ML19347B539

Monthly Operating Repts for Sept 1980

ML19347B539
Person / Time
Site:	Quad Cities
Issue date:	10/01/1980
From:	Beth Brown, Tubbs R COMMONWEALTH EDISON CO.
To:
Shared Package
ML19347B538	List: ML19347B537 ML19347B539
References
NUDOCS 8010150313
Download: ML19347B539 (22)

Text

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT SEPTEMBER 1980 COMMONWEALTH EDISON COMPANY

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AND 10WA-ILLlH0ls GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 8010150313

TABLE OF CONTENTS 1

1 1. Introdue lon

11. Summary of Operating Experience A. Unit One j B. Unit Two lit. 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 Corrective Maintenance of Safety Related Equipment D.

IV. Licensee Event Reports J

V. Data Tabulations i VI. Unique Reporting Requirements I

} A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data 1/11. Refueling Information ,

i Vill. Glossa ry 1

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i I. INTRODUCTION 1

Quad-Cities Nuclear Power Station is composed of two Bolling Water 1

Reactors, each with a Maximum Dependable Capacity of 769 MWe net, located j in Cordova, Illinois. The Station is jointly owned by Commonwealth Edi;en Company and towa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Inc. and the primary construction contractor was United Engineers & Constructors. The condenser cooling 4

method is a closed-cycle spray canal, and 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 I and 2 respectively were October 18, 1971, and April 26, 1972. Commerical generation of power began on February 18, 1973, for Unit I and March 10, 1973, for Unit 2.

This report was compiled by Becky Brown and Robert Tubbs, telephone number 309-654-2241, extensions 245 and 174.

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11.

SUMMARY

OF OPERATING EXPERIENCE A. UNIT ONE September 1-30: Unit One remained shutdown for the entire reporting period for End of Cycle Five Refueling Outage.

S. UNIT TWO September 1-4: Unit Two began the reporting period at a load of 587 MWe, increasing the load at a rate of 5 MWe/ hour until 760 MWe was achieved at 1320 on September 2. Load was held steady until 1530 on September 3, when 25 MWe were dropped due to high main condenser backpressure. .Laad was held at an average of 722 MWe through September 4.

September 5-6: Load was held at 730 MWe until 0700 September 5, when load was increased at 20 MWe/ hour per Load Dispatcher's request. Load was held from 0815 to 0850 when it was increased again at a rate of 10 MWe/ hour.

At 0950 the rate was reduced to 5 MWe/ hour until 1250 when a load of 775 MWe was achieved. On September 6 an average load of 769 MWe was held.

September 7-8: At 0025 on September 7 load was dropped per Load Dispatcher's request from 766 tiWe to 700 MWe at 0105 At 0350 load was again dropped to 550 MWe at 0505 At 0715 load was increase at a rate of 50 MWe/ hour, which was reduced to 5 MWe/iour at 0945 On September 8, at 0915, load was held at 785 MWe.

September 9-11: Over this three day period an average load of 785 MWe was held.

September 12: The following load changes were made per Load Dispatcher's request at their respective rates and times; 0323, decreased at 100 MWe/

hour for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; 0415, increased at 50 MWe/ hour for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; 0515, increased at 25 MWe/ hour for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; 0615, increased at 5 MWe/ hour; 1210, hold load at 789 MWe; 1745, reduced at 50 MWe/ hour; 2030, hold load at 650 MWe.

September 13-14: Over this two period an average load of 672 was held.

September 15-17: On September 17 at 0000 load was increased 25 MWe/ hour for I hour per Load Dispatcher's request; at 0100 the rate was reduced to 5 MWe/ hour and at 1730 a load of 793 MWe was held. Over tne remainder of this period an average load of 786 MWe was held. l September 18-20: Starting at 0200 the following load changes were made f per Load Dispatcher's request: 0200, reduced load at 100 MWe/ hour for l 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; 0330, increased load at 50 MWe/ hour; 0430. reduced rate of in-crease to 20 MWe/ hour; 0530, reduced rate again to 5 MWe/ hour; 1435, held load at 790 MWe. On September 19-20 an average load of 788 MWe was held.

September 21-23: Per Load Dispatcher's request and to perform turbine weeklies and reverse condenser flow, the following load changes were made on September 21: 0210, reduced load at 100 MWe/ hour; 0630, increased load at 50 MWe/ hour for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />; 1000, increased load at 75 MWe/ hour; 1100 reduced rate of increase to 50 MWe/ hour; 1200 reduced rate again to 5 MWe/ hour; 1945, held load at 788 MWe. On September 22 load was held at 786 MWe. On September 23, per Load Dispatcher's request, the following load changes were made: 0325, decreased load at 100 MWe/ hour for I hour; 0425, held load at 685 MWe; 0445 increased load at 5. MWe/ hour for I hour; 0545, reduced rate of increase to 15 MWe/ hour; 0645, reduced rate again to 5 MWe/ hour; 1315, held load at 780 MWe.

September 24-27: Ove.- this four day period load was held at an average of 792 MWe, until 2140 on September 27, when it was reduced at 100 MWe/ hour for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

September 2C-29: At 0235, per Load Dispatcher's request, load was reduced at 100 MWe/ hour for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to a load of 585 MWe at 0335 At 1030, load was increased at a rate of 50 MWe/ hour, dropping to 2S MWe/ hour at 1230, and 5 MWe/ hour at 1430. This increase was continued until 0530 on September 29 when a load of 795 nWe was held.

September 30: Unit Two ended the reporting period holding a load of 782 MWe.

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lit. PLANT _0R PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE i

A. Amendments to Facility License or Technical Specifications On September 8,1980, the NRC issued Amendment 58 to DPR-29 and Amendment 53 to DPR-30 for quad-Cities Station, Units I and 2. These a.nendments revise the Technical Specifications to allow the count rate on the SRM channels to go below three counts per second when there are two or less fuel assemblies la a quadrant, and they are positioned adjacent to the SRM in that quadrant.

B. Facility or Procedure Changes Requiring NRC Approval There were no facility or procedure changes requiring NRC approval for the reporting period.

C. Tests and Experiments Requiring NRC Approval There were no test or experiments requiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the safety related maintenance p~erformed on Unit One and Unit Two during the I' reporting period. The headings indicated in this summary include Work Request Numbers, LER Numbers, Components, Cause of Mai-functions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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UNIT ONE MAINTENANCE

SUMMARY

l CAUSE RESULTS S EFFECTS W.R. LER OF ON ACT10tl TAKEN TO NUMBER NUMBER COMPONENT HALFUNCTION SAFE OPERATION PREVENT REPETITION Q07344 SBGT Demister Demister was dirty. Dp is 2.0 inches Replaced filters; tested 1/2A-7501 and train cannot proper flow of SBGT achieve 4000 cfm train, flow.

qo1537 HPCI Room Access Door needed to be Repair or replace Built third door and Interlock Doors replaced. HPCl Interlock rewired new doors.

doors to provide Visual and secondary tight scaling to containment test.

assure secondary containment capability.

Q01536 Pipe Penetrations Penetrations Fire protection was Scaled penetrations.

Into HPCI Room needed sealing. needed at penetration Performed visual and Access interlock between HPCI Room and secondary containment Asca interlock and to test.

assure secondary con-tainment integrity.

Q04379 Squib Valve Resistors and Replace resistors per installed four 20 ohms Monitor Circuit lugs needed SIL 186. resistors in each squib 1130-725 A/B & replacing.' circuit and rewired.

726 A/B ' Replaced lugs; tested both.

Q07640 1/2 Diesel Prime switch had Prime switch short Pump bound a little; Generator shorted. prevents changing rotated it and broke fuel filters. free. Tested.

Q07643 SRH Channel 23 Load burned off Opera tion is unstable; Replaced 390 uf capacitor 390 uf capacitor. period meter fluctu- in integration card in ates erratically, chassis.

UNIT ONE MAINTENANCE

SUMMARY

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

NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION l

i q00677 Unit i Torus Not found. Metal-to-metal sound Disassembled operator l

l Purge Valve from cylinder when and valve; found no i 1-1601-55 operated. Last few problem; re-assembled

! inches of travel in and tested valve.

l open direction very Jerky and noisy.

i Q07737 Unit 1 Refuel Jumpers faul ty. Bridge will not go Re-landed jumpers to f

Bridge 833 over vessel. correct terminals; tested.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUfdCTION SAFE OPERATION PREVENT REPETITION q04380 Squib Valve Resistors and lugs Replace resistors per installed four 20 Monitor Circuit needed replacing. SIL 186. ohms resistors in 1130-725 A/B & each squib circuit 726 A/B and rewired. Replaced w!re lugs; tested both replacements.

407358 80-21/0;L N2 Inlet Valve Valve operating The valve would not Removed and replaced 2-1601-57 motor burned due operate remotely. motor; stroked valve to a internal three times; tested.

short.

q07693 Diesel Gener- The Diesel Gener- There was no The thermal overloads ator Supply Fan ator supply fan ventilation in the were replaced.

Breaker breaker thermals diesel generator were found tripped room.

on 9-8-80 & 9-11-80.

q07706 Reactor Bldg. Solenoid Valve "B" valve did not Rebuilt solenoid valve.

Vent isolation was sticking. close during Valve 2-5741B surveillance.

q07399 250V Battery Current & s,ensing No output voltage, Replaced current Charger 2-8350 limit board faulty. sensing and limit and sensing limit board; board' overheated. tested.

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IV. '.lCENSEE EVENT REPORTS The following is a tabular summary of all license event reports for quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 4

6.6.B.1. and 6.6.B.2. of the Technical Specifications.

UNIT ONE Licensee Event

~Recort 'sumber Date Titie of Occurrence

'80-21/03L 9-1-80 Local Leak Rate Test Failures 80-22/03L 9-3-80 HPCI Turbine Area Hi Temperature Switch setpoint drift 80-23/03L 9-10-80 Open Fire Stop Cable Spreading Room

~80-24/03L - - --

9-14-80 Removed fuel element with less than 3 cps on SRM 25/01T 9-17-80 Core spray piping cracks UNIT TWO

80-21/03L 9-14-80 Core spray M0-2-1402-3A failed to open

V. DATA TABULATIONS 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 i

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OPERATING DATA REPORT

~~ ~~ D O C K ET~ N O .- ~ 50-254 ~ ~ - - - -

UNIT ONE DATE October 1,1980 COMPLETED BY R-C--Tubbs -

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TELEPHONE 309-654-2241, ext. 176 OPERATING STATUS 0000 040180

1. Reporting period 2400 093080 Gross hours in reporting period: 720

2. Currently _outhorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA

4. Reasons for restriction (if any):

5. Nunber of hours reactor was critical 0.0 5725.1 60439.2

6. Reactor reserve shutdown hours 0.0 0.0 342 M

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7IHourslene~rstir~ on line~ ~~ ~ - - O '. Of 5623.1 57664'.0~~~~

0. Unit reserve shutdown hours. 0.0 0.0 909.2

9. Gross thernal energy generated (MWH) 0 11394718 115938699

~ ' iOT Gr oss 'eled tFichl'~ ~erierciy ge' nFoted (MWH) ~~

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~~~28 ~~ 662758-~~~~ 3 37285812

._,ii. . Net electr_ical._ energy generated (MWH) ._ _

-15163 _ 3370446 _

34785982 _

=12.# Reactor service factor 0 . 0_ 87.1 82.2

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1 ~ Reactor availability factor O ' . 0. ~ ~ ~ ~ ~~B7.i '~ ~8 6.8

14. ..Un i t service factor 0 . 0_ 85.5 78.4

.L5. Unit ovallobility factor 0 . 0_ 85.5 79.6 cop'a city' factor (Usin'g Des.MWe) ~~

Ti.6". ~. U n i t ' -- 2 . 7 ~ ' ~66.7' ~ ~ 6 1~. 5 17.. Unit capacity factor (using MDC) -2.7 65.0 59.9

18. Unit forced outage rote 0 . 0. __

3.6 7.8

19. Shutdowns' scheduled over next 6 nonths (Type,Date,and Duration of each):

20. If shutdown at end of report period,estincted dote o f s t ar t u p _.]1_2.2_-80 _ .

1The MC noy be lower than 759 MWe during periods of high ombiant tenperatore due 7: the thernal perfornr.ce of the spray canal.

OPER ATING DATA REPORT DOCKET NO~. ' ~ 5 0 -- 2 65~ - ~ ~~--- -

IJNIT , TWO D ATE October 1,1980

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TELEPHONE 309-654-2241, ext. 176 OPERATING STATUS 0000 090180

1. Reporting period:2400 093080 Gross hours in reporting period: 720

2. Currently authorized power level (MWI): 2511 Max. Depend capacity.

(MWe-Net); 769* Design electrical roting (MWe-Net): 789

_ __ 3 _.~.P o w e r level __to_which restricted (if any)(MWe-Net): NA

4. Reasons for restriction (if any):

___ S.t _ N u mb e r_o f_ h o u r s_ _r_e ac t o r .w os_. c r i t i c al ,_

720.0 3781.5 _ 56910.4

6. Reactor reserve shutdown hours 0.0 0.0 2985.8 73 Hours gem rotor oi line"~'~' 720.0 ~~3662707 54453.8

_, 8_. . Unit . reserve _ shutdown hours._ 0.0 0.0_ 702.9 9.~ Gross thermal energy generated (MWH) 1723851 8178905 111195014

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l 10.~ Gross electrical energy gereroted(MWH) 539384 ~ ~ ~ ^ 2557070~ 35420120

- _11. .. Net el_ectric_ol_ energy generoted(MWH) ._

514940 2395916 _

33138441

12. Reactor service factor 100.0 57 5 78.3

15. Reactor ovallobility factor 10 0 . 0f 57.5 ~ ~82.5

_ 1-4.. Unit _ service factor. _ . _ _

100.0_ _

55.7 _

75.0. l 15.. Unit availability factor 100.0 55.7 75 9, l

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16 .' ! U n i t capacity factor (Using Des.MWe)

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59:3 17.. Unit copccity. foct_or (Using MDC) 90.6 46.2 ---

57.8 -._._._1

18. Unit forced outoge rote 0.0 5.7 9.0

19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each):~ ~~'

20. If shutdown at end of report period,estincted date o f s tor t up ___NA __________. . _ .

tihe EDC ray be lower then 769 MWe during periods of high cabiant tenperatore due to the thernal performance of the spray canal.

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APPENDIX B~

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 UNIT - ONE - -- -- - - -

DATE October 1. 1980 COMPLETED BY R C Tubbs 1- . . . _ _ _ _ . . . _ . . .

TELEPHONE 309-654-2241. ext.-176 -

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Geotember 1980 . - . . .-. . . . . - - . . . . _ . . . . . - .

~ DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net) (MWe-Net)

1. -26.3 17. -18.0

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18.

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3' _ _

-29.5 19. -17.8 ,

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4. -29.2 20. -18.0

- : 5 '. ' -28.8' 2i. - - - -- - i 7 . -

-31.8 22. -18.9

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7. -28.8 23. -16.0

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9. -28.5 25. -17.5 1.0. -26.i 26. -16.9

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12 . -19.5 28. -19.0 __

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16. -17.5 l INSTRUCTIONS

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Cn this forn, list the overage daily unit power level in We-Net for each day in the reporting nonth.Conpote to the nearest whole necowatt.

These figures will be used to plot a graph for each reporting nonth. Note that when noxinos dependable capacitv is vsed for the net electrical roting of the unit there ncy be occasions when the daily overage power level exceeds the 1017. line (or the restricted power level line).,In such cases,the overage daily unit power output shet should be footnotej to explain the apparent onenoly

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APPENDIX B

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265

.. UNIT TWO - -- --

DATE October 1, 1980 COMPLETED BY R C Tubbs

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MONTH September 1980 _ _ , _ _ _ . _ ..__

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) .._ - .

(MWe-Net)-. . - - - . .- _ _ . - _ .__ .

.. i . 616,i 17, 752.5

~ 709.4 ~~ ~ ~ " 73 0 . 7 ~ ~

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3. 696.9 19. 744.3 - _.. _ _ . _

4, 688.7 20, 746.0

~~~5. 720.7 21.

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~'663.5 - - -

. . _ _ . . 6. 735.2 22, 743.4 g

7, 644.2 23, 730.0

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8., 742,0 24. 751.3~

9. 728.2 25. 750.4 . - .- -._

10. 742.3 26. 752.7 ti. 746.0 27. ~~ 738.9 ~~ ~

12 . 710.8 28, 643.4

.13 , 630.2 29. 743.O i-4 , 645.3 30. ~ 7 4 2 . 2 --

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16. 746.7 _' s INSTRUCTIONS <

Cn this form, list the average daily unit power level in HWe-Net for each do; in the reporting month. Compute to the f;torest b.hele negswett. I These figures ill be used to plot a graph for each reporting nonth. Note that when noxinen de;endable capa:ity is v143 fo.- the net electrical roting of the Unit,there nay be occasions when the daily overo;e pour level exceeb the i 1111 line (or the restricted power level line).In such cases,the overage daily snit power outpit sheet should be i futnoted to erplain the oppurent ansegly l w

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APPENDIX D QTP 300-513 50-265 UNIT SilVTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO. March 1978 UNIT NAME quad-Cities Unit Two R. C. Tubbs COMPLETED BY DATE October 1, 1980 309-654-2241, ext.

REPORT MONTil SEPTEMBER 1980 TELEPHONE

'* 174 m 8 s m = Eb x 5 l Ee 8 @ $ LICENSEE pg gg

${_,"

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DURATION $ EVENT y8 g8

. DATE (HOURS) m ygg REPORT NO.

• 8 CORRECTIVE ACTIONS / COMMENTS R

NONE I

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l VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:

A. Main Stean Relief Valve Operations There were no main steam relief valve operations for the reporting period.

6. Control Rod Drive Scram Timing Data For Units One and Two There were no control rod drive scram timing data for the reporting period.

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Vll. REFUELING INFORMATION l

The following information about future reloads at quad-Cities Station was requested in a January 26, 1978, IIcensing memorandum (78-24) f rom S. E. O' Brien to C. Reed, et. al . , ti tled "Dresden, quad-Ci ties , and Zion Station - NRC request for refueling information dated January 18, 1978.

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Eev1sson V yU g March 1973 l

Og< QUAD-CITIES REFUEt.l!!G b'

A'

- It! FORMAT 10!? REQUEST

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1 Reload: 5 _ cycle: 6 .

.. Unit: _

8 91_"8n (shut-aewn (EOC5

2. Scheduled date for next refueling shutdown: - .

following refueling: 12-7-8o(Startup BOC6}

3 Scheduled date for restart '

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thereafter require a technical .

k. Will refueling o'r resumption of operation No, Plan 10CFR50.59 ' reloads specification change or other license amendment:The review will be conducted for future cycle:, of Quad Cities Unit 1.

in June, 1980. '

scheduled date(s) for submitting proposed.1icensing action and supporting a 90 days 5

information: June, 1980 for loCFR50.59 related changes crior to shutdown.

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e.g., new or

6. important licensing considerations associated with refueling,

' different fuel desig'n or supplier, unreviewed design 'or performance Snalysis -

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

New fuel designs: Retrofit 8x8 fuel 2.65- w/o% (^- 224) '

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The number of fuel assemblies. ,

724 I

a. Number of assemblies in core:

ilumber of assemblies in si cnt fuel pool: 596  ;

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- S. The present licensed spent fuel pool storage capacity and the size of any l increase in licensed storage capacity that has been requested or is planned - . . 1 in number of fuel assemblies: . .

l 1460 . ,,- . f a.

Licensed storage capacity for' spen't fuel: . ~.

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None .  ;

b. Planned increase in licensed storage:

9 The projected date of the last refueling that can licenr.ed be discharged capacity: Septek.ber, to the1985 5 pent ~ fuel pool assuming the present (end of batch discharge' capability) X P P R O V E IJ APR 2.01973 Q.C.O.S.R.l

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QTP 30 M 38

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Rnvision 1 46 <s- -

March 1973

- 0 QUAD-CITIES REFUEL!!iG

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"9 P  % ;d tru a INFORMAT10!! REQUEST r: .

2 Reload: 4 Cycie: 5 I'.".

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Unit: . n:1f . _

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Scheduled date for next refueling shutdown: _11 4'-79 (Shutf4 f. . f 1-17-80 (Startur.. M

.~. w Scheduled date for restart following refueling: ~

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4. Will refueling or resumption of operation thereafter require a technical-

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for future cycles of Quad Cities Unit 2.

No, Plan 10CFR50.59 Reloads specification change or other license 'amandment: The review will be conducted by early September, 1979 .

5 scheduled date(s) for submitting proposed licensing action and supporting '

information: Early August, 1979 fe locFR50 59 related changes ~ 90 days prior to shutdown.

t

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t e.g., new or i 6. Important licen.:nc; considerations. associated w'ith refueling,

' ' different fuel design e cuoplier, unreviewed design or performance analysis methods, significant changek in fuel design, new operating procedures: -

, j New Fuel Desi5n: Retrofit 8xo xael (18cs)_

a nat. U at bundle top and bottora P b two larger water rods _

}- c new enrichment distribution - - - -

~~

. - -d prepressurized

!. This fuel design was 'previously used for Quad Citie's Unit 1 Cycle 5 ~

1 and Dresden Unit 2 Cycle 7

-5 7 The number of fuel assemblies. , ,

! a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 492 I.

} 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies: -

' a. Licensed storage capacity for' spent fuel: 146q .

4 I~ b. Planned increase in licensed storage: None

, 9 The projected date of the last refueling that can be discharged to the

? spent' fuel pool assuming the present licensed capacity: March,~ 1986 (End of batch discharge capability)

APPROV_.D t

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APR 2.01973 1 .-

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' O. C. O. S. R.

2

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

CRD - Control Rod Drive System SBLC - Standby Liquid Control System MSIV -

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

High Pressure Coolant injection System SRM - Source Range Monitor IRM - Intermediate Range Monitor LPRM - Local Power Range Monitor APRM - Average Power Range Monitor TIP - Traveling incore Probe RBCCW - Reactor Building Closed Cooling Water System TBCCW - Turbine Building Closed Cooling Water System RWM -

Rod Worth Minimizer SBGTS - Standby Gas Treatment System HEPA -

High-Efficiency Particulate Filter RPS - Reactor Protection System IPCLRT - Integrated Primary Containment Leak Rate Test LPCI - Low Pressure Coolant injection Mode of RHRS

- _ _ . . . RBM -

Rod Block Monitor BWR " ~ - Bolling Water Reactor ISI - In-Service inspection NPC -

Maximum Permissible Concentration PCI -

Primary Containment isolation SDC - Shutdown Cooling Mode of RHRS LLRT - Local Leak Rate Testing MAPLHGR - Maximum Average Planar Linear Heat Generation Rate RO -

Reportable Occurrence DW -

Drywell RX -

Reactor EHC -

Electro-Hydraulic Control System MCPR -

Minimum Critical Power Ratio PC10MR - Preconditioning interim Operating Management Recommendations LER - Licensee Event Report ANSI -

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