ML20053A024
| ML20053A024 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/11/1982 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| LAC-8276, RO-82-001, RO-82-1, NUDOCS 8205240444 | |
| Download: ML20053A024 (10) | |
Text
-
1 DlDA/RYLAND h
[k COOPERAT/VE
- PO BOX 817
(%8? 7M4%0 May 11, 1982 In reply, please refer to LAC-8276 DOCKET NO. 50-409 MEMMUltz'__
w &*p,ug Mr. James G. Keppler, Regional Director i
U. S. Nuclear Regulatory Commission gr) l Directorate of Regulatory Operations sh)
[
re n,
o elt Road Glen Ellyn, IL 60137 03TT
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR PROVISIONAL OPERATING LICENSE N0. DPR-45 SPECIAL REPORT 82-01
REFERENCE:
(1)
LACBWR Technical Specifications Section 4.2.2.22, Action 9
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 four separate occasions when reactor thermal power changed by more than 15% of Rated Thermal Power within one homr while in Operational Condition 1 or 2.
The separate occasions are discussed in sections as follows:
SECTION 1 -----F eb ru a ry 18, 1982 S EC T I ON 2-----F eb ru a ry 24, 1982 SECTION 3-----March 30, 1982 SECTION 4-----April 9,
1982 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.
8205240444 820511 DR ADOCK 05000 f,Qy 14 gg WP-1 Mr. James G.
Keppler, Regional Director May 11, 1982 U. S. Nuclear Regulatory Commissi';n LAC-8276 l
Very truly y
-s,
- 6 tW Frank Linder, General Manager FL:LSG:eme I
ATTACHMENTS i
j CC:
Director, Office of Inspection and Enforcement j
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Document Control Desk i'
U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i
Resident Inspector I
l l
l i
i Wp-1 !
SPECIAL REPORT 82-01 INTRODUCTION 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 than 15% of rated thermal power within one hour.
This special re. sort is required to contain the information determined by the ana2ysis plus additional information regarding reactor power history, fuel burnup, cleanup flow history, offgas activity levels, and gross alpha activity l
levels.
SECTION 1 At 1042 on February 18, 1982, the reactor automatically shutdown when an erroneous low forced circulation flow signal was transmitted to Power-Flow Safety Channel No. 1.
GROSS S-y ACTIVITY AND IODINE ANALYSIS Time of Sample:
1305, 02/18/82 Sample Results:
Gross S-y-----------0.521 pCi/ml I-131---------------3.09 x 10-3 pCi/ml l
I-133---------------3.00 x 10-2 pCi/ml I - 13 5 --------------- 4. 8 2 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:
1300, 02/16/82 - 1305, 02/18/82-------73%
(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 the thermal power change:
Primary Purification Flow Rate 1000, 02/16/82 - 1042, 02/18/82-------41 gpm I
Primary Purification Decontamination Factors (S-y) i
- 0151, 02/18/82-------------------------
38:1 0100, 02/22/82------------------------25.7:1 WP-1 1
,,, -.,,. ~..,. -..
I SPECIAL REPORT 82-01
)
(4)
Offgas Activity Levels for 48 Hours Prior to Thermal Power Change:
0800-1600, 02/16/82----------------------156 Ci/ day 1600-2400, 02/16/82----------------------160 Ci/ day 1
0000-0800, 02/17/82----------------------159 Ci/ day 0800-1600, 02/17/82----------------------159 Ci/ day 1600-2400, 02/17/82----------------------187 Ci/ day 0000-0800, 02/18/82----------------------192 Ci/ day (5)
Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:
1
- 0148, 02/18/82---------------------------3.97 x 10 8 pCi/ml
- 1042, 02/18/82---------------------------Thermal Power Change
- 0056, 02/22/82---------------------------3.15 x 10-7 pCi/ml SECTION 2 l
At 0902 on February 24, 1982, reactor thermal power decreased from 83% to a minimum of 48* when the 1B Forced Circulation Pump tripped.
GROSS 6-Y ACTIVITY AND IODINE ANALYSIS a
j Time of Sample:
1455, 02/24/82 Sample Results:
Gross 8-y-----------l.004 pCi/ml I-131---------------4.97 x 10-3 pCi/ml I-133---------------5.24 x 10-2 pCi/ml I-135---------------1.05 x 10-1 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:
0900, 02/22/82 - 1100, 02/23/82--------82%
i 1200, 02/23/82 - 0902, 02/24/82--------83%
i (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 4
power change:
l Primary Purification Flow Rate 0900, 02/22/82 - 0902, 02/24/82-------41 gpm.
i WP-1..
SPECIAL' REPORT 82-01 Primary Purification Decontamination Factors (S-y)
- 0100, 02/22/82------------------------25.7:1
- 0042, 02/25/82------------------------30.3:1 (4)
Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
0800-1600, 02/22/82----------------------268 Ci/ day 1600-2400, 02/22/82----------------------294 Ci/ day 0000-0800, 02/23/82----------------------276 Ci/ day 0800-1600, 02/23/82----------------------276 Ci/ day 1600-2400, 02/23/82----------------------306 Ci/ day 0000-0800, 02/24/82----------------------313 Ci/ day (5)
Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:
- 0056, 02/22/82---------------------------3.15 x 10-7 pCi/ml
- 0902, 02/24/82---------------------------Thermal Power Change
- 0038, 02/25/82---------------------------8.72 x 10-8 pCi/ml SECTION 3 At 1847 on March 30, 1982, the reactor automatically shutdown.
The probable cause of the trip was a line fault in the DPC 69 kv grid tripping a Main Power Transformer relay.
GROSS Sy ACTIVITY AND IODINE ANALYSIS i
Time of Sample:
2111, 03/30/82 Sample Results:
Gros s 8 7------------0.8 9 4 p C i/gm I-131---------------4.03 x 10-J pCi/gm I-133---------------3.53 x 10-2 pCi/gm I-13 5---------------5. 9 5 x 10- 2 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 thermal power change:
1800, 03/28/82 - 0900, 03/30/82---------75%
1000, 03/30/82 - 1847, 03/30/82---------74%
(2)
The approximate fuel burnup of assemblies in a symmetrical core region is depicted in Figure 2.
WP-1 - -. _ -,
SPECIAL REPORT 82-01 (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 chanse:
Primary Purification Flow Rate 1800, 03/?8/82 - 1847, 03/30/82---------41 gpm Primary Purification Decontamination Factor (SV) 0040, 03/29/82------------20.7:1
- 0030, 04/01/82------------- 47:1 (4)
Offgas Activity Levels for 48 Hours Prior to Thermal Power Change:
1600-2400, 03/28/82------------252 Ci/ day 0000-0800, 03/29/82------------253 Ci/ day 0800-1600, 03/29/82------------245 Ci/ day 1600-2400, 03/29/82------------246 Ci/ day 0000-0800, 03/30/82------------240 Ci/ day 0800-1600, 03/30/82------------235 Ci/ day (5)
Gross Alpha Activity Level Starting With the Last Sample Taken Prior to Thermal Power Change:
- 0036, 03/29/82-----------------<3.47 x 10 8 pCi/ml
- 1847, 03/30/82-----------------Thermal Power Change
- 0026, 04/01/82-----------------3.42 x 10-7 pCi/ml SECTION 4 Reactor thermal power decreased from approximately 50% to 30%
between 0100 and 0200 on April 9, 1982 during the shutdown to commence the refueling outages Inaccurate steam flow indication-led to the greater than 15% power change per hour, GROSS Sy ACTIVITY AND IODINE ANALYSIS Time of Sample:
0426, 04/09/82 Sample Results:
G ros s S y------------0.8 57 p Ci/gm I-131---------------3.22 x 10-J pCi/ml I-13 3 --------------- 2. 7 5 x 10- 2 pCi/ml I-135---------------5.08 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:
0100, 04/07/82 - 2300, 04/08/82-----78-77%
- 2400, 04/08/82----------------------63%
- 0100, 04/09/82----------------------50%
WP-1 Special Report 82-01 r
(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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior tx) the thermal power change:
Primary Purification Flow Rate 0100 - 0700, 04/07/82----------------41 gpm 0800, 04/07/82 - 1500, 04/08/82------41 gpm 1600 - 2400, 04/08/82----------------41 gpm 0100 - 0200, 04/09/82----------------40 gpm Primary Purification Decontamination Factor (SV)
- 0116, 04/08/82-------------------41:1
- 1313, 04/28/82-------------------16:1 (4)
Offgas Activity Levels for 48 Hours Prior to Thermal Power Change:
}
0000-0800, 04/07/82------------314 Ci/ day 0800-1600, 04/07/82------------320 Ci/ day 1600-2400, 04/07/82------------320 Ci/ day 0000-0800, 04/08/82------------317 Ci/ day 0800-1600, 04/08/82------------306 Ci/ day 1600-2400, 04/08/82------------280 Ci/ day (5)
Gross Alpha Activity Level Starting With the Last Sample Taken Prior to Thermal Power Change:
- 0112, 04/08/82-----------------l.00 x 10-7 pCi/ml 0100 - 0200, 04/09/82----------Thermal Power Change
- 1312, 04/28/82-----------------1.04 x 10-7 pCi/ml
}
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IO IlN IN CORE Ft.UX MONITORS Q PLANT NORTH FIGURE 1 QUARTER CORE FUEL EXPOSURE ESTIMATION (GMD/MTU)
AN INDICATION OF REGIONAL EXPOSURE AS OF PEPAUARY 28, 1982 Tile AVERAGE EXPOSURE:
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FIGURE 2 QUARTER CORE FUEL EXPOSURE ESTIMATION (GMD/MTU)
AN INDICATION OF REGIONAL EXPOSURE AS OF l'.ARCII 31, 1982 Tile AVERAGE EXPOSURE:
12.356 GWD/f1TU
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FIGURE 3 QUARTER CORE FUEL EXPOSURE ESTIMATION (GMD/MTU)
AN INDICATION OF REGIONAL EXPOSURE AS OF APRIL 9, 1982 Tile AVERAGE EXPOSURE:
12.481 GWD/f1TU