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=Text=
=Text=
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NARRATIVE
 
==SUMMARY==
OF OPERATING EXPERIENCE May 1986 At the onset of the May reporting period, the plant was in the refueling outage which commenced March 7, 1986. At 1841 on May 6, the reactor was taken critical and startup testing commenced. At 2015 on May 6, the reactor was manually shutdown due to a malfunction on the lower control rod drive mechanism in position No. 3.
At 1822 on May 7, the reactor was taken critical. At 0028 on May 8 the reactor scrammed from low power due to a spike on Nuclear Instrumentation (NI)
Channel No. 5. The instrument drawer was replaced. The reactor was taken critical at 0652 on May 8. At 0843 on May 9, the reactor scrammed from low power due to a spike on NI Channel No. 5.                  The spiking was determined to be due to the positive high voltage power supply. The power supply was replaced.
At 1520 on May 9, the reactor was again taken critical.
At 0231 on May 10, the reactor was manually shutdown from low power due to a lagging fire in the IB Forced Circulation Pump cubicle. The fire was extinguished within 9 minutes. At 2001 on May 10, the reactor was taken t      critical.
At 0702 on May 13, the reactor scrammed from low power due to failure of the 1A Static Inverter. A circuit board in the inverter was replaced. The reactor was taken critical at 1345 on May 14.
At 1202 on May 15, the reactor was manually shutdown from low power due to water leakage from the upper flange of Upper Control Rod Drive Mechanism No.
: 2. Flange bolts were tightened and the leakage stopped. The reactor was taken critical at 1512 on May 15. The turbine-generator was connected to the DPC grid at 0607 on May 16, thus ending the 1986 refueling outage.
At approximately 1220 on May 25, the 1A Forced Circulation Pump (FCP) tripped due to loss of seal inject flow. Reactor power decreased from 78% to 47%.
The seal inject supply valve to the 1A FCP closed due to water in its controller regulator and E/P converter. The reactor was manually shutdown at j      2045 on May 25, to drain water from the control air system, mainly from valve l      regulators associated with the seal inject system.
I l      At 0020 on May 27, the reactor was taken critical and at 1533, the turbine-generator was synchronized to the DPC grid. A slow power escalation was conducted, with approximately 83% being reached by the end of the May reporting period.
In addition to the work discussed above, major safety-related maintenance performed during the month of May included capping an unused reactor vessel water level probe connection which leaked during hydrostatic tests, installation of lower control rod drive mechanisms, and replacement of the personnel airlock inner door upper shaft seal. The following Type B and C leakage tests were conducted during May. All tests passed.
8608180103 ADOCK h o PDR409                                                                      IEN PDR                                                                                                  l(i l    R
                    -    -    . . - . . . -      - - . . , - . . ,-  - - ~ - . _ - - -- ----- .-. .-- -,          - - -
 
Test                              Leakage (SCFH)
Personnel Airlock (post-maintenance tests)      15.03 7.89 6.76 0
Retention Tank Pump Discharge Valve              0.72
 
4 OPERATING DATA REPORT DOCKET No. 50-409 DATE          06/06/86 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:
      ~1. Unit Name: La Crosse-Boiling Water Reactor
: 2. Reporting Period: 0000, 05/01/86 to 2400, 05/31/86
: 3. Licensed Thermal Power (MWt ): ~ 165
: 4. Nameplate Rating (Gross MWe ):                                                  65.3
: 5. Design Electrical Rating (Net MW e):                                                    50
: 6. Maximum Dependable capacity (Gross MWe ): 50
: 7. Maximum Dependable Capacity (Net MWe ):                                                              48
: 8. If Changes Occur in Capacity Ratings (Items 3 Through 7) Since Last Report, Give Reasons:
: 9. Power Level To Which Restricted, If Any (Net MW e):
: 10. Reasons for Restrictions, If Any:
l l
l                                                                                                                This Month                              Yr.-to-Date                          Cumulative
: 11. Hours In Reporting Period                                                                                    744                                      3,623                            145,346 l    12. Number Of Hours Reactor Was Critical                                                                        491.2                                    1,832.0                            97,912.9 i    13. Reactor Reserve Shutdown Hours                                                                                0                                          0                                478 14.. Hours Generator On-Line                                                                                    335.1                                    1,625.0                            91,125.9 i
: 15. Unit Reserve Shutdown Hours                                                                                    0                                          0                                79 l    16. Gross Thermal Energy Generated (MWH)                                                                    37,590.7                                  213,816.2                      12,672,778 8
: 17. Gross Electrical Energy Generated (MWH)                                                                  11,195                                    66,021                          3,805,230 l
: 18.        Net Electrical Energy Generated (MWH)                                                              9,913                                    60,252                          3,528,997
: 19.      Unit Service Factor                                                                                    45.0                                      44.2                                62.7 I
: 20.      Unit Availability Factor                                                                                45.0                                      44.9                                62.8
: 21.      Unit Capacity Factor (Using MDC Net)                                                                    27.8                                      34.7                                50.6
: 22.      Unit Capacity Factor (Using DER Net)                                                                    26.7                                      33.3                                48.6
: 23. Unit Forced Outage Rate                                                                                      11.3                                      17.1                                9.8
: 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
None l
: 25. If Shut Down At End Of Report Period, Estimated Date of Startup:                                                                                                                    NA
: 26. Units In Test Status (Prior to Commercial Operation):                                                                                                Forecast                        Achieved i                                                                                          INITIAL CRITICALITY l                                                                                          INITIAL ELECTRICITY COMMERCIAL OPERATION i
WP-6.8 i
        . , _ . - . _ _ . . . _ . , - - _ , , ~ , - ,      ,.____,...-.,____-,,_m, ,                ,,....._m        -_                  __._..m._,_            _m_.,...__.,,_,-,.___,,m.                  . _ _ .
 
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.        50-409 UNIT LACBWR DATE 06/06/86 COMPLETED BY            L.S. Goodman TELEPHONE 608-689-2331 MONTH      May 1986 DAY      AVERAGE DAILY POWER LEVEL                                              DAY        AVERAGE DAILY POWER LEVEL (MWe-Net)                                                                                (MWe-Net) 1                  0                                                          17                            26 2                  0                                                          18                            31 3                  0                                                          19                            34 4                  0                                                          20                            33 5                  0                                                          21                            33 6                  0                                                          22                            33 i
7                  0                                                          23                            34 8                  0                                                          24                            36 9                  0                                                          25                            26 10                  0                                                          26                              0 11                  0                                                          27                              4 l
12                  0                                                          28                            26 r
13                  0                                                          29                            35 14                  0                                                          30                              38 15                  0                                                          31                              39 16                  8 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
WP-6.8
 
UNIT SHUTDOWNS AND POWER REDUCTIONS                                                ,
DOCKET NO. 50-409 UNIT NAME LACBWR DATE 06/06/86 REPORT MONTH    MAY 1986                        COMPLETED BY    L.S. Goodman TELEPHONE 608-689-2331 Method of  Licensee                              Cause & Corrective Duration                              Shutting Down  Event      System    Component          Action to No . Date              Type l            (Hours)                  Reason 2      Reactor 3  Report #    Code 4      Code 5        Prevent Recurrence 86-04          03-07-86          S                366.1                      C              3        86-06      EB        CKTBRK  Refer to March 1986 report for the discussion of the scram which occurred during the shutdown for this re-fueling outage. The refueling outage continued during the month of April.
86-05          05-25-86          F                  0                          A              4        NA        CB        PUMPXX  Power was decreased from 78%
to I.7% when the 1A Forced Circulation Pump tripped due to loss of seal inject flow.
The seal inject supply valve closed due to water in its controller regulator and E/P converter.
86-06          05-25-86          F                  42.8                      A              1        NA        PA        INSTRU  The reactor was shutdown in order to drain water from the control air system, s pecifi-cally from the regulators associated with seal inject system valves.        -
1                                  2                                                                                3                          4 Reason:                                                                        Method:                    Exhibit G-Instructionse F: Forced                          A-Equipment Failure (Explain)                                                  1-Manual                  for Preparation of Data S: Scheduled                      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 & License Examination F-Administrative                                                                                        5 G-Operational Error (Explain)                                                                              Exhibit 1 - Same Source H-Other (Explain)
 
0                                                                                                                ,
l 17    stLf        )%f S        [M      COOPERAT/VE
* P.O BOX 817    2615 EAST AV SOUTH
* LA CROSSE. WISCONSIN S4601 June 6, 1986                      (608) 788 4 000 In reply, please refer to LAC-11654 DOCKET NO. 50-409 Of fice of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555
 
==SUBJECT:==
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 MONTHLY OPERATING DATA REPORT FOR MAY 1986
 
==Reference:==
(1) NRC Letter, Reid to Madgett, dated September 19, 1977.
(2) NRC Letter, Reid to Madgett, dated December 29, 1977 Gentlemen:
In accordance with instructions contained in Reference (1) and Technical Specification Amendments contained in Reference (2), we are submitting information concerning operability and availability of the La Crosse Boiling Water Reactor (LACBWR) for the Month of May 1986.
Please contact us if there are any questions concerning this report.
Very truly yours, DAIRYLAND POWER COOPERATIVE James W. Taylor, General Manager JWT:LSG:sks cc:  J. G. Keppler, Regional Administrator, NRC-DRO III John Stang, LACBWR Project Manager NRC Resident Inspector D. Sherman ( ANI Library)
INPO 7
(h'%      ii
                                                                    - -        _.            --      .}}

Latest revision as of 01:17, 30 December 2020

Monthly Operating Rept for May 1986
ML20205D602
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 05/31/1986
From: Goodman L, Malin L, Taylor J
DAIRYLAND POWER COOPERATIVE
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-11654, NUDOCS 8608180103
Download: ML20205D602 (6)
v • d • e


Text

_ - _

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE May 1986 At the onset of the May reporting period, the plant was in the refueling outage which commenced March 7, 1986. At 1841 on May 6, the reactor was taken critical and startup testing commenced. At 2015 on May 6, the reactor was manually shutdown due to a malfunction on the lower control rod drive mechanism in position No. 3.

At 1822 on May 7, the reactor was taken critical. At 0028 on May 8 the reactor scrammed from low power due to a spike on Nuclear Instrumentation (NI)

Channel No. 5. The instrument drawer was replaced. The reactor was taken critical at 0652 on May 8. At 0843 on May 9, the reactor scrammed from low power due to a spike on NI Channel No. 5. The spiking was determined to be due to the positive high voltage power supply. The power supply was replaced.

At 1520 on May 9, the reactor was again taken critical.

At 0231 on May 10, the reactor was manually shutdown from low power due to a lagging fire in the IB Forced Circulation Pump cubicle. The fire was extinguished within 9 minutes. At 2001 on May 10, the reactor was taken t critical.

At 0702 on May 13, the reactor scrammed from low power due to failure of the 1A Static Inverter. A circuit board in the inverter was replaced. The reactor was taken critical at 1345 on May 14.

At 1202 on May 15, the reactor was manually shutdown from low power due to water leakage from the upper flange of Upper Control Rod Drive Mechanism No.

2. Flange bolts were tightened and the leakage stopped. The reactor was taken critical at 1512 on May 15. The turbine-generator was connected to the DPC grid at 0607 on May 16, thus ending the 1986 refueling outage.

At approximately 1220 on May 25, the 1A Forced Circulation Pump (FCP) tripped due to loss of seal inject flow. Reactor power decreased from 78% to 47%.

The seal inject supply valve to the 1A FCP closed due to water in its controller regulator and E/P converter. The reactor was manually shutdown at j 2045 on May 25, to drain water from the control air system, mainly from valve l regulators associated with the seal inject system.

I l At 0020 on May 27, the reactor was taken critical and at 1533, the turbine-generator was synchronized to the DPC grid. A slow power escalation was conducted, with approximately 83% being reached by the end of the May reporting period.

In addition to the work discussed above, major safety-related maintenance performed during the month of May included capping an unused reactor vessel water level probe connection which leaked during hydrostatic tests, installation of lower control rod drive mechanisms, and replacement of the personnel airlock inner door upper shaft seal. The following Type B and C leakage tests were conducted during May. All tests passed.

8608180103 ADOCK h o PDR409 IEN PDR l(i l R

- - . . - . . . - - - . . , - . . ,- - - ~ - . _ - - -- ----- .-. .-- -, - - -

Test Leakage (SCFH)

Personnel Airlock (post-maintenance tests) 15.03 7.89 6.76 0

Retention Tank Pump Discharge Valve 0.72

4 OPERATING DATA REPORT DOCKET No. 50-409 DATE 06/06/86 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:

~1. Unit Name: La Crosse-Boiling Water Reactor

2. Reporting Period: 0000, 05/01/86 to 2400, 05/31/86
3. Licensed Thermal Power (MWt ): ~ 165
4. Nameplate Rating (Gross MWe ): 65.3
5. Design Electrical Rating (Net MW e): 50
6. Maximum Dependable capacity (Gross MWe ): 50
7. Maximum Dependable Capacity (Net MWe ): 48
8. If Changes Occur in Capacity Ratings (Items 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MW e):
10. Reasons for Restrictions, If Any:

l l

l This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744 3,623 145,346 l 12. Number Of Hours Reactor Was Critical 491.2 1,832.0 97,912.9 i 13. Reactor Reserve Shutdown Hours 0 0 478 14.. Hours Generator On-Line 335.1 1,625.0 91,125.9 i
15. Unit Reserve Shutdown Hours 0 0 79 l 16. Gross Thermal Energy Generated (MWH) 37,590.7 213,816.2 12,672,778 8
17. Gross Electrical Energy Generated (MWH) 11,195 66,021 3,805,230 l
18. Net Electrical Energy Generated (MWH) 9,913 60,252 3,528,997
19. Unit Service Factor 45.0 44.2 62.7 I
20. Unit Availability Factor 45.0 44.9 62.8
21. Unit Capacity Factor (Using MDC Net) 27.8 34.7 50.6
22. Unit Capacity Factor (Using DER Net) 26.7 33.3 48.6
23. Unit Forced Outage Rate 11.3 17.1 9.8
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None l

25. If Shut Down At End Of Report Period, Estimated Date of Startup: NA
26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved i INITIAL CRITICALITY l INITIAL ELECTRICITY COMMERCIAL OPERATION i

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. , _ . - . _ _ . . . _ . , - - _ , , ~ , - , ,.____,...-.,____-,,_m, , ,,....._m -_ __._..m._,_ _m_.,...__.,,_,-,.___,,m. . _ _ .

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 UNIT LACBWR DATE 06/06/86 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 MONTH May 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 26 2 0 18 31 3 0 19 34 4 0 20 33 5 0 21 33 6 0 22 33 i

7 0 23 34 8 0 24 36 9 0 25 26 10 0 26 0 11 0 27 4 l

12 0 28 26 r

13 0 29 35 14 0 30 38 15 0 31 39 16 8 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

WP-6.8

UNIT SHUTDOWNS AND POWER REDUCTIONS ,

DOCKET NO. 50-409 UNIT NAME LACBWR DATE 06/06/86 REPORT MONTH MAY 1986 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 Method of Licensee Cause & Corrective Duration Shutting Down Event System Component Action to No . Date Type l (Hours) Reason 2 Reactor 3 Report # Code 4 Code 5 Prevent Recurrence 86-04 03-07-86 S 366.1 C 3 86-06 EB CKTBRK Refer to March 1986 report for the discussion of the scram which occurred during the shutdown for this re-fueling outage. The refueling outage continued during the month of April.

86-05 05-25-86 F 0 A 4 NA CB PUMPXX Power was decreased from 78%

to I.7% when the 1A Forced Circulation Pump tripped due to loss of seal inject flow.

The seal inject supply valve closed due to water in its controller regulator and E/P converter.

86-06 05-25-86 F 42.8 A 1 NA PA INSTRU The reactor was shutdown in order to drain water from the control air system, s pecifi-cally from the regulators associated with seal inject system valves. -

1 2 3 4 Reason: Method: Exhibit G-Instructionse F: Forced A-Equipment Failure (Explain) 1-Manual for Preparation of Data S: Scheduled 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 & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain)

0 ,

l 17 stLf )%f S [M COOPERAT/VE

  • P.O BOX 817 2615 EAST AV SOUTH
  • LA CROSSE. WISCONSIN S4601 June 6, 1986 (608) 788 4 000 In reply, please refer to LAC-11654 DOCKET NO. 50-409 Of fice of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 MONTHLY OPERATING DATA REPORT FOR MAY 1986

Reference:

(1) NRC Letter, Reid to Madgett, dated September 19, 1977.

(2) NRC Letter, Reid to Madgett, dated December 29, 1977 Gentlemen:

In accordance with instructions contained in Reference (1) and Technical Specification Amendments contained in Reference (2), we are submitting information concerning operability and availability of the La Crosse Boiling Water Reactor (LACBWR) for the Month of May 1986.

Please contact us if there are any questions concerning this report.

Very truly yours, DAIRYLAND POWER COOPERATIVE James W. Taylor, General Manager JWT:LSG:sks cc: J. G. Keppler, Regional Administrator, NRC-DRO III John Stang, LACBWR Project Manager NRC Resident Inspector D. Sherman ( ANI Library)

INPO 7

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