ML20132F750

Monthly Operating Repts for June 1985

ML20132F750
Person / Time
Site:	Point Beach
Issue date:	06/30/1985
From:	Fay C, Krause C WISCONSIN ELECTRIC POWER CO.
To:	NRC
References
CON-NRC-85-16 VPNPD-85-53, NUDOCS 8507190029
Download: ML20132F750 (10)

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DOCKET NO.

59-?66 UNIT NAME Point Beach Unit 1 DATE July 8, 1985 COMPLETED BY C. W.'Krause TELEPHONE 414/277-2001 AVERAGE DAILY UNIT POWER LEVEL MONTH June, 1985 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1

-2 11

-2 21 114 2

-2 12

-1 22 112 3

-2 13

-3 23 245 4

-2 14

-5 24 423 5

-2 15

-5 25 437 6

-2 16

-10 26 219

-1 17

-12 27 412 7

-2 18

-13 28 450 8

9 19 8

29 498

-2 10 20 48 30 497

-2 31 EQR-28a (01-79)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266 UNIT NAME Point Beach Unit'l' DATE July 8, 1985 REPORT MONTH June, 1985 COMPLETED BY C.

W.

Krause TELEPHONE 414/277-2001 mW C

W tD o 4

o-N oC#

Ev C

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No.

Date g

gg g

Licensee Event y

g'o Cause and Corrective Action m

e om e

um Report No.

m co To Prevent Recurrence Q-M G) to C o

E:

3:

O oo 1

850405 S

450.4 C

1 N/A ZZ ZZZZZ5 Continuation of refueling outage.

2 850620 S

10.2 B

1 N/A ZZ ZZZZZL Unit removed from service to com-plete turbine overspeed tests.

3 850626 F

7.1 A

3 85-003-00 EE INVT Unit tripped off line due to blown fuse in inverter 1DY03 and subsequent loss of instrument bus.

Blown fuse caused by failed circuit board which was replaced.

F: Forced Reason:

3 4

Method:

Exhibit G-Instruc-S: Scheduled A-Equipment Failure (explain) l-Manual tions for Prepar-B-Maintenance or Test 2-Manual Scram ation of Data Entry C-Refueling 3-Automatic Scram Sheets for LER File D-Regulatory Restriction 4-Other (explain)

(NUREG-0161)

E-Operator Training & License Exam F-Administrative 5

AD-28B Exhibit I-Same G-Operational Error (explain)

Source (01-78)

H-Other (explain)

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No.:

50-266 Unit Name:

Point Beach Unit 1 Date:

July 8, 1985 Completed By:

C. W.

Krause Telephone:

414/277-2001 During the period, the twelfth Unit 1 outage for refueling and maintenance was completed.

On June 5, 1985, the control rods at positions J4 and F12 were removed for inspection after making unsatisfactory attempts to move them with the control rod drive mechanisms.

On the following day, the two fuel assemblies were removed and inspected.

On June 7, a flexure pin was removed from guide tube F12 and a broken insert tang was removed from one of the new flexureless inserts from guide tube J4.

Both pieces resulted from the flexureless insert modification work.

To resolve these concerns, all of the new inserts were removed for inspection and testing and three of them were replaced with spares.

Also, the flexure pins that were removed were positively inventoried and all of them are accounted for.

Additionally, the top of the core and all control rod guide tubes were inspected and no findings were noted.

Due to damage noted during a visual inspection, the control rod drive shaft at core location F12 was replaced.

On June 16, filling of the reactor coolant system was completed and cold rod drop tests were satisfactorily performed.

On the following day, containment integrity was established and reactor coolant system heatup commenced.

On June 18, hot rod drop tests were completed and the reactor was taken critical at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> for the first time in 12 weeks.

The generator was placed on line on June 19 a t 1823 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.936515e-4 months <br />.

On June 20, 1985, the unit was removed from service for turbine overspeed tests.

The unit was placed back on line approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> later and was held at approximately 150 MWe net for three days because of high steam generator feedwater conductivity.

On June 23, power escalation began after the conductivity came down to within Steam Generator Owners Group Water Chemistry Guidelines.

By 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on June 24, the unit reached 88% power where it was maintained for fuel conditioning.

On June 26, at 0723 hours0.00837 days <br />0.201 hours <br />0.0012 weeks <br />2.751015e-4 months <br />, a circuit board failure caused a blown fuse in the 1DY03 inverter causing power to the white instrument bus to be lost.

The unit experienced an immediate turbine runback to 70% power due to loss of power to NIS Channel 42 and then experienced a reactor trip on low steam generator level with a coincidental steam flow / feed flow mismatch due to loss of power to the steam generator level programmer coincident with loss of power to one of the "B"

steam generator level channels.

Alternate power was supplied to the white instrument bus via backup sources and the reactor was taken critical at 1027 hours0.0119 days <br />0.285 hours <br />0.0017 weeks <br />3.907735e-4 months <br />.

The generator was placed back on line I

. at 1429 hours0.0165 days <br />0.397 hours <br />0.00236 weeks <br />5.437345e-4 months <br /> and was back at 88% power on June 27.

On June 28, the unit achieved full power operation.

The NRC was notified of the event by a red phone call and a Licensee Event Report will be issued concerning this event.

Safety-related maintenance that was performed during the period-included installation of the mod,ification for control rod withdrawal on a turbine runback, changeout of various safeguards relays, and inspection of safeguards and reactor protection instrumentation racks.

On June 21, it was determined that the spare blue hot leg RTD was connected to the protection system circuitry.

The normal RTD was reconnected.

OPERATING DATA REPORT DOCKET NO. 50-301 DATE July 8, 1985 COMPLETED BY C. W. KRAUSE TELEPHONE 414 277 2001 DEERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 2

. NOTES

2. REPORTING PERIOD:

JUNE 1985

3. LICENSED THERMAL POWER (MWT):

1518.

4. NAMEPLATE RATING (GROSS MWE):

523.8

5. DESIGN ELECTRICAL RATING (NET MWE):

497.

6. MAXIML*M DEPENDABLE CAPACITY (GROSS MUE): 509.

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

485.

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

NOT APPLICABLE

9. POWER LEVEL TO UHICH RESTRICTED, IF ANY (NET MuE): NOT APPLICABLE

10. REASONS FOR RESTRICTIONS, (IF ANY): NOT APPLICABLE THIS MONTH YR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720 4,343 113.208

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 4,343.0 100,315.4

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 207.1

14. HOURS GENERATOR ON LINE 720.0 4,343.0 98,652.4

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 198.1

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,081,247 6,536,038 138,289,010

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 368,320 2,226.920 46,867,060

18. NET ELECTRICAL ENERGY GENERATED (MWH) 351,871 2,130,116 44,641,521

19. UNIT SERVICE FACIOR 100.0 100.0 87.1

20. UNIT AVAILABILITY FACTOR 100.0 100.0 87.3

21. UNIT CAPACITY FACTOR (USING MDC NET) 100.8 101.1 80.3 i

22. UNIT CAPACITY FACTOR (USING DER NET) 98.3 98.7 79.3

23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.3 2

24. SHUIDCUNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

l Annual refueling outage scheduled to commence September 20, 1985.

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUIDOWN DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

DOCKET NO, 50-301 UNIT NAME Point Beach Unit 2 DATE July 8, 1985

~

COMPLETED BY C. W.

Krause TELEPHONE 414/277-2001 AVERAGE DAILY UNIT POWER LEVEL MONTH June. 1985 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET

~.j l

493 11, -

493 21 493 493 12 493 22 494 2

3 493 13 493 23 492 4

492 14 492 24 492 5

493 15 493 25 492 6

493 16 493 26 494 7

493 17 493 27 494 8

493 18 492 28 493 9

474 19 493 29 470 492 20 492 30 411 10 31 EQR-28a (01-79)

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m NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No.:

50-301 Unit Name:

Point Beach Unit 2 Date:

July 8, 1985 Completed By:

C. W.

Krause Telephone:

414/277-2001 Unit 2 operated at approximately 493 MWe net throughout the period.

On June 9, load was reduced to approximately 420 MWe for a turbine stop valve test.

On June 23, 24 & 25, load was reduced to 490 MWe for two hours for load follow purposes.

Load was reduced to approximately 380 MWe for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> on June 29 and for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> on June 30 for load follow purposes.

Primary-to-secondary steam generator leakage remains stable at less than 10 gallons per day.

Safety-related maintenance performed during the period in-cluded adding oil to the Unit 2 "A" reactor coolant pump to clear an alarm of the reactor coolant pump oil sump level.

No evidence of leakage was detected.

F l

4

^t

.(

1 Wisconsin Electnc eowca couranr 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 July 10, 1985 VPNPD-85-53 NRC-85-16 Director of Nuclear Regulatory Operations U. S. NUCLEAR REGULATORY COMMISSION Washington, D.

C.

20555 Gentlemen:

MONTHLY OPERATING REPORTS POINT BEACH NUCLEAR PLANT Attached are monthly operating reports for Units 1 and 2, Point Beach Nuclear Plant, for the calendar month of June 1985.

Very truly yours, Vice President-Nuclear Power C. W. Fay Attachments Copies to J.

G.

Keppler - NRC, Region III NRC Resident Inspector R. S.

Cullen - PSCW a,

.