ML20125E406

Monthly Operating Repts for Nov 1992 for Dnps,Units 1,2 & 3

ML20125E406
Person / Time
Site:	Dresden
Issue date:	11/30/1992
From:	King G, Schroeder C COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CWS-LTR-#92-732, NUDOCS 9212170043
Download: ML20125E406 (26)

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Common::ealth Edison December 1, 1992

. 9,esden Nuclent Power Station j< an.#: CWS 1.TR D 2-732 Morns, Illinois 60450 Telephone 815!942 2920 Director, Nuclear Reactor Regulation United States Nucicar Regulatory Commis ; ion Washington, DC 20555 Attention: Document Control Desk Centlement

Subject:

Monthly Operating Data Report Dresden Nuclear Power Station Conrnonwealth Edison Company Docket Nos.50-010, 50-237, and 50-249 En c l o s e d i s t he Rre s d enjiu c l e a r.lowe r_St a t inn _ lion t hly_0pera.t iti g_ S umoa ryle p.o r t for November, 1992. This information is supplied to your office in acec,rdance with the instructions set forth in Regulatory Guide 1.16.

Sincerfly, (pa/les N1W. schroeder l Station Manager CWS/GHK:kis Enclosure

cc NRC Region III Office j Illinois Dept. of Nrclear Safety, State of Illinois U.S. NRC, Document Management Branch Nuclear Licensing Administrator Vice Pres. - BWR Operations General Manager - Nuclear Services T. S. Engr. (2)

NRC Senior Resident Inspector Nuclear Quality Programs - Dresden Nuclear Engineering Manager Comptro11er's Office Manager - Quality Assurance / Nuclear Safety Manager - Reliability Programs INFO Records Center

UDI,Inc.- Wash. D.C.

File /NRC Op. Data File / Numerical i

16002s sn 9212170043 921130 PDR ADDCK 05000010 d/k r

PDR V \

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l mud!1tLY NRC SW9tARY OF OFFJtATING KKPERIENCE, CHANCES, TESTS, AND EXPERIMENTS PER RECUlWIURY CUIDE 1.16 AND 10 CFR 50.59 FOR 1RESDEN NUCIX.AR POWER STATION CG990NWCALTH KDISON C(MFANY FOR NOVEMBER, 1992 URIT DOCEII LLCENSE 1 050-010 DPR-2 2 050-237 DPR-19 3 050-249 DPR-25 4

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TABLE OF CONTENTS 1

. NOVMMBER, 1992 NRC REPORT f

i 4 1.0 Introduction i

2.0 Stammary of Operating Experience j 2.1 Unit 2 Monthly Operat!ng Experience Summary.

j 2.2 Unit 3. Monthly Operating Experie ice Summary.

l l 3.0 Operating Data Statistica l l l j 3.1 Monthly Operating Data Report - Unit 2 3.2 Monthly Operating Data Report - Unit 3 l 3.3 Average Daily Power Level Data - Unit 2 1 3.4 Average Daily Power Level Data - Unit 3 j 3.5 Unit Shutdown and Power Reduction Data - Unit 2 l 3.6 Unit Shutdown and Power Reduction Data - Unit 3 3.7 Station Maximum Daily Load Data 4.0 Unique Reporting Requirements t 4.1 Main Steam Relief and/or Safety Valve Operations - Unit 2 and Unit 3 I 4.2 Off-Site Dose Calculation Manual Changes j 4.3 Major changes to the Radioactive Waste Treatment i 4.4 Failed Fuel Element Indications

! 4.4.1 Unit 2 j 4.4.2 Unit 3 l

5.0 Plant or Procedure Changes, Tests, Experiments, and Safety Related

! Malutenance i

j 5.1 Amendments to Facility L2 cense or Techni al Specifications

5.1.1 Unit 2 l 5.1.2 Unit 3 l S.2 Changes to Procedures which are Described in .he Final Safety Analysis Report (FSAR) (Units 2 and 3) 5.3 Significant Tests and Experiments Not Describot in the FSAR (Units 2 and 3) 5.4 Safety Related Maintenance (Units 2 and 3) 5.5 Completed Safety Related Modificationn 5.6 Temporary System Alterations Installed l 5.7 Other Required 10 CFR 50.59 Evaluations (Units 2 and 3) l

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10 Introduct.lon 2 . .

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. Dr'esden Nucicar Power Station is a three reactor generating facility owned and operated by the Commonwealth Edison Company of Chicago, j Illinois. Dresden Station is located at the confluence of the Kankakee and Des Plaines Rivers, in Grundy County, near Morris. Illinois.

j Dresden Unit 1 is a General Electric Boiling Water Reactor with a design 4 net electrical output rating of 200 megawatts electrical (MWe). The unit j

! is retired in place with all nuclear fuel removed from the reactor i vessel. Therefore, no Unit 1 operating data is provided in this report.

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

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

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

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i This report for November, 1992 was compiled by Gregory H. King of the

Dresden Technical Staff, telephone number (815) 942-2920, extension 2648. i

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2.0 SIM1ARY OF OPERATING EKPERIENCE FC3 NOVIMBER,1992 2.1 UNIT 2 MONTilLY OPERAlb0 EXPERIENCE

SUMMARY

i 11-01-92 to 11-30-92 Unit 2 entered the month on line and operating at 756 d

MWe as specified by the System Load Dispatcher (LD).

The unit operated at maximum load or in Economic

) Generation Control (ECC) as specified by the LD the entire month with an availability of 100.0% and a

capacity factor of 81.92%.

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2.0 FtM1ARY OF OPERATING EXPERIENCE FOR NOVFMBER,1992 2.2 UNIT 3 MONTilLY OPERATING EXPERIENCE

SUMMARY

! 11-01-92 to 11-10-92 Unit 3 entered the month on-line and operating at 791 MWe and' operated through 11-07-92 at 0227 when the unit

> was taken manually off line and the Reactor was maJe I

sub-critical at 0236 hours0.00273 days <br />0.0656 hours <br />3.902116e-4 weeks <br />8.9798e-5 months <br /> of t'.e Ase day. This was accomplished to enter the drywell and repair the pneumatic actuator instrument line of the 1A Main Steam Isolation Valve (MSIV). After satisfactory repairs in j the drywell were completed, the Reactor was brought

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critical on 11-09-92 at 1857 hours0.0215 days <br />0.516 hours <br />0.00307 weeks <br />7.065885e-4 months <br /> and the unit was synchronized to the system on 11-10-92 at 0759 hours0.00878 days <br />0.211 hours <br />0.00125 weeks <br />2.887995e-4 months <br />.

) 11-11-92 to 11-30-92 The unit operated the remainder of the month steadily

increasing load to maximum load or in EGO as specified by the LD with an availability of 89.23% and a capacity factor of 69.98%.

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3.0 OPERATINO DATA REPORT

. 3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO DOCKET No. 050-237 i DATE December 1, 1992 l COMPLETED BY G. H. King TELEP110NE (815) 942-2920 I

OPERATING STATUS i l

1. REPORTING PERIOD: NOVEMBER, 1992  !

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2. CURRENTLY AUTil0RIZED POWER LEVEL (MWth): 2,527 MAXIMlM DEPENDABLE CAPACITY (MWe NET): 772  ;

DESIGN ELECTRICAL RATING (MWe Net): 794 l

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> 3. POWER LEVEL TO WIIICII 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

_Thiallonitt Yr-to-Date_. ._Cumulatin_

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5. Il00RS IN PERIOD 720 8,040 197,688

6. TIME REACTOR CRITICAL (Hours) 720.0 7,024.2 149,042.8

7. TIME REACTOR RESERVE SHUTDOWN (Hours) 0.0 0.0 0.0

< 8. TIME GENERATOR ON-LINE (Hours) 720.0 6,913.7 142,920.2

9. TIME GENERATOR RESERVE Sl!UTDOWN (llours) 0.0 0.0 0.0

10. TilERMAL ENERGY GENERATED (MWilt Gross) 1,525,355 13.117,825 294,739,335

, 11. ELECTRICAL ENERGY GENERATED (MWHe Gross) 492,171 4,144,169 94,113,153 1

12. ELECTRICAL ENERGY GENERATED (MWHe Net) 468,275 3,923,908 89,954.695

13. REACTOR SERVICE FACTOR (%) 100.0 87.4 75.4

14. REACTOR AVAILABILITY FACTOR (%) 100.0 87.4 75.4

15. GENERATOR SERVICE FACTOR (%) 100.0 86.0 72.3

16. GENERATOR AVAILABILITY FACTOR (%) 100.0 86.0 72.3

17. CAPACITY FACTOR (USING MDC Net) (%) 84.1 63.2 58.9

18. CAPACITY FACTOR (USING DER Net) (%) 81.9 61.5 57.3 i 19. FORCED OUTAGE FACTOR (%) 0.0 14.0 12.0

20. SilUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (Type, Date and Duration of Each)

D2R13 Refueling Outage Scheduled to begin on January 4, 1993.

21. IF S!!UTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A

3.0 OPERATING DATA REPOLT 3.2 OPERATING DATA REPORT - DRESDEN UNIT TilREE DOCKET No. 050-249 DATE December 1, 1992 COMPLETED BY G. H. King l TELEPHONE (815) 942-2920 l 4  :

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i OPERATING STATUS

1. REPORTING PERIOD: NOVEMBER, 1992 l l

2. CURRENTLY AUT110RIZED POWER LEVEL (MWth): 2,527 '

NAXIMUM DEPENDABLE CAPActiY (MWe Net)

773

DESIGN ELECTRICAL RAT'1G (MWe Net)

794

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

4. REASONS FOR RESTRICTIONS (IF ANY): N/A REPORTING PERIOD DATA

._Iltis MonttL _Yr-tn-Dati. _Cuntulatire_

5. IlOURS IN PERIOF 720 8,040 187,273

6. TIME REACTOR CRITICAL (Hours) 655.7 5,019.4 134,919.1

, 7. TIME REACTOR RESERVE SHUTDOWN (flours) 0.0 0.0 0.0

8. TIME GENERATOR ON-LINE (Hours) 642.5 4,734.4 129,618.3

9. TIME GENERATOR RESERVE SHUTDOWN (llours) 0.0 0.0 0.0

! 10. TilERMAL ENERGY GENERATED (MWHt Gross) 1,297,619 8,774,017 266,128.050

11. ELECTRICAL ENERGY GENERATED (MWife Gross) 419,678 2,792,645 85,699,487

12. ELECTRICAL ENERGY GENERATED (MWile Net) 399,233 2 625,289 81,167,437

13. REACTOR SERVICE FACTOR (%) 91.1 62.4 72.0

! 14. REACTOR AVAILABILITY FACTOR (%) 91.1 62.4 72.0

15. GD.'ERATOR SERVICE FACTOR (%) 89.2 58.9 69.2 l 16. GENERATOR AVAILABILITY FACTOR (%) 89.2 58.9 69.2

17. CAPACITY FACTOR (USING MDC Net) (%) 71.7 42.2 56.1

18. CAPACITY FACTOR (USING DER Net) (%) 69.8 41.1 54.6

19. FORCED OUTAGE FACTOR (%) 10.8 10.0 11.3

20. SilUTDOWNS SCilEDULED OVER Tile NEXT 6 MONTHS (Type, Date and Duration of Each)

NONE.

21. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP f N/A I

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l 3.3 AVERACK 11AILY UNIT POWER LEVEL l I

i DOCKET No. 050-237 )

UNIT Dresden 2 DATE December 1, 1992 COMPLETED BY G. II. King TELEP110NE (815) 942-2920 MONTil: NOVFMBER, 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe Net) 01 639 17 653 02 697 18 611 03 6 14 19 648 04 633 20 fi45 _

05 690 21 6A7- _

06 6B1 22 643 07 679 23 640 _._

08 670 _ 24 638-09 6k7 25 63h _ . _ _

10 651 26 621 11 6.% 27 61L 12 653 28 613 13 669 29 52.8 14 658 30 577 15 (L63 i 16 652 l

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3.4 AVERACE IMILY UNIT POWER IEVEL

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4 DOCKET No. 050-249 UNIT Dresden 3 DATE December 1, 1992 COMPLETED BY G. H. King TELEPHONE (815) 942-2920 l

MONTil NOVIMBER, 1992 i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe Net) 01 __ _0 53 17 168-02 745-__ 18 62ry 1

03 316 19 M2_.

04 _3M 20 653 l 05 733 21 344 06 612 22 31a 07 6 _ 23 6.00 ___

08 0 24 728 09 0 25 765 10 210 26 724 11 6&4 _.__ 27 7.24 12 563 28 718 l

l 13 589 29 124 14 _61 7 30 7_17 l

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16 695 1

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DOCKET No. 050-237 UNIT NAME Dresden Unit .

DATE December 1, 1992 COMPLETED BY G. H. King TELEPHONE (815) 942-2920 3.5 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH NOVDIBER, 1992 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE & CORRECTIVE 2 0

, NO. DATE TYPE I DURATION REASON SHUTTING EVENT CODE CODE 5 ACTION TO 3 REPORT # PREVENT RECURRENCE (HOURS) DOWN REACTOR l' NONE 1 2 3 4 F: Forced Reason: Method: Exhibit G Instructions for S: Scheduled A Equipment Failure (Explain) 1 Manual Preparation of Data B Maintenance or Test 2 Manual Scram Entry Sheets for Licensee C Refueling 3 Automatic Scram Event Report (LER) File D Regulatory Restriction 4 Other (Explain) (NUREG-0161)

E Operator Training & Licensee Examination 5 Load Reduction l F Administrative j G Operational Error 5 Exhibit I Same Source H Other (Explain) 2 ZCWSLT92/296

1 DOCKET No. 050-249 UNIT NAME Dresden Unit 3 DATE December 1, 1992 COMPLETED BY G. H. King -

TELEPHONE (815) 942-2920 3.6 UNIT SHUTDOWNS AND POWER Rh3JCTIONS REPORT MONTH NOVDtBER, 1992 l

METHOD OF LICENSEE SYSTEM COMPONENT CAUSE & CORRECTIVE 2 CODE 5 WO. DATE TYPE 1 DURATION REASON SHUTTING EVENT CODE' ACTION T0 (HOURS) DOWN REACTOR 3 REPORT # PREVENT RECURRENCE 7 11-07-92 F 77.5 A 1 N/A LD N/A Off-line manually to repair lA MSIV pneumatic line air leak in the Drywell.

8 11-21-92 F 44.0 N/A 5 (N/A) N/A N/A N/A Reduced load below 1100 MWth to come off the cooling lake and discharge directly to the river.

I 1 2 3 4 F: Forced Reason: Method: Exhibit G Instructions for S: Scheduled A Equipment Failure (Explain) 1 Manual Preparation of Data B Maintenance or Test 2 Manual Scram Entry Sheets for Licensee C Refueling 3 Automatic Scram Event Report (LER) File D Regulatory Restriction 4 Other (Explain) (NUREG-0161)

E Operator Training & Licensee Examination 5 Load Reduction F Administrative G Operational Error 5 Exhibit I Same Source H Other (Explain)

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1 3.7 COMMONWEALTil EDISON COMPANY i DRESDEN NUCLEAR POWER STATION .

j MAX 1 MUM DAILY ELECTRICAL LOAD j FOR IEE MONTH OF NOVEMBER,1992 f Day Hour Ending KWe

! 1 1500 1,538,800 2 1800 1,533,000

+ 3 0100 1,270,300 4 2400 1,4?8,500 l

1 5 2200 1,515,500 6 0100 1.507,500 7 0100 899,700 1 8 0100 715,200 j 9 1300 725,300 10 2300 1,227,700 11 1200 1,247,700 12 1300 1,341,900 13 0300 1.529,000 14 2400 1,473,500 i 15 0600 1,519,400 i 16 0400 1,477,600 i 17 2000 1,393,700

, 18 0500 1,390,700 i 19 0100 1,386,200 l 20 G500 1,357,200 l

21 2200 1,153,400

22 0100 1,071,800

, 23 2000 1,376,400 '

24 1900 1,492.900 i 25 0300 1,447,000

! 26 1500 1,430,900 27 1800 1,432,000 l

28 2200 1,428,400 29 0300 1,405,700 -

l 30 1200 1,425,100 l

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! 4.0 UNIQUE REPORTING REQUIREMENTS I

i 4.1 MAIN STEAM RELIEF VALVE OPERATIONS j Relief valve operations during the November, 1992 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 j circumstances resulting in its actuation.

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l' I Valves No. and Type Plant Description j

.i Vait Datt Acluded OLAtluallpaa CondLtions _QLlYent a_

i 2 No Unit 2 Main Steam Relief and/or Safety Valve actuations occurred during this reporting p9riod.

i 3 No Unit 2 Main Steam Relief and/or Safety Valve actuations occurred during this reporting period.

f 4.2 0FF-SITE DOSE CALCUIATION MANUAL (ODCM) CIIANGES No ODCM changes were reported for the month of November, 1992.

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4.3 MA.10R CllANGES TO Tile RADIDAUTIVE WASTE TREA'IMENT SYSTl?tS DURING NOVIMBER , 1992 l

Current Status of Radioactive Waste Treatment System Upgrade Project:

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The Waste Neutralizer Pumps A and B Replacement Modification i M12-2/3-87-002P is complete and operational. The Ra Naste Precoat Area 4 Sample Sink mechanical portion of Modification M12-2/3-87-002F is corr.phte and operational. The Radwaste Seal Water Pump System Modification M12-2/3-87-002M is complete and operational. The Radwaste

Floor Drain Collector Pump replacement Modification M12-2/3-87-002N will be starting in mid-December, 1992.

4.4 FAILED FUEL E1RiENT INDICATIONS  !

j 4.4.1 Unit 2 Unit 2 fuel performance during November, 1992 continued to show no

indications of leaking fuel. This is based on the sum of the activities i of the six (6) Noble Gases as measured at the Recombiner. Therefore, Unit 2 had excellent fuel performance.

4.4.2 Unit 3 l Unit 3 fuel performance during November, 1992 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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S.0 PIANT OR PROCEDURE CHANCES TESTS, EXPERIMENTS, AND SAFETY RE1ATED MAINTF. NANCE 5.1 Amendments to Facility License or Technical Specifications.

5.1.1 Unit 2, November, 1992.

Unit 2 Amendment #118, dated October 01, 1992.

This amendment will allow unlocking High Radiation Area (HRA) doors to the areas where the dose rates are less than 1,000 millirem per hour (mr/hr). The NRC has recognized that professional health physics staffs, sophisticated radiation protection programs, and new dosimetry technology provide adequate barriers to unathorized overexposures. To implement this change, electronic dosimetry is required to be worn by all persons entering the HRA. The major benefit realized by this amendment is the redaction in manhours associated with controlling the HRA's with "R-keys" and maintaining key logs.

Access to High-High Radiation Areas will continue to be 1

controlled by locks as well as the RWP Program. All HRA's will conspicuously posted as such. The Radiation Protection Department will inform station personnel when the allowances associated with this amendment will be implemented.

Unit 2 Amandment #119, dated November 01, 1992.

This amendment to Technical Specification (TS), Section 3/4.9.

primarily are requested to: 1) Revise the operability requirements for a diesel generator when performing preventative maintenance and surveillance testing; 2) Revise the operability of a diesel generator upon loss of the other auxiliary electrical equipment; 3) Revise the 125 Volt DC battery availability requirements to address the use and inclusion in the TS of the alternate 125 Volt DC batteries; and 4) Revise the battery testing requirements to include both service and performance test Surveillance Requirements (SR)that reflect current industry standards.

Specific changes to the TS are identified below:

1) Battery survelliance requirements (4.9.A.3) have been revised to remove reference to battery discharge tests and to provide new surveillance requirements which reflect the performance and service tests required per IEEE Standards.

2) The words "..ulth the head off.." have been-

, removed from Limiting Conditions for Operations (LCO) 3.9.B.

3) The monthly diesel operability surveillance has been split into SR's 4.9.D.1.a. for start test and 4.9.D.1.b. for a run and load test. This change was made to finalize the method for demonstrating operability as described in TS Interpretation 14.

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5.0 PIANT OR PROCEDU'iR CHANCES, TESTfi, EXPERIMlWPS, AND SAFETY RELATED 1 MAINTENANCF. (Continued)

Unit 2 /anendment #119 (Continued)

4) LCO's 3.9.B.1. and 3.9.B.2.a. have been revised to change the words " demonstrated operable to

" demonstrated operable per Specification 4.9.D.1.a.". )

5) LCO 3.9.B.2.b., which allowed a 90 minute period for preventative maintenance prior to declaring a diesel generator inoperable has been removed.

This paragraph is no longer required.

6) LCO's 3.9.B.3. and 3.9.B.4. have been revised to include LCO's for the 125 Volt DC alternate batteries is allowed.

Unit 2 Amendment #120, dated November 22, 1992.

This amendment has removed the LCO SR reflecting additional restrictions associated with Spent Fuel Cask Handling required prior to August 30, 1976. LCO's and SR's for High Energy Piping Integrity (Section 3/4.11) have also been removed since the modifications to high energy piping systems have been completed and the provisions of Section 3/4.11 are no longer required.

Specific changes are made to:

TS 3.10.F.3.

l TS 4.10.F.2.

j TS 3/4.11 (Deleted) i s

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5.0 PLANT OR PROCEDURE CllANCES, TESTS, EXPERIMENTS, AND SAITTY RElATED MAINTENANCE (Continued) 5.1.2 Unit 3, November, 1992.

Unit 3 Amendment #114, dated October 01, 1992.

This amendment will allow unlocking liigh Radiation Area (HRA) doors to the areas where the dose rates are less than 1,000 millirem per hour (mr/hr). The NRC has recognized that professional health physics staffs, sophisticated radiation protection programs, and new dosimetry technology provide adequate barriers to unathorized overexposures. To implement this change, electronic dosimetry is required to be worn by all persons entering the llRA. The major benefit realized by this amendment is the reduction in manhours associated with controlling the llRA's with "R-keys" and maintaining key logs.

Access to liigh-liigh Radiation Areas will continue to be controlled by locks as well as the RWP Program. All llRA's will conspicuously posted as such. The Radiation Protection Department will inform station personnel when the allowances associated with this amendment will be implemented.

Unit 3 Amendment #115, dated November 01, 1992.

This amendment to Technical Specification (TS), Section 3/4.9.

primarily are requested to: 1) Revise the operability requirements for a diesel generator when performing preventative maintenance and surveillance testing; 2) Revise the operability of a diesel generator upon loss of the other auxiliary electrical equipment; 3) Revise the 125 Volt DC battery availability requirements to address the use and inclusion in the TS of the alternate 125 Volt DC batteries; and 4) Revise the battery testing requirements to include both service and performance test surveillance requirements that reflect current industry standards.

Specific changes to the TS are identified below:

1) Battery Surveillance Requirements (4.9.A.3) have been revised to remove reference to battery discharge tests and to provide new surveillance requirements which reflect the performance and service tests required per IEEE Standards.

2) The words "..with the head off.." have been removed f rom LCO 3.9.B.

3) The monthly diesel operability surveillance has been split into SR's 4.9.D.1.a. for start test and 4.9.D.1.b. for a run and load test. This change was made to finalize the method for demonstrating operability as described in TS Interpretation 14.

4) LCO's 3.9.B.1. and 3.9.B.2.a. have been revised to change the words " demonstrated operable: to

" demonstrated operable per Specification 4.9.D.1.a.".

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5.0 PIANT OR PROCEDURE CilANGES, TESTS, EXPERIMENTS, AND SAFETY REIATED MAINTENANCE (Continued)

Unit 3 Amendment #115 (Continued)

5) LCO 3.9.B.2.b., which allowed a 90 minute period for preventative maintenance prior to declaring a diesel generator inoperable has been removed.

This paragraph is no longer required.

6) LCO's 3.9.B.3, and 3.9.B.4. have been revised to include LCO's for the 125 Volt DC alternate batteries is allowed.

Unit 3 Amendment #116 dated November 22, 1992.

This amendment has removed the LC0 SR reflecting additional restrictions associated with Spent Fuel Cask Handling required prior to August 30, 1976. LCC's and SR's for High Energy Piping Integrity (Section 3/4.11) have also been removed since the modifications to high energy piping systems have been completed and the provisions of Section 3/4.11 are no longer required.

Specific changes are made to:

TS 3.10.F.3.

TS 4.10.F.2.

TS 3/4.11 (Deleted) 5.2 Changes to Procedures Which are Described in the FSAR (Units 2 and 3 during November, 1992.

Table 5.2.1, attached, summarizes the procedures described in the FSAR which were approved fcr use during this reporting period. Only those procedures that have required a new or an additional 100FR 50.59 review of changes are included.

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CHANGES TO PROCEDURES WHICH ARE DESCRIBED IN THE FSAR (UNITS 2 AND 3) FOR NOVEMBER, 1992 i

SUMMARY

OF i PROCEDURE TYPE PROCEDURE NO. PRQCEDURE TITLE / DESCRIPTION CHANGES i-Dresden Instrument DIS 0700-04 Intermediate Range Monitor (IRM) Rod Block and 2 Surveillance Procedure Scram Functional Test.  !

a Dresden Operating DOP 0400-01 Reactor Manual Control System Operation. 1 1

Procedures DOP 0400-02 Rod Worth Minimizer. 2 ,

Dresden Operating DOS 1300-01 Isolation Condenser Five Year Heat Removal 3 Surveillance Procedures Capacity Test.

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DOP 6600-01 Diesel Generator Surveillance Tests. 3

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1 2. Changed for clarification, intent of procedure unchanged.

l 3. Changed to incorporate requirements for new equipment; intent of procedure unchanged

l. 4. Changed to implement improved testing / calibration methodology; intent of procedure unchanged.

1 XCWSLT92/296 1

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}l 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 July, 1992 are listed below:

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SP 92-08-114 RADWASTE PUMP SEAL WATER MODIFICATION TEST (M12-2/3-87-002M) q The purpose of this special procedure was to detail the i steps necessary to verify that the Pump Seal Water System and associated components operate per design.

1 SP 92-10-121 WASTE NEUTRALIZER PUMP REPLACEMENT MODIFICATION TEST 2

(M12-2/3-87-002P)

The purpose of this special procedure was to detail the i

steps necessary to verify that the Waste Neutralizer Pumps 2/3-2019A and 2/3-2019B and associated equipment operate per design.

1 SP 92-10-122 AUXILIARY AIR COMPRESSOR OPERATION DURING REPLACEMENT OF THE UNIT 3C INSTRUMENT AIR COMPRESSOR

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The purpose of this special procedure was to provide i guidance for the Auxiliary Compressor Pre Start-up Checks,

Compressor Start-up and Compressor operation when connected to the Instrument Air System.

l SP 92-10-126 UNIT 2 AND 3 REACTOR BUILDING EQUIPMENT DRAIN TANK (RBEDT)

CLEANUP l 1he purpose of this special procedure was to detail the steps necessary to set up the required equipment and to perform the clean-up of the Unit 2 and Unit 3 RBEDT.

1 l SP 92-11-129 ANNUNCIATOR MODIFICATION M12-2-088-022B STAGE 5. 6 TESTING OF MULTI-INPUT WINDOWS ON PANEL 902-5 The purpose of-this special procedure was to verify proper operation of-all multi-input annunciator windows associated i with the Main Control Room Panel 902-5.

SP 92-11-130 ANNUNCIATOR MODIFICATION M12-2-088-022B STAGE 5, 6 TESTING OF MULTI-INPUT WINDOWS ON PANEL 902-8 l

The purpose of this special procedure was to verify proper l

operation of all multi-input annunciator windows associated i with the Main Control Room Panel 902-8.

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_-_ . . ~ . .- .. - ... _ __ - - - - - -- . . - . . . _ . - - - . . _ _ ._

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

(Continued)

SP 92-11-132 CONSTRUCTION TEST FOR M12-0-091-006 The purpose of this special procedure was to provide instructions to test the Motor Operated Valves )MOV) modifi(d per Modification M12-0-091-006, 2 to 4 Rotor, Palance of Plant MOV Limit Switch Replacement. Testing was done in accordance with the requirements of the criteria specified in the Modification Approval Letter.

SP 92-11-133 BACKUP CONTROL ROOM COOLING WATER FLOW EFFECT ON UNIT 2 CLOSED COOLING SERVICE WATER (CCSW) PUMP PERFORMANCE AND CCSW VAULT ROOM COOLER FLOW RATE ADJUSTMENT The purpose of this special procedure was to determine the effect on Unit 2 CCSW Pump performance caused by Control

. Room HVAC Train B operating at present day conditions and most limiting conditions. Also, an additional purpose of this special procedure was to adjust the CCSW Vault room cooler flow rate.

SP 92-11-134 ANNUNCIATOR MODIFICATION M12-2-08R-022B STAGE 5, 6 TESTING OF MULTI-INPUT WINDOWS ON PANEL 902-3 The purpose of this special procedure was to verify proper operation of all multi-input annunciator windowa associated with the Main Control-Room Panel 902-3.

SP 92-11-135 ANNUNCIATOR MODIFICATION M12-2-088-022B STAGE 5, 6 TESTING OF MULTI-INPUT WINDOWS ON PANEL 902-4 The purpose of this special procedure was to verify proper operation of all multi-input annunciator windows associated with the Main Control Room Panel 902-4.

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i 5.4 fiafety Related Malutenance (Unit 2 and 3) l Safety related maintenance activities for November,1992 are stuumarized 4 in the attached tables.

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5.5 C(wepleted Safety Reinted Modifications (Unita 2 and 3)

Modifications which have been authorized for operation during November, 1992 are listed. For ease of reference, the changes have been identified by their design change control modification number. Previously, only modifications that had been completely closed out were reported.

Madification_Ho_. Descriplion None. Not Applicable.

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a 1 5.6 Temporary System Alterations Installed (Unit 2 and Unit 3) i j A " Temporary System Alteration" refers to electrical jumpers, lifted leads, removed fuses, fuses turned to non-conducting position, fuses j moved from normal to reserve holder, temporary power supplies, test j switches in alternate positions, temporary blank flanges, and spool i pieces. Alterations controlled and documented as part of a routine out-of-service or other procedure, alterations which are a normal feature j of system design, and hoses installed as part of a venting or draining process are not included.

J l 5.6.1 Unit 2 November, 1992 i

! Temporary l System Installation Removal A11craLion_E h Descriplinn Date _Da11_.

l 11-29-92 This temporary alteration 11-01-92 12 Months i removed the harmoale filter 1 circuit and internal 7 second time

delay f rom ABB 27n Undervoltage Relays 127-3-B23-1 and 127-4-B23-1 i and replaced the instantaneous

! Agastat EGFD Relay 427Y1-23-1 with an Agastat ETR Adjustable Relay to maintain the 7 second time delay l

requirements for Bus 23-1 on Panel

! 2253-83. This was done to resolve l the adverse effect that radiation i has upon the ABB Undervoltage l Relays.

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! II-34-92 This temporary alteration 11-01-92 12 Months removed the harmonic filter circuit and internal 7 second time delay from ABB 27n Undervoltage l Relays 127-3-B24-1 and 127-4-B24-1 i and replaced the instantaneous

Agastat EGFD Relay 427Y1-24-1 with l an Agastat ETR Adjustable Relay to maintain the 7 second time delay l requirements for Bus 24-1 on Panel j' 2252-84. This was done to resolve the adverse effect that radiation has upon the ABB Undervoltage l Relays.

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5.o Temporary System Alterations Installed (Unit 2 and Unit 3)

Continued 5.6.2 Unit 3 November, 1992 Temporary System Installation Removal Alt.cration l o1 Deacription Date Jate_

111-46-92 This temporary alteration 11-08-92 15 Months installed an electrical jumper between terminal points 3 and 4 of Junction Box 3TB-A19 to provide a bypass of MSL tunnel high temperature switch 3-261-16B.

which has cable leads that have been damaged and are due for replacement during the next refueling outage. The other three temperature switches are operable and the two of four Technical Specifcations are satisfied.

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I 5.7 Other Units 2 and 3 Required 10 CFR 50.59 Evaluations for July,1992 3

Other required 10 CFR 50.59 evaluations include Set Point Changes,

< Rlgging Evaluations and changes to equipment not reported in Sections 5.2 through Section 5.6.

Ins _tallation301 Dearrl2 tion None. Not Applicable.

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