ML19325F213

Monthly Operating Repts for Oct 1989 for Point Beach Nuclear Plant,Units 1 & 2

ML19325F213
Person / Time
Site:	Point Beach
Issue date:	10/31/1989
From:	Krause C WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML19325F211	List: ML19325F210 ML19325F213 ML19325F214
References
NUDOCS 8911170040
Download: ML19325F213 (8)

Text

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8911170040 891108'~ ~-2 PDR ADOCK 05000266 -- 3-R pgn

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OPERATING DATA REPORT DOCKET NO. 50-266 ,.

DATE November 6, 1989 4

COMPLETED BY C. W. KRAUSE TELEPHONE 414 221 2001 OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 1 . NOTES .

2. REPORTING PERIOD: OCTOBER 1989 . .

3. LICENSED THERMAL POWER (MWT): 1518 . .

4. NAMEPLATE RATING (GROSS MWE): 523.8 . .

5. DESIGN ELECTRICAL RATING (NET MWE): 497. . .

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 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:

4 NOT APPLICABLE

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE): NOT APPLICABLE

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

11. HOURS IN REPORTING PERIOD 745 7,296 166,440

12. NUMBER OF HOURS REACTOR WAS CRITICAL 745.0 6,264.3 136,879.8

13. REACTOR RESERV'. SHUTDOWN HOURS 0.0 0.0 652.7

14. HOURS GENERATOR ON LINE 745.0 6,242.8 134,075.3

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 837.9

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,092,473 8,919,601 186,262,425

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 378,030 3,025,730 62,854,780

18. NET ELECTRICAL ENERGY GENERATED (MWH) 361,125 2,887,987 59,872,455

19. UNIT SERVICE FACTOR 100.0 85.6 80.6 j 20. UNIT AVAILABILITY FACTOR 100.0 85.6 81.1

21. UNIT CAPACITY FACTOR (USING MDC NET). 99.9 81.6 73.7

, 22. UNIT CAPACITY FACIVR (USING DER NET) 97.5 79.6 72.4

23. UNIT FORCED OUTAGE RATE O.0 0.0 1.9

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

! FORTY-TWO DAY REFUELING AND MAINTENANCE OUTAGE SCHEDULE TO CO!91ENCE MARCH 30, 1990 4 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUTDOWN DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC. LETTER DATED SEPTEMBER 22, 1977

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DOCKET NO.52-266 UNIT NAME Point Beach, Unit-1

.DATE November 6, 1989 COMPLETED BY C. W. Krause ,

TELEPHONE 414/221-2001 AVERAGE DAILY UNIT POWER LEVEL MONTH OCTOBER 1989 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL ?OWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 284 11 495 21 495 2 425 12 496 22 496 3 493 13 495 23 494- __

4 494 14 498 24 495 5 494 15 473 25 496

6 493 16 494 26- 494 7 492 17 495 27 495 8 493 18 496 28 495 9 492 19 494 29 495 10 493 20 495 30 495 31 494 i -

1 EQR-28a (04-86)

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UNIT SHUTDOWNS AND POWER REDUCTIONS ~ DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE- November-6,-1989' REPORT MONTH OCTOBER 1989 COMPLETED BY C. W. Krause TELEPHONE 414/221-2001 a

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.* vi 4 o Ot o Ev C an o oc m SCO ce os No. Date $ 8$ $ MO Licensee Event $3 @'s Cause & Corrective Action Ei y- 84 yyy

E; .C Report No. gu go To Prevent Recurrence un 9 890930 S O F 5 Not applicable ZZ ZZZZZZ Load reduced to low electrical demand and to aid nuclear fuel conservation. -

1 F: Forced 2 Reason: 3 Method: 4 Exhibit F-Instructions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maintenance or Test 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG-0161)

D - Regulatory Restriction 4 - Continuation of E - Operator' Training & Previous Shutdown Licensing Exam 5 - Reduced Load sExhibit H-Same Source-F - Administrative 6 - Other (explain)

G - Operational Error (explain)

H - Other (explain)

EQR-28B (04-87)

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. NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE

, Docket No. 50-266 I

Unit Name Point Beach Unit 1 Date November 6, 1989 Completed By C. W. Krause Telephone 414/221-2001 l Unit 1 began the report period at 284 MWe. net (57%) due to low electrical system demand and an effort to conserve nuclear fuel.

The unit power generation was escalated to.494 MWe net (full power) on October 2, 1989, and was maintained at that power level for the remainder of the report period.

It was determined that the ATWS mitigating actuation circuitry (AMSAC) had an improper enabling / disabling setpoint. By design, the P-20 bistable was set at 40% turbine power based on first stage pressure. The Technical Specification change (15.3.5-3 Item 3.b) which added the channel, incorrectly based the setpoint on reactor power. The non-conservative setpoint was reset to 30%

turbine power to ensure the operation of the instrument channel at less than 40% reactor power. Licensee Event Report 89-008 was '

sent to the NRC to describe the circumstances of this event. A revision to the Technical Specifications will be submitted to the NRC to clarify the fact that turbine power greater than 40% is the power level at which AMSAC is required.

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OPERATING DATA REPORT

! DOCKET No. 50-301 -

DATE November 6, 1989 COMPLETED BY C. W. KRAUSE TELEPHONE 414 221 2001 OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 2 . NOTES .-

2. REPORTING PERIOD: OCTOBER 1989 . .

3. LICENSED THERMAL POWER (MWT): 1518 . .

4. NAMEPLATE RATING (GROSS MWE): 523.8 . .

5. DESIGN ELECTRICAL RATING (NET MWE): 497. . .

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 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 WHICH RESTRICTED, IF ANY (NET MWE): NOT APPLICABLE I 10. REASONS FOR RESTRICTIONS, (IF ANY): NOT APPLICABLE i

! THIS MONTH YR TO DATE CUMUIATIVE

11. HOURS IN PEPORTIUG PERIOD 745 7,296 151,225

12. NUMBER OF HOURS REACTOR WAS CRITICAL O.0 6,331.6 132,433.8

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.6 216.7

14. HOURS GENERATOR ON LINE O.0 6,232.7 130,329.3

15. UNIT RESERVE SHUTDOWN HOURS 0.0 4.8 302.2

16. GROSS THERMAL ENERGY GENERATED (MWH) O 9,372,690 185,318,524 l 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) O 3,216,010 62,889,710

18. NET ELECTRICAL ENERGY GENERATED (MWH) O 3,069,901 59,924,323

! 19. UNIT SERVICE FACTOR 0.0 85.4 86.2

( 20. UNIT AVAILABILITY FACTOR O.O 85.5- 86.4

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 86.8 81.0 .

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 84.7 79.7

23. UNIT FORCED OUTAGE RATE O.0 2.0 1.2

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

NONE

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DA*"E OF STARTUP: November 21, 1989 DATR REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

c DOCKET NO. 50 -- . . ,

UNIT NAME Point Beach, Utut 2 DATE November 6, 1989 COMPLETED BY 'C. W. Kranse TELEPHONE 414/221-2001 AVERAGE DAILY UNIT POWER LEVEL MONTH OCTOBER 1989 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 -2 11 0 21 -2 2 -1 12 -1 22 -2 3 _

0 13 -2 23 -2 4 0 14 -2 24 -2 5 0 15 -2 25 -2 6 0 16 -2 26 -2 7 0 17 -2 27 -2 8 _

0 18 -2 28 -1 9 0 19 -2 29 -2 10 0 20 -2 30 -1 31 -2 EQR-28a (04-86)

UNIT SHUTDOWNS ANT e M REDUCTIONS DOCKET NOo 50-301 UNIT NAME Point Beach Unit _2 DATE November 6, 1989 REPORT MONTH OCTOBER 1989 COMPLETED BY C. W. Krause-TELEPHONE 414/221-2001 c

3 o 4 c^ ce 44 Q es c om c o u e

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,e v :s m ocu ce oe No. Date $ S@

u: , ,0j$ Licensee Event $3 $*3 Cause & Corrective Action E4 gw (E y Report No. go gu To Prevent Recurrence E: .c vs 4 890923 S 745 C 1 Not Applicabl. ZZ ZZZZZZ Continue the annual refueling and maintenance outage, unit startup scheduled for November 21, 1989

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1 F: Forced 2 Reason: 3 Method:

• Exhibit F-Instructions S: Scheduled A - Equips.ent Failure (explain) 1 - Manual for preparation of B - Maintenance or Test 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG-Ol61)

D - Regulatory Restriction 4 - Continuation of E - Operator Training & Previous Shutdown Licensing Exam 5 - Reduced Load 5 Exhibit H-Same Source F - Administrative 6 - Other (explain)

G - Operational Error (explain)

H - Other (explain)

EQR-28B (04-87)

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t NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE i

< Docket No. 50-301 l Unit Name Point Beach Unit 2 Date November 6, 1989  ;

completed By C. W. Krause  !

Telephone 414/221-2001  !

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Unit 2 commenced the fifth week of its 15th refueling and 1 maintenance outage. The startup of the unit is projected to be  !

November 21, 1989.  !

On October 6, 1989, during the performance of nuclear power ,

intermediate range instrument calibrations, an inadvertent  !

reactor trip signal was generated. Subsequent investigation  !

indicated a loose cable on an instrument power supply connection  !

initiated the trip signal. Licensee Event Report 89-005 was i drkfted to describe the details of the event, j On October 13, 1989, while preparing to conduct reactor vessel inservice examinations, the reactor vessel lower internals '

engaged the internals support stand irregularly. Late the next day, Maintenance personnel freed the internals from the stano, ,

The internals were inspected and sustained no damage. l Inspections of the steam generators discovered 27 pluggable )

indications in the A generator and 6 pluggable indications in the i B generator. Two hundred ninety-eight (298) tubes were sleeved in ,

the B 9enerator as a conservative measure. In addition, 190 mechanical tube plugs in both steam generators were repaired with j the " plug in plug" method. Licensee Event Report 89-006 will be '

drafted to describe the details of the steam generater work. l

On October 27, 1989, while testing circuitry for a modification  !

which would interrupt feed flow from the condensate and heater  :

drain pumps during a steam line break accident, an inadvertant  ;

safety injection signal was generated. Licensee Event Report - 89-007 will be drafted to describe the details of the event. i Outage maintenance activities include the replacement of D06 station battery; modifications to pressurizer valve operators PORV 2-430 and 2-431C nitrogen backup supplies; modifications to ,

the accumulator level transmitters; replacement of the feedwater i flow transmitters; replacement of main feed pump P-28B; the installation of a new containment penetration; Foxboro controller module refurbishment; replacement of the residual heat removal relief valve flange; replacement of six low pressure turbine blades; the installation of anticipated transient without scram (ATWS) mitigation instrument channel; the replacement of connectors for the rod position indication detectors; the reactor I

vessel ten year examination. ,

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