Text

Monthly Operating Repts for May 1992 for Quad-Cities Nuclear Station,Units 1 & 2
	ML20097E697
Person / Time
Site:	Quad Cities
Issue date:	05/31/1992
From:	Michael Benson, Tietz G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GCT-92-027, GCT-92-27, NUDOCS 9206120318
	Download: ML20097E697 (24)
	v • d • e

Commonwealth Edison ound Citts Nuct:ar PowIr Station 22710 206 Avenue North Corcova, Illinois 61242 Telephone 309/654-2241 i

GCT-92-027 June 4, 1992 U. S. Nuclear Regulatory Commission ATTN:

Document Control Desk Hashington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report MC._Qontit_Ros. 50-254 and 50-265 P

Enclosed for yott information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of May 1992, Respectfully, r

COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION 6bal) 6-f Gerald C. Tietz Technical Superintendent GCT/MB/dak Enclosure cc:

A. B. Davis, Regional Administrator T. Taylor, Senior. Resident Inspector n

. Ts u i

9206120318 No$hg' '

DR ADOCK 05000254 PDR

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QUAD-CITIES NUCLEAR P0HER STATION UNITS 1 AND 2 i

I MONTHLY PERFORMANCE REPORT MAY 1992 3

r COMMONHEALTH EDISON COMPANY AND IONA-ILLINOIS GAS & ELECTRIC COMPANY

[

NRC DOCKET NOS. 50-254~AND 50-265-LICENSE NOS. DPR-29 AND DPR-30 F

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TABLE OF CONTENTS I.

Introduction II. Summary of Operating Experience A.

Unit One B.

Unit Two l

l III. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A.

Amendments to facility License or Technical Specifications B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval' D.

Corrective Maintenance of. Safety Related Equipment IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions 4

VI. Unique Reporting Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data

[

l VII. Refueling Information VIII. Glossary 7-l T814 g

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-r-yy 4

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I.

IBIR0DUC110N Quad-Cities Nuclear Power Station is composed of two Boiling ' Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois.

The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company.

The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors.

The Architect / Engineer was Sargent & Lundy, Incorporsted, and the primary construction contractor was United Engineers & Constructors.

The Mississippi-River is the condenser cooling water source.

The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265. -The date of initial Reactor critica11ttes 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 Matt Benson and Debra Kelley, telephone number 309-654-2241, extensions 2995 and 2240.

s T514

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II.

SUMt%RLOE_QEERAIING_EX2ERLERCE A.

UniL0ne l

For the month of May 1992, Quad Cities Unit One performed nine load l

l reductions per Chicago Load Dispatch (CLD).

They occurred on the following days to the limiting load provided:

Day toad AdditionALReason j

5-1-92 725 MHe 5-2-92 750 MHe 5-2-92 225 MWe Drywell Equipment Drain i

l Sump Replacement.

5-6-92 665 MHe 5-9-93 535 MWe 5 11-v2 650 MWe 5-13-92 550 MHe 5-15-92 700 MHe 5-21-92 600 MWe On May 30, Unit One was shutdown to repair tubs leaks on the main condenser, l

B.

Unit Two Quad Cities Unit Two went critical on May 5 to end Refuel Outage l

Q2R11.

The generator was loaded to the grid on May 11 and full load was reached on May 17.

The period before reaching full load had a number of power changes below 50% for testing purposes (i.e. RCIC, TIP, etc...).

On May 23, power was reduced to 465 MWe to determine'the Flow Control Line (FCL).

CLD ordered load reductions to 700 MWe-for the mornings of May 24 and 25.

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III.

PLANT ORROCEDURLCHANGEL._IESISmEXEERIMElilS.

AND_SAEEILRELAIIDJi&Ilil1MANCE A.

Amendment 1_to_EacilitLL tc ens e_sr_.IechnicaLSpecific ations There were no Amendments to the facility License or Technical Specifications for the reporting period.

B.

EAcility_or_Er_o_c e d ure_ClangeLBe guirinsJiRC.2paron1 There were no facility or Procedure changes requiring NRC approval for the reporting period.

C, Imits and E4terimentslegulringJiRC_Appron1 There were no Tests or Experiments requiring NRC approval for the reporting period.

D.

CorieltiMJiainiEDAace of Safetylelate.d_Eguipment The following represents a tabular summary of the major safet) related maintenance perforrJ ' on Units One and Two during the reporting period.

This summary includes the following:

Hork Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

T814

Y v

UNIT 1 MAINTENANCE

SUMMARY

WORK RE0 JEST SYSTEM EID DESCRIPTION if0RK PERFORMEQ~

[

.Q00083 0670 Replace secondary disconnect MF As Found: MF and MG slide. cons' cts broken. As and MG in Cub 1 Bus 13-1.

Left:

Installed slide contacts.. J Cubicle 10 into Cubicle 1.

1 Q98600 6700'

. Repair racking screw on breaker As Found: Racking screw slightly bent. As left:

60.

Replaced racking screw.

. Q99947 9400 Replace Compressor "B" Train A/C As Left: Replaced compressor.

l with like for like.

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

UNIT 2 MAINTENANCE

SUMMARY

HORK RE00EST SYSTEM EID DESCRIPTION HORK PERFORMER Q00535 6705 Output breaker from 1/? DG to BUS As Found: Secondary contacts broken. As Left:

23-1 damaged.

Installed new sliding contact block.

Q00560 2301 Repair leak on HPCI oil filter.

As Found: 0-Ring hard and cracked. As Left:

Replaced with new 0-Ring.

QOO686 1601 Repair air ieaks and check valves As Found:

No visual damage. As Left:

Tightened on air contre' system on torus fitting.

relief valve.

QOO690 1601 Repair air leak on valve As Found: Air lines leaking. As left: Repaired 2-1601-56 Torus Purge.

air lines.

Q00932 756 Investigate and repair Rod Block As Found:

RBM 7 bypassed. As left: Cleaned edge Monitor #7.

connector contacts.

RBM 7 operational.

Q86175 302 Repair SCRAM Discharge Volume As Left: Replaced relay on aux relay board.

Level Switch.

'Q95695' 1402 Investigate and repair Solenoid As Left: Replaced solenoid with a new one.

2B CS Testable Check Va.1ve.

Installed new magnetic switch. Corrected wiring.

I As Found: Cubicle at MCC 29-2 intact. As Left:

098674 8292 Replace the circuit breaker for the U2 DG cooling pump fan -

Installed new breaker into cubicle.

Cubicle E5.

Q98675 8292 Replace the circuit breaker for As Found: Cubicle at MCC 29-2 intact. As Left:

the U2 DG cooling. pump fan -

Installed new breaker into cubicle.

Cubicle F1.

l.

Q99329 756/2417 Repair power supply to High As left:

Replaced power supply.

Voltage LPRM 24-17 Detector B.

TS 15

UNIT 2 MAINTENANCE

SUMMARY

HORK REOUEST SYSTEM eld _QESCRIPTION HORK PERFORMED 099380 1402 Investigate and repair B Core As Found: Packing was loose. As Left: Realigaed Spray Testable Check Valve.

shafts.

Replaced missing tubing connector.

099679 261 Repair spring can on flow flash As Found:

Rods were bent. As Left:

Replaced rod.

pot.

099767 2252 Repair U2 DG room panel 2252-37 As Found:

Removed pinched section of wire and wiring.

Installed new lug.

Installed new ty-raps.

Q99830 203 Repair main steam line inside As Found:

Limit switches set incorrectly. As isolation air operated valve.

Left: Reset limit switches. Lubricated stem and spring guides.

Q99842 201 Repair support for spring can for As Found: Rods bent or missing. As Left:

high side line 261-9.

Replaced bolts and nuts.

Q99842 201 Repair support for spring can for As Found: Rods bent or missing. As Left:

high side line 261-9.

. Replaced bolts and nuts.

Q99842 201 Repair support for spring can for As Found: Rods bent or missing. As left:

low side line 261-9 A.

Replaced bolts and nuts.

Q99842

'201 Repair support for spr~ng can for As Found: Rods bent or missing. As Left:

low side line 261-9 B.

Replaced bolts and nuts.

Q99853 756/3249 Investigate and repair LPRM 32-49 As Found:

Lo light unlit. As Left: Calibrated Detector B cards.

downscale alarm 11ght.

.Q99868 1001 Replace contactor for limitorque As Found: Contact was removed. As Left:

'RHR LPCI mode inject valve

. Installed new contactor assembly.

Inboard.

i L

TS IS

t UNIl 2 MAINTENANCE

SUMMARY

HORK REOUEST S151F.B EID DESCRIPTION HORK PERFORMED Q99905 2301 Repair air leak on solenoid HPCI As left: Replaced solenoid. No leaks found after l

testable check valve.

snooping.

Q99940 220 Replace broken support on U2 D.H.

As Found: Rods broken. As Left: Installed nev spring can pipe.

rod.

Q99943 756-Investigate power to B and C As Found: Fuse blorn for the 5V power supply for level LPRMs from APRM #1.

the A and C LPRM's. APRM bypassed. As left:

Pulled trip card and installed new fuse. Work request written for repair of bad card.

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l IV.

LICENSELEVIMLREEORIS 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 as-set-forth in sections 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

UNII_1 Licensee Event Report _ Number Data 11tle_of_0rcur.tence 92-011 05-30-02 A Recirc Loop Temp Recorder not workirg.

Missed T.S. Surveillance.92-013 04-23-92 Second level undervoltage relays setpoint nonconservative.

This one from last month was cancelled.

Included in 2-92-013.

URIL2 92-015 05-12-92 RCIC Flow Oscillations - RCIC INOP.92-016 05-19-92 CAM line pipe hanger outside design basis,92-017 05-24-92 RCIC INOP due to a hole-in the 2B C.S./RCIC submarine door.

TS 14

V.

DATA _ TABULA 110NS 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 18 14 6

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APPENDIX C OPERATING DATA REPORT DOCKrT N0 50_254 UNIT One DATE,)unt L_399L COMPLETED BY MalLBenign TELEPHONE 13091_bi4-ZZ41 OPERA 11NG STATUS 0000 050192

1. REPORTING PERIOD: 240Q_

.05119L GROSS HOURS IN REPORTING PERIOD: 2 44____ _

2. CURRENity AUTHORIZED POWER LEVEL (HWt): 2511.

MAX. DEPEND. CAPACITY: 219 DESIGN ELECTRICAL RATING (HWe-Net): 189

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

4. REASONS FOR RCSTRICTION (IF ANY):

THis HONTH YR TO DATE CUHULAllVE

5. HUMBER OF HOURS RLACTOR WAS CRITICAL...........

72LZQ

._.335L50

___.119B62JQ

6. REACTOR RESERVE SHUIDOWN HOURS..................

A Q_

Q10_

341119_.

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

121.10

_ 3313dQ 135564.Z0

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

0A 01

_.909.l_

?. GRO$$ THERHAL ENERGY GENERATED (MWH).............

16181002B_.

_BQ15)QLQ 29105E914 1

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

_53215310_

_ZG11D2910

_94606165 A

11. NET ELECTRICAL ENERGY GENERATED (HWH)............

.115025 A

_1521911 1

_.B9235341d_

12. REACTOR SERVICE FACT 0R...........................

_ __S6204 9L20 79 23

13. REACTOR AVAILABillIY FACT 0R......................

96194 91.90 81.11

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

9hS2 91.39 71dQ

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

96m92 9L11 77.31

16. UNIT CAPACITY FACTOR (Using HDC) 90.16 9Qal 65124

....s...........

17. UNIT CAPACITY FACTOR (Using 1.esign HWe)

Bldl 61110 6410Z

18. UNIT FORCED OUTAGE kAis.

6 QB 9.22 5J1

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

20. IF SHUTDOWN AT END OF REFORT PER100. ESTIMATED DATE OF STARTUP:

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMEDCIAL OPERATION Ts v4 1.16-9

- ~

f APPENDIX C OPERATING DATA REPORT DOCKET NO 5.0-165 UNIT Iwn.

DATE hne 4. 1992

?

COMPLETED BYI BatLftnin L TELEPHONE 13011_654-2241 OPERATING STATUS

. 1 p

0040 050192 l

1. REPORTING PERItD:.2400 0$3192_ GROSS HOURS IN REPORTING PERIOD:.744 i

2. CUPRENTt.Y AUTHORITED POWER LEVEL (MWt): Zhil MAX. DEFEND. CAPACITY: 769 DESIGN ELECTRICAL RATING (HWe-Net): 789

. i

3. POWER LEVEL TO WHICH RESTRICTED (If ANY) (MWe-Net): tuA r

-- e

4. REASONS FOR RESTRICTION (IF ANY):

THIS HONTH YR TO DATE CUHULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL............

515210 555255 134030225

6. REACTOR RESERVE SHU100WN HOURS.................

0,D_

0.0 2935 2.

g

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

460.30 460155 130480.45 f

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

0. 0..

0,0 702.9_

{

f

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

1007769.6.

1007944.80 281011831,80 i

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

.320051.QQ

_32A101,DA 2025Q2 L DA

11. NET ELECTRICAL ENERGY GENERATED (HWH)............

_._1015162DA-

-281910.00 85416085.00

12. REACTOR SERVICE FACT 0R...........................

-74.64 15.23 76.61

' l f

13. REACTOR AVAILABILITY FACT 0R......................

74.64 15 23 78.32 2

14. UNIT SERVICE FACTOR

.................s 61.82._

12 63 74.58 i

i

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

61.87.

12.63 74.98

16. UNIT CAPACITY FACTOR (Using t10C) 53.05 IQ2Q5 -

63.49

17. UNIT CAPACITY FACTCR (Using Design HWe)..........

51.71 9.BA

'61.88

18. UNIT FORCED OUTAGE RATE.........................

0.0 '

__ 0.0 8.06

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19. SHUTDOWNS SCHEDULED OVER NEXT 6 HONTHS (TYPE. DATE. AND D1) RATION OF EACH):

f

20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

21. UNITS IN TEST STATUS (PRIOR TO CON!ERCIAL OPERATION):

l FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY

-COMMERCIAL OPERATION l

+

1.16-9 TS 14

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l APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE hae_L_1122 COMPLETED BY Malt _DLuon TELEPHONE 1303L654-2241 MONTH Hav 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MHe-Net) 1.

764 17.

165_

2.

762 18. __

767 3.

350 19.

770 4.

6.93 20.

766 1

5.

776 21.

763 6.

777 22.

105 7.

737 23.

_164 8.

775 24, 768 9.

709 25.

771 J

10.

772 26.

773 11, 732 27.

772 12.

766 28.

770 13.

715 29, 702 14, 771 30.

0 15.

764 31.

-8 16.

767 INSTRUCTIONS On this form, list the average daily unit power level in MHe-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 leve! line).

In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

Ta u 1.16-8

APPCr4 DIX B AVERAGE DAILY UNIT P0 tier LEVEL DOCKET NO 50:265 UNIT Iwo DATE Juae_4 _1392 COMPLETED BY Matt _Hetison TELEPHONE 1309L654-2211 HONTH _May_1932 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P0HER LEVEL (MHe-Net)

(HHe-Het)

1. _

17.

52.7_

2.

8 18.

774_

3. 19.

785 4.

-B 20.

-- 283 5.

-8 21.

72 2 6.

-8 22, 7B2 7.

-B_

23.

701 8.

-8

24..

750 9.

- B_

25.

760 10.

-8 26.

789 11.

.16 27.

787 12.

L43 28.

790_.

13.

237 29.

785 14.

261.

30.

7B3 13.

351 31.

73 3 16.

JOB INSTRUCTIONS On this form list the average daily unit power level in HHe-Net for each day in the re nrting month. Compute to the nearest w! ale-megawatt.

These figures aill 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, tnere may be cccasions when the daily average power level exceeds the 1001, 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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P VI. UNIQULREEORIING_RLOUIREMENIS

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The following items are included in this report based on prior comitments (o i

the commission:

A.

Main _S t e am_R elleLYah e_0p eration s 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.

Unit:

Two

(

Date:

5/11/92 Vahes. Actuated Noi_LIype_of_Attuttlon 2-203-3A, 3B, 3C, 3D, 3E Normal Surveillance and Post Maintenance following Q2R11.

flani_ fond 111oni: Startop from Q2R11.

l F

Descrlation_oLhenti:

l The 2-203-3A Target Rock Safety / Relief valve was operated twice due to the Acoustic monitor associated by this valve not giving open indicatton on the first try. Acoustic Monitor worked on second operation.

B.

Cont toLRod_.Drhe_S c tam _lbning _D a t a_.for_ Unit s_0ne_a nd_ho The basis for reporting this data to the Nuclear Regulatory Consnission are specified 1_n the surveillance requirements of Technical Specifications i

4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units One and Two control Rod I

Drive Scram Timing for the reporting period. All scram timing was performed with reactor pressure greater than 800 PSIG, l

l TS14

_ _ _.. ~. _..

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 1-1-92 TO 12-31-92 AVERAGE TIME IN SECONDS AT 1 MAX. TIME INSERTED FROM FULLY HITHDRAhN FOR 90%

INSERTION DESCRIPTION NUMBER 5

20 50 90 Technical Specification 3.3.C.1 &

DATE OF ROOS 0.375 0.900 2.00 3.5 7 sec.

3.3.C.2 (Averase_1crram Insertion Tlead__

2-19-92 2

0.28 0.67 1.43 2.48 J-2 Drive Replacement (J-2), Scram Valve N-7 2.55 2-20-92 1

0.32 0.69 1.45 2.45 N-5 Scram Valve Work N-5 2.45 5-12-92 177 0.31 0.69 1.47 2.58 L-13 Start-up Scram Timing Unit Two 3.43 TS 75 A

O Vll. REfuE11NC_llifDRIMII0li The following information about future reloads at Cuad-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.

e 19 14

QTP 300-532 o

Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION RE F T 1.

Unit:

91 Reload:

11 Cycle:

12 2.

Scheduled date for next refueling shutdown:

9-5-92 3.

Scheduled date for restart following refueling:

12-5-92 4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

NOT AS YET DETERMINED.

5.

Scheduled date(s) for submitting proposed licensing action and supportir>; Nformation:

NOT AS YET DETERMINED.

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

NONE AT PRESENT TIME.

7.

The number of fuel assemblies.

4.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1405 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:

7 b.

Planned increase in licensed storage:

0 9.

The projected date of the last refueling that can-be discharged to the spent fuel pool assuming the present licensed capacity:- 2009 APPROVED (final) 14/0395t 001 3 0 1969 C).C.O.S.R.

QTP 300-532 Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

11 12 Cycle:

2.

Scheduled date for next refueling shutdown:

03/06/93 3.

Scheduled date for restart following refueling:

06/05/93 4.

Will refueling or resumption of operation thereafter require a fechnical Specification change or other license amendment:

NOT AS YET DETERMINED.

5.

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

NOT AS YET DETERMINED.

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, un:eviewed design or performance analysis methoJs, signtficant changes in fuel design, new operating-procedures:

NONE AT PRESENT TIME.

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

n39 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 dato of the last refueling that can be discharged to the-spent. fuel pool assuming the present licensed capacity: 2009 APPROVED i

(final) 14/0395t DCT 3 01969 O.C.O.S.R.

VIII.

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

ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Honitoring ANSI

- American National Standards Institute APRM

- Average Power Range Monitor ATHS

- Anticipated Transient Without Scram BHR