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Special Rept 85-01:providing Results of Sampling & Analysis Actions & Addl Operational Info for Six Occasions When Reactor Thermal Power Changed by More than 15% of Rated Thermal Power within 1 H
	ML20128N914
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	07/18/1985
From:	Taylor J; DAIRYLAND POWER COOPERATIVE
To:	James Keppler; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
	85-01, 85-1, LAC-11015, NUDOCS 8507260296
	Download: ML20128N914 (12)
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\ D DA/RYLAND h [k COOPERAT/VE

PO. BOX 817 2615 EAST AV SOUTH July 18, 1985

LA CROSSE WISCONSIN S4601 (608) 788 4 000 In reply, please refer to LAC-11015 DOCKET No. 50-409 Mr. James G. Keppler, Regional Administrator ppIORITY ROUTING ,

U. S. Nuclear Regulatory Commission Directorate of Regulatory Operations g_c V f "-",e C 31 Region III p k . ', f -

799 Roosevelt Road h & -

v Glen Ellyn, IL 60137 di g1nj-Z pem _a

SUBJECT:

DAIRYLAND POWER COOPERATIVE fit.EM LA CROSSE BOILING WATER REACTOR PROVISIONAL OPERATING LICENSE NO. DPR-45 SPECIAL REPORT 85-01

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 six 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, 2 and 3 as follows:

SECTION 1- April 20, 1985 SECTION 2 April 27, 1985 SECTION 3 May 17, 1985 SECTION 4-----July 10, 1985 SECTION 5 July 11, 1985 SECTION 6 July 11, 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 sampling required.

If there are any questions concerning this report, please contact us.

Sincerely, DAIRYLAND POWER COOPERATIVE 8507260296 850718 9 DR ADOCK 05 g ggy jg-James W. Taylor' General Manager FL:PDB:sks Attachments [ gg ZPO I

. o Mr. James G. Keppler, Regional Administrator July 18, 1985 U. S. Nuclear Regulatory Commission LAC-11015 cc: Director, Office 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 WPl.8.1 _ . _ . . . . . . . . . . ~ i

INTRODUCTION SPECIAL REPORT 85-01 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 At 2052 on April 20, 1985, the reactor scrammed due to failure of a scram solenoid.

GROSS S-Y ACTIVITY AND IODINE ANALYSIS Time of Sample: 0020, 04/21/85 Sample Results: Gross S-Y ------------ .0728 pCi/mi I-131------------------5.38 x 10-4 pCi/mi I-133------------------6.36 x 10-3 pCi/mi 1-135------------------8.41 x 10-3 pCi/ml ADDITIONAL INFORMATION (1) Reactor Thermal Power Level starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change:

2052, 04/18/85 - 2052, 04/20/85-------------esacalating slowly from 61%

to 70%.

(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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change:

Primary Purification Flow Rate 2052, 04/18/85 - 2052, 04/20/85 ------------41 spm.

Primary Purification Decontamination Factors ( S-Y)

Decon factors prior to the scram not available since this was the initial start-up following refueling.

0036, 04/25/85 ----------------------882:1 WP1.8.1 r . .. . .. .. .

(4) Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:

1600-2400, 04/18/85 ---- 141 Ci/ day 0000-0800, 04/19/85 ------- - - =

114 Ci/ day 0800-1600, 04/19/85 ---------------------- 148 Ci/ day 1600-2400, 04/19/85 --

--- 156 Ci/ day 0000-0800, 04/20/85 ----------

176 Ci/ day 0800-1600, 04/20/85 ---------------------- 183 Ci/ day (5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:

0252, 03/07/85 ------------------ ----7.48 x 10-8 pCi/ml 2052, 04/20/85 ----- -

Rated Thermal Power Change 0032, 04/25/85 ----- -------------7.83 x 10-8 pCi/ml i

WPl.6.1 m

j

SECTION 2 At 0721 on April 27, 1985, the reactor scrammed due to Low Reactor Water Level while transfering from IB to 1A Reactor Feed Pump.

CROSS S-Y ACTIVITY AND IODINE ANALYSIS Time of Sample: 1240, 04/27/85 Sample Results: Cross S-Y---------- .0618 pCi/mi 1-131---------------7.03 x 10-4 pCi/mi 1-133---------------5.88 x 10-3 pCi/ml I-135---------------6.77 x 10-3 pCi/mi ADDITIONAL INFORMATION (1) Reactor Thermal Power Level starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change:

0721, 04/25/85 - 0721, 04/27/85 -------------escalating slowly from 76%

to 82%

(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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change:

Primary Purification Flow Rate 0721, 04/25/85 - 0721, 04/27/85 ------- 41 gpm.

Primary Purification Decontamination Factors (S-Y) 0036, 04/25/85 ----------------------- 882:1 0044, 04/29/85 ----------------------- 1157:1 (4) Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:

0000-0800, 04/25/85 ----------------------- 123 Ci/ day 0800-1600, 04/25/85 ----------------------- 124 Ci/ day 1600-2400, 04/25/85 ----------------------- 125 Ci/ day 0000-0800, 04/26/85 ----------------------- 128 Ci/ day 0800-1600, 04/26/85 ----------------------- 140 Ci/ day 1600-2400, 04/26/85 ----------------------- 140 Ci/ day (5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change 0032, 04/25/85 ---------------------- 7.83 x 10-8 pCi/mi 0721, 04/27/85 ----------------------Rated Thermal Power Change 0042, 04/29/85 ---------------------- 2.48 x 10-7 pCi/mi WP1.8.1

- ___-_-_-_______-___________________-__A

r SECTION 3 I At 0405 on May 17,1985, the reactor scrammed due to a low Control Rod Drive gas or oil signal.

CROSS 3-Y ACTIVITY AND IODINE ANALYSIS Time of Sample: 0725, 05/17/85 Sample Results: Cross S-Y---------- .139 pCi/ml I-131---------------1.15 x 10-3 pCi/mi 1-133---------------1.22 x 10-2 pCi/ml I-135---------------1.47 x 10-2 pCi/mi ADDITIONAL INFORMATION (1) Reactor Thermal Power Level starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change:

0405, 05/15/85 - 0405, 05/17/85----------------------- ~ 97%.

(2) The approximate fuel burnup of assemblies in a symmetrical core region is shown in Figure 2.

(3) Cleanup Flow llistory starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change:

Primary Purification Flow Rate 0405, 05/15/85 - 0405, 05/17/85 ------ 42 gpm.

Primary Purification Decontamination Factors (S-Y) 0220, 05/16/85 ---- - -------------- 1064:1 0144, 05/20/85 ------- ------------

737:1

,3 (4) Offgas Activity Levels Starting 48 Ilours Prior to Thermal Power Change:

0000-0800, 05/15/85 ----------------------- 171 Ci/ day 0800-1600, 05/15/85 ----------------------- 170 Ci/ day 1600-2400, 05/15/85 ----------------------- 187 Ci/ day 0000-0800, 05/16/85 ----------------------- 193 Ci/ day 0800-1600, 05/16/85 ----------------------- 194 Ci/ day 1600-2400, 05/16/85 ----------------------- 192 Ci/ day (5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:

0222, 05/16/85 ---------------------- 8.45 x 10-8 pCi/mi 0405, 05/17/85 ----------------------Rated Thermal Power Change 0145, 05/20/85 ---------------------- 6.01 x 10-8 pCi/ml WPl.8.1 1

SECTION 4 At 0850 on July 10, 1985, the reactor power dropped from 97% to 47% when the 1A Forced Circulation Loop was isolated due to the closing of the 1A FCP Discharge Valve.

GROSS b-Y ACTIVITY AND IODINE ANALYSIS Time of Sample: 1124, 07/10/85 Sample Results: Cross S-Y---------- .212 pCi/mi 1-131---------------1.23 x 10-3 pCi/mi 1-133---------------1.26 x 10-2 pCi/mi 1-135---------------2.68 x 10-2 pCi/mi ADDITIONAL INFORMATION (1) Reactor Thermal Power Level starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change:

0850, 07/08/85 - 0850, 07/10/85----------------------- ~ 97%.

(2) The approximate fuel burnup of assemblies in a symmetrical core region is shown in Figure 3.

(3) Cleanup Flow llistory starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change Primary Purification Flow Rate 0850, 07/08/85 - 0850, 07/10/85 ------ 42 gpm.

Primary Purification Decontamination Factors (S-Y) 0052, 07/08/85 ----------------------- 1195:1 0034, 07/11/85 ----------------------- 775:1 (4) Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:

0800-1600, 07/08/85 ----------------------- 154 Ci/ day 1600-2400, 07/08/85 ----------------------- 154 Ci/ day 0000-0800, 07/09/85 ----------------------- 154 Ci/ day 0800-1600, 07/09/85 ----------------------- 156 Ci/ day 1600-2400, 07/09/85 ----------------------- 155 Ci/ day 0000-0800, 07/10/85 ----------------------- 154 Ci/ day (5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:

0050, 07/08/85 ---------------------- 8.07 x 10-8 pCi/ml 0850, 07/10/85 ----------------------Rated Thermal Power Change 0032, 07/11/85 ---------------------- < 4.48 x 10-8 pCi/mi WPl.8.1

SECTION 5 At 1000 on July 11, 1985, the reactor power dropped f rom ~ 50% to ~ 30% when the 1A Forced Circulation Loop wss isolated due to the closing of the 1A FCP Discharge Valve.

GROSS S-Y ACTIVITY AND IODINE ANALYSIS Time of Sample: 1310, 07/11/85 Sample Results: Gross S-Y---------- .158 pCi/ml 1-131---------------8.32 x 10-4 pCi/ml 1-133---------------8.52 x 10-3 pCi/ml I-135---------------1.83 x 10-2 pCi/mi ADDITIONAL INFORMATION (1) Reactor Thermal Power Level starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change:

1000, 07 /09/8 5 - 08 50, 07 /10/85 --------------------- ~ 97 %

0850, 07/10/85 -------------------------------dropped to 45%

0850, 07/10/85 - 1000, 07/11/85---escalating slowly from 45% to 50%.

(2) The approximate fuel burnup of assemblies in a symmetrical core region is shown in Figure 3.

(3) Cleanup Flow History starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change Primary Purification Flow Rate 1000,07/09/85 - 1000, 07/11/85 ------ 42 gpm.

Primary Purification Decontamination Factors (S-Y) 0034, 07/11/85 ----------------------- 775:1 0223, 07/15/85 ----------------------- 1470:1 (4) Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:

0800-1600, 07/09/85 ----------------------- 156 Ci/ day 1600-2400, 07/09/85 ----------------------- 155 Ci/ day 0000-0800, 07/10/85 ----------------------- 154 Ci/ day 0800-1600, 07/10/85 ----------------------- 42 Ci/ day 1600-2400, 07/10/85 ----------------------- 48 Ci/ day 0000-0800, 07/11/85 ----------------------- 50 Ci/ day (5) Cross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:

0032, 07/11/85 ---------------------- < 4.48 x 10-8 pCi/ml 1000, 07/11/85 ----------------------Rated Thermal Power Change 0221, 07/15/85 ---------------------- < 4.86 x 10-8 pCi/ml WPl.8.1

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1s.3 IN CORE FLUX MONITORS Q PLANT NORTH Figure 1-Quarter Core Fuel Exposure Distribution (GWD/hifU) as of April 27, 1985. The Core Average Exposure is 7.531 GWD/Ftru.

SECTION 6 At 1420 on July 11, 1985, the reactor power dropped from ~ 45% to ~ 25% when the LA Forced Circulation Loop was isolated due to the closing of the 1A FCP Discharge Valve.

GROSS S-Y ACTIVITY AND IODINE ANALYSIS Time of Sample: 1717, 07/11/85 Sample Results: Cross S-Y---------- .162pci/mi 1-131---------------8.57 x 10 4 pC1/mi 1-133---------------9.95 x 10 3 pCi/mi 1-135---------------2.20 x 10 2 pCi/mi ADDITIONAL INFORMATION (1) Reactor Thermal Power Level starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change:

1420, 07 /09/8 5 - 08 50, 07/10/85 ---------------------- ~ 97%

0850, 07/10/85 - 1420, 07/11/85 ---------------------- operating between 30% to 50% power while investigating valve problems.

(2) The approximate fuel burnup of assemblies in a symmetrical core region is shown in Figure 3.

(3) Cleanup Flow History starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to thermal power change:

Primary Purification Flow Rate 1420, 07/09/85 - 1420, 07/11/85 ------ 42 gpm.

Primary Purification Decontamination Factors ( S-Y) 0034, 07/11/85 ----------------------- 775:1 0223, 07/15/85 ----------------------- 1470:1 (4) Offgas Activity Levels Starting 4d Hours Prior to Thermal Power Change:

0800-1600, 07/09/85 ----------------------- 156 Ci/ day ,

1600-2400, 07/09/85 ----------------------- 155 Ci/ day 0000-0800, 07/10/85 ----------------------- 154 Ci/ day 0800-1600, 07/10/85 ----------------------- 42 Ci/ day 1600-2400, 07/10/85 ----------------------- 48 Ci/ day 0000-0800, 07/11/85 ----------------------- 50 ci/ day (5) Cross Alpha Activity Level Starting With Sample Prior to Thermal Power Change 0032, 07/11/85 ---------------------- < 4.48 x 10-8 pCi/mi 1420, 07/11/85 ---------------------Rated Thermal Power Change 0221, 07/15/85 ---------------------- < 4.86 x 10-8 pCi/mi WP1.8.1

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Quarter Core Fuct Exposure Distribution (GWD/hrfu) as of May 17, 1985. The Core Average Exposure is 8.124 GWD/hfrU.

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Quarter Core Fuel Exposure Distribution (GWD/hfrU) as of July 10, 1985. The Core Average Exposure is 8.747 GWD/hfru.

ML20128N914

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