Text

Monthly Operating Repts for Oct 1991 for Dresden Nuclear Power Station
	ML17174A960
Person / Time
Site:	Dresden
Issue date:	10/31/1991
From:	Eenigenburg E, Maxwell D; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
	91-675, NUDOCS 9111130022
	Download: ML17174A960 (36)
	v • d • e

'

Co.'onwealth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 EDE LTR:

91-675 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Attention:

Document Control Desk

Subject:

Monthly Operating Data Report Dresden Nuclear Power Station Commonwealth Edison Company November 1, 1991 Docket Nos.50-010. 50-237. and 50-249 Gentlemen:

Enclosed is the Dresden Nuclear Power Station Monthly Operating Swmnary Report for October, 1991.

This information is supplied to your office in accordance with the instructions.set forth in Regulatory Guide 1.16.

Please note that the report contains information which had been previously submitted to your attention on an annual basis in accordance with 10 CFR 50.59.

EDE:DCM:dwh Enclosure cc: U.S. NRC Region III Office Sincerely,

'J.). ~~

E. D. Eenigenburg Station Manager Dresden Nuclear Power Station Illinois Dept. of.Nuciear Safety, State of Illinois U.S. NRC, Document Management Branc!t/

Nuclear Licensing Aaministrator Vice Pres. -

BWR Operations General Manager - Nuclear Services T. S

Engr * ( 2)

NRC Senior Resident Inspector Nuclear Quality Programs - Ores.den Nuclear Engineering Manager Comptroller's Office Manager - Quality Assurance/Nuclear Safety Manager - Reliability Programs INPO Records Center

File/NRC Op. Data File/Nwnerical ZEDE91/425 150072

- ~

MOM'l'JILY :NllC.

SJDIWtY OF OPERATING KXPKR.IENCI.

<!RANGIS. TESTS. AND WKR.J11ENTS PER. REGULATORY GUIDE 1.16 Mm 10 CFll 50.59 DRK-c;DEN NtJCIMR POWEil STATION C<llQMW.l'B EDISOH C<llPANY FOR. ocm:en. 1221 DOCKET LICENSE 1

050-010 DPR-2 2

050-237 DPR-19 3

050-249 DPR-25 ZEDE91/425/2

TABLE OF CONTENTS 1.0 Introduction 2.0 Summary of Operating Exper~ence 2.1 Unit 2 Monthly Operating Experience Swmnary for October, 1991 2.2 Unit 3 Monthly Operating Experience Swmnary for October, 1991 3.0 Operating Data Statistics 3.1 Monthly Operating Data Report - Unit 2 3.2 Monthly Operating Data Report - Unit 3

'3.3 Average Daily Power Level Data - Unit 2 3.4 Average Daily Power Level Data - Unit 3 3.5 Unit Shutdown and Power Reduction Data - Unit 2 3.6 Unit Shutdown and Power Reduction Data - Unit 3 3.7 Station Maximum Daily Load Data 4.0 Unique Reporting Requirements 4.1 Main Steam Relief and/or Safety Valve Operations - Unit 2 and Unit 3 4.2 Off-Site Dose Calculation Manual Changes 4.3 Major changes to the Radioactive Waste Treatment 4.4 Failed Fuel Element Indications 4.4.1 Unit 2 4.4.2 Unit 3 5.0 Plant or Procedur~ Changes. Tests. Experiments, and Safety Related Maintenance 5.1 Amendments to Facility License or Technical Specifications 5.1.1 Unit 2 5.1.2 Unit 3 5.2 Changes to Procedures Which are Described in *the Final Safety Analysis Report (FSAR) (Units 2 and 3) 5.3 Significant Tests and Experiments Not Described in the FSAR (Units 2 and 3) 5.4 Safety Related Maintenance (Units 2 and 3) 5.5 Completed Safety Related Modifications 5.6 Temporary System Alterations Installed 5.7 Other Required 10 CFR 50.59 Evaluations (Units 2 and 3)

ZEDE91/425/3

l~O Introduction Dresden Nuclear Power Station is a three reactor generating facility owned and operated by the Conunonwealth Edison Company of Chicago, Illinois.

Dresden St~tion is located at the confluence of the Kankakee and Des Plaines Rivers, in Grundy County, near Morris, Illinois.

Dresden Unit 1 is a General Electric Boiling Water Reactor with a design net electrical output rating of 200 megawatts electrical (MWe).

The unit is retired in place with all nuclear fuel removed from the reactor vessel.

Therefore, no Unit 1 operating data is provided in this report.

Dresden Units 2 and 3 are General Electric Boiling Water Reactors with design net electrical output ratings of 794 MWe each.

Waste heat is rejected to a man-made cooling lake using the Kankakee River for make~up and the Illinois River for blowdown.

The Architect-Engineer for Dresden Units 2 and 3 was Sargent and Lundy of Chicago, Illinoi~.

This report for October, 1991 was compiled by Donald C. Maxwell of the Dresden Technical Staff, telephone number (815) 942-2920, extension 2489.

ZEDE91/425/4

2.0 SUMMA.RY OF OPERATING EXPERIENCE FOR OCTOBER. 1991 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE

SUMMARY

10-01-91 to 10-31-91 ZEDE91/425/5 Unit 2 entered the month on line and operating in Economic Generation Control (EGC) at 788 MWe/Hr per the System Load Dispatcher., Operations continued at maximwn loads or in EGC through 10-21-91.

The unit was manually taken off line at 2120 hours0.0245 days 0.589 hours 0.00351 weeks 8.0666e-4 months because of the Station 250V Battery System being declared inoperable based on test results involving the Unit 3 250V Battery.

The Reactor was made subcritical at 2151 hours0.0249 days 0.598 hours 0.00356 weeks 8.184555e-4 months of the same day.

Startup of the unit will commence after satisfactory resolution of battery operability.

The unit remained off line through the reminder of the month with an availability of 67.29% and a capacity factor of 57.20%.

fl '

SUMMARY

OF OPERATING EXPERIENCE FOR OCTOBER. 1991 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

10-01-91 to 10-31-91 Unit 3 remained off line during the month of October for its 12th Refueling Outage (D3Rl2).

ZEDE91/425/6 Major work during the month included:

Primary Containment Local Leak Rate Testing (LLRT) and valve repairs.

In-Service Inspection (!SI) of various Primary System Piping.

Diesel Generator Modifications and testing.

Normal Refueling Outage related work.

Main Turbine Overhaul.

3.0 OPERATING DATA REPORT 3.1 OPERATING DATA REPORT - UNIT TWO OPERATING STATUS

1.

REPORTING PERIOD: October. 1991 DOCKET NO. --'0,._.5'""'""0'----=2..._3 7.__ __ _

DATE November 1. 1991 COMPLETED BY __.D"°-'.L......>OC,_..._._,M....,axw...=.:_..e_,,,_l.,,._l _

TELEPHONE -~<

8~1~5~)_94~2~~~2~9=20~

2.

CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 MAX DEPEND CAPACITY (MWe-Net) 772 DESIGN ELECTRICAL RATING (MWe-Net) 794

3.

POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

N/A

4.

REASONS FOR RESTRICTIONS (IF ANY):

N/A REPORTING PERIOD DATA

5.

HOURS IN PERIOD 6;

TIME REACTOR CRITICAL (Hours)

7.

TIME REACTOR RESERVE SHUTDOWN (Hours)

8.

TIME GENERATOR ON-LINE (Hours)

9.

TIME GENERATOR RESERVE SHUTDOWN (Hours)

10.

THERMAL ENERGY GENE.RATED (MWHt-Gross)

11.

ELECTRICAL ENERGY GENERATED(MWHe Gross)

12.

ELECTRICAL ENERGY GENERATED (MWHe-Net)

13.

REACTOR SERVICE FACTOR (%)

14.

REACTOR AVAILABILITY FACTOR (%)

15.

GENERATOR SERVICE FACTOR (%)

16.

GENERATOR AVAILABILITY FACTOR (%)

17.

CAPACITY FACTOR (USING MDC) (%)

18 *.

CAPACITY FACTOR (USING DESIGN MWe) (%)

19.

FORCED OUTAGE FACTOR (%)

20.

SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (Type, Date and Duration of Each)

NONE This Month Yr-to-Date 745 7,296 501.9 5,274.2 o.o 0.0 501.3 5,033.7 o.. o o.o 1,109,413 10,017,367 354,967 3,163,207 338, 911 2,976,603 67.4 72.3 67.4 72.3 67.3 69.0 67.3 69.0

.58.9 52.8 57.3 51.4 32.7 19.9

21.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP 11-08-91 ZEDE91/425/7 Cumulative 188,184 142,013.2 o.o 136,006.6 o.o 281,621,510 89,968,984 85,041,104 75.5 75.5 72.3 72.3 58.5 56.9 11.1

3.0 OPERATING DATA REPORT 3.2 OPERATING DATA REPORT - UNIT THREE OPERATING STATUS

1.

REPORTING PERIOD: October. 1991 DOCKET NO._0~5~0~-~2~49~---

DATE November 1. 1991 COMPLETED BY ~D~*~c~*~M=axw~~e~l=l __

TELEPHONE _(~8~1~5~)~9~4~2~-~2~92~0~-

2.

CURRENTLY AUTHORIZED POWER LEVEL (MWth):

2,527 MAX DEPEND CAPACITY (MWe-Net) 773 DESIGN ELECTRICAL RATING (MWe-Net) 794

3.

POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

N/A

4.

REASONS FOR RESTRICTIONS (IF ANY):

N/A

5.

HOURS IN PERIOD

6.

TIME REACTOR CRITICAL (Hours)

7.

TIME REACTOR RESERVE SHUTDOWN (Hours)

8.

TIME GENERATOR ON-LINE (Hours-)

9.

TIME GENERATOR RESERVE SHUTDOWN (Hours)

10.

THERMAL ENERGY GENERATED (MWHt-Gross)

11.

ELECTRICAL ENERGY GENERATED(MWHe Gross)

12.

ELECTRICAL ENERGY GENERATED (MWHe-Net)

13.

REACTOR SERVICE FACTOR (1)

14.

REACTOR AVAILABILITY FACTOR (1)

15.

GENERATOR SERVICE FACTOR (1)

16.

GENERATOR AVAILABILITY FACTOR (1)

17.

CAPACITY FACTOR (USING MDC) (1)

18.

CAPACITY FACTOR (USING DESIGN MWe) (1)

19.

FORCED OUTAGE FACTOR (1)

20.

SHUTDOWNS SCHEDULED OVER THENEXT 6 MONTHS (Type; Date and Duration of Each)

REPORTING PERIOD DATA This Month Yr-to-Date Cumulative 745 7,296 177,769 o.o 5,355.9 129,899.7 0.0 o.o 0.0 o.o 5,248.4 124,883.9 o.o o.o o.o 0

9,004,746 257,354,033 0

2,751,886 82,906,842

-5,850 2,578,363 78,552,782 0.0 73.4 73.1 o.o 73.4 73.1 o.o 71.9 70.3 o.o 71.9 70.3 0.0 45.7 57.2 o.o 44.5 55.7 o.o 2.2 11.3 Scheduled Refuel Outage (D3Rl2) began September 8, 1991.

21.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP December 21, 1991.

ZEDE91/425/8

3.3 AVERAGE DAILY UNIT POWER LEVEL MONTH OCTOBER. 1991 DAY 1

2 3

4 5

6.

7 8

9 10 11 12 13 14 15 16 AVERAGE DAILY POWER LEVEL (MWe-Net) 755 4

724 746 666 308 608 753 753 754 752 752 380 449 698 4

ZEDE91/425/9*

DOCKET NO. 050-237 UNIT II DATE November 1. 1991 COMPLETED BY D. c. Maxwell DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 TELEPHONE 815/942-2920 AVERAGE DAILY POWER LEVEL (MWe-Net) 759 754 759 755 548

3.4 AVERAGE DAILY UNIT POWER LEYEL DOCKET NO. _0....,5.._.0._-.... 2...... 4,,_9 ----

UNIT__.._,II.._.I.__ ____ _

DATE November 1. 1991 COMPLETED BY D. c.. Maxwell TELEPHONE 815/942-2920 MONTH OCTOBER. 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 17 2

18 3

19 4

20 5

21 6

22.

7 23 8

24 9

25 10 26 11 27 12 28 13 29 14 30 15 31 0

16 ZEDE91/425/10

NO.

DATE 13 10-21-91 1

F: Forced S: Scheduled ZEDE91/425/11 3.5 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH OCTOBER,1991 TYPE1 REASON2 METHOD OF

LICENSEE SYST~ COMPO~

DURATION SHUTTING EVENT CODE CODE (HOURS)

DOWN REACTOR3 REPORT II F

243.67 H

1 91-013/050237 EI BTRY 2

Reason:

A-Equipment Failure (Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensee Examination F-Administrative G-Operational Error 8-0ther (Explain) 3

Method:

1-Manual 2-Manual Scram 3-Automatic Scram 4-0ther (Explain) 5-Load Reduction 4

DOCKET NO._0=5~0~-~2~3~7 ___ _

UNIT NAME Dresden Unit II DATE November 1, 1991 COMPLETED BY D. C. Maxwell TELEPHONE (815)942-2920 CAUSE & CORRECTIVE ACTiON TO PREVENT RECURRENCE Manual Turbine trip and manual Reactor shutdown because of the 250 Vdc Battery System being declared inoperable based on Unit 3 250V Battery testing results

Exhibit G-Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161) 5 Exhibit I - Same Source

NO.

DATE 3

09-08-91 F: Forced S: Scheduled ZEDE9ll425ll2 3.6 UNIT SHUTDQWNS AND POWER REDUCTIONS REPORT MONTH OCTOBER, 1991 TYPE1 DURATION (HOURS) s 745.0 2

Reason:

METHOD OF REASON2 SHUTIING DOWN REACTOR 3 c

1 A-Equipment Failure (Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction LICENSEE EVENT REPORT #

NIA 3

E-Operator Training & Licensee Examination F-Administrative G-Operational Error.

H-Other (Explain)

SYSTEM COMPONENT CODE 4 co Di NIA NIA Method:

!-Manual 2-Manual Scram 3-Automatic Scram 4-0ther (Explain) 5-Load Reduction 4

DOCKET NO.__,._05~0~-~2~4~9~---

UNIT NAME Dresden Unit III DATE November 1, 1991 COMPLETED BY D. C. Maxwell TELEPHONE (815)942-2920 CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE Off-line for the Unit's 12th Refueling Outage (D3Rl2).

Exhibit G-Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161) 5 Exhibit I - Same Source

3.7 COMMONWEALTH EDISON COMPANY - DRESDEN NUCLEAR POWER STATION MAXIMUM DAILY ELECTRICAL LOAD FORM Day 1

2 3

4 5

. 6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 ZEDE9ll425ll3 FOR THE MONTH OF OCTOBER, 1991 Hour Ending 0100 1000 1600 1700 0100 2400 2400 1000 0100 1400 1100 1300 0100 2400 2300 2400 0100 1700 0600 1800 1000 NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA kWe 790,000 788,100 760,500 800,500 750,800 526,500 708,900 806,500 797,000 790,000 814,000 789,800 669,700 605,800 811,000 814,400 808,200 797,700 790,100 789,700 815,700 0

0 0

0

4.0 UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period, October, 1991, are sununarized in the following table.

The table includes information as to which relief valve was actuated, how it was actuated, and the circtUDstances resulting in its actuation.

Valves No. and Type Actuated of Actuations Plant Conditions Description of Events 2

No Unit 2 Main Steam Relief and/or Safety Valve actuations occurred during this reporting period.

2/3 10-03-91 Spare Safety Valve Serial NtUDber.

BK 6260 Bench Tested.

3 times NIA This spare safety valve was bench tested and rebuilt for future use *.

3 No Unit 3 Main Steam Relief and/or Safety Valve actuations occurred during this reporting period.

4.2 OFF-SITE DOSE CALCULATION MANUAL (ODCM) CHANGES No ODCM changes were reported for the month of October, 1991.

ZEDE91/425/14

4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TREA1MENT SYSTEMS DURING OCTOBER, 1991 Current Status of Radioactive Waste Treatment System Upgrade Project:

Minimal Radwaste upgrade project work was performed, in view of Unit 3 refueling activities.

The upgrade will be back on schedule after D3Rl2.

4.4 FAILED FUEL ELEMENT INDICATIONS 4.4.1 Unit 2 Dresden Unit 2 fuel performance during October, 1991 continued to show no indications of leaking fuel.

This is based on the sum of the activities of the six noble gases as measured at the recombiner.

Unit 2 had exceilent fuel performance.

4.4.2 Unit 3 This item is not applicable to Unit 3 during October, 1991, since the unit was shutdown. for refueling.

ZEDE91/425/15

5.0 PI.ANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS. AND SAFETY RELATED MAINTENANCE 5.1 Amendments to Facility License or Technical Specifications.

No new amendments to. facility license or Technical Specifications were approved for use during October, 1991.

5.2 Changes to Procedures Which are Described in the FSAR (Units 2 and 3) during October, 1991.

Table 5.2.1, attached, sununarizes the procedures described in the FSAR which were approved for use during this reporting period.

ZEDE91/425/16

TABLE 5.2.l CHANGES TO PROCEDURES WHICH ARE DESCRIBED IN THE FSAR (UNITS 2 AND 3) FOR OCTOBER, 1991 PROCEDURE TYPE PROCEDURE NO.

PROCEDURE TITLE/DESCRIPTION None N/A There were no new procedure a 10CFR 50.59 evaluation

Administrative change; intent of procedure unchanged.

Changed for clarification, intent of procedure unchanged.

changes that required Changed to incorporate requirements for new equipment; intent of procedure wichanged

SUMMARY

OF CHANGES N/A NOTES:

1.

2.

3.

4.

Changed to implement improved testing/calibration methodology; intent of procedure wichanged.

ZEDE91/425/17

5.3 Significant tests and experiments not described in the FSAR (Units 2 & 3)

Significant special procedures involving tests not described in the FSAR which were approved during the month of October, 1991 are listed below:

SP 91-08-91 NUCLEAR DATA 9900 GAMMA SPECTROMETRY SYSTEM The purpose of this procedure was to provide instructions for the calibration and operation of the Nuclear Data 9900 Gamma Counting Room System.

SP 91~08-9i 48/24 v 3B BATTERY MODIFICATION TEST Ml2-3-87-58 The purpose of this procedure was to detail the steps necessary to verify the operability of the 48/24 3B battery feed breaker, ammeter relays, and associated equipment.

SP 91-09-107 REMOVE AND RESTORE TRANSFORMER 32 DURING REFUEL OUTAGE D3Rl2 The purpose of this procedure was to provide instructions for supplying Unit 3 electrical loads using the Unit 3 Diesel Generator and removing Transformer 32 from service.

Upon restoration of Transformer 32, this procedure provided instructions to return to a normal electrical line up.

SP,91-10-118 ANNUNCIATOR MODIFICATION.Ml2-3-88-022B TEST FOR TEMPORARY HORN WIRING AND NEW POWER CABLE FEED The purpose of this procedure was to test the installation of Engineering Change Notices (ECN) 12-209E, 62-01, 87, and 87-01.

1) ECN 209E installed wiring for the new Annunciator Horns on Control Room Panels 903-3, 903-4, 903-5, 903-6, 903-7, and 903-8.

This comprised of testing the Silence, Acknowledge, Reset and Test Buttons on each panel.

2) ECN'87, 87-01, and 62-01 'installed new power feed cables from DC Bus 3A and 3B to the Annunciator Panel 903-34, and changed the wiring for fuses protecting the Annunciator System.

3) Testing verified proper installation of the new Main and Reserve power feeds and the rewiring of the fuses on the 903-34 panel.

SP 91-10-128 ANNUNCIATOR MODIFICATION Ml2-3-88-22B STAGE 5, 6 SINGLE INPUT WINDOWS AND MISCELLANEOUS TESTING ZEDE91/425/18 The purpose of this procedure was to test and verify operation of all Single-input Annunciator Windows associated with Main Control Room Panels 903-3, 903-4, 903-5, 903-6, 903-7, and 903-8.

5.3 Significant tests and experiments not described in the FSAR (Units 2 & 3)

(Continued)

SP 91-10-129 PROCESS WASTE COLLECTOR TANK THROUGH 'A' WASTE FILTER AND

'A' MAX DEMINERALIZER TQ THE WASTE SAMPLE TANKS The purpose of thi~ procedure was to detail the steps necessary to process the Waste Collector Tank through 'A' Waste Filter and 'A' Max Demineralizer to the Waste Sample Tanks.

SP 91-10-130 PROCESS WASTE COLLECTOR TANK THROUGH 'B' WASTE FILTER AND

'A' MAX DEMINERALIZER TO THE WASTE SAMPLE TANKS The 'purpose of this procedure was to detail the steps necessary to process the Waste Collector Tank through 'B' Waste Filter and 'A' Max Demineralizer to the Waste Sample Tanks.

SP 91-10-131 ALTERNATE ROD INSERTION SCRAM AIR HEADER BLOWDOWN TIMING TEST The purpose of this procedure was to demonstrate that the replacement of the Unit 3 Control Rod Drive System 3-305-116 Valves on row 4 of the Hydraulic Control Units has not al~ered the ability for the Scram Air Header to depressurize through the Alternate Rod Insertion. Valves within the required time.

SP 91-10-133 UNIT 3 DIESEL GENERATOR MAIN BEARINGS CHECK The purpose of this procedure was to run the Unit 3 Diesel Generator at low idle to facilitate a qualifying inspection of the Main Bearings following engine maintenance during the D3R12 Refuel Outage.

SP 91-10-138 UNIT 3 250 VOLT DC STATION BATTERY PERFORMANCE TEST ZEDE91/425/19 The purpose of this procedure was to detect deterioration of the Unit 3 250 Volt DC Batteries over time by verifying and trending total battery capacity.

The Battery System capacity was determined by discharging the batteries at a constant rate, equal to the manufacturer's rating of the batteries for the selected test length, to the minimal terminal voltage.

5.4 Safety Related Maintenance (Unit 2 and 3)

Safety related maintenance activities for October, 1991 a~e SUDUDarized in the attached tables.

ZEDE91/425/20

-0260-*M Tm:;

rYIWS

!**-~*~ 3!:; 3 HPCI STM LINE OIFF PRESSURE 2?f.~381A D*- :; 'A' 11202 MON.

1-IF.~TEI<;

3-2303-TG HPCI TURNING OEAR A* 07AF'RM-* 3

~RM CH 3 !CPS i20 2--;~61-30C MAIN SrE~M LCNE LO PR~SS SW.

M*-1198[1-.l 64 DIG SW SUPORT M-1198**164

?3'!1 **01A ANNUNCIATOR 620 (903-4!

--0260-MISC rHWS r1,:.11 ur:;rc ur

-:::: tNTE:i*~ANf.E r:r.mr,:r::c TI VE l""IF W(1 ~~;;..~:~

1*1-:; __ 1.'!:-:NT I IJE flh

~19807 3 CORRECTIVE 1-IR DO 31 99 Ffi:FVENT l VE WR DO.::-:::~:::6 PREVENTIVE W Fi [I 0 3 *Vi'.:*

f"F::U![N I Jl!E:

,,.~f=\\:

Ot') ]~;i ::*.:.~,

f'RE'JENT I VF..:

i.m no::r::;74 r.; Clf':l<f.:: C: T J \\IE WH D<Hr::;~:.:4 LER Ufi OU 1"1'.ii.il:.

Mi'.-1L.1 1.1:1*: i I.UN NUMBER c;,:;u::;E i--~ESUL T N/A NIA N/A N/A NIA NIA

--*...:**~---**.. -

N/A N/A N/A REPLACED RELAY WITH NEW AND TF~TED.

i<EFU1L[U n::r:NSM J TIT.F: PEE

!*!Ol~I\\

INSTRUCTIONS.

T IGHTf.NED SOLENOID RCJO 2 TURNS 8.

AOJUSTED YOKE NUT 2 1/2 TUNRS. RETIOHTEN PLATE II. RF.IAlNfl.\\'. NUT.. ADD'I. 901.f.NOllJ 1:::m:i (II-

~ TIJf\\NS :i, l/? TUf\\M ON \\'IJKF: NUT.

INSTALLED TEST [QUIP to MONITOR SWTTCH RLSPON~E UN TUR81Nf lRIP.

INSTALLED SPACER WASH~R ON LOAO PIN.

PF.R WR AND FCII WORI< PACl<AGL E FOR INSPECTION ANO

£ WHEN COMPLETE.

COMPLETFO PER UEST 'ANl.t FC.I. I:

WUf::I( l'ACl<l\\liE -

ANU TESTCO NEW RlLnY.

EfJIJIPMENT J-6641--11 11/G FUEL. OH. F*r;*Es GAl.liiF

_,*-.:;.:;,;,J F'Ef UEING GRAF'F'LE

- - l02--ll(M**l.l 1.r;*Ms 1t.:I.?,i.3, :1.t1,.1 "';, *u.,.1 7.,.1 ::::

3-202-4A LIMITORQUE

~

.;-?"'()1-**"0

-:1

'"1'.

M.O. 3-1!.)01*-27A MO 3--140.l**11A VA~;Ml~~l101-1A

~~~.*;~/ '~~-

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1*U\\ I UI([ UF Mf.HNTENANCE cns*r'.:f::C:T 1 VE

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l*h[ '.JENT I VE WF

[19~:~975 1::.1l'*:l*:t::CTJ 1.)L

1*.IF>

I. r;' '!0 J.:;

PREVENTIVE WR [1963.?0 PF:F.:'Vf'.NT I VE Wf<

D969:~:o PREVf::NTlVE 1,.m D'f696:t PREVENTIVE WP [196962 i::*r;;EVENT :r t)E Wf\\' Cl9t.)97.?

PREVENT.IVE

!>JR 096986 rREVENTIVE WR [196997 LE.R OH OUTt1UL NUMBER NIA N/A NIA NIA N/A NIA N/A NIA N/A N/A r1r1L.Fl.H-!l. i ION CAUSE RESULT CORRECTJVE ACTJUN r:;[f'l..ACETI 01.[I FAIL.FU f)A1Jf3[ WITH (\\ Nr:w rAt.CBRAff 0 GAUGF.

u~s IALU:l.1 1d::.srnAINH*lLI MEUIANL.i1'i UN BOTH SIDES OF MAIN HOIST DRUM.

JiNl.!:ilHd111*, DFITl::tUNE [(l**T(\\(f\\'...

n1:n11::r:1 hiW TF::n.1 f!ii \\HLI. r:F i"El~H11::ML[1 111.mrnr; Ott fAGI::.*

REMOVED, INSPECTED AND FOUND GREASE ACCEF'TAE:LE. GREASE l.CVEL ACCEF'TABLF.:.

f(EMD\\,.'l::C:I, I ~ISF'ECTED MID FOl.INU rmE:ASr

~CCEFfABLE. GREASE LEVEL ACCLPTABLE.

WILL INSTALL GREASE RELIEF KIT UNDER WR 395017 REMOVED* INSPECTED AND FOUNn AREASE ACCFF'l AE:l. L.

Gf\\Eli~;r Ll.VEL (1CCEI 'lAl::LE.

REMOVED, INSPECTtD ANb FOUND GREASE ACCEPTABLE. GREASE LEVEL ACCEPTABLE.

.PERFORMED I UE:RICA'l JON JN:WElTl\\lN. MOV

'* 'tULL BE f\\F:r::u IL T U~!PEt*: WR(U~l(if]

,I

~

!.' t *,

INSPECTED ANO FOUND OREASE E. GREASE LEVEL AC~EPTABLE.

INSPECTED AND FOUND GREASE

E.

GREASE LEVEL ACCEPTALE.

UJUIPMENT

-
- :rn i *-0 l'~ 2?01-~ MO VALVE Ntl I Uld': OF MAINTENANCE f'f\\F:vr::N r.r. VE

[,_,1:.: P'l 7 6 7 3 J-6134-3~

rREVlNTIVE JC RX S.O. CLG. PP 4KV CUBICLE WR 098380 HF'CI CDLl.1 F"fiST

~>TAI\\"! l [':;I l::!Jl.! Ir*

l'l*\\1-c\\'l.iH I 'JF l,Ji:;:

[19~:":!9(/~!

.~/3 ROOF

2/3.OG/HPCI ROOF 8UJCKS 6300-MJSC

~ACCUMULATORS:LINE 33-0338A-1 roR ALL 3-0305-101 VALVES IN 1\\0W 5 PREVENTI\\JE Wf\\

[19~J,969 Ff\\EVENTJ\\!C IJJr\\ D992':'i';;

LER OR UU I Md.

M11U-Utlt f lUN NUMBER CAUSE RESULT NfA N/A N/t\\.

NIA N/A CORRECTIVE ACTfUH f\\[M!JV((1, TN5F'EC1TU ANO nll.INll ril\\U'\\5f.'.

Tl.1 r,~F Ar:r:FFT*"H-:1... E.

Gf.'FA~:r. 1.F l,l[I i'"1f'(Tf'T/\\F:I. F.

CLEANED CUf:lCLl; CllANlJE[! uu*1 (1lJX MW POSITION SWITCH. LUBRICATED LINKAGE ANO ALL PIVOT POINT.

HFiTtd.. L TF'.iT [(JIJH'** *1E'..iTU.! Miit Rl*.M(l'./EU HS"! [l,l! IJ F*MENT.

REMOVED ROOF BLOCKS TO SUPPORT UNtT 3 2301--10 !Jf'\\LVE RffLACEMENL C!.lMF'LETEtt ROOF BLOCK lNSTALLATJON ANO SFALJNG.

FfJIJI~'MENT

-' :::-* 0 3-**Cli:A 341'.;!5 LR!.' A-- 3-11*':';

.:'/ :::-0 3****[111061 c:;pr1RE CRD 1061

/ >()

>*-CJ( l 064 sr*Aru:. c1:;:u l OM U3-03CR141 SF'ARE: CRD 1041 Al:J**C>3-CH1.<>78

~*r1RE CRD 1073 3-0 3-CRA!'.17 3 4 SPf1RE: CFID A 87 311

,J 3-0ZO 3 J. --SPAR SPARE FEEOWATER CHECK VALVE

~: 13-03*-Cf\\1070 CONTROL ROD DRIVE

-/3-03-CR1445 CRD 1441'5' :*

W: I U!*:E UF M1:\\HJli:NANCE r*r:.:E'..,'E~J*y T VE f'IF W'Jqp*:*!f.,

RE

VFNT 1 VE i*m noo8?9 F'h:t: '*ILNT J:'..'E.

i*m uoos *:~o PREVENTIVE

.11/fi' [ 10083.1 PRF.:VE:Nl IVE Wh Doo:B::::

F'RF.\\.'ENT J VE WF D008:>l TREVENTIVE 1-m no1. 352 fliF'JENTl'![

l:)f( (*()2940 f'RF.l/f.:NT.t vr.:

t~J:;:

D89~~%

l"'l'(E'JENT l ',!L wi:;: D<?05 lo LLR DE Cll..I I 1'1!.:*..

NUMBEF:

NIA N/A NIA N/A NIA N/A N/A N/A N/A h*'il:.'* ~.. 11!!.! J.UN r.:rHJ:;i::

m:suu CORRECT(l,lf: ACTllJN U:Ai< 11::5*: r:fm

~)/N 1'13 116~\\. r:lfi'.[ \\*!H*:i::u

,.. Ti... I ~*T,'.,/,If! (:orr< r: T HFl~D !.:1.)l'Sf :rn:H:::,.

!'!<!)

.. J' Iii' !ii*: I": MIO Ul~r.*IJllF'I 11"1(< :*Ji.'. I*.!'!* t1I :.

r-h r ::*;..

r::-: r iJ:,:c.

~ r.\\F r r-i: ~: t:i1L *:=. nu i_i1\\:)i* :~*~.

i... [i:1li I E~i I ITI Cf\\LI 1 Ol, l. l*lf.:I J IT:

WI mr: RUJULS i TO REBUIL.D CRD 1061.

!.Uil{ IF'.:;nJ:i crm JOI.JI.. TH: \\*11:m.:11 I i.1.l[f(

P1iffl

~:;ucK LT HEALi L('iJ*~;CREW'). l)Jfl PIH'.).

~':[FOF:F Ml[I AFTF.:J~ CAl..'i !JN l*)AI Jt:il:'i.

r*ASSEU LE.Al< r ES r

LEAK TESTED CRD 1041. TIE WIRED FILTER AND SOCKET HEAD SCRENS. DID All P~T5 P.FFORF AND AFTER CAL!-> ON 11AUGFS.

PASSElt L.l:.AK TE!3T l.CAK fE5TEO DRIVE 10/B f!E WH(l[I 1*1urn l\\ SllCKET HlAU CfWUCRBI.

CHECKED SN. TESTED GAUGE BEFORE ANO

. AFTER.

LEAK TESTEn CRD A 87~4.TIF WIRFD FILTER 1iND c.IAU I: T HEAD Ci)f*'SCREW'.i. UWCKFD

~*:N ANO [I JD PM l f.;.

f':EFORI* AND AITH'. CAU; ON r:i1!\\GF~: **PMi~'iF* ()

I. Ef\\K rc:r.

INSPECTED' RE-MACHINEDt REPAIRED AND TESTED F.W. CHECK VALVE PER WORK INSTRuc*r10Ns.

SATISFIED nLL HOLD ANO PMT POINTS.

LEAK TESTHI CRU S/N.1010.

Tll. WlRU1

*.. FILTER. ANr:i. SOCK FT I IEnD C1~FSCRL W. CHECK Ell

~E TESfED. DRIVE PAUSEU LEnK ELI CFm.

'l.L wrnED Fll..ll:.R MW AD CAPSCREW!i, CHECKED SIN ON 1 UNCOUPLING PIN. 010 ALL PMT'S.

E'D TEST.

EIJUIF'MENT

.:.:; J-**() 3-CI( ":20 r:: F:fl ':1?0

?/ :.; **O.=!*-*Cf~'.297 r:Rfl :?.91'

'.:'/3-03-CH887A CRD 887A

'/**-() 3-G:980

.[I 980 2HIOL..-1A 1001-lA ~PARE WEDGE

u3-03-rn124 CRD 124

u:::-o3-*rn5o CRD 50

'1; ui._i.:: ur Mr'\\ rtHFNANCE 1*1,r.: 1.. i[~!T I 'Ji l*.Ji*

j1"i~:~?{1 /

PREVENTI'JE

~~r.* [192276 f'l'~EVENTIVE l~I'\\ [h"1iJ110 PREVENTIVE wr' D99on:

F'REVENT I VF

!~Ii: [)99('.1.?

PREVENTIVE WR fl990~~ 1.

f'l'\\El..'ENT l l..'E WR [199023

,_.:1 I I

I_ i *Ii* ;_'

i..,.,: :*J ! I:

~-1, !'II '.*

LER cm uu ;-,-,,;;

NUME!H:

N/A N/A N/A N/A NIA NIA N/A h1**1i... r i,_I;*::.

IGN C~USE "RESULT r:nRRFCl J 'JF fiCTJ (I~~

I LAI<

f'ES I U:r CRD 3;:~().

rJ[ ~I( RUI I 1.. !Tl\\

ANU C:!iCl'l'"TllFA[I r::/.\\r*c;ri::EWS.. rrrrr PM"I ::. I.JC HPl... i:i :: "' i i !"H~*n 1* re:.., :r:i-01::1

'-ol*i', ti1 *1.1:;

. t,!.. ~;

11r~ htil l(iF'.:;.. r:*r\\','*:1 Tr Tl****:r..

!... Lt'll<

iU:i.ILU CF\\D ::: 1.<::..

TII.: WJF:1; 1.!:i ILi\\....

SOCKEI HEAO CAPSCREWS. CKO nN UN DRlVl

~

UNCOUPLING PIN. BEFORE & nFTER CALg ON OAOES. DRIVE 252 PASSED lEST.

I.LAV.

r ['.}![II CHU

~*n" I J! IHRI i.r II 1. I Fl~

r\\i'W

~'!IC:< I ; I IEA[I u~r*(;c1::n1s..

["1 u.:r PMT 'i' lit::

HUL[I p, WITNESS f'T!l..

m~r*ma*: (1N.r1 (lf"H:r::

u1u; u1~ (;r11JGEs. F"r*,(;snr Tl::~>T.

L~AK TESTlO CRO.

TIE WIRED FIL.TER AND SOCK ET tlEAC1 CAF'SC:f~EW!.l' CllFCKElr SIN !lN oFn 1JF AND 11NcouP1... r NG PIN.. o rn M.. J. F"MT

s.

CFU f"()'j~;r 1.1*

IT~n" I CAI< fES rf.Jt Cf([I 9U*:).

TH:

~ll:fd::t:r I* II H:f<

AND SOLl<ETHEAD CAl"!>rnEWS. [I ![I PMTS, Ql HOLD B WITNESS PTS. BEFORE AND AFTER CALS ON GAUGES. PASSED TEST.

REMOVED FXTSTING STEI LITE FROM wronF **

f~'.LMi1CllINLD <:;TEL.. LIH. SrH:t '.:iFJ Eli Al.L. f'Mt..' ::\\.

HOLD r*orNT'*:" 11.n:;:Nl:.U (IVl'.R TO iTCllNT.UiL.

~3EfiV IC[*:;..

LEAK TESTED CRO 124.. WROTE WR TO REBUILD CRD 124.

LEAK rESTrn CR[! 50..

TH:

~li:RFI) F'IL.TH:

AND.SOCKEHIEA[1 CAF)Cl<EWS. [I ![1 f"MT~;, fJC TNESS PTS. 8EFOkE ANU AFTER

.AUGES. PASSED LfAK TEST.

ED CRD 161.

TIE WIRED FILfER THEAD CAPSCREWS. DID PMTS, QC

!'.HO!-D I!. WITNESS r*rn.. 1m:*m::1*: (\\Nii (\\I HT\\

Cf11 '

ON* GAUGES.

F'(',~;s1T1 LL:l'1K TL'.:;T.

ID CR[I 6323. REBUILD DRIVE OER WR D*-*03782

EQUIPMENT 2/ 3-03-Cf(27

'~RD 27 2/ ::i-o 3*-*rn97 CF:D 97 2/3-03-CR730 CRO.,30

"-O "-cr,"A""i"...

.. I J

[I A8544 213-03-CRA-!'.!276 CRD f~-K~/ 6 2/3-03-CR412C CRO 412C 2/3-03-0\\733C CRD -133c NnJUNE OF

LER.OR OUTAGl.

MACNTENANCE

., ~

NUMBER

~~)

~'

i r:*Rf.VENTIVE

\\'.'.,<:.

r :*N/A WR [199024

.'~" '*' '

l'f(E\\.'ENT l '..!F wr.;; U9?0?6 PREVENTIVE WR ll990Z3 F"RE VENT l VE WR [199029 PRF.::VENTt VF.

WR D99o:n.

PREVENTIVE WR D9903?

PlE'JENT.L \\IE WR

[*9903:~

PREVENTIVE WR [199034 r'l'\\f'.:'.'ENT.l Vl WR [1990;!8 N/A NIA N/A NIA N/A NIA N/A N/A Mm.r:1.n11;*i ION CAUSE RESULT

__...;.......;.;...J,-:....1.;;.

CORRECTIVE ACTtON LEAK TESl CRD 27. TIE~IRED FIITER1 SOCKETHEAD CAPSCRE:WS..

CHFCKE11 SN ON CRll ANO UNPO!IF'LINGF'IN.

t)EflJl\\'f e, r'irl[fi'. (J1L ON GAGES. l1FUVE F'A'.;f:iU.l U:*!'IK Tf-'.:l.

L[AK TESTED CRD 950.

TIE WIFlU FILTER AND SOCKETHEAD BOLTS.

DIO ALL PMTS, QC HOLO Q WITNESS PTS. BEFORE AND AFTER CALS ON OAUGES. PASSED LEAK TEST.

LEAK TESTED CRD 97.,

TIE WIRLD FIL.Tt:r~ R SOCKET HEAD CAPSCREWS. CKD SN ON DRIVE R UNCOUPLING PIN. BEFORE & AFTER CAL5 ON GAGES. DRIVE,_9~ PASSED n:sr.

q LEAK rEstEo cite t3o.

wkate: ~R t0 REBUILD CRD 730* '.

LEAK TESTED CR[IA3".'.i44.. Tif w CRr*:n FILTER AND. SOCKEHIEAO CAF:SCR.EWS *. 010 F.**MTS, QC HOLD e. WITNESS :PTS;;,B~FOR£, ANb AFTER ** '.;'.

CALS ON GAUGES* PMSEO LEAi< TEST

LEAK TESTF.o cRo A'-i321i. r H: w rnrn nlilR AND SUCH TllEAO CAP~)Cf"\\E!*'S.. D IO (ill. f-'MTS.

llAD E:E.F@E AND AF"! FR CAL!> ON Or\\llGf.S.

PASSED n:sr.

LEAK TEStEO CRD *.

~ ht. NlREO FILTER. ANb SOCKET HEAD CAPSCREW51 CHECKED S/N ON

'. OR IVE AND UNCOUPLING PINN 0'1[1 ALL PMT Is.

CRO PASSFO TEST.

~.

{'I. ;:

".(:

.i.

0 CRD 4~7C. TIE MIRED FILTER &

AO CAPSCRFWS. CKO SN ON ORJVf. ~

. G PIN. BEFORE & AFTER CALS ON

., IVE 4:~ n: lA'.\\SE[!

ff~; T.

rn crw.

rn: wrnEO FILTER ANO AD CAPSCREws~

CHECKED SIN ON

. ON UNCOUPLING PIN.

OID ALL

. RD F'ASSED TE:ST.

EQlJIPMENr 213-0 3-CIP09C 1.:1::n 709C

u3-03***CIU036 CRD 1036

~.: / ::?-0 3.. -CI~ l 029 CF([I l 029

?/3-03-rnM CR[) 6"'

lli(._3-03-Cl\\A~444 9'[1 A5444 213-03-7052 CRD 7052 2/3-03-CR819 CRO 819

oi)I** LI Y 1.. ;f:.i.f.': 11::.l.I I'll\\.IN 11. i*lf'1Nl..l:.

NATURE OF

.,. LER,01( OUTAUI:

MA I NTENANCE *r ';t*** {,NUMBER PREVENTIVE

. **4l :t' NIA l*ir:: [199041.

F'f\\L'JENT IVE.

WI'.;; D99042 Pf\\EVEN r I t,/E Wf\\ D9?04 :;:

PREVENTIVE WR [199044 PF\\E-:VENTI VE Wf'\\ [199047 PREVENTIVE WR [19?04:'.:!

.....,.,N/A N/A N/A NIA NIA MALFUNCTION CAUSE RESULT CORRECTIVE ACTION LEAK TESTED CRO 709C. TIE WIRED FILfER f\\ND SOCK FT HEAD CAPSCREW. Cl*IECl<F:D r;1N ON CF::U AN[I I JNCDLIF'L [NI j r* rn. Jl(-)[1 [:IT I lJ::E (\\ND l'tr TEF: u.1..u ON GAUl*JI'. \\'.)..

l*'()S!)EC! TFS j'"

LEAK TESlED CRD 1036. WR 003781 WRITTEN TO REBUILD CRO 1036.

LEAK TESlEU CRD 1029 TIE IHRED f'ILTrn 11, SOCKET HFAl1 C:AF*~::CREW CHECKED

~;N ON DRIVE.

BEFOl~E e, iiFTrn CAL:;

ON 'GAUGES *. DRIVE PASSED TEST.*

LEAK TESTED CRD 64. WROTE WORK REOUEST TD REBUILO CRD 6....

LEAK fESTED CRD A5441.TH: WIRLD FIUER AND SOCKET HEADio\\oCAPSCREJill:>., CHKli SN. OlCJ F'ti!TS

HAD BEFO~~ ANO. AFTER CALS ON GADE PASSED LEAK TEST; Lf.'.AK TESTEO CRO 70!'.'i2 / FOt.iNO DRIVE TO.

llAVE EXCESS LEAKAGE IROM COL.LEI HOUSE.

DH IVE OIDN' T CYCLE. WROTF \\Im TO f(EE:IJJL[I ORIVE.

PREVENTIVE WR 099077

. N/A

~*i:...;;;... z.:;;,.o~'. ~*,1 'LE.Ak TESTED ORD 9i9~;:'?~tlE wiR£b Ftl'TER. *

~..

t.*,.*. ':F *~i *."HO SOCK ET HEAD CAf>S~tlilS *... CHK o.. SN. 0 I ti..

<; *./. ;'.k l!'fittEh., HAD' 8lf'0"£'. AND.; AFTER CALS ON GAGE*

. *' PAS SEO* Lf.AK TEST.I' * *

. t_

HJUIF'MENT 0700-6 AF'f;'M CH. b

'--700-*24

'~lE:

1

.. PRM 1B-?4-57

~'.-261-30A 02 MSL LOW PRESSURE SWITCH e:HM I NAL BLOCK FUSE HULUEri'

~:-261-30 MAIN STM LINE LP SWITCH l25V OC f)YSTEM 2<'.042 U-2 R_BEDT f*UMF'

.RM 48~~~'

~~*.. (~*-: *,:.,;

1\\J:~ I LJl\\E UF LE.R. Of\\ OU Uitii.

~1r1U UN(. i ION MA CNTENANCE.

.~~JJ~BER CAUSE RESULT ccmr~ECT IVE

,*' r.;<M(A 1*m r1007t2 CORRECT JV[

N-*A l~h ['() ':) -:;()'.;:'.

CORRECTIVE N/A WR D03352 CORRECTIVE NIA

~m D0::\\3':'i4 PREVENTIVE N/A

~m ["*()'.-:3,SJ CORRECTIVE NIA WR DO :~722*

CORF\\:ECT I 1, 1E l~Fi'. [r() 1()99 CORRECTIVE WR 083149 N/A NIA N/A CORRECTIVE ACTION REf'LACE[I PIJSHflUTTON

~iWITCH Prn TF:AVFLLFR..

CuMPLU EU L.ilF' 200 U AND Liff :.:oo Fi PER INSTRUCTIONS. PACKAGE BFING SENT TO NUCLEAR ENGINEERING.

F:LF'L.ACE ;.;1-1 J: ICll WHLi'! Mn!. F'l.!SI IE:IJ 1 T!JN CDMES I~!..

INSTALLED AND CALIBRATED FOUR NEW SWITCHES.

L..UOSUI \\JI'

'!CREW~; IJF IERMHIAI. '.:JRlF'.<'.\\ND MOVE UP ro MEET ornrn TrnMINAL BLOCI<.

EXTEND WIRES ON AA115&AA116 TERMINAL BLOCK TO PROPER LENGTH.

IJSED TEMF' l'ILTF.RATJflN T(l rNSTAl.1 lH\\T F!JUIF Hl

!.)~'61 -::or;. 'iY!) n:M i::UIJRNHI HJ i*HJRMAL U. '-'H!IFH [I NO U' l<i'1r:E, Cl [(1F:Fl:i fEMPDRAY At TERATION.

PERFORMED GROUND CHECKS ON BUS 2A-1.

125 voe GROUND ALARM CLEARED.

. RO~ ~R~NSFORME~?URNT.

!_.Y~ LOMF'ONEN l S..

RIJ'l.()CEI1 LPRM 48-*09-n. rOUND ND

EQUIPMENT

30!'.l-M-2.I. !'.I

'IR swr1v l:RACF p IF'F SUF'F'()f.."l C*?00.. *16 1118 LPRM 16-4/B <APRM t5J NiCi'I Uf\\C or M(;INTENANCE t'FLVP.:NT IV~

'*ll'i jl?';9r."~

LER Of\\ Ol.!T(.')UI:

NUMBER N/A N/A' Mt"II_F1.1r.11.: 1 I UM CAUSE RESULT

(:()RRECT l VE ACT.UJN RE.SET ANCt1flRS' r ! mnTNF.ll r,01. T!'J"

()[l.Jt.18TEl.1 r.;wAv [::PtVT.

REl"LALE.lt fJ *1 & 68 UN LPl~M t.J1l::D nm LPRM 16-418.

TESTED CARD ON BENCH AND IN APRM PAGE.

PERFORMED PMV.

RETURNED TO SERVICE.

5.5 Completed Safety Related Modifications (Units 2 and 3)

Only modifications which have been completely closed during October, 1991 are listed; modifications which are authorized for use but not completely closed will be reported based on the date of their final closure.

For ease of reference, the changes have been identified by their design change control modification number.

Modification No.

Description Ml2-2/3-87-002AL This partial modification connects and places into service a Run-Timer and indicating lights to monitor the Unit 3 Drywell Equipment Drain Sump Pump B at Radwaste Control Panel 2223-4.

These devices are ~ired in parallel with an existing Run-timer and indicating lights in the Reactor Building.