ML19296B736
| ML19296B736 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/15/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| LAC-6786, RO-80-01, NUDOCS 8002210435 | |
| Download: ML19296B736 (5) | |
Text
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.s DstIItYLitND I*0 WEIT COGI*EItatTAVE Ba Crone, 01' conan h
54601 Q-L(g February 15, 1980 In reply, please refer to LAC-6786 Mr. James G.
Keppler, Regional Director U.
S. Nuclear Regulatory Coatmission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, IL 60137
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
FROVISIONAL OPERATING LICENSE NO. DP R-4 5 SPECIAL REPORT 80-01 REFERENCE :
(1)
LACBWR Technical Specifications Section 4.2.2.22, Action g.
Dear Mr. Keppler:
In accordance with the provisions of Reference (1), a Special Report is submitted covering results of sampling and analysis actions together with additional operational information for an occasion on February 1, 1980, when reactor thermal power changed by more than 15% of Rated Thermal Power within one hour while in Operational Condition 1 or 2.
This report provides a summary of operating data and radiological data for the time period prior to the thermal power change along with the results of the additional sampling required.
If there are any questions concerning this report, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE Frank Lindcr, General Manager (,Q 8002210 js
Mr. James G.
Keppler, Regional Director LAC-6786 U.
S.
Nuclear Regulatory Commission February 15, 1980 FL: LSG: abs ATTACIIMENTS CC:
Director, Of fice of Inspection and Enforcement (30)
U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555 Director, Office of Management, Information, and Program Control (3)
U.
S.
Nuclear Regulatory Commission Washington, D. C.
20555 a
SPECIAL REPORT NO. 80-01 INTRODUCTION LACBNR Technical Specifications, Section 4.2.2.22, Action g, requires sampling and analysis for Iodine-131, -133, and -135, as well as gross beta and gamma activity between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a thermal power change of greater than 15% of rated thermal power within one hour.
This special report is required to contain the information determined by the analysis plus additional information regarding reactor power history, fuel burnup, cleanup flow history, offgas activity levels, and gross alpha activity levels.
SECTION 1 A reactor scram occurred at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on February 1, 1980, due to a spurious undervoltage signal 6:cm the Turbine Building lA Motor Control Center.
The reactor was operating at 85% of rated thermal power (41 MWe) at the time of the scram.
GROSS By ACTIVITY AND IODINE ANALYSIS Time of Sample:
0453, 2/1/80 Sample Results:
Gross By--------5.93 x 10 1 pCi/gm Il31------------2.029 x 10-3 pCi/gm I l33------------4.514 x 10-3 uCi/gm I135------------< 8.167 x 10-3 pCi/gm ADDITIONAL INFORMATION (1)
Reactor Thermal Power Level starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the thermal power change:
0200, 1/30/80 - 0200, 2/1/80 85%
(2)
The appropriate fuel burnup of assemblies in a symmetrical core region is depicted in Figure 1.
(3)
Cleanup Flow History starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the thermal power change:
Primary Purification Flow Rate 0200, 1/30/80 - 0200, 2/1/80 40 GPM Primary Purification Decontamination Factors (By) 0126, 1/31/80 1360:1 0443, 2/4/80 469:1 SPECIAL REPORT NO. 80-01 (4)
C fgas Activity Levels for 48 Hours Prior to Thermal Power Change 0000-0800, 1/30/80--------------------------------292 Ci/ day 0800-1600, 1/ 3 0 / 8 0 --- -------- ------------------ -- - 2 7 9 C i/d ay 1600-2400, 1/30/80--------------------------------294 Ci/ day 0000-0800, 1/31/80------ -------------------------193 Ci/ day
- 0800-1600, 1/31/80--------------------------------195 Ci/ day 1600-2400, 1/31/80--------------------------------205 Ci/ day
- Change due to issuance of revised calculation constants after recalibration.
(5)
Gross Alpha Activity Level Starting With the Last Sample Taken Prior to the Thermal Power Change:
- 0126, 1/31/80---------------------------< 2.69 x 10-8 pCi/gm
- 0200, 2/1/80----------------------------Reactor Scram 0443, 2/ 4 / 8 0 -- --- - -- - -- --- - --- -- --- --- -- - < 2.65 x 10-8 pCi/gm 2-
SPECIAL REPORT NO. 80-01 QUARTER CORE FUEL EXPOSURE ESTIMATION (GWD/MTU).
AN INDICATION OF REGIONAL EXPOSURE AS OF FEBRUARY 1, 1980.
TIIE AVERAGE EXPOSURE:
7.922 GWD/MTU A
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