ML20005D673

Monthly Operating Repts for Nov 1989 for LaSalle County Nuclear Power Station

ML20005D673
Person / Time
Site:	LaSalle
Issue date:	11/30/1989
From:	Diederich G, Thunstedt J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8912140084
Download: ML20005D673 (27)

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, Commonwealth Edison :

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LaSalle County Nuclear Station; F

Rural Route #1, Box 220

, Marseillescillinois 61341 :

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Telephone 815/357-6761

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Director of Nuclear _ Reactor Regulation.

-United States Nuclear Regulatory Commission

Mail Station F1-137 Washington, D.C.

20555 ATTN: Document Control Desk Gentlemen:

Enclosed:for your information is the monthly performance report covering L

'LaSalle County Nuclear Power Station for November, 1989.

Very truly yours,'

_i O

G. J. Diederich f0/ Station Manager i-LaSalle County Station l

tNN'

[ GJD/JWT/sjj Enclosure

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'A.

B.' Davis, NRC, Region III NRC Resident Inspector LaSalle Ill.-Dept. of Nuclear Safety P. Shemanski, NRR Project Manager D.

P.

Galle, CECO D..L.

Farrar, CECO-i INPO Records Center' L. J. Anastasia, AIP-Coordinator, Nuclear Services J. E. Kuskey, GE Resident T. J. Kovach, Manager of Nuclear Licensing Lil W. F. Naughton, Nuclear Fuel. Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle l

' Terry Novotney, INPO Coordinator, LaSalle Station T. A.

Hammerich, Regulatory Assurance Supervisor J. W..Gieseker, Technical Staff Supervisor Central File c

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'F LASALLE NUCLEAR' POWER STATION

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UNIT 1 MONTHLY PERFORMANCE REPORT l

NOVEMBER 1989 COMMONWEALTH EDISON COMPANY

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NRC DOCKET NO. 050-373 s

LICENSE NO. NPF-11 4

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TABLE OF CONTENTS

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I.

INTRODUCTION

,[

II.- ' REPORT A.-

SUMMARY

'OF OPERATING EXPERIENCE B.

PLANT. OR PROCEDURE CliANGES, TESTS, EXPERIMENTS,. AND SAFETY CELATED MAINTENANCE.

1.

Amendments to Facility License'or Technicel Specifications 2.

Changes to procedures which are described in the Safety Anal sis Report

'~

3 <.

Tests and Experiments not covered in the Safety Analysis Report' 4.

Corrective Maintenance of Safety-Related Equipment-5.

Completed Safety-Related Modifications C.

LICENSEE EVENT REPORTS D.

DATA TABULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Leval 3.

Unit Shutdowns and Power Reductions

+

.E.

UNIQUE REPORTING REQUIREMENTS 1.

Main Steam Relief Valve Operstions 2.

ECCS System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioactive Waste Treatment Syster.;

5.

Indicat'ons of Failed Fuel Elements ZCADTS/5

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JNTRODUCTION The LaSalle County Nuclear Power Station is a two-unit f acility owned by

)

Commonwealth Edison Company and located near Marseilles, Illinois.

Each unit is a Bolling Water Heactor.with a designed net electrical output of 1078 Megawatts. Waste haat is rejected to a man-made cooling pond'using-the Illinois River for make-up and blowdown. The architect-engineer was q

Sargent-and Lundy and the primary construction contractor was Commonwealth Edison Company.

Unit One was issued operating license number NPF-11 on April 17, 1982.

Initial criticality was achieved on June 21, 1982 and commercial power o} 3 ration was commenced on January 1,- 1984.

This report was compiled by John W. Thunstedt, telephone number (815)357-6761, extension 2463.

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' Ill: MONTHLY REPORT'

• A.

SUMMARY

OF OPERATING-EXPERIENCE DAY

. Ilmt.

Event A-1 0000 Reactor subcritical, generator off-line, L1R03 in progress.

30 2400 Reactor subcritical, generator off-line, L1R03 in progress..

B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED-MAINTEN ANCE.

1.

Amendments to the-Facility License or Technical Specification.

(None) 2.

Changes to procedures which are described in the Safety Analysis Report.

(None) l' 3.

Tests and Experiments not described ir. the Safety Analysis Report.

(None) 4.

Major. corrective maintenance to Safety-Related Equipment.

(See Table 1) 5.

Completed Safety-Related Modifications.

I (See Table 2) t 3

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MAJOR CORRECTIVE MAINTENANCE TO

- s SAFETI-RELATED EQUIPMENT

' HORK REQUEST RESULTS'AND EFFECTS NUMBER COMPONENT CAUSE OF. MALFUNCTION.

ON SAFE PLANT OPERATION-

-CORRECTIVE.ACTIONe (Unit 0)

(None)

(Unit 1)

L82653 lE12-S001B B RHR IDC Service water-side fouling Loss of cooling capacity Hydrolazed L94374 1E22-S001 1B-D/G Broken wire on shut-down Erratic control Replaced solenoid; Governor solenoid L94408 lE12-F048B Check Fouled internals Valve sticks closed Cleaned internals-

. Valve L94473 1E12-F084C Check Fouled internals Valve sticks closed Cleaned internals.

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COMPLETED SAFETY-RELATED MODIFICATIONS HUliBER DESCR_IETION LM01-0-85-021 Install limit switch and_ time delay panel to monitor the emergency escape hatch'above the storage tank room for the Diesel Generator ODG01K.

M01-0-87-011 Revise the start circuit of diesel generator

'O' to prevent a fail-to-start trip, the start circuit is modified to interlock cranking lockout switch S6 with both the air start solenoids and timer K39.

M01-0-88-011 Installation of a Redundant Access Control Systm (RACS) which will utilize existing card readers and' alarm sensors to control access through vital area doors.

~

M01-1-84-098 Removal of the-isolation and alarm function of the Riley i

Modules for the Reactor Water Cleanup Pump Room Temperature Leak Detection (LD) System.

M01-1-85-050 Install limit switch and time delay panel to monitor the-emergency escape hatch above the storage tenk room for the Diesel Generator 1DG0lK.

M01-1-85-051 Install limit switch and time delay panel to monitor the emergency escape hatch above the storage tank room for the Diesel Generbtor 1DG0lK.

M01-1-86-085 Modify the_ control circuitry to prevent closure of the diesel generator = breaker.onto e faulted bus-and also trips the breaker upon bus fault indication as long as an ECCS signal is not present.

M01-1-87-007 Replace the existing " Local-Remote" transfer switch and add a new set of control circuit fuses to existing sw1*chgear breaker controls for the Diesel Generator '1A' Feed Breakers.

M01-1-87-009 Replace the existing " Auto-Manual" ttansfer switch and add a new set of control circuit fusos to existing Generaor and Engine-Control Panel 1DG02JB for the DG "11" Control Circuit.

M01-1-87-010 Replace the existing " Local-Reniote" transfer switch and add a new set of control circuit fuses to existing switchgear breaker controls for the DG "lA" CWP 1DG01P Feed Dreaker, r

M01-1-87-012 Replace the existing " Auto-Manual" transfer switch and ndd a new set of control circuit fuses to existing Generator and Engine Control Panel.0DG02JB for the DG "0" Control Circuit.

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N01-1 013 :: ~ Rdp1Cc3 thi duisting " Local-Rem 3td" trcnsf0r cwitch:s End god a -

4 nIw estiof cratrol' circuit.futss to exicting cwitchg;2r"br0ckor

. c:ntrols; for~ th3 ESS Division 2 Fcsd Bronkors, RHR Pump 1B

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Circuit and the RR SW pumps IC and 1D circuits.

M01-1-87-090- ' Revise the' start circuit of diesel generator 1B to prevent a fall-to-start trip unless the air start solenoids have been-i energized,' allow continuous cranking of the diesel engine for

~the entire time delay set of crank liit timer K39.

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'M01-1-89-018 Modify the:VR-dampers indication lights to provide a green' 4

light when the damer. ts fully closed, and a red light when the damer is in fally open position and both lights in the-intermediate position.'-

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'89-025-00 11/01/89 Loss'of Bus.142Y Due to Closing Switchgear Door and i f

Jarring Relays.

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.89-026-00 11/06/89 Inadvertent PCIS Isolation s89-027 11/13/89 - Inadvertent PCIS Signal 189-028-00

'11/22/89' Output' Breaker Failure to Close

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DATA TABULATIONS h'

1.- Operating. Data Report (attached) 2.

AverageDailyUnitPower' Level (attached) 1 3 '. Unit' Shutdowns and Power Reductions (attached).

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D.i DPERATING DATA REPORT-DOCKET NO. 950-373

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DATE December ie,1989 gCW 3'

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COMPLETED BY J.W. THUNSTEDT I1 TELEPHONE (815)-357-6761; y

[0PERATINGSTATUS P,1.SREPORTINGPERIOD:~

iI NDVESER 1989-

=GROSSHOURSINREPORTINGPERIOD:

720 -

p 7 E.y h2kCURRENTLY. AUTHORIZED POWER LEVEL (Mih 3,323:

MAX DEPEND CAPACITY (Me-Net):

1,036 f* #

DESIGN ELECTRICAL. RATING.(Me-Net) 1,079; (iij;[y' f3.:rPOWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

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4Oj REASONS FOR. RESTRICTION (IF ANY)

' REFUELING,(LtR03)

REPORTING PERIOD DATA

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THIS MONTH YEAR-TO-DATE

~ CUMULATIVE p &lC W5kTIMEREACTORCRITICAL-(HOURS)-

0.0 6,114.0

.32,134.fi c,

(a j-J6tlTIMEREACTORRESERVESHUTDOWN(HOURS)'

O.0 0.0 -

'1,641.2 v.

[ % TIME GENERATOR ON-LINE (HOURS) 0.0-7 6,103.B -

'31,418.3 r

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W 8 4 TIME GENERATOR. RESERVE SHUTDOWN (HOURS)-

0.0 0.0-1.0 R

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19,054,990 87,833,568

59. THERMAL ENERGY GENERATED ( M Hi-Gross).

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}io.[ELECTRICALENERGYGENERATED(MWHe-Gross).

.0' 4,422,787 29,068,541, a f.

e yti.'ELECTRICALENERGYGENERATED(MHe-Net)

-7,227 6,164,778 27,740,307 t

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(.,13 3 REACTOR SERVICE FACTOR (I)-

0.0 76.1 61.9' d

313. REACTOR AVAILABILITY FACTOR (I) 0.0=

76.1 65.1:

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. 0.0 75.9 60.6 s

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15! AVAILIBILITY FACTOR (I) 0.0-75.9 60.6' la

16. CAPACITY FACTOR l(USING MDC) (%)

-1.0 74.0 51.6

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--0.9 71.1

49.6.

517,{APACITYFACTOR(USINGDESIGNMe)(%)

L18..FORCEDOUTAGEFACTOR(%)

0.0 1.4 10.1 l

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$ 19! SHUTDOW M SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

. (None) l J20!'IF SHUTDOWN AT END OF REFORT PERIOD, ESTIMATED DATE OF STARTUP:

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' DECEMBER 28,1989 l'

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PCTHOD OF YEARLY TYPE SHUTTING DONN SEQUENTIAL F: FORCED DURATION THE REACTOR OR CORRECTIVE NUMBER DATE S: SCHEDULED (HOURS)

REASON REDUCING POWER

- ACTIONS /CODGENTS 54 9/15/89 S

720 C

4 Refueling Outage (LlR03).

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E.' UNIQUE REPORTING REQUIREMENTS--

11.

Safety / Relief valve operations ~

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT

-(None)

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ECCS System Outages j

OUTAGE NO EQUIPMENT PUP. POSE

-j 2

(Note ' the year and ~ unit numbers have been ommitted f rom the Outage Number)

(Unit 0) 319 0 D/G (Misc.)

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1 320 0 D/G Fuel Oil Day Tank j

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-0 D/G ODF-047 (Crank case pressure).

323 O D/G (Misc.)

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324-0 D/G (Misc.)

-325 0 D/G Perform LES-GM-129 326

.0 D/G Cooling Water Pump Perform L92504 327 0 D/G Perform LMS-DG-Ol' 328 0 D/G Replace banana plugs 329 0 D/G Clear Temp System Change 1-957-89 l'

332 0 D/G B Air Compressor Resolve loading problem 334 ODG08CD Repair unloader.

335' ODG01K Torque cylinder heads 339 0 D/G Resolve output breaker problem (Unit 1) 1311 1A D/G Feeder Breaker Replace Control Switch L

l 1314 1A D/G Tighten DC lugs 1315 1A D/G Perform hot-engine checks l

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-1A~D/G R;p10c2chicid$j U

13'19 1B D/G' R:plir 1E22-NS10.

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1320 LPCS Pump (Administrative) 1328-1E22-F005 (HP)

Add packing rings for LLRT 1334-'

1A RHR Enforce RPV Drain path j

1335L 1C RHR

-Fill Rx cavity from SF

-l 1350 1E12-F004C (RH)

Perform LES-EQ-112

.j 1366 1E12-F004D (RH)

Perform LES-EQ-112 1372 1E12-C003_(RH)

Replace '74' Relay "1373 1E12-F068 (RH)

(Administrative) 1389 1E12-F092C/B (RH)

Perform LTS-500-110 y

1 1392 ODG01K Auxilleries (Administrative) 1393 ODG01K Air. System Cross-tie receivers 1394 ODG01K Auxillaries Install temporary power 1395~

ODG01K Auxiliaries Install temporary power i

.1400 1E12-F)08 (RH)

Replace lug on 1B21H-K30 1

1407 1E12-F004A (RH)

Inspect torque switch 1408 1E12-F016A (RH)

Repack valve 1409 1E12-N029A (RH)

Replace valve manifold 1413 1E12-F041A (RH)

Repair actuator

.1476 LPCS (Administrative) 1490 1E12-C300D (RH)

Lubricate coupling l

1491 1E51-F064 (RI)

Repair oil leak i

1502 1E12-F099A (RH)

Perform LES-AP-101 1503 IB D/G Inspect governor shutdown valve 1513 RCIC Water-leg Pump Lubricate coupling 1515 RH Water Leg Pump (Div III) Clean check valves F084B & C l

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. i1 1516 1E21-C001 LPCS Pump' Flu:h m ttr croling-coil r

1518-c1E12-F068B B RHR WS Parform LES-EQ-112 1

152'6-1E12-F087B (RH)

Inspect breaker 1542-1E12-F041A (RH)

Add valve packing-1545 1DG023 (Administrative)

'1547' RHR SDC Perform LES-PC-106 1549

'19G023 (Administrative) 1564:

RHR 24B & 27B Run S/D Cooling.

L 1586 HPCS Perform Div III response time test' 1596 1E22-S001 (HP)

Repair fuel leak 3.-

Changes to the Off-Site Dose Calculation Manual (None).

4.

Major changes to Radioactive Waste Treatment Systems.

(None) 5.

Indications of Failed Fuel Elements.

(None)-

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LASALLE NUCLEAR POWER STATION-UNIT.2 MONTHLY PERFORMANCE REPORT NOVEMBER,.1989-COMMONWEALTH EDISON COMPANY-t

,NRC DOCKET NO. 050-374 l

LICENSE NO. NPF '. }

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i TABLE OF CONTENTS I.

INTRODUCTION f

II.

REPORT A.

SUMMARY

OF OPERATING EXPERIENCE

- )B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAI"TENANCE 1.

Amendments to Facility License or Technical Specifications 2.

Changes to procedures which are described in the Safety Analysis Report.

3.

Tests and Experiments not covered in the Safety Analysis Report.

4 Corrective Maintenance of Safety-Related Equipment 5.

Completed Safety Related Modifications C.

LICENSEE EVENT REPORTS D.

DATA TABULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Level 3..

Unit Shutdowns and Power Reductions E.

UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations 2.

ECCS System Outages

.3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioactive Waste Treatment System 5.

Indications of Failed Fuel Elements ZCADTS/7

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I.

INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near harseilles, Illinois. Each L'

unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is_ rejected to a man-made cooling pond using the~ Illinois River.for make-up and blowdown.

The architect-engineer was

'Sargent and Lundy-and the primary construction contractor was Commonwealth Edison Company, s

Unit Two was issued operating license number NPF-18 on~ December 16, 1983.

Initial criticality was achieved Tnt March 10, 1984 and commercial

power operation was commenced on June 19, 1984.

This report was complied by John W. Thunstedt, telephone number (815)357-6761 extension 2463.

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- I I'.. MONTHLY' REPORT-

SUMMARY

OF OPERATING EXPERIENCE A..

_ Time-Event

' day 1

0000 Reactor critical, generator on-line at 3305 MWT.

0300 Reduced load to 3080 MWT for CRD exercising.

1000 Returned to full power.

8 0300

, Reduced load to 2961 MWT for CRD, MSIV, and Control Valve Testing.

1200 Returned to full power.

~

l 15 0100 Reduced load to 3056 MWT for CRD exercising.

1200 Returned to full power.

19 0000 Reduced load to 2013 MWT to reduce dose rates in FW heater bay.

0700 Returned.to full power.

22 0100-Reduced load to 2934 MWT for CRD exercising and rod-line adjustment.

1100 Returned to full power.

29 0000' Reduced load to 2530 for CRD exercising, MDRFP testing, and rod-pull.

1300 Returned to full power.

30 2400 Reactor critical, generator on-line at 3323 MWT.

B.-

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

l..

knendments to the Facility License or Technical Specification.-

(None) 2.

Changes to procedures which are described in the Safety l

Analysis Report.

(None) l l

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MAJOR' CORRECTIVE MAINTENANCE TO SAFETT-RELATED EQUIPMENT WORK REQUEST..

RESULTS AND EFFECTS NUMBER COMPONENT,

.CAUSE OF MALFUNCTION-CN SAFE PLANT OPERATION-CORRECTIVE ACTION.

L94740 2B21-NO38 S-O-R Worn-internals Reject limits exceeded

' Replaced switch' Switch b -'

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. COMPLETED SAFETY RELATED MODIFICATIONS f,

MODIFICATION NUMBER DESCRIPTION __

M01-2-85-070 Install a limit switch and time delay panel to monitor the

. emergency escape hatch above the storage tank room for i

HPCS Diesel Generator 2DG01K.

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- M01-2-85-071 Install a limit switch and time delay panel to monitor the emergency escape hatch'above the storage tank _ room for HPCS Diesel Generator 2E22-S001.

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4 C.i LICENSEE EVENT-REPORTS-i

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,.<mg 89-016-00:

11/09/89; RWCU Leak Detection Isolation ~.

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'89-017-00' zll/17/89' HPCS Min Flow Bypass Switch Failure.

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. DATA TABULATIONS

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1. Operating Data Report (Attached) 1

2. Average Daily Unit-Power Level (Attached) 3.. Unit Shutdowns and Power Reductions (Attached)

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D.'i -l 0PERATIE DATA REPORT i

'DOCl(ET NO. 050-374' l

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UNIT LASALLE TWO!

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'e DATE December 10, 1989 :

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COMPLETED BY J.W.THUNSTEDTE M

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7 OPERATIE STATUS -

sc Lt.1REPORTINGPERIOD:

NOVEMER1989l GROSS HOURS IN' REPORTING PERIOD:

720 y,.-

'2.l CURRENTLY.AUTHORIZEDPOWERLEVEL(Wt):

3,323T

_ MAX DEFEND CAPACITY (Me-Net);

% i,036 '

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DESIGN ELECTRICAL RATING (Me-Net)

1,078 -

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32POWERLEVELTOWHICHRESTRICTED(IFANY)(Ne-Net):

(None)'

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4.-~REASONSFORRESTRICTION(IfANY)i (N/A).

REPORTING PERIOD DATA'-

THIS MONTH YEAR-TD-DATE iCUMULATIVEi

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5. TIME REACTOR CRITICAL (HOURS) 720.0:

.5,925.1-

29,403.1-6 TIME REACTOR RESERVE SHUTDOWN (HOURS)

- 0.0 0.0 1,716.9.

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7.-iTIME GENERATOR DN-LINE (HOURS)-

720.0 5,848.1 28,939.1 e L8 a TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 fa

,9MTHERM#.ENERGYGENERATED(MWHt-Gross)'

2,334,840 17,967,600 83,907,208 f10. ELECTRICAL'ENERGYGENERATED(MHe-Gross)-

798,800 5,921,917

~ 27,625,255_

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iL ELECTRICAli ENERGY GENERATED '(MWHe-Net) 774,542 5,699.005-26,438,255 e

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12. REACTOR SERVICE FACTOR (%)

100.0 73.7 65.5 El3.REACTDRLAVAILABILTTYFACTOR(%)

100.0 -

73.7 69.3 114. SERVICE FACTOR (Z) 100.0 3

72.7 64.5-

_y ot$." AVAILIllILITY FACTOR -(%).

_100.0 72.7-64.5 116. CAPACITY FACTOR (USING MDC) (%)

103.8 68.4 56.9 -

i ii7.CAPACITYFACTOR-(USINGDESIGNNe)(Z)'

99.8 65.8 54.6' i.18. FORCED OUTAGE FACTOR (%)'

O.0 15.7 16.7-

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

Refueling (L2R03) 03/17/90 12 Weeks L 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

(N/A)

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DATE December io,1989 COMPLETED BY J.W. THUNSTEDT TELEPHONE (015)-357-6761 p.

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REPORT PERIOD:

NOVEMBER 1989-DAY-POWER DAY POWER

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1,082 17 1,103 0

'i,097 18 1,078 -

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'3 1,100 19 687 h

4 t,100 20 937 s

5 i,100 -

21 1,090 '

' 6 1,101 22 1,084

- 7 1,105 23 1,100

- B-1,085 24 i,101 9."

i,102 25

.1,102 10 1,096 26 1,100 11 1,101 27 1,100 12 1,102 28 1,095 13 1,103 29 1,038 14 1,100 30 1,102 15 1,082 31 16 1,099

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METHOD OF YEARLY TYPE SHUTTING DOWN SEQUENTIAL F: FORCED-DURATION-THE REACTOR OR

' CORRECTIVE NUMBER DATE S: SCHEDULED (HOURS)'

REASON CODE REDUCING PONER ACTIONS /CODMENTS 31 19 S

0.0 F

5 Reduce dose rates in FW.

heater bay.to permit-inspection.'

32 29 S

0.0 B

5 CRD exercising, MDEFP; testing,_. rod-pull.

Corrections to the August 1989 Report:

20 1

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' 0. 0 G

4 Repaired feed pump.

26 26 S

140.8 H

3 RR Pump Seal repairs.

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UNIQUE. REPORTr.':G REQUIREMENTS.

1. S fsty/R311cf V&lv] Op;rctiona VALVES NO & TYPE PLANT DESCRIPTION RATE ~

ACTUATED ACTUATIONS CDliDlIlQti QE_EYENT (None) 2.

ECCS System Outages-QUIAGE.XQ.

EQU.IEMENT EUEEDHE NOTE: The year and unit designators have been ommitted from the Outage Number.

h 2004 2E12-F087B (RH)

Perform EQ inspection 1005 2E12-F040B (RH)

Perform EQ. inspection 1006 2E12-F093 (RH)

Perform EQ inspection l

m 1007 2E12-F049A (RH)

Perform EQ inspection 1009 2C'RER Pump Replace oil 1011 2E12-C003B (RH)

Perform EQ inspection 1019 HPCS (Administrative) 1033 2B D/G A Air Repair valve Compressor

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Changes to the Off-Site Dose Calculation Manual l

l (None).

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Major changes to Radioactive Waste Treatment Systems.

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Indications of Failed Fuel Elements.

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