ML20138L843
| ML20138L843 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 10/21/1985 |
| From: | Taylor J DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 85-02, 85-2, LAC-11197, NUDOCS 8510310423 | |
| Download: ML20138L843 (8) | |
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[k COOPERAT/VE eO BOxsi7 2sts EAST AV SOUTH = LA CROSSE WISCONSIN 54601 October 21, 1985 (608) 788 4 000 In reply, please refer to LAC-lll97 DOCKET No. 50-409 Mr. James G. Keppler, Regional Administrator U. S. Nuclear Regulatory Commission PMMITY @Sll@.
Directorate of Regulatory Operations
{E hy Region III Eo Q.. ' %
799 Roosevelt Road 4{
-QL-Glen Ellyn, IL 60137 pF7 t% l it 7
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SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR PROVISIONAL OPERATING LICENSE NO. DPR-45 SPECIAL REPORT 85-02
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 reacto.
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, 2 and 3 as follows:
SECTION 1 July 25, 1985 SECTION 2-
-September 9, 1985 SECTION 3--
-September 14, 1985 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 samplitg required.
If there are any questions concerning this report, please contact us.
Sincerely, 8510310423 851021 DAIRYLAND POWER COOPERATIVE PPR ADOCK 05000409 g
PDR James W. Taylor General Manager JWT:PDB:sks Attachments 4
407251985 N'
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Mr. James G. Keppler, Regional Administrator October 21, 1985 U. S. Nuclear Regulatory Commission LAC-lll97 cc: Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 Document Control Desk i
U. S. Nuclear Regulatory Commission l
Wachington, DC 20555 Resident Inspector l
l WPl.8.1 i
INTRODUCTION SPECIAL REPORT 85-03 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 ga ama 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 greatet 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 At 1115 on July 25, 1985, the reactor scrammed from 96.5% power due to a ground in the gas pressure scram circuit on the Control Rod Drive No. 8.
GROSS 4-y ACTIVITY AND IODINE ANALYSIS Time of Sample: 1322, 07/25/85 Sample Results: Gross a-Y
-.0791 pCi/ml I-131
-1.04 x 10-3 pCi/ml I-133-
-2.69 x 10-3 pCi/ml 1-135
1.09 x 10-3 pCi/ml ADDITIONAL INF0DiATION (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:
1115, 07/23/85 - 1115, 07/25/85--
~ 96%.
(2) The approximate fuel burnup of assemblies in a symmetrical core region is shown 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 thermal power change:
Primary Purification Flow Rate 1115, 07/23/85 - 1115, 07/25/85
--42 gpm.
Primary Purification Decontamination Factors (d-Y) 0152, 07/25/85
-- 1126:1 737:1 0205, 07/29/85 1
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i (4) Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
-- 152 Ci/ day 0800-1600 07/23/85 ----
1600-2400, 07/23/85
- 148 Ci/ day 0000-0800, 07/24/85 --- --
- 157 Ci/ day J
- 146 Ci/ day J
0800-1600, 07/24/85 ------==
=--
1600-2400, 07/24/85
146 Ci/ day
--- 146 Ci/ day 0000-0800, 07/25/85 (5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:
0154, 07/25/85 ------
< 4.86 x 10-8 pCi/ml Rated Thermal Power Change 1115, 07/25/85 1.09 x 10-7 pCi/ml 0205, 07/29/85 -
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SECTION 2
At 0210 on September 9, 1985 the 1A FCP Discharge Valve closed due to an erroneous Forced Circulation Loop A Temperature signal. The reactor power dropped from 96% to 68%.
GROSS o-y ACTIVITY AND IODINE ANALYSIS Time of Sample: 0557, 09/09/85 Sample Results: Gross s-y
.204 LCi/ml 1-131
---9.20 x 10-4 uCi/ml 1-133-
--1.15 x 10-2 pCi/ml
- 2.47 x 10-2 pCi/ml I-135----
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:
0210, 09/07/85 - 0210, 09/09/85
~ 96%.
(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 0210, 09/07/85 - 0210, 09/09/85
-- 42 gpm.
Primary Purification Decontamination Factors (8-Y) 0207, 09/09/85 828:1 0118, 09/12/85
-- 740:1 (4) Of fgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
147 Ci/ day 0000-0800, 09/07/85
--- 149 Ci/ day 0800-1600, 09/07/85
145 Ci/ day 1600-2400, 09/07/85 145 Ci/ day 0000-0800, 09/08/85 -----
0800-1600, 09/08/85 145 C1/ day 1600-2400, 09/08/85
150 Ci/ day (5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:
0208, 09/09/85
< 4.66 x 10-8 pCi/ml 0210, 09/09/85
---Rated Thermal Power Change 1.29 x 10-7 pCi/ml 0122, 09/12/85 WP1.8.1
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T SECTION 3
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At 1555 on September 14, 1985 the reactor scrammed from 96% power due to High l
Reactor Water Level when power was lost to an Irstrument Bus in the Control Room.
GROSS J-Y ACTIVITY AND IODINE ANALYSIS Time of Sample: 1850, 09/14/85
.116 pCi/ml Sample Results: Gross d-Y I-131
1.14 x 10-3 pCi/ml
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I-133
9..c 3 x 10-3 pCi/ml I-135
-1.21 x 10-2 pCi/ml ADDITIONAL INFORMATION (1) Reacter 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:
l 1555, 09/07/85 - 1555, 09/09/85
~ 96%.
(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 1555, 09/07/85 - 1555, 09/09/85 42 spm.
Primary Purification Decontamination Factors (d-Y) 0118, 09/12/85 ------
740:1 0111, 09/16/85 - -
=--- -
689:1 (4) Offras Activity Levels Starting 48 Hours Prior to Thermal Power Change:
0800-1600, 09/12/85
-- 144 Ci/ day 1600-2400, 09/12/85 --
145 Ci/ day 0000-0800, 09/13/85 ----
148 Ci/ day 0800-1600, 09/13/85
-- 137 Ci/ day 1600-2400, 09/13/85
- 149 Ci/ day 0000-0800, 09/14/85
- 149 Ci/ day 1
(5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Chan e:
o 0122, 09/12/85
1.29 x 10-7 pCi/ml 1555, 09/14/85
-Rated Thermal Power Change 0114, 09/16/85
- 1.00 x 10-7 pCi/ml WP1.8.1
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PLANT yQQ[g Quarter Core Fuel Exposure Distribution (GWD/MTU) as of September 9, 1985. The Core Average Exposure is 9.921 GWD/MTU.
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