ML20236Y215
| ML20236Y215 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/15/1987 |
| From: | Taylor J DAIRYLAND POWER COOPERATIVE |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 87-02, 87-2, LAC-12215, NUDOCS 8712110180 | |
| Download: ML20236Y215 (7) | |
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M 9 DA/RYLAND hh[M[ COOPERATIVE.. P O BOX 817 2615 EAST AVE $O . LA CROS I608) 788-4000 JAMES W. TAYLOR General Manager FNIORITY R0'JiIt:0 May 15, 1987 kd----SM In reply, please PRWJ,$~ ?C ~
, ;; j refer to LAC-12215 g7dqhgf DOCKET NO. 50-409 '-
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Mr. A. Bert Davis, Regional Administrator U. S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, IL 60137
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL' OPERATING LICENSE NO. DPR-45 SPECIAL REPORT 87-02
Reference:
(1) LACBWR Technical Specifications Sections 4.2.2.22, Action g.
Dear Mr. Davis:
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 two 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.
i The separate occasions are discussed in sections 1 and 2 as follows: l SECTION 1- -----February 16, 1987 SECTION 2-------April 6, 1987 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.
8712110180 870515 PDR ADDCK 05000409 s PDR Kb PCI-19 M 35gp.
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Mr. A. Bert Davis Page 2 May 15, 1987 LAC-12215 If there are any questions concerning this report, please contact us.
Sincerely, DAIRYLAND POWER COOPERATIVE M
James W. Taylor General Manager JWT:PDB:sks Attachments cc: NRC Fesident Inspector T. Bournia, LACBWR Project Manager Director, Office of Inspection and Enforcement f' U. S. Nuclear Regulatory Commission Washington, DC 20555 i
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. e W k c SPECIAI,! REPORT 87-02 INTRODUCTION LACBWR Technical 5;ocifications, Section 4.2.2.22, Action g, requires sampling and analysis ftr Icdine-131, -133 and -135, as well as gross beta and / I 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 informattra determined by the analysis plus additional information regarding reactor power history, fuel burnup, cleanup flow history, offgas'." '/ (c.
activity levels and gross alpha activity levels.l 7 )
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SECTION 1 At 1702 on February 16, 1987, the reactor was manually scrammed from f8%
power. The reactor was scramned because of an erroneous indication of low voltage on Turbine Building MCC1A. <
GROSS 6-y ACTIVT.TY AND IODINE ANALYSIS ,
i Time of Sample: 1944, 02/10/87 g i
Sample Results: Gross E y ------------------ .110 xCi/ml 10 pCg/ml I-131------------ 7--------"--7.42 I-133------------- -----------6.94 x 10'3 pCi/ml I-135-------------------------1.05 x 10-2 pCi/ml
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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:
1702, 02/14/87 - 1702, 02/16/87 ------------- ------- ~ 98%.,
(2) The approximate fuel burnup of assemblies i in a symmetrical core , ; region is shown in Figure 1. 1 i
'(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: i Primary Purification Flow Rate '
i 1702, 02/14/87 - 1702, 02/16/87 -------------42 gpm Pruficiation Decontamin9ti$7 ,[ actor (6-y)
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0054, 02/16/87 -----------L----- 622:1 0058, 02/19/87 --------- - --- 2362i b
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(4) Offgas Activity Levels Starting 48 Hours Prior to f fneraal Power Change .(
0800-1600, 02/14/87 ------- --------- 222 Ci/ day 1600-2400, 02/14/87 ---------------- 224 Ci/ day 0000-0800, 02/15/87 ---------------- 215 Ci/ day '
0800-1600, 02/15/87 -------- + ---- 226'Ci/ day 1600-2400, 02/15/87 ------------ J-- 215 Ci/ day 0000-0800, 02/16/87 ---------------- 21P C1/ day PCI-19 o \
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g (5) , Gross Alpha Activity Level Startindith Sample Prior to Thermal Power
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i 0052, 02/16/87 -------------------r..< 5.46 x 10-8 Ci/ml
, 1702, 02/16/ 87 l - --------------- - ', an66 i Therma'.lf .?ower Change 0056, b2 /19 / 87 ' ,- ' --------------- * ' '. 09 x ,10 - 7 pC1/ml i';
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SECTION 2
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At; U l* ca April 6,1987, reactor pwer dropped from 98% to 681' following a -
trip of's the le Forced Circula71on Pump. . Reactor power was then further reduced to
~ 1B% by inse?: ton of control ro6d - i i
l GROSS s-y ACTIVIIT AND TODISF. ANALYSIS Tim? of Sample: 1822, 04/06/87 c' Sample Results: G r osa 8 - y - - - - - - - - - - - - -- - - - - - - .115 C1/ml I-1% ------------------------ G.65 x 10-" pCi/ml I ;:1------------------- ----?.23 x 10-8 pGi/mi I - 1 %- - - - - - - - - - - - - -- - - - - -- - - - - 1. 5 4 x 10 - 2 ';tpi/ml ADDITIONAL INFORMATION (11 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:
1A15, 04/04/87 - 1415, 04/06/81 -- --------------- ~ 99%.
.' (2) The approximate fuel burnap of assemblies in a symmetrical core region is shown in Figure 2.
. (3) CIeenup 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 tharmal power change:
,f;tlimary__ Purification Plow Rate 1415, 04/04/87 - 1415, 04/06/87 ------------- 42 gpm PrL:tary 3trification D9 contamination Factors (E-y) 0056, C h / 06 / 87 ----------------------- 763 : 1 G)S6, 04/09/87 --------------------- -2562:1 (4) Off gts Activity Levels Starting 48 Hours Prior to Thetml Power Channn I
0800-1600i 04/04/87 ---------------- 139 Ci/ day 1600-2400, 04/0A/S7 ---------------- 145 Ci/ day 0000-0800, 04/05/87 ---------------- 140 Ci/ day 0800-1600, 04/05/37 ---------------- 136 Ci/ day 1600-2400, 04/05/87 ---------------- 148 Ci/ day 0000-0800, 04/06/87 ---------------- 142 Ci/ day (5) Cross AQ13 a Activity Level, Starting With Sample Prior to Thermal Power Change:
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'- 0054, 04/06/87 ---------- ---------- < 5.5a x 10-8 pCi/ml 1 19 5, 04 / 06 / 87 --------------------- Rated Thermal Power Change 0054, 04/09/87 --------------------- 1.80 x 10-7 pC1/ml I t !
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,, IN CORE FLUX MONITORS Q PLAhlT Figure 1 Quarter Core Fuel Exposure Distribution (GWD/MTU) as of February 16, 1987. The Core Average Exposure is 10.385 (GWD/MTU).
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- 7.0 y IN CORE FLUX MONITORS Q PLANT Figure 2 Quarter Core Fuel Exposure Distribution (GWD/MTU)
N@TH as of April 6, 1987. The Core Average Exposure is 11.031 (GWD/MTU).