVERAGE DAILY POWER LEVEL                                           DAY AVERAGE DAILY POWER LEVEL
(                                                                                                                     (MWe-Net)                                (MWe-Net) f-                                                    1.                                                                    742                  17.                 765 I                                                   2.                                                                      760                  18.                 766 3,                                                                     764                  19.                 767
: 4.                                                                      760                  20.                 766 l                                                    5.                                                                     549                  21.                 765 i                                                    6.                                                                     187                  22,                 764
                                                                                                                                                                                         ~J
: 7.                                                                     714                  23,                 763                           i
: 8.                                                                     710                  24.                 762
: 9.                                                                      769                  25,                 760 l
l                                                     10.                                                                   767                  26.                 762 11,                                                                   768                  27.                 762
: 12.                                                                   770                  28,                  62
: 13.                                                                   769                  29.                 -12
: 14.                                                                    91                  30.                 -12
: 15.                                                                   389                  31.
: 16.                                                                   718 INSTRUCTIONS: On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. These figures will 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 l                                                   occasions when the daily average power level exceeds the 100% line (or the restricted power level line). In such L
cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.
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                                                                            ,                               APPENDIX C OPERATING DATA REPORT DOCKET NO.: 50-254 UNIT: One DATE: July 10,1998 COMPLETED BY: Lynne llamilton TEEPIIONE: (309) 654-224i OPERATING STATUS 0000 060198
: 1. REPORTING PERIOD: 2400 063098 GROSS IIOURS IN REPORTING PERIOD: 720
: 2. CURRENTLY AUTIIORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789
: 3. POWER LEVEL TO WillCH RESTRICTED (IF ANY)(MWe-NET): N/A
: 4. REASONS FOR RESTRICTION (IF ANY):
                                                                                                                                       ' THIS                     YEAR TO DATE                              CUMULATIVE 5, NUMBER OF llOURS REACTOR WAS CRITICAL                                                                            677.00                          694.40                               173069.80
: 6. REACTOR RESERVE SHUTDOWN HOURS                                                                                     0.00                            0.00                                 3421.90
: 7. IlOURS GENERATOR ON LINE                                                                                         610.50                          610.50                               167905.80
: 8. UNIT RESERVE SilUTDOWN llOURS                                                                                      0.00                            0.00                                  909.20
: 9. GROSS TIIERMAL ENERGY GENERATED (MWil)                                                                       1320628.80                      1320628.80                            366757871.40
: 10. GROSS ELECTRICAL ENERGY GENERATED (MWII)                                                                    419223.00                       419223.00                            118672592.00
: 11. NET ELECTRICAL ENERGY GENERATED (MWH)                                                                       397077.00                       397077.00                            106552046.00
: 12. REACTOR SERVICE FACTOR                                                                                          94.03                           15.99                                   75.31
: 13. REACTOR AVAILABILITY FACTOR                                                                                    94.03                           15.99                                   76.80
: 14. UNIT SERVICE FACTOR                                                                                            84.79                           14.06                                   73.06
: 15. UNIT AVAILABILITY FACTOR                                                                                        84.79                           14.06                                   73.45
: 16. UNIT CAPACITY FACTOR (Using MDC)                                                                                71.72                           11.89                                   60.29
: 17. UNIT CAPACITY FACTOR (Using Design Mwe)                                                                         69.90                           11.59                                   58.76
: 18. UNIT FORCED OUTAGE RATE                                                                                         12.25                            0.03                                    7.21
: 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTilS (TYPE, DATE, AND DURATION OF EACll):
Refuel, 11/07/98,40 days.
: 20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A
: 21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST                       ACIIIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERAITON 1.16-9 TECHOP3\NRC\MONTHLYRPT. DOC l
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, 's 1 o APPENDIX C OPERATING DATA REPORT DOCKET NO.: 50-265 UNIT: Two DATE: July 10.1998 COMPLETED BY: Lynne llamilton TELEPIlONE: (309) 654-2241 OPERATING STATUS 0000 060198
: 1. REPORTING PERIOD: 2400 063098 GROSS IIOURS IN REPORTING PERIOD: 720
: 2. CURRENTLY AUTIIORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789
: 3. POWER LEVEL TO WillCil RESTRICTED (IF ANY) (Mwe-NET): N/A
: 4. REASONS FOR RESTRICTION (IF ANY):
TIIIS MONTil YEAR TO DATE         CUMULATIVE
: 5. . NUMBER OF IIOURS REACTOR WAS CRITICAL                                                 665.50           875.25         165242.30
: 6. REACTOR RESERVE SIIUTDOWN HOURS                                                             0.00           0.00           2985.80
: 7. HOURS GENERATOR ON LINE                                                                 618.00           759.30         160729.15
: 8. UNIT RESERVE SIIUTDOWN 110URS                                                               0.00           0.00            702.90
: 9. GROSS TIIERMAL ENERGY GENERATED (MWil)                                              1492269.60       1710808.80      350067065.12
: 10. GROSS ELECTRICAL ENERGY GENERATED (MWH)                                            469183.00        531197.00      112293741.00
: 11. NET ELECTRICAL ENERGY GENERATED (MWil)                                              448289.00        502397.00 -    106449855.00
: 12. REACTOR SERVICE FACTOR                                                                    92.43          20.15             72.39
: 13. REACTOR AVAILABILITY FACTOR                                                               92.43          20.15             73.70
: 14. UNIT SERVICE FACTOR                                                                       85.83          17.48             70.42
: 15. UNIT AVAILABILITY FACTOR                                                                  85.83          17.48             70.72
: 16. UNIT CAPACITY FACTOR (Using MDC)                                                          80.97          15.04             60.64
: 17. UNIT CAPACITY FACTOR (Using Design Mwe) '                                                 78.91          14.66             59.11
: 18. UNIT FORCED OUTAGE RATE                                                                   14.17          11.84             11.19
: 19. SHUTDOWNS SCllEDULED OVER NEXT 6 MONT11S (TYPE, DATE, AND DURATION OF EACH):
None
: 20. IF SIIUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A
: 21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST           ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERAITON 1.16-9 TECHOP3WRCWlONTHLYRPT. DOC k_____                _ _ _ _ _ _ _ _ _ _ _ _   _ _ _ . _ _ _ _ _ _ . _

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254                                                                                                                        COMPLETED BY                                      Lynne Hamilton UNIT NAME: One                                                                                                                          TELEPHONE:                                         309-654-2241 DATE:                            July 10,1998                                                                                            REPORT MONTH                                      June 1998 NO       DATE                   TYPE            DURATION  REASON       METHOD                             LICENSEE                                                            SYSTEM COMPONENT                       CORRECTIVE FOR            (HOURS)                         OF                               EVENT                                                        CODE    CODE                     ACTIONS / COMMENTS S                       SHU1 TING                                    REPORT DOWN                                       NO.
REACTOR 984T2   980601                            S       21.3     11                    4                                            -                                                -        -                           Continuauon of Maintenance Outage QlP01 (Unplanned Extension) 9843    980604                           F        18.6     A                     9                                            -                                                -        .-                     Moisture Separator Drain Tank Control Valve Problems 984)4   980607                            $        0        B                    5                                            -                                                -        -
                                                                                                                                                                                                                                      . Rod Shuttle For Fuel Precondition 9845    980614                            S        0        B                    5                                            -                                                  .      -
Control Rml Shuffle 984E    980627                            F       69.6     A                     3                                            -                                                -        -                         SDV Switch Failure 1
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APPENDIX D
                                                                         ,                  UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.       50-265                                                                         COMPLETED BY:     Lynne Hamilton UNIT NAME:       Two                                                                            TELEPHONE:        309-654-2241 DATE:            July 10,1998                                                                   REPORT MONTH:     June 1998 NO-      DATE    TYPE     DURATION        REASON                                       METHOD     LICENSEE SYSTEM  COMPONENT          CORRECTIVE FOR       GIOURS)                                                        OF        EVENT   CODE      CODE       ACTIONS / COMMENTS S                                                                   SHUTI1NG    REPORT DOWN         NO.
REACTOR 98412  980605     F         13.3                          A                               9          -      -          -
Performed Repairs to the
                                                                                                                                                                                                  #2 Combined Intercept Valve 98-03  980607     S          O                             B                              5          -      -          -
Shume Control Rods For Fuel Preconditioning 9844   980614     F         19.1                          A                               9          -      -          -
                                                                                                                                                                                                  #3 CV EHC Oil leak 98415  980615     S          0                             B                              5          -      -          -
CRD ShufDe 9
                                                                ' 84)6 980628     F         69.6                          A                               3          -      -          -
Lightmng Stnke Caused Generator Trip h
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VI. UNIOUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:
                                  '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.
1]Lnjt One Date: June 1,1998 Valve Actuatsd:                                                                                                              No. & Tvoe of Actuation:
1-0203-3A                                                                                                                   1 Manual 1-0203-3B                                                                                                                   1 Manual 1-0203-3E                                                                                                                   1 Manual Plant Conditions: Reactor Pressure - 320 psig Description of Events: QCOS 0203-03 " Main Steam Relief Valves Operability Test" Valves 1-0203-3C and 1-203-3D were tested on the Unit I shutdown on 12/20/97. No maintenance was performed on 1-0203-3C or 1-0203-3D that required testing.
,                                   B.                  Control Rod Drive Scram Timine Data for Units One and Two-The basis for reporting this data to the Nuclear Regulatery Commission is 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 timing was performed with reactor pressure greater than 800 PSIG.
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                      ,                          VII. REFUELING INFORMATION 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.
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       ,#                                                                                                                             QTP 0300-S32
  '.                                                                                                                                  Revision 3 e                                                                                                                                   April 1997 QUAD CITIES REFUELING INFORMATION REQUEST
: 1.                               Units                                               01   Reload:       14    Cycle:                                                            15                    l
: 2.                                Scheduled date for next refueling shutdown:                                                                11/07/98
                                                                                                                                                                                                                         )
: 3.                               Scheduled date for restart-following refueling:                                                     '12/17/98
: 4.                               Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:
Yes
: 5.                               Scheduled date(s) for submitting proposed licensing action and supporting information:
                                                  ' Approved
: 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                                                                                                                                                          I Approx. 216 SPC 9X9IX Fuel Bundles will be loaded.
: 7.                               The number of fuel assemblies.
                                                                                                                                                                                                                         ]
: a.                                Number of assemblies in core:                                                                        724
: b.                                Number of assemblies in spent fuel pools                                                    1933
: 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:                                                   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:                                                                                              2002 l
1 l
I                                                                                                                                                                                                                         l i
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I (final) 1 L                                                                                                                                                                                                    - .________________o

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  '                                                                                                                                                                                                                                                  QTP 0300-S32
    ,                                                                                                                                                                                                                                                 Revision 3 April 1997
                                                                   ,                                                                                                                                          QUAD CITIES REFUELING INFORMATION REQUEST j                                   1.                                  Unit:                                                                  02                                                                      Reload        14      Cycle:                                                                             15
: 2.                                  Scheduled date for next refueling shutdown:                                                                                                                                                                                  1/8/2000
: 3.                                  Scheduled date for restart following refueling:                                                                                                                                                                             2/17/2000
: 4.                                 Will refueling or resumption of operation thereafter require a Technical
!                                                                      specification change or other license amendment Yes                                                                                                       .
I                                    5.                                Scheduled date(s) for submitting proposed licensing action and l                                                                       supporting information:
August, 1999
: 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:
N/A
: 7.                                 The number of fuel assemblies.
: a.                                 Number of assemblies in core:                                                                                                                                                                              724
: b.                                 Number of assemblies in spent fuel pools                                                                                                                                                          2943
: 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:                                                                                                                                                          3897
: b.                                  Planned increase in licensed storage:                                                                                                                                                                                        0 9,                                 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:                                                                                                                                                                                                       2002 (final) 2 E                                                                                                                                                                                                                                        _

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                                                                             ' VIIL GLOSSARY
: Tl e following abbreviations which may have been used in the Monthly Report, are defined _
below:
ACAD/ CAM                       Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI                     - American National Standards Institute
                        ;APRM                       - Average Power Range Monitor ATWS-                      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 l-                     1IPCLRT-                      ategrated Primary Containment Leak Rate Test IRM.                       Enermediate Range Monitor ISI                         .. wrvice Inspection
(                      -LER'~                        Ucensee 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 L                         MSIV'                     LMain 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 i                         RBM                        Rod Block Monitor l                      : RCIC'                       Reactor Core Isolation Cooling System L                         RHRS                       Residual Heat Removsl System RPS                      - Reactor Protection System RWM                        Rod Worth Minimizer SBOTS -                    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 TIE                     - Traversing Incore Probe TSC.                        Technical Support Center 1
TECHOP3\NRC\MONTHLYRPT. DOC .
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