ML20137T719

Monthly Operating Repts for Mar 1997 for Quad Cities Nuclear Station,Units 1 & 2

ML20137T719
Person / Time
Site:	Quad Cities
Issue date:	03/31/1997
From:	Moore K, Pearce L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-97-034, LWP-97-34, NUDOCS 9704160152
Download: ML20137T719 (21)

Text

-

C 8 Commonwealth th>n Gimpany Quad Citics Generating Station 22710 206th Avenue North

- Cordova, !!. 61212-9740 Tei.w;-ns 1-221i i

LWP-97-034 April 9, 1997

~

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 j

^

i

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC Docket Nos. 50-254 and 50-265 Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of March,1997.

Respectfully, Comed Quad-Cities Nuclear Power Station b 0.

lp L. W. Pearce Station Manager LWP/dak g

Enclosure Q']Sl cc:

A. Beach, Regional Administrator C. Miller, Senior Resident Inspector 1G0018 STMOR@497.LWP

~

9704160152 970331 l

DR ADOCK 0500 54 A I?nicom Company i

e a

HOT: TECH SPEC VIOLATION IF THIS REPORT IS NOT POSTMARKED BY THE 10th of the MONTH NRC REPORT ROUTING CONCUR.RENCE FORM REPORT: March NRC Month Report l

Y-/0 - 9 7 ORIG 1NATOR

/

DATE 4

f

% %3 ~ t>'-

6h, DEPARTMENT SUPERINTENDENT OR DESIGNEE DATE h

/dlf)

A REGULfJdRY ASSURANCE DATE D _ 6 &k )

4'-/6 ~ 9 7 EITE VICE PRESIDENT / STATION MANAGER DATE RETURN FORM TO REGULATORY ASSURANCE, RON BAUMER FOR FILING

e i

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT MARCH 1997 COMMONWEALTH EDIS0N COMPANY AND MID-AMERICAN ENERGY COMPANY j

'NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 i

113CHOM\\NRC\\ MONTHLY.RPT

TABLE OF CONTENTS j

I.

Introduction II.

Summary of Operating Experience A.

Unit One B.

Unit Two III.

Plant or Proceduro 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 IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report l

B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions 2

VI.

Unique Reporting Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary i

TECHOP3\\NRCG40N1HLY.RPT

i 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 Mid-American 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 C0-254 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 Kristal Moore and Debra Kelley, telephone number 309-654-2241, extensions 3070 and 2240, respectively.

l

\\

l 1amon#mmucwnuxan

• e II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One began the month of March 1997 on-line. On March 11, 1997 at 1138 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.33009e-4 months <br />, Unit I came off-line.

The reactor was manually scrammed on March 11, 1997 at 1331 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.064455e-4 months <br /> to repair / replace a Reactor Protection System Scram Relay. The reactor went critical on March 16, 1997 at 2242 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.53081e-4 months <br />. Forced Outage Q1F39 was concluded on March 17, 1997 at 1516 hours0.0175 days <br />0.421 hours <br />0.00251 weeks <br />5.76838e-4 months <br />, when the generator was synchronized to the grid.

'A problem with the Moisture Separator Drain Tank (MSDT) necessitated a load drop on March 20, 1997. A Heater Bay entry was made to investigate the 3508B MSDT Level Control Valve.

On March 21, 1997 at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> the Turbine Generator was tripped in order to repair the 3508B MSDT Level Control Valve. However, while the Turbine was being taken off-line, an Electro Hydraulic Control.(EHC) aberration was experienced. On March 22,1997 at 1104 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.20072e-4 months <br />, a manual scram was inserted to repair and test the EHC System. The station was able to duplicate the problem with the EHC System, with four of the ten shutoff valves malfunctioning.. All ten shutoff valves were replaced.

On March 27, 1997, restart was on hold pending approval of a Technical Specification Amendment required by the NRC. The reactor went critical on March 28, 1997 at 1714 hours0.0198 days <br />0.476 hours <br />0.00283 weeks <br />6.52177e-4 months <br />, and Forced Outage Q1F40 was terminated on March 29, 1997 at 0508 hours0.00588 days <br />0.141 hours <br />8.399471e-4 weeks <br />1.93294e-4 months <br /> when the generator was synchronized to the grid.

B.

Unit Two Quad Cities Unit Two was shutdown the entire month of March due to l

Refuel Outade Q2R14.

Start-up is scheduled for May 15, 1997.

I TBCHOP3\\NRC400NTHLY.RFT

1 i

III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

i, AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Soecifications Technical Specification Amendment No.172 was issued on. February 28, 1997 to Facility Operating License DPR-29 and Amendment No. 168 to Facility Operating License DPR-30 for Quad Cities Nuclear Power i

j Station.

t The amendments would update the pressure-temperature (P-T) curves contained in the Dresden and Quad Cities Technical Specifications to L

22 Effective Full Power Years (EFPYs).

[

i i

Technical Specification Amendment No.173 was issued on March 4,1997 to Facility Operating License DPR-29 and Amendment No. 169 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The amendments would change the Technical Specifications (TS) by allowing a single control rod to be moved when the plant is in the Hot Shutdown or. Cold Shutdown condition provided that the one-rod-out interlock is Operable and the reactor mode switch is in the Refuel position.

Technical Specification Amendment No.174 was issued on March 14, 1997 to Facility Operating License DPR-29 and Amendment No. 170 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The amendments would revise the technical specifications to clarify and maintain consistency between the operability requirements for protective instrumentation and associated automatic bypass features.

Technical Specification Amendment No.175 was issued on March 27, 1997 to Facility Operating License DPR-29 and Amendment No. 171 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The proposed amendments provided (1) an evaluation of the Unreviewed Safety Question (USQ) involving the control room operator dose resulting from an error in the secondary containment volume, (2) a change in Technical Specification (TS) 4.7.P.2.b.and 4.7.P.3 values for the allowed methyl iodide penetration for the standby gas treatment charcoal adsorbers, and (3) change of TS 5.2.C to reflect the new calculated free volume of the secondary containment. The licensee requested that these amendments be processed on an emergency basis.

B.

Facility or Procedure Chanaes Reauirina NRC Acoroval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C.

Tests and Exoeriments Reauirina NRC Acoroval There were no Tests or Experiments requiring NRC approval for the reporting period.

TECHOPS\\NRC\\HONTHLY.RPT

m__.

IV.

LICENSEE EVENT REPORTS 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 requirements of 10CFR50.73.

UNIT 1 Licensee Event Reoort Number Q11g Title of occurrence 97-003 2/21/97 Control Room HVAC Flow Low (Downgraded to PIR 1-97-047)97-003 3/26/97 Secondary Containment Volume Less than that Described in 4

FSAR.97-004 3/20/97 RHRSW Event 10/26/96--RHRSW Pumps Found in a Degraded Condition due to Inadequate Evaluation of Replacement Pump Casing Bolts.97-005 3/19/97 HPCI Made Inoperable to Evaluate an Abandoned Cable.97-006 3/27/97 Reactor Water Clean Up Appendix "R" Requirement.

i 97-007 3/31/97 U-1 Diesel Generator Auto-start.

NOTE:

Sequence of LER Numbers is out of order due to reuse of numbers.

l UNIT 2 Licensee Event Report Number Qalg Title of occurrence 97-003 3/21/97 2B Core Spray Pump Room Looler Inoperable.

TECHOP3\\NRC\\ MON 1NLY.RPT

T 4

s 4

4 V.

DATA TABULATIONS l

1 The following data tabulations are presented in this report:

A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions 4

l 1

4 l

l 4

5 4

r l

1 i

j i

i

)

s 4

i l

4 a

4 i

l 4

11! CHOP 3WRC440NTHLY RVf d

. - ~ -. -

~.n...

~~

. - -, ~.. _ ~ - ~...

. - -.. - ~..

~ _ - ~ -. - - -. -...

3 l

4 APPENDIX C OPERATING DATA REPORT DOCKETNO. 50-254 i

UNrr One DATE April 10,1997 I

COMPLETED BY. Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 030197

1. REPORTING PERIOD 2400 033197 OROSS HOURS IN REPORTING PERIOD: 744

2. CURRElfrLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 709.

DESIGN ELECTRICAL RATING (MWe-NET): 789

3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Ne0: N/A

4. REASONS POR RESTRICrlON (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 464.60 1880.60 166389.80

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 409.70 1825.70 161354.60

8. UNrr RESERVE SHirrDOWN HOURS -

0.00 0.00 909.20

9. OROSS THERMAL ENERGY GENERATED (MWH) 843134.40 4218976.80 351391859.30.

- 10. OROSS ELECTRICAL ENERGY GENERATED (MWM) 268959.00 1367570.00 113789000.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 256110.00 1306679.00 107461648.00

12. REACTOR SERVICE FAcrOR 62.45 87.%

76.02

13. REACTOR AVAILABILITY FACIOR 62.45 87.06 77.58

14. UNrr SERVICE FAcrOR 55.07 84.52 73.72

15. UNTr AVAILABILrrY FACTOR 55.07 84.52 74.13

16. UNrr CAPACrrY FACTOR (Using MDC) 44.76 78.67 63.84

17. UNTT CAPActrY FACTOR (Using Design MWe) 43.63 76.67 62.23

18. UNrr PORCED OUTAGE RATE 44.93 15.48 7.58

19. SHirrDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): N/A

20. IF SHirTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A

21. UNrrs IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INrrtAL CRrrlCALITY INrrIAL ELECIRECfrY COMMERCIAL OPERATION 1.1. >-9

• lTfMOP3\\NitC\\ MON'lHLY.RFr -

1.

1 3

i APPENDDC C OPERATING DATA REPORT 2

DOCKET NO.

50-265 UNIT Two DATE April 10,1997 i

e COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 030197

1. REPORTING PERIOD: 2400 033197 OROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACrrY: 769 4

DESIGN ELECTRICAL RATING (MWe-NET): 789 i

3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Net): N/A j

4. REASONS FOR RESTRICrlON (IF ANY):

TH15 MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrr! CAL 0.00 1408.30 161994.85

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 0.00 1407.70 157657.05

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENEROY GENERATED (MWH) 0.00.

3477281.20 343149370.02

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 1118808.00 110135945.00

11. NET ELECTIUCAL ENERGY GENERATED (MWH) 0.00 1076518.00 104396239.00

12. REACTOR SERVICE FACTOR 0.00 65.20 74.54

13. REACTOR AVAILABILrrY FACTOR 0.00 65.20 75.92

14. UNrr SERVICE FACTOR 0.00 65.17 72.55

15. UNrr AVAILABILTTY FACTOR 0.00 65.17 72.87

16. UNTT CAPActrY FACTOR (Using MDC) 0.00 64.81 62.47

17. UNrr CAPACirY FACTOR (Using Design MWe) 0.00 63.17 60.89

18. UNrr FORCED OUTAGE RATE 0.00 0.00 11.08

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH): N/A

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 5/15/97

21. UNrrS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTrlAL CRTilCALrrY INTilAL ELECTRICirY COMMERCIAL OPERATION

1. l u-9 TECHOP3\\NitC\\blONTHLY.RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE April 10. 1997 1

COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 HONTH _ March. 1997 j

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net)

(MWe-Net) 1.

783 17.

29 2.

728 18.

375 3.

784 19.

603 4.

784 20.

306 5.

784 21.

81 6.

783 22.

-8 7.

785 23.

-6 8.

784 24.

d 9.

783 25.

-6 10, 784 26.

-6 11.

179 27.

-6 12.

-7 28.

-6 13.

-6 29.

76 14.

-7 30.__

544 15.

-7 31.

772 16.

-7 _

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 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.

1.16-8 TECHOP3WRC\\MONTMLY.RPT

APPENDIX B l

AVERAGE DAILY UNIT POWER LEVEL l

DOCKET N0 50-265 UNIT Two DATE April 10. 1997 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 1

MONTH March. 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-8 17.

-8 2.

-8 18.

-8 3.

-8 19.

-8 4.

-8 20.

-8 5.

-8 21.

-8

.2 6.

-8 22.

-7 7.

-8 23.

-5 8.

-8 24.

-6 9.

-8 25.

-6 10.

-8 26.

-6 11.

-8 27.

-6 12.

-6 28.

-6 13.

-6 29.

-8 14.

-7 30.

-8 15.

-7 31.

-8 16.

-6 i

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 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.

1.16-8 113 CHOP 3\\NRC\\ MONTHLY RPT

i l

APPENDIX D j

UNIT SHUTDOWNS AFD POWER REDUCTIONS 1

DOCKET NO.

50-254 i

UNIT NAME One COMPLETED BY Kristal Moore DATE April 10. 1997 REPORT MONTH March, 1997 TELEPHONE 309-654-2241 4

O@

to g-g gM M

lH na a

8 E

i n

h m

m u

.xM LICENSEE DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS 97 04 3/11/97 F

147.7 A

2 Shutdown Due to Repair / Replace of a Reactor Protection System Scram Relay - QlF39.

9745 3/20/97 F

0 A

5 load Drop was Perfornwd to Investigate i

Problems with the 3508B Moisture Separator Drain Tank (MSDD Level Control Valve.

I I

9742 3/21/97 F

186.6 A

2 Shutdown to Repair the 35088 MSDT Level I

Control Valve and to Repair and Test the Electro Hydrautile Control System - QlF40.

i 3

I 1

4 N

1 1

l i

4 1

5 l

l 1

i i

4 1

1 113 CHOPS \\l4ItC\\ MONTHLY.RIT i

T i

f APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE Aoril 10, 1997 REPORT MONTH March 1997 TELEPHONE 309-654-2241 4

b H

1 oE@

x

=

=

=

gb s"

Es En b

g E8 8

he m

LICENSEE DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO.

DATE (HOURS)

REPORT 97 43 3/1/97 S

744 C

4 Continuation of Refuel Outage Q2R14.

=_-

T1; CHOP 3\\NRC\\MONUiLY.RPT

I a

5 1

VI. UNIOUE REPORTING REQUIREMENTS 4

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 for the reporting period.

I B.

Control Rod Drive Scram Timina Data for Units One and Two i-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 timing as l

performed with reactor pressure greater than 800 PSIG.

I 1

1TCHOP3\\NRC\\ MONTHLY.RPT

RESULTS OF SCRAM TIMING MEASUREMENTS

~ ~

PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/97 TO 03/31/97 l

l AVERAGE TIME IN SECONDS AT %

l MAX. TIME l l

l INSERTED FROM FULLY WITEDRAWN l FOR 90s

! INSERTION !

DESCRIPTION j-NUMBER j

5 20 1

50 90 Technical Specification 3.3.C.1 E DATE

! OF RODS

! O.375 ! O.900 2.00 3.5 7 sec.

3.3.C.2 (Avermoe Scram Insertion Timal l

l l

l l

i l

2/17/97 l

14 1 0.314 l 0.712 l 1.528

! 2.671 l

3.010 l STT for Viton Issue U-1 (Core Wid Ave. Times) l l

l l

l l

(J-14) l 1

l l

ll l

l 3/29-31/97 l

21 l 0.316 l 0.708 l; 1.513 l 2.645 3.010 l STT for Tech Spec (19) (Core Wide Ave. Times) l l

l l

(J-14) l PMTV (2) ll l

1 l

ll l

ll l'

l l

l l

l ll l

l l

ll l

1 l

l l

ll l

l l

l l

l l

l l

l l

l l

i i

i l

l l

1 l

l l

l l

l l

l l

l l

l l

l l

i l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l I

l l

l l

l l

l i

l l

1 l

l l

l I

I I

I B

3 L

l I

l f

l l

l W

l l

l l

l I

r l

l i

l l

l

?

I NRCISCRM11MF_FRM l

L F

.... ~_

i l

6 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.

I i

e 4

4 l

i l

i l

1 s

i i

J d

l 4

e i

n i

a TECHOP3\\NRCWON1HLY.RPT

g_.

i VIII. GLOSSARY

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

i ACAD/ CAM - Atmospheric Containment Atmospheric i

Dilution / Containment Atmospheric Monitoring j

ANSI

- American National Standards Institute APRM

- Average Power Range Monitor ATWS

- Anticipated Transient Without Scram BWR

- Boiling Water Reactor CRD

- Control Rod Drive 2 -

EHC

- Electro-Hydraulic Control System E0F

- Emergency.0perations Facility GSEP

. Generating Stations Emergency Plan HEPA

- High-Efficiency Particulate Filter HPCI

- High Pressure Coolant Injection System j

HRSS

- High Radiation. Sampling System i

IPCLRT

- Integrated Primary Containment Leak Rate Test l

IRM

- Intermediate Range Monitor ISI

- Inservice Inspection i

LER

- Licensee Event Report l

LLRT

- Local Leak Rate Test LPCI

- Lew Pressure Coolant Injection Mode of RHRs LPRM

- Local Power Range Monitor MAPLHGR

- Maxjmum Average Planar Linear Heat Generation Rate MCPR

- Miriimum Critical Power Ratio l

MFLCPR

- Ma::imum Fraction Limiting Critical Power Ratio a

MPC

- Maximum Permissible Concentration

~

MSIV

- Main Steam Isolation Valve NIOSH

- National Institute for Occupational Safety and Health j

PCI.

- Primary Containment Isolation i

PCIOMR

- Preconditioning Interim Operating Management Recommendations RBCCW

- Reactor Building closed Cooling Water System RBM

- Rod Block Monitor RCIC

- Reactor Core Isolation Cooling System RHRS

- Residual Heat Removal System i

RPS

- Reactor Protection System j.

RWM

- Rod Worth Minimizer i

SBGTS

- Standby Gas Treatment System j

SBLC

- Standby Liquid Control SDC-

- Shutdown Cooling Mode of RHRS

[

SD'l

- Scram Discharge Volume SRM

- Source Range Monitor j

TBCCW

- Turbine Building Closed Cooling Water System TIP

- Traversing Incore Probe TSC

- Technical Support Center 1BCHOPS\\NRC\\ MONTH 1.Y.RPT

. ~.

~.

a l

QTP 300-532 Revision 2 3

I QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

ni Reload:

14 Cycle:

is 2.

Scheduled date for next refueling shutdown:

2 /9a ton 3.

Scheduled date for restart following refueling:

5/29/98 l

4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other Ilconse amendment.

No 6

l S.

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

',j i

l 5/9/98 6.

Important Ilconsing 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 5

Approx. 216 SPC 9X9IX Fuel Bundles Q1R15 will be loaded.

.i 7.

The number of fuel assemblies.

if.

a.

Number of assemblies in core:

724 m

i i

b.

Number of assemblies in spent fuel pool:

1991 8.

~ The present licensed spent fuel pool storage capacity and the size of J.

any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

3657 i

a.

Licensed storage capacity for spent fuel:

l 0

b.

Planned increase in licensed storage:

t l

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

2002 i

(

APPROVED (final)

OCT 3 01989

-I-14/0395t O.C.O.S.R.

s g

L QTP 300-532 l

Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unft:

02 Reload:

13 Cycle:

14 2.

Scheduled date for next refueling shutdown:

3/1/97 1

l 3.

Scheduled date for restart following refueling:

5/15/97 l

4.

Will refueling or resumption of operation thereafter require a Technical 3.W 0'

f Specification change or other license amendment:

Yes i

j 5.

Scheduled date(s) for submitting proposed licensing action and R

l supporting information:

Submittals began August 1996; ongoing process.

i l

6.

Important licensing considerations associated with refueling, e.g., new J

l or different fuel design or-supplier, unreviewed design or performance

'l analysis methods, significant changes in fuel design, new operating

.l j

procedures:

i 216 Siemens 9X91X Power Corporation Fuel Bundles will be loaded during Q2R14.

i

'l i

7.

The number of fuel assemblies.

4, a.

' Number of assemblies in core:

0

[)o 1

.a '

j b.

Number of assemblies in spent fuel pool:

3667 8.

The present licensed spent fuel pool storage capacity and the size of i,

any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

4 4

3897 I

a.

Licensed storage capacity for spent fuel:

0 b.

Planned increase in licensed storage:.

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2002 APPROVED (final)

OCT 3 01989 14/0395t Q.C.O.S.R.