ML20058L585

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Monthly Operating Repts for Nov 1993 for Dresden Nuclear Power Station
ML20058L585
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 11/30/1993
From: Spedl G, Sykes K
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GFSLTR-93-0169, GFSLTR-93-169, NUDOCS 9312170093
Download: ML20058L585 (32)


Text

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December 13, 1993 GFSLTR 93-0169 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Contml Desk Gentlemen:

Subject:

Monthly Operating Data Report Dresden Nuclear Power Station Conunonwealth Edison Company Docket Nos.50-010,50-237, and 50-249

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Enclosed is the Dresden Nuclear Power Station Monthly Operatine Summary Renort for November 1993. No 10 CFR 50.59 evaluations are included in this report. As stated in last month's report, changes implemented in July 1993 and l

thereafter are expected to be reported along with the FSAR updates. This change in reporting frequency remains within the guidance provided in 10 CFR 50.59(b)(2), which states that the report on changes, tests and experiments, with the accompanying safety evaluation summaries, may be sulunitted annually or along with the FSAR updates as required by 50.71(c), or at thorter intervals as may be specified by the licensee.

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

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Gary F. Spedi )

Station Manager j

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Enclosure cc:

NRC Region III Office Illinois Dept. of Nuclear Safety, State of Illinois -

U.S. NRC, Document Managernent Branch Nuclear Licensing Administrator t

Site Vice President r

Regulatory Assurance NRC Senior Resident Inspector Site Quality Verification - Detsden' Site Engineering and Construction Manager l

Nuclear Oversight Manager / R. Janecek General Electric Comptroller's Office INPO Records Center UDI,Inc.- Wash.,D.C.

File / Numerical Li\\WKfROCfLNTMCR\\CID93dlee.93 I

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Enclosure cc:

NRC Region III Office i

Illinois Dept. of Nuclear Safety, State of Illinois l

U.S. NRC, Document Management Branch j

Nuclear Licensing Administrator j

Site Vice President l

Regulatory Assurance l

NRC Senior Resident Inspector Site Quality Verirx:ation - Dresden l

l Site Engineering and Construction Manager -

Nuclear Oversight Manager / R. Janecek i

General Electric Comptmiler's Office INPO Records Center i

UDI,Inc.- Wash.,D.C.

File / Numerical j

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1 MONTIILY NRC

SUMMARY

OF OPERATING EXPERIENCE, i

CIIANGES, TESTS, AND EXPERIMENTS PER REGULATORY GUIDE 1.16 AND 10 CFR 59.59 FOR DRESDEN NUCLEAR POWER STATION

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COMMONWEALTII EDISON COMPANY l

FDR November,1993 4

UNIT DOCKET LICENSE i

1 050-010 DPR-2 2

050-237 DPR-19 3

050-249 DPR-25

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i TABLE OF CONTENTS f

Novanber,1993 NRC REPORT i

1.8 Intrd=4aa=

2.s h

ry er Opnating Erpsience 2.1 Unit 2 Monthly Operating Experience Sanmary.

2.2 Unit 3 Menthly Operating Experience Summary.

3.0 Operating Data Statistm l

3.1 Monthly Operating Data Report - Unit 2 3.2 Monthly Operating Data Report - Unit 3 i

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 l

3.7 Unit 2 Maximum Daily Electrical Load Data l

3.8 Unit 3 Maximwn Daily Electrical Load Data i

4.9 Unique Reporting F:; '

i 4.1 Main Steam Relief and/or Safety Valve Operations - Unit 2 and Unit 3 i

l 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 i

5.0 Plant or Procedure Changes, Tests, Experimants, and Safety-Related Maintemanor l

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 Hnal Safety Analysis Report (FSAR) (Units 2 and 3) 5.3 Significant Tests and Experunents Not Described in the ISAR (Units 2 and 3) 5.4 Safety. Related Maintenance (Units 2 and 3) 5.5 Completed Safety-Related Modifications 5.6 Tanporary System Alterations Installed 5.7 Other Required 10 CFR 50.59 Evaluations (Units 2 and 3) l i

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1.9 Intr =ameia=

l Drmden Nuclear Power Station is a three reactor generating facility owned and operated by the Commonwealth l

Edison Company of Chicago, Illinois. Dmden Station is heated at the connuence of the Kankakee and Des Plaina Rivers, in Grundy County, near Morris, Ilhmus.

Dresden Unit 1 is a General Electric Boiling Water Reactor with a design net elecincal output rating of 200 megawatts electrical (MWe). The unit is retired in place with all nuclear fuel runoved from the reactor vessel.

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

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

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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, Illinois.

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l This report for Novernher,1993, was compiled by Kevin W. Sykes of the Druden Regulatory Assurance Staff, i

telephone number (815) 942-2920, extension 2704.

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SUMMARY

OF OPERATING EXPERIENCE FOR Novensber,1993 J

2.1 UNIT 2 MONTIILY OPERATING EXPERIENCE

SUMMARY

i 11/01/93 to 11/30/93 Unit 2 entered the month shutdown. The unit was shutdowiat 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> on i

I 10/25/93 in order to repair the 2D Traversing incore Probe (TIP) indexer and replace the 2B TIP detector. The unit resnained in shutdown through November 29 l

to cornet a Main Steam Isolation Valve (MSIV) problan identireed during the.

3 outage. The probleen was investigated under Problem Investigation Report (PIR) 12-2-93-151, MSIV Operator Air Seal Leak and Parts Deraciency Problem on all-New MSIV Operaton. The Unit was placed in startup at 2126 houn on November I

28, and the reactor reached criticality at 2253 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.572665e-4 months <br /> on November 28.

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2.0

SUMMARY

OF OPERATING EXPERIENCE FOR Novensber,1993 f

2.2 UNTT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

11/01/93 to 11/30/93 Unit 3 entered the month critical and on line and continued through the end of the

-f month.

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1 3.0 ~ OPERATING DATA REPORT 3.1 OPERATING DATA REPORT - DEtFRIEN UNIT TWO I-(

DOCKET No.

650-237 j

l DATE December 1,1993 H

COMPLETED BY K. W. Sykes j

TELEPHONE (815) 942-2920

-j OITRATING STATUS -

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1. REPORTING PERIOD: Novuusbar,1993

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2. CURRENTLY AUTHOEtI7Fn POWER LEVEL (MWah): 2,527 <

MAXIMUM DEPENDABLE CAPACITY (MWe NET): L772

.l DESIGN ELECTRICAL RATING (MWe Net)i 794' j

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net): N/A

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4. REASONS FOR RESTRICTIONS (IF ANY): N/A-

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REPORTING PERIOD DATA -

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j FARAMENE

-- MERS RAONM YEAR TO BATE Ctasta.411VR 5.

HOURS IN FERIOD 720 3016 205,704 6.

TIME REACTOR CRITICAL Glears) 49 4143 152,970 7.

TIME REACTOR RESERVE SIIUTDOWN Gleers) 0 0

0 8.

TIME GENERA 1DR DN-LINE Gloeus) 28 4044 146,533

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TIME GENERATOR RESERVE SHUTDOWN Glours) 0 0

0 10.

THERMAL ENERGY GENERATED (MWHe Gruss) 31,822 8,590,351

~ 342,625,171

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ELECTRICAL ENERGY GENERATED (MWHe Cross) 10.586 2.702,219 96,571,682 12.

ELECTRICAL ENERGY GENERATED (MWHe Net)

- 3,659 2.535,067 92,302,367 l

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REACTOR SERYlCE FACTOR (5) 6A 51.7 74.4 I

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REACTOR AVAILABILITY FACTOR (%)

6A 51.7

~ 74.4

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GENERATOR SERVICE FACTOR (%)

3.9 50.4 71J 16.

GENERATOR AVAILABILITY FACTOR (%)

3.9 50.4 71J l

17.

CAPACITY FACTOR (USING MDC Net) (5) 0.7

. '41 A 58.1 l

18.

CAPACITY FACTOR (USING DER Net)(%)

8.6 39A 56 3 19.

FORCED OUTAGE FACTOR (%)

- 96.1 18.1 12.3 20.

SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (Type, Date and Duration of Each) l NONE.

21.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP' N/A l'

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3.0 OPERATING DATA REPORT 3.2 OPERATING DATA REPORT - DRESDEN UNIT TIIREE DOCKET No.

050-249 DATE December 1, 1993 COMPLETED BY K. W. Sykes TELEP1IONE (815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: Nove-be,1993
2. CURRENTLY AUTIIORIZED POWER LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE 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 REPORTING PERIOD DATA 5.

IIOURS IN PERIOD 720 8016 196,033 6.

TIME REACTOR CRITIC.*.; Glomn) 720 6373 141.962 7.

TIME REACTOR P.ESERYJ 11UTDOWN 01oun)

'O 0

0 8.

TIME GENERATOR ON-LINE Gloun) 720 6307 136,571 9.

TIME GENERATOR RESERVE SIIUTDOWN Gloun) 0 0

0 10.

TIIERMAL ENERGY GENERATED (MWIIt Grens) 1,694,674 14,651.756 282,181J11 11.

ELECTRICAL ENERGY GENERATED (MWIIe Cross) 551.52t i 4,710,601 90.675.550 12.

ELECTRICAL ENERGY GENERATED (MWile Net) 524.284 4,486,693 86,107,905 13.

REACTOR SERVICE FACTOR (%)

100 79.5 72.4 14.

REACTOR AVAILABILITY FACTOR (%)

100 79.5 72.4 5.

GENERATOR SERVICE F/CTOR (%)

100 78.7 69.7 16.

GENERATOR AVAILABILITY FACTOR (%)

100 78.7 69.7 17.

CAPACITY FACTOR (USING MDC NN) (%)

94.2 72.4 56.8 18.

CAPACITY FACTOR (USING DER Net)(%)

91.7 70.5

- $5J 19.

IV)RCED OUTAGE FACTOR (%)

0 21.3 11.8 20.

SHUTDOWN 5 SCHEDULED OVER THE NEIT 6 NONTES (Type, Date and Duration of Each)

Refuel Outage 13, D3R13, is scheduled for March 1994. The scheduled duration for this refuel outage is 13 weeks.

21.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A

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i 3.3 AVERAGE DAILY UNIT 2 POWER LEVEL i

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'l DOCKET No.

050-237 UNIT Dresden 2 1

DATE Dectsnber 1,1993 COMPLETED BY K. W. Sykes TELEPHONE (815) 942-2920 l

MONTH: Novennbar,1993 1

1 DAY AVERAGE DAILY NET ^

DAY AVERAGE DAILY NET POWER LEVEL (MWe)

POWER LEVEL (MWe)

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=0

'18 0

2 0

19 0

3 0

.20 0

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4 0

-21 0

5 0

n 0

6 0

23 0

7 0

24 0

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8 0

25 0

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0 26 0

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27 0

11 0'

28 0

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12 0

29 58 13 0

30 394 14 0

u 15 0

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17 0

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3.4 AVERAGE DAILY UNIT 3 POWER LEVEL l

l DOCKET No.

050-249 UNIT Dresden 3 DATE Decennher 1,1993 COMPLETED BY K. W. Sykes TELEPHONE (815) 942-292C l

MONTH: Nomsber,1993 i

n DAY AVERAGE DAILY NET -

DAY AVERAGE DAILY NET POWER LEVEL (MWe)

POWER Lt. VEL (MWe) 1 734 18 728 2

731 19 725 l

3 729

- 20 713 4

746 21 720 I

5 770 22 715 6

743 23 712 7

770 24

'708 8

764 25 691 9

759 26 703 l

10 754 27 689 11 751 28 687 12 742 29 694 13 740 30 695 14 726 5

738 16 731 17 727

3.5 UNrr 2 SHtTTDOWNS AND POWER REDUCTIONS REPORT MONTH OF November,1993 NO.

DATE TYPE (1)

DURATION REASON (2)

METHOD LICENSEE SYSTEM COMPO-COPJtEC-(HOURS)*

OF EVENT CODE (4)

NENT TIVE SHUTTING REPORT # -

CODE (5)

/frlONS/

DOWN COM-REACTOR MENTS (3) 11 931101 F

692 B

1 NA NA NA SEE NOTE I BELOW i

Year 40-date forced outage bours = 896; Cumulative forced outage hours = 20,620 NOTE 1: Unit 2 entered the month shutdown. The unit remained in shutdown through November 29 to correct a Main Steam isolatim Valve (MSIV) problem identified during the outage. The problem was investigated under Pmblem lavestigation Report (Pik) 12-2-93-151,MSIV Operstor Air Seal leak and Parts Deficiency Problem on all New MSIV Operatc,rs.

TABLE KEY:

(1)

(3)

F: Forced Method:

S: Scheduled I. Manual

2. Manual Scram (2)
3. Automatic Scram Reason:
4. Other (Explain)

A Equipment Failure (Explain)

5. Load Redaction B Maintenance or Test C Refueling (4)

D Regulatory Restriction Exhibit G Instructions for Preparation of Data Erray Sheets for Licensee Event Reports (LER) File (NUREG4161)

E Operator Training & Licensing Exam F Administrative (5)

G Operational Error Exhibit I Same Source as above.

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H Other (Explain) l i

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l 3.6 UNrr 3 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH November,1993 NO.

DATE TYPE (1)

DURATION REASON (2)

METHOD LICENSEE SYSTEM COMPO-CORREC-(HOURS)*

OF EVEKr CODE (4)

NEhT TIVE SHUTTING REPORT #

CODE (5)

ACTIONS /

DOWN COM-REACTOR MENTS (3)

None i

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I Yearete forced outage hours = 1707; Cumulative forced outage hours = 18,239 TABLE KEY:

(1)

(3)

F: Forced Method:

S: Scheduled I. Manual

2. Manual Scram (2)
3. Automade Scram Reason:
4. Other (Explain)

A Equipment Failure (Explain)

5. Load Reduc 6on B Maintenance or Test C Refueling (4)

D Regulatory Restriction Exhibit G Instructions for Preparation of Data Entry Sheets for Licenace Event Reports (LER) File (NUREG4161)

E Operator Training & Licensing Exam F Administrative (5)

Exhibit I Same Source as above.

H Other (Explain) 1

3.7 UNIT 2 MAXIMUM DAILY ELECTRICAL LOAD FOR THE MONTH OF November,1993.

Day Hour Ending UNIT 2 MAXIMUM DAILY ELECTRICAL LOAD (KWe) 1 0

2 0

3 0

4 0

5 0

6 0

7 0

8 0

9 0

10 0

12 0

12 0

13 0

14 0

15 0

16 0

17 0

18 0

i 19 0

..-.1 20 0

21 0

22 0

i 23 0

24 0

25 0

26 0

27 0

28 0

j 29 2400 182,000 30 1100 509,000

4 3,8 UNIT 3 MAXIMUM DAILY ELECTRICAL LOAD FOR November,1993 Day Hour Ending UNIT 3 MAXIMUM DAILY ELECTRICAL LOAD (KWe) 1 0100 774,000 2

0100 771,000 3

0100 768,000 4

1800 810,000 5

0700 810,000 6

1100 812,000 7

0500 811,000 8

0100 802,000 9

0100 799,000 10 1400 792,000 1I 0100 789,000 12 0100 785,000 13 0700 785,000 14 1000 785,000 15 0600 777,000 16 0100 773,000 17 0900 770,000 18 0100 766,000.

19 0100 762,000 20 1300 764,000 21 0100 759,000

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22 0100 754,000 23 0400 752,000 24 0100 748,000 25 1200 753,000 26 0100 747,000 27 1400 746,000 28 1400 741,000 29 0100 74l,000 30 0100 729,000

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4.0 L'NIQUE REPORTING REQUIREMEfES 4.1 MALN STEAM RELIEF VALVE OPERATIONS None 4.2 OFF-SITE DOSE CALCULATION MANUAL (ODCM) CHANGES

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4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TREATMENT SYSTEMS DURING Novesnber,1993 None.

i 4.4 FAHED MJEL F1RMENT INDICATIONS l

4.4.1 Unit 2 Unit 2 fuel perfonnance during Novanber,1993, continued to show no indications of leaking fuel. This is based on the

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sum of the methities of the six (6) Noble Gases as measured at the Recombiner. Therefore, Unit 2 had excellent fuel performance.

4.4.2 Unit 3 Unit 3 fuel perfonnance during Novanber,1993, continued to show no indications of leaking fuel. This is based on the sum of the activities of the six (6) Noble Gases as measured at the Recombiner. Therefore, Unit 3 had excellent fuel performance.

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I 5.0 PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAM!TY RELATED MAINTENANCE 5.1 Amendments to Facility License or Technical Specifications during November,1993.

None.

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4 5.2 Additional Changes to Proceduris Which are Described in the FSAR (Units 2 and 3) during the months prior to July 1993. Only those procedures that required a new or an additional 10 CFR 50.59 review of changes are included. Changes implanented during July,1993 and thettafter we expected to be reported along with the FSAR updates in accordance with 10 CFR 50.71(e).

PROCEDURE TYPE PROCEDURE NUMBER PROCEDURE TITLE /

SUMMARY

OF DESCRIPTION CHANGES None L

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

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No Special W=a involving tests not decribed in the FSAR, which war apprwed dwins the montis prior

. July,1993, were nyarted se agodatory Assur=

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5.4 Safety am 18=W===re (Unit 2 med 3)

Safety related maintenance activities for November-Deconher,1993 (i.e. approximately Nevernher 15 ti augh December 15), are stanmarized in the attached tables.

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DRESDEN UNIT 2 SAFETY RELATED MAINTEN'iNCE NATURE OF LER OR DUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 2-1600 CORRECTIVE N/A WORK COMPLETED PER TNIS NWR AND FCII MISC-SYS-PRESSURE-SUPPRESSIGN 00222G iuP M 02226-01T-02.

24700-APRM3 FREVEfff-IVC

UA REPLACE 0 APRM 0 3 AVO CARD--Z27 X2 ANO-X5 MONITOR AVERAGE POWER RANGE 002027

& APRM 14 AVG CARD Z29 K2. OC WITNESSE@

CHANNEL 3 REPLACEMENT AND COMPLETION OF DIS 700-2 2-0700-APRM4 PREVENTIVE N/A REPLACED APRM 43 AVG CARD Z29 K2.AND K@

MONITOR AVERAGE POWER RANGE D02827

& AFRM 44 AVG CARD 229 K2. QC WITNESSE@

CHANNEL 4 REPLACEMENT AND COMPLETION OF DIS 700-2 2-302-1578 CORRECTIVE N/A PUT ON NEW TUVE, NUTS, FERRULES, VALVE A0 GATE SDV DRAIN 003811 CONhECTORS, ELBOS PST. TEMP CLEARED AN3 VERIFIEO-NO-EEAKO.

2-302 CORRECTIVE-N/A REMOVED EXISTING'P-R SS PLUGS, INSPECT 1 CRD1YSTREM U2 MISC D0519G IM910E OF PORTO TOR OCORIO. PUT-C RIN00 DN NEW P-4 PLUGS. TilREADEli CONNECTIONS AND 0-RINGS LUCRICATED PROPERLY.

2-302 CGRRFCTIVE N/A CRD SYSTEM U2 MISC 005191 REMCVED-EMISTINO I-4 00 PLUCS. IN0rECTE INSIDE OF PORTS FOR DEBRIS. PUT.0-RINGS

-ON P-4' PLUGS. THREADED CONNECTIDNS-AND s

0-RINGS.HAVE BEEN PROPERLY. LUBRICATED.

2-1501-44A PREVENTIVE N/A INSTLD NEW CYCLONE SEPARATOR SYS. REPLCl PUMP CENTRIFUGAL A CONTAINMENT D05358 4 CASING BOLTS. 2 COUPLINGS INSTALLED TI CLG SERV WTR PROVIDE RETURN FROM SEPARATORS. OTHER usunlH69s

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.u uu n wu 2-5612-A

~ PREVENTIVE'.

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AND

~- ' UPPER COVER? SEALING SURFACE: CLEANED:

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COOLER 2A TURBINE OIL D05424 A BALZONA MATERIAL APPLIED AND SANDED b TLAT. LOWER COVER REPLACEO WITi; OAM TYPE FLDATING WATER BOX.

2-1301-1 PREVENTIVE N/A UNPACKED VALVE 2-1301-1, CLEANED VALVE-MO-ISO-CONG RX OUTLET 005743 GTUFFINe-BOX ANO STEE--REPA6i(E0 OAMC INSIDE ISOLATION VALVE. TORQUED TO 66 FT/LOS.

,n 2:r7828-t-J4 CURRECT!vu mn nu vu nmw iu.

m, s m

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.....nmu SWGR BRK ISOL RX OUT ISOL VLV D06325 AND CHECKING PRINT 12E-26'/4E. REMOVED 3 2-1301-1 POINT TERMINAL CLCK. QC VERIF INSTLTN 01 i

NEW BLOCK AND PEPLACEMENT OF NIRES.

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DRESDEN UMIT 2 SAFETY RELATED MAINiENANCE NATURE OF LER OR CUTAGE MALFUNCTIOM EQUIPMENT MAINTENANCE RUMBER CAUSE RESULT CORRECTIVE ACTION 2-305-101-46-55 PREVENTIVE N/A INSTALLED FREEZE HACKETS ON 1" 101 S.S.

VACVE MANUAC GATE URivE-lNSERi D06891-LINE FOR DOS M ISCONNECTED AND TMSFECTE1 RISER ISO VALVE INTERNALS. CLEANED, INSTALLED NEN STEM, WEDGE, AND PACKING, REINSTALLED.

2 300-191-92-o6 rutvEniivE n/A ERFORHEU riURK FER ririF TAVELER, DHF VALUE MANUAL GATE DRIVE INSERT 006392 305-05, DMS 305-01. PERFORMED PMV'S PER RISER 150 BHEET.

2 2 305-101-34-55 PREVENTIVE N/A USED FREEZE JACKETS ON VLV 101. VALVEL


=-

VALVE MANUAL GATE DRIVE INSERT D06895 MAINT COMPLETED PER WORK INSTRUCTIONS.

RISER ISO 2-305-101-38-59 PREVENTIVE N/A PERF FREEZE PER DNP 305-05. DISASSEMBLEI VALVE MANUAL GATE DRIVE INSERT 006896 VALVEBONNET, CLEANED PARTS AND BONNET RISLK ISD ASSY rINSTAttED NEM STEM 7 MD MEDGE ASSY NEN PACKING BLUE CHECKED.

2-305-102-34-03 PREVENTIVE N/A PERFORMED FREEZE PER DMP 0305-05.'

VatVE MANUAL 6AiE drive U06897 IN5FECTED AND FERFORMEU FREVENTATIVE i

WITHDRAW RISER ISO MAINT PER DMS0305-01.

2-300-102-38-03 FREvENilvE N/A FERFURHEU WORK FER nni/ TRAVELER VALVE MANUAL GATE DRIVE-006098 DNP 305-05, DMS 305-01. PERFORMED,ALL WITHDRAW RISER ISO PMV'S PER,PMT SHEET.

e 2-303-102-30-07 CORRECTIVE N/A CUT GUT VALVE PER MMP TRAVELER STEPS 3 VALVE MANUAL GATE DRIVE D06899 THROUGH 11. PERF WORK PER DMP 305-05, WITHDRAW RISER ISO DMS 305-01, DAP 3-2, NELD MAPS, HIRS ANI

. WF5 6-6-6. Fthr. nLL FHV u rtn reu onr.r i,

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2 VALUE MANUAL GATE DRIVE.

PREVENTIVE-,-~~

N/AI W ------- R --------

l 2 305-102-34-07 PERF WORK PER MMP/ TRAVELER,'DNP-3C6-059 D06900 DMS 305-01. PERF PMT'S PER PMT SHEET.%

WITHDRAW RI6En 150 2-305-102-38-07 PREVENTIVE N/A FREEZED SEALED. REMOVED BONNET, WEDGE VAtVE MANUAC-GATE drive UO6?Di ASSV. FGR REBtfILD. REPt*CED-STEM A WELLi WITHDRAW RISER ISO ASSY. REPACKED VLV, BLUE CHECKED'OK.

iREINSTALLED AND TORQUED.

2~305-iO2-46-Oi PREvENiivE N/A FREEZE 5EALEDFERLHF3GG-05.REMGVE[

VALUE MANUAL GATE DRIVE-006903 DONNET/WEDI)E. PREFORMED Bl.UE CHECK OK.

WITHDRAW RISER ISO.

REPACKED STUFFING BOX AND INSTALLED BONNET WITH NEW GASKET. TORQUED BOLTS.

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DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 2-305-102-46-11 PREVENTIVE N/A FREEZE SEALED PER DNP 305-05. REMOVED VAEVE MANUAL UAit; LIKAVE-D06904 CONNET-PER-DMS-305=01--I NST AttfD-NEN i

WITHDRAW RISER ISO.

STEM AND WEDGE. BLUE CHECKED. CLEANED ALCOHOL.

2-G05-iO2-54=19 PREVEi1TIVE N/A FREETE SEALED FER GMT 3GG-0G. REMGUED VALVE MANUAL GATE DRIVE-D06906 BONNET PER DMS 305-01. INSTALLED NEW WITHDRAW RISER 150.

STEM AND WEDGE. BLUE CHECKED. CLEANED ALCOHOL.

2-305-102-54-19 PREVENTIVE N/A

=

GRUOND OUT OLD VAVLE AFTER BLUE CHECK VALVE MANUAL GATE DRIVE-006906 FAILED. WELDED NEW VLV PER WPS 8-8-B.

WITHDRAN RISER ISO.

RECHECKED BLUE CHECK, PASSED.

2-305-102-54-31 PREVENTIVE N/A PERFORMED WORK PER MMP/TRAVERL, VALVE MANUAL GATE DRIVE-006907 DMP 305-05/DMS 305-01. PERFORMED PMV'S WITHDRAW-RISEfrISO.

PER-FMT-SHEET.

PERFORMEDFREEZEONLINE.' CUT'00T'DLDb 2-305-102-42-35 PREVENTIVE N/A UAtVE MANUAt-GATE DRIVE-00670G VLV-8--WEtOED IN NEW GNE. OLUE CHECKEB-WITHDRAW RISER ISO.

NEW VLV & INSTALLED NEW GASKET. PERF'O DMP 305-05 a DMS 305-01. 0-8-8 FOR WELD 23305-102=46-35 FREVENTIVE h/4 FERF'D FREEZE ON CRD ACCUMULATOR 44--35 VALVE MANUAL GATE DRIVE-D06909 M9 HCU.VLV. DISASSEMBLED / CLEANED /..

WITHDRAW RISER ISO.

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PMT SHEET.

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VALVE MANUAL GATE DRIVE.

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PMT ':MCCT.

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ESTABLISHEDFREEZETOINPSECT/r[EPAIRV 2-305-102-50-51 PREVENTIVE N/A VALVE MANUAt-GATE DRIVE-008913 IMTERNAL3 PER CMP 305-051 DMO 205 01,0 NITHDRAW RISER ISO.

PMT SHEET.

2-3 5 AV4-'lO D1 I"ntVLI14 A VL n/M AnasnLLLu rnLLLL unur.L s. ntnuvbu punowa' VALUE MANUAL GATE DRIVE-006914 INSPECTED VLV INTERNALS. INSTALLED NEW WITHDRAW RISER ISO.

STEM / WEDGE / PACKING. REINSTALLED.

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DRESDEN UNIT 2 SAFETY RELATLD MAINIENANCE NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 2-305-102-42-55 PREVENTIVE N/A PERFORMED WORK PER MMP/ TRAVELER, VAtVE MANUAL GATE DRIVE D05913-l WITHDRAW RISER ISO DN P-305-0 Dr-f)MDS-30S"01 rPE RF0ftMED-FMV*

PER PMT SHEET.

23305-102=33=35 FREVENT-IVE ii/A REPtACECNe0MNET-FRett-Meti' 46-UG 102-VALVE MANUAL GATE DRIVE 1106916 WITHDRAW RISER ISO VLV. REMOVED / REPLACED VLV STEM / WEDGE P2 DMS 0305-01. TOROUED TO 19-21 FT/LDS.

2-305-102-34-55 PREVENTIVE N/A FREE 7E SEALED TO INSPECT / REPAIR ULV VALVE MANUAL GATE DRIVE D06917 INTERNALS PER DMP 305-05, DMS 305-01.

WITHDRAW RISER ISO MMP/TRAVELR FOR PMV'S PER PMT SHEET.

2-305-102-38-59 PREVENTIVE N/A FREEZE SEALED. DISASSEMBLED VLV BONNET, VALVE MANUAL GATE DRIVE D06918 CLEANED PARTS, REPLACED STEM / WEDGE, NE[

WIT 11 DRAW-RISER ISD McK INtWBtOE-CHECKEDrPMV'3-t*f R DMP 305-05, DMS 305-01.

2-305-112-38-59 PREVENTIVE N/A REMOVED / CLEANED BONNET STEM / WEDGE, B003 UAtVE MANUAt1ATC SCRAii 007026 DISCHARGE RISER ISO

& BONMET--OtUC-CMECKED-OK---IN*tTAttt0 DONNET W/NEW STEM AND WEDGE. 10RQUED TO 20 FT/LOS.

2-305-112-54-43 FREVENHVE N/A REMOVED / CLEANED BONNE-T-94EM/HEDOC. DODY VALUE MANUAL GATE SCRAM D07032 B BONNET. BLUE CHECKED OK. INSTALL ED DISCHARGE RISER ISO BONNET W/NEW STEM AND WEDGE. TOROUED TO 20 FT/LBS.

2-305-112-58-35 PREVENTIVE N/A


----~~---

REMOVED / CLEANED BONNET STEM / DISC, BODY VALVE MANUAL GATE SCRAM D07033 S BONNET. BLUE CHECKED NEW STEM AND DISI DISCHARGE RISER ISO FAILED.

21305-112-50-11 PREVENTIVE N/A BONNET / STEM WEDGE & GASKET'REHdVEb/P VALVE MANUAL GATE SCRAM D07039 REPLACED. BLUE CHECK ACCEPTABLE.

DISCHARBE-RISER-ISO TORO 9ED--TC 20 FT/tBO.

2-305-112-42-07 PREVENTIVE N/A BONNET / STEM WEDGE & GASKET REMOVED /

VALVE-MANUAt-BATE-SCRAM D07042 REPh AGEttr-bh0E-CHEEM-NOT-ABC E PT ABL E.

DISCHARGE RISER ISO 2-305-ur-34 c; FREVENT-IVC N/^i REMOVED /REPEAeEf*-INTERN AL0 5 Ot-UE-C4fEEME#

VALVE MANUAL GATE SCRAM 007047 GEAT. TORQUED TO 20 FT/LBS.

DISCHARGE RISER ISO

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.u..u co imrNiENANCE NATURE OF LER OR OUTAGE MALFilNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 2-0202-28 PREVENTIVE N/A REPLACED MECH SEAL. ALIGNED MOTOR 10 PUMP-B-REACTOR-CIRCUtATING 007106 PUMP-PER-DMP-0202-01T-DMP-0202-02, DMP 0202-03 AND STATION TRAVELER.

2-0202-46 FREvENTivE N/A CiiECiCED TGROUE UN VOi(E TU BGNNET AND VALVE NO GATE RX RECIRC PP D07108 YOKE TO OPERATOR.

SUCTION VALVE 2-0202-58 PREVENTIVE N/A-TORGUED YOKE TO OPERATOR BOLTING.TO 225 VALVE M0 DATE RX RECIRC PP DISCHARGE 007110

.FT/LBS, YOKE'TO BONNET BOLTING TD-389 FT/LBS.

2-0203-3A PREVENTIVE N/A

- =

REMOVED AND INSTALLED REBUILT TARGET VALVE RELIEF TARGET ROCK A 007115 ROCK PER DMP 0200-47.

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2-0203-3C PREVENTIVE

'N/A' i---------L 1TOOK BRACKET 0FF.! REINSTAL ED WITH'NEW-VALVE ret 3EF ELELiROMATIC C D07117 LI3C GUIW r-PILGT FLUG, TeROUED 70 ;7C FT/LBS. SEAL RING RETAINER W/NEW RING, TO 209. PUT GAG BACK ON SDLENDID BRACKE 2-Oev3-su FREvEniivE W/A REFi*eEO-Eteet0MATIC WITM REGUILO. GLGj VALVE RELIEF ELECTROMATIC D 007118..

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JGASKET 0K, G0/NO G0 GAUGE. PUT NEW 4m

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REMOVED PILOT GASKET, CLEANED PILOT-ARE VALVE RELIEF ELECTROMATIC E D07119 QC OKAYED. PUT NEW PIOT BACK W/NEW i

GASKET. PUT BRACKET BACK ON/TOROUED TO' PT/t93.

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VALUE D SAFETY RELIEF MAIN'

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PIPING.TESTEDVLVPERDMP200-03.;DIDj STCAM ALL FHV'5 ANG GC HCLG FGINT3.

2-0203-4A PREVENTIVE N/A REMOVED / REPLACED SRV. PERFORMED AS FOUN' VnLvt a use t s i Rei. Att nnin uG7123 NFT-TEST-PPER DNF ZGG-03. ADDRESSEO 1W STEAM g

Q HOLD PTS AND PMV'S.

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@ g,]g 2~300-ta-su-a rntvensAvt nm nr nuvtu uuv uanr nnnuni inm nu.r_u nom VALVE AD SPLIT BODY, SCRAM 007225 SET DIAPHRAGM PRESSURE.

DUTLET VALVE nW e+

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EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 2-305-127-34-27 PREVENTIVE N/A INSTALLED NEW DIAPHRAGM, SET PRESSURE l

VALCVE AD 1FtTT Buuye dCRAM D07226 OUTLET VALVE 23305-127-30-23 PREVENTIVE N/A

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N5TALLED NEM-ttIAPtfRh0Mr3ET-tRES3tfRE---

VALVE A0 SPLIT BODY, SCRAM D07227 OUTLET VALVE 2-305-127-34-23 PREVENTIVE N/A INSTALLED NEW DIAPHRAGM PER DNS 0300-01 VALVE A0 SPLIT BODY, SCRAM D07228 REPLACED 2 BROKEN BOLTS. LUBED ALL OUTLET VALVE BOLTING MATERIAL. STROKED AND ADJUSTED vat 4/E -TO-SPEC 5.

2-305-127-38-23 PREVENTIVE N/A INSTALLED NEW DIAPHRAGM. TORQUED STEM VALVE A0 SPLIT BODY, SCRAM 00722V NUT TO 30 FT/LBS. LUDED ALL BOLTING OUTLET-VAtVE MftiERiftt;- RDdtf3TED-INLET #001ttM*AtVES-TO SPECS PER PROCEDURE.

2-305-127-34-19 PREVENTIVE N/A INSTALLED NEW DIAPHRAGM. TOROUED STEM VAtVE AD SPLii BUUV, 5 CRAM U07230 NUT f*fftB3rtOtfPt-TNO-tttfT-2G FT/LBS.

DUTLET VALVE CLEAi4ED & LUBED ALL BOLTING MAIERI AL.

ADJUSTED STROKE OPENING PRESSURE TO SPEt 23305-127-55-19 FREVENTIVE N/A CLEAifED/IN5FECTfD-AND-INSTALLEC NEN VALVE A0 SPLIT BODY, SCRAM 007231 DIAPHRAGM. SET DIAPHRAGM PRESSURE.

OUTLET VALVE V

7 2-305-127-42-19 PREVENTIVE N/A INSTALLED NEW DIAPHRAGM. LUBED BOLTING VALVE AD SPLIT BODY, SCRAM 007232 MATERIAL. TORQUED STEM NUT OT 30 FT/LDS OUTLET VALVE AND COUPLING NUT TO 10 FT/LBS. STROKED AND ADdOSTED-VAtVE-TO GPECG.

.,., A > c 2-305-127-46-19 PREVENTIVE N/A :

VALVE A0 SPLIT BODY, SCRAM D07233

- REPLACED 'OTAPHRAGM WITH ' NEW. LUBED BOLT-2---------


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ING MATERIAL ~. TORQUED STEM NUT TO 30 ET<

z OuiLL6 VALVt.

LC5 UNU COUILING NUT TC 1G FT/L55.

STROKED VALVE AND ADJUSTED TO SPECS.

2-305-127-50-19 PREVENTIVE N/A INSTALLED DIAPHRAGM, SET PRESSURE.

VAEVE Au SPtis tsuur, dLMars v07234 OUTLET VALVE 2-0220-3 FREVENTivE N/A REFLACED WGRN GEAR, IN5TALLED NGV, OPERATOR MOV STEAM DRAIN TO D09218 REPLACED DECLUTCH LEVER / SHAFT / FORK ASM/

COND GREASE RELIEF KIT. COMPLETED DY DMP 0400-15 & 16.

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DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 2-0751A CORRECTIVE N/A REPLACED SRM21 DETECTOR. DISCONNECTED &

ELEMENT SRM-21 DETECTOR Ot7121 CONNEC T ED-S RM-2t-TO-SUPP0ttTEM*S-REPA f ft-SRM DRIVE TUBE. RETESTED AFTER EMD FINISHED. PASSED MITERIA AND PNV.

2-1751A CURRECTIVE N/A 15TALLED HEW DRIVE TUBE. WEW IiiH ELEMENT SRM 13 DETECTOR D17121 DETECTOR INSTALLED.

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ORESDEN UNIT 2/3 SAFETY RELATED MAINTENANCE o

NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION g

2/3-200-003 PREVENTIVE N/A REPLACED PINS AND BUSHINGS. REPAIRED VAEUE CRECK svant retuwaitn uus v0130; etsi auta rts NORK INbihubl1UNb 1RAVELER S-1 MMP DEV 1.

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  • Sardy Raamhd Modification (Units 2 and 3)

No additional modifications authorized for operation during the months prior to July,1993 ~ were reported to l

Regulatory Assurance. As stated in last month's report, changes implemented during July,1993 and thereafter will be reported with the FSAR updates in accordance with 10 CFR 50.71(e).

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l 5.6 Temsporary Syssam Alterations lastaBed (Unit 2 and Unit 3)

A "Tanporary Systan Alteration" rders to electrical junpers, lifted leads, renoved funes, fumes turned to non<mnducting position, fines moved fran nonnat to reserve holder, tanporary power supplia, test switches in alternate positions, tanporary blank flanges, and spool pieces. Alterations contmiled and documented as part of a routine out-of-service or other procedure, alterations which are a normal feature of systan design, and hoses installed as part of a venting or draining process are not included.

No additional ta=porary alterations approved for use during the months prior to July,1993 west repoded to Regulatory Assurance. As stated in last month's report,10 CFR 50.59 evaluations performed during July,1993 c.nd thereafter will be reported with the FSAR updates in accordance with 10 CFR 50.71(c).

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'l 5.7 Other Units 2 and 3 Requierd 10 CFR 50.59 Evaluations Other required 10 CFR 50.59 evaluations include Set Point Changes (SPC), Rigging Eraluations and changes to equipment not reported in Sections 5.2 through Section 5.6.

No additional evaluations performed during the months prior to July,1993 were reported to Regulatory Assurance. As stated in last month's report,10 CFR 50.59 evaluations perfonned during July,1993 and thereafter will be reported with the FSAR updates in accordance with 10 CFR 50.71(e).

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