ML20211E497
| ML20211E497 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/04/1986 |
| From: | Taylor J DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 86-02, 86-2, LAC-11642, NUDOCS 8606160109 | |
| Download: ML20211E497 (8) | |
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D DA/RYLA&J h [k COOPERAT/VE
- PO BOX 817 2615 EAST AV SOUTH = LA CROSSE. WISCONSIN 54601 June 4, 1986 (608) 788-t000 In reply, please refer to LAC-Il642 DOCKET No. 50-409 PP.IcaITY R0uilNG
- ,LiL1: Wat Mr. James G. Keppler, Regional Administrator U. S. Nuclear Regulatory Commission d y / ,e ,. g.fd_
h-Directorate of Regulatory Operations b F " AA Region 111 799 Roosevelt Road N-N-W -
Glen Ellyn, IL 60137 flL W
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR PROVISIONAL OPERATING LICENSE NO. DPR-45 SPECIAL REPORT 86-02
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 three separate occasions when reactor thermal power changed by more than 15% of Rated Thermal Power within one hour while in Operational Condition 1 and 2.
The separate occasions are discussed in sections 1 and 2 as follows:
SECTION 1 March 7, 1986 SECTION 2-----May 25, 1986 SECTION 3-----May 25, 1986 Each section 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.
Sincerely, 8606160109 860604 ^
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{DR ADOCK 0500 9 James W. Taylor 777 General Manager b, , {
JWT:PDB:sks Attachments Ill WPl.8.I
Mr. James G. Keppler, Regional Administrator June 4, 1986 U. S. Nuclear Regulatory Commission LAC-11642 cc: Director, Of fice of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Resident Inspector i
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INTRODUCTION SPECIAL REPORT 86-02 LACBWR 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 t-han 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 At 2150 on March 7, 1986, the reactor scrammed from 72% due to a loss of the 1B 2400 volt bus while transferring the station load to the reserve transformer. The reactor was in the process of being shutdown for refueling outage.
GROSS d-Y ACTIVITY AND IODINE ANALYSIS Time of Sample: 0027, 03/08/86 Sample Results: Gross S-y ------------ .067 pCi/ml I-131------------------1.29 x 10-3 pCi/ml I-133------------------8.34 x 10-3 pCi/ml 1-135------------------1.35 x 10-2 pCi/mi 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 thermal power change:
2150, 03/05/86 - 2150, 03/07/86 ------------ ~ 80%.
2100, 03/07/86 - 2150, 03/07/86 ------------- 80% to 72%, reactor shutdown in progress.
(2) The approximate fuel burnup of assemblies in a symmetrical core region is shown in Figure 1.
(3) Cleanup Flow llistory starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to thermal power change:
Primary Purification Flow Rate 2150, 03/05/86 - 2150, 03/07/86 ------------ 43.5 g pm.
Primary Purification Decontamination Factors (8-Y) 0049, 03/06/86 ---------------------- 1532:1 Sample not taken after power change as reactor was shutdown for refueling.
WPl.8.1
(4) Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
1600-2400 03/05/86 ---------- 157 C1/ day 0000-0800, 03/06/86 -------------- 158 C1/ day 0800-1600, 03/06/86 - - - - -- - 158 Ci/ day 1600-2400, 03/06/86 - - - - - - - - - 155 Ci/ day 0000-0800, 03/07/86 - - - - - - 160 Ci/ day 0800-1600, 03/07/86 - - ---- - 160 Ci/ day (5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:
0045, 03/06/86 ---------------- 3 . 9 3 x 10-8 pCi/ml 2150, 03/07 /86------- --------- Rated Thermal Power Change Sample not taken af ter power change as reactor was shutdown for refueling.
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SECTION 2 At 1220 en May 25, 1986, reactor power dropped from approximately 78% to approximatly 45% due to the 1A Reactor Forced Circulation Pump tripping.
1 GROSS S-Y ACTIVITY AND IODINE ANALYSIS Time of Sample: 1518, 05/25/86
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i Sample Results: Cross S-Y ----- .155 pCi/mi 1-131---------------1.11 x 10-3 pCi/ml 1-133----------1.44 x 10-2 pCi/ml 1-13 5--- -- - 3.29 x 10-2 pCi/ml 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 thermal power change:
1220, 05/23/86 - 1220, 05/25/86 -----
escalating slowly from 72%
to 78%.
(2) The approximate fuel burnup of assemblies in a symmetrical core region is shown in Figure 2.
(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 thermal power change:
Primary Purification Flow Rate 1220, 05/23/86 - 1013, 05/25/86 ------- 44 gpm.
1013, 05/25/86 - 1220, 05/25/86 ------- O g pm.
Primary Purification Decontamination Factors (6-Y) 0100, 05/23/86 ------------------- 299:1 j 0038, 05/29/86 ----------------------- 233:1 i
(4) Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
0800-1600, 05/23/86 ----------------------- 124 Ci/ day 1600-2400, 05/23/86 ----------------------- 130 Ci/ day 0000-0800, 05/24/86 ----------------------- 126 Ci/ day 0800-1600, 05/24/86 ------------------- --- 126 Ci/ day 16 00-2 4 00 , 0 5 / 2 4 / 8 6 ------------------- --- 13 0 C i / d a y 0000-0800, 05/25/86 ----------------------- 125 Ct/ day (5) Cross Alpha Activity Level Starting With Sample Prior to Thermal Power Change 0057, 05/23/86 ---------------------- 2.16 x 10-7 pCi/ml 1220, 05/25/86 ----------------------Rated Thermal Power Change 0036, 05/29/86 ---------------------- 1.86 x 10-7 pC1/ml WPl.8.1
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, SECTION 3 1
At 1950 on May 25, 1986, the reactor was manually shutdown at a rate greater than 15% per hour due to problems with the control air system.
GROSS S-Y ACTIVITY AND IODINE ANALYSIS i
4 Time of Sample: 0106, 05/26/86 I Sample Results: Gross S-Y---------- .047 pCi/ml
2.31 x 10-4 pCi/mi I-131 i 1-133---------------2.14 x 10-3 pCi/ml l I-135---------------3.03 x 10-3 pci/ml i
ADDITIONAL INFORMATION l (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 thermal power change:
1950, 05/23/86 - 1220, 05/25/86 ----------------- escalating slowly i from 72% - 78%
i 12 20 , 05 / 2 5 / 8 6 - 19 50 , 0 5 / 2 5 / 8 6 ------------------ ~ 4 5 % .
(2) The approximate fuel burnup of assemblies in a symmetrical core region is shown in Figure 2.
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 thermal power change:
Primary Purification Flow Rate 1950, 05/23/86 - 1013, 05/25/86 ------ 44 gpm.
] 1013, 05/25/86 - 1950, 05/25/86 ------ 0 g pm.
Primary Purification Decontamination Factorn (6-Y)
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0100, 05/23/86 ----------------------- 299:1 0038, 05/29/86 ----------------------- 233:1
, (4) Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
1600-2400, 05/23/86 ----------------------- 130 Ci/ day 0000-0800, 05/24/86 ----------------------- 126 Ci/ day 0800-1600, 05/24/86 ----------------------- 126 Ci/ day
! 1600-2400, 05/24/86 ----------------------- 130 Ci/ day 1 0000-0800, 05/25/86 ----------------------- 125 Ci/ day 0800-1600, 05/25/86 ----------------------- 40 Ci/ day (5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:
0057, 05/23/86 ---------------------- 2.16 x 10-7 pCi/mi 19 50, 05/25/86 ----------------------Rated The rmal Powe r Change 0036, 05/29/86 ---------------------- 1.86 x 10-7 pCi/ml WPl.8.1 1
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I NORTH FIGURE 1 Quarter Core Fuel Exposure Distribution (GWD/h!TU) as of klarch 7,1986. The Core Average Exposure is 13.146 GWD/Ffru.
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15.1 IN CORE FLUX MONITORS Q PLANT NORTH FIGURE 2 Quarter Core Fuel Exposure Distribution (GWD/MTU) as of April 25, 1986. The Core Average Exposure is 7.244 GWD/>frU.
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