ML20003G133
| ML20003G133 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 04/23/1981 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| LAC-7486, RO-81-03, RO-81-3, NUDOCS 8104280338 | |
| Download: ML20003G133 (11) | |
Text
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D DA/RYLAND h
COOPERAT/VE po sox 817
- 2615 EAST AV south. LA CROSSE. WISCONSIN 54601 (608) 788 4 000 April 23,1981 In reply, please refer to LAC-7486 DOCKET NO. 50-409 rp g[ h Mr. James G.
Keppler, Regional Director d[
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Nuclear Regulatory Commission 01.
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.A Directorate of Regulatory Operations Region III (2
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I 799 Roosevelt Road Glen E.11yn, IL 60137 j
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SUBJECT:
DAIRYLA'ID POWER COOPERATIVE Nk U
LA CROSSE DOILING WATER REACTOR p
PROVISIONAL OPERATING LICENSE NO. DPR-45 hk SPECIAL REPORT 81-03
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 five separate occasions when reactor thermal power changed by more than 15% of Rated Thermal Power within one hour while in Operational Condition 1 or 2.
The separate occasions are discussed in sections as follows:
SECTION 1-----January 3 0, 1981 SECTION 2-----January 31, 1981 SECTION 3-----February 1, 1981 SECTION 4-----March 9, 1981 SECTION 5-----March 16, 1981 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.
1-810.4ze0337 5
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--U. ; S. Nuclear-Regulatory ~ 'Conmission April 23,-1981 Very truly yours,
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DAIRYLAND POWER COOPERATIVE Frank Linder, General Manager FL:LSG: abs ATTACIDiENTS
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Director, Office of -Inspection and Enforcement (30)
U.
S.. Nuclear Regulatory Commission Washington, D. C.
20555 Director, Office.of Management, Information, and Program Control (3)
U.
S. Nuclear Regulatory Commission Washington,-D.
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20555 i
Resident ~ Inspectors I
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SPECIAL REPORT'80-03 7
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r INTRODUCTION LACBUR Technical Specifications, :Section 4.2.2.22, Action g,
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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 report is required to contain the information determined by the analysis plus additional information regarding reactor power history, fuel burnap, cleanup flow history, offgas activity levels, and gross alpha activity levels.
SECTIO:I 1 Reactor thermal power increased froo 0.1% to 18% over an approximately.20-minute period-co==encing at 2100 on January 30, 1981, when the main steam bypass valve was being opened during-plant startup.
~
GROSS S-Y A'ID IODINE ANALYSIS Time of Sample:
0059, 1/31/81 Sample Results:
Gross Sy-----0. 0 666 uCi/ml I-131--------9.772 x'10-5 pCi/ml I-133--------2.149 x 10-3 pCi/ml I-135--------6.803 x 10-3 pCi/ml ADDITIONAL I?! FORMATION (1)
Reactor Thermal Power Level Starting 48 Hours Prior to Thermal Power Change:
2100, 1/28/81 - 2000, 1/30/81--------10 x-10-4 % ~ 0.1%
(2)
The approximate fuel burnup of asseablies in a symmetrical region is shown in Figure 1.
(3)
Cleanup Flow History Startina 48 Hours Prior to Thermal Power Change:
Primary Purification Flow Rate 2000-2100, 1/28/81------------43.5 gpm
- 2200,
./28/81-----------------44.0 gpm
- 2300, 1/28/81-----------------43.5 gpm
- 2400, 1/28/81-----------------40.0 gem
- 0100, 1/29/81-----------------38.0 gpm
- 0200, 1/29/81-----------------35.5 gym 0300-0400, 1/29/81------------35.0 gpm 1
- 0500, 1/29/81-----------------33.0 gpm 1
SPECIAL REPORT 80-03 o
'M
- 0600, 1/29/81-----------------37.0 gpm 0700, 1/29/81-------~----------35.0 gpm
- 0800, 1/29/81-----------------37.0~gpm
'l 0900-1100, 1/29/81------------Shutdown 1200-1500, 1/29/81------------40.0 gpm 1600-1700, 1/29/81-----===
-43.0 gpm
- 1800, 1/29/81-----------------43.5 gpm
- 1900, 1/29/81-----------------44.0 gpm 2000-2100, 1/29/81------------44.5 gpm 2200-2300, 1/29/81------------45.0 gpm 2400,-1/29/81 - 0300, 1/30/81-45.5 gpm 0400-0500, 1/3 0/81------------4 6. 0 gpm 0600-1500, 1/3 0/81------------ 4 5. 5 gpm
- 1600, 1/30/81-----------------45.2 gpm 1700-2000, 1/30/81------------45.0 gpm Primary Purification Decontamination Factor (SV)
- 0108, 1/29/81-----------------56.6:1
- 0144, 2/2/81------------------>233:1 (4)
Of fgas Activity Levels Starting 4 8 Hour s Prior to Thermal Power Change:
No offgas flow.
(5)
Gross Alpha Activity Starting With Sample Prior to Thermal Power Change:
- 0036, 1/26/81-----------------5.65 x 10-7 pCi/ml 2100, 1/30 /81-----------------The rmal P owe r Change
- 0138, 2/2/81---------------- *5.46 x 10-6 pCi/ml
- 0555, 2/2/81------------------l.79 x 10-7 pCi/ml i
- 0709, 2/2/81------------------1.27 x 10-7 pCi/ml
- Refer to RO 81-03, LAC-7383, dated February 25, 1981.
SECTION 2 Reactor Thermal Power was decreased from 26% to.1% in approximately 40 minutes, starting at 0250 on January 31, 1981.
Steam was being routed through the main steam bypass valve prior to putting the turbine on the line, when the valve operator hydraulic seal commenced leaking oil. Power was reduced to allow maintenance on the main steam bypass valve operator.
L SPECIAL REPORT 80-03 if I
GROSS 8-y AND IODINE ANAI.YSIS Time of Sample:
0842, 1/31/81 Sample Results:
Gross Sy------0.0131 pCi/ml I-131---------8.990 x 10-5 pCi/ml I-133---------l.138 x'10-3 pCi/ml I-135---------l.679 x 10-3 pCi/ml ADDITIONAL INFORMATION (1)
Reactor Thermal Power Level Starting 48 Hours Prior to Thermal Power Change:
0250, 1/29/81 - 2200, 1/30/81--------Refer to Section 1.
2200-2300, 1/30/81-------------------18%
2300, 1/30/81 - 0200, 1/31/81--------18%926%
(2)
The approximate fuel burnup of assemblies in a symmetrical region is shown in Figure 1.
(3)
Cleanup Flow History Starting 48 Hours Prior to Thermal Power Change:
Primary Purification Flow Rate-0250, 1/29/81 - 2200, 1/30/81--------Refer to Section 1 2200, 1/30/81 - 0250, 1/31/81--------45.0 gpm Primary Purification Decontamination Factor (By) 0108, 1/29/81------56.6:1 0144, 2/2/81------->233:1 (4)
Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
No significant offgas flow.
(5)
Gross Alpha Activity Starting With Sample Prior to Thermal Power Change:
0036, 1/26/91------5.65 x 10-7 pCi/ml 0250, 1/31/81------Thermal..ser Change-0138, 2/2/81----- *5.46 x 10-6 pCi/ml 0555, 2/2/81-------1.79 x 10-7 pCi/ml 0709, 2/2/81-------l.27 x 10-7 pCi/ml
- Refer to RO 81-03, LAC-7383, dated February 25, 1981.
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SPECIAL REPORT 80-03 e
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SECTION 3 The reactor automatically shut down from 28% rated thermal power at 1134 on February 1, 1981, when lA and 1B 2400-volt buses were de-energized when an operator opened an incorrect air break switch, disconnecting the reserve auxiliary transformer fran the 69 KV supply line.
GROSS 8-y ACTIVITY AND IODINE ANALYSIS Time of Sample:
1201, 2/1/81 Sample Results:
Gross By------9.30 x 10-2 pCi/gm I-131---------3.83 x 10-5 pCi/gm I-133---------6.04 x 10-4 pCi/gm I-135---------l.42 x 10-3 pCi/gm ADDITIONAL INFORMATION (1)
Reactor Thermal Power Level Starting 48 Hours Prior to Power Change:
1100, 1/30/81 - 0330, 1/31/81--------Refer to Section 2.
0330-0700, 1/31/81------------------
.2%
0800-1700, 1/31/81------------------.1%.2%
- 1712, 1/31/81------------------------Reactor Scram fram.22%
- 1811, 1/31/81------------------------Reactor Critical 1811-2100, 1/31/81-------------------0a.2%
2100-2300, 1/31/81------------------
.2%*20%
2400, 1/31/81 - 0200, 2/1/81---------20%427%
0300-1134, 2/1/81--------------------28%
(2)
The approximate fuel burnup of assemblies in a symmetrical region is depicted in Figure 1.
(3)
Cleanup Flow History Starting 48 Hours Prior to Thermal Power Change:
Primary Purification Flow Rate 1100, 1/30/81 - 0300, 1/31/81--------Refer to Section 2.
0300-2300, 1/31/81-------- ----------45.0 gpm
- 2400, 1/31/81------------------------44.5 gpm 0100-0600, 2/1/81--------------------44.0 gpm 0700-1134, 2/1/81--------------------44.5 gpm Primary Purification Decontamination Factors (8y) 0108, 1/29/81------56.6:1 0144, 2/2/81------->233:1
'Y SPECIAL REPORT 80-03 G
(4)~ Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
1100,~1/30/81 - 2400, 1/31/81---------No significant offgas generation.
0600, 2/1/81 - 0800, 2/1/81-----------100 ci/ day (5)
Gross Alpha Activity Starting with Sample Prior to Thermal Power Change:
- 0036, 1/26/81-------------------------5.65 x 10-7 pCi/ml
- 1134, 2/1/81--------------------------Reactor Scram
- 0138, 2/2/81------------------------ *5.46 x 10-6.uci/ml
- 0555, 2/2/81--------------------------l.79 x 10-7 pCi/ml
- 0709, 2/2/81--------------------------l.27 x 10-7 pCi/ml
- Refer to RO 81-03, LAC-7383, dated February 25, 1981.
SECTION 4 At 1420 on March 9, 1981, the reactor automatically shutdown from-85% rated thermal power due to low voltage RB 480-volt MDC 1A iden the 1B 2400-volt bus was de-energized when switching from reserve to main plant feeds.
GROSS B-y ACTIVITY AND IODINE ANALYSIS _
Time of Sample:
1943, 3/9/81 Sample Results:
Gross Sy------0.149 pCi/gm I-131---------9.897 x 10-" pCi/gm i,
I-133---------l.236 x 10-3 pCi/gm i
i I-135---------1.125 x 10-2 pCi/gm ADDITIONAL INFORMATION (1)
Reactor Thermal Power Level Startina 48 Hours Prior to Power Change:
1400, 3/7/81 - 1420, 3/9/81----------85%
(2)
The approximate fuel burnup of assemblies in a symmetrical j
region is depicted in Figure 2.
(3)
Cleanup Flow History Starting 48 Hours Prior to Thermal Power Change:
Primary Purification Flow Rate 1400, 3/7/81 - 1100, 3/9/81----------40 gpm 1200-1420, 3/9/81--------------------39 gpm 1
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SPECIAL REPORT 80-03
- 1 Primary Purification Decontamination Factors (By) 0029, 3/9/81-- - ---1462:1 0059, 3/12/81------336:1 (4)
Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
0800-1600, 3/7/81-----
92 Ci/ day 1600-2400, 3/7/81--------------------88 Ci/ day 0000-0800, 3/8/81--------------------94 Ci/ day 0800-1600, 3/8/81--------------------98 Ci/ day 1600-2400, 3/8/81-------------------100 Ci/ day 0000-0800, 3/9/81--------------------94 Ci/ day (5)
Gross Alpha Activity Starting With Sample Prior to Thernal Power Change:
- 0025, 3/9/81-------------------------2.48 x 10-8 uCi/gm
- 1420, 3/9/81-------------------------Reactor Scram
- 0057, 3/12/81------------------------< 3.10 x 10-a uCi/gm SECTION 5 Between 1440 and 1500 on March 16, 1981, reactor thermal power increased frcm 85% to 101.8%, an increase of 16.8% power.
The turbine was taken off line from 1440 to 1500 to work.cn1 the turbine governor control relays and steam was routed through the main steam bypass valve, which is rated at greater than 100% of.
full steam flow.
The removal of turbine extraction steam resulted in a decrease in feedwater temperature at the recirculation headers.
Due to the negative temperature co2fficient of the reactor, thermal power increased.
Preliminary heat balance calculations showed a thermal power increase of approximately 14%, while nuclear instru-i mentation displayed a lesser increase, due to the steam flow compensation feature of the Automatic Gain System.
Therefore, primary samples were not taken in the required 2-6 hours following a greater than 15% thermal power change.
Later, more exact calcu-lations determined the power increase to have been 16. 8%.
The samples taken do not show any increase in primary activity.
The offgas activity was 141 Ci/ day the shif t before the power increase, 143 Ci/ day the shif t it occurred, and 138 and 129 Ci/ day, the following two shifts.
These offgas activity levels definitely do not demonstrate any increase due to the power increase.
3
-SP2CIAL REPORT _80-03
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. GROSS 8-y ACTIVITY AND IODINE ANALYSIS
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s Time of Sample:
0135, 3/17/81
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Results of Sample:
Gross 87------0.222 pCi/gm Time of Sample:
0857, 3/18/81' I
Results of Sample:
I-131------8.535 x'10-" pCi/gm I-133------3.75 x 10 3 pCi/gm I-135------< 5.21 x 10-4 pCi/gm ADDITIONAL INFORMATION (1)
Reactor Thermal Power Level Starting 48 Hours Prior to Thermal Power Change:
1400-2400, 3/14/81-------------------74%-81%-
0100-0500, 3 /15 /81------------------- 8 2 %- 8 5 %
0600-1200, 3/15/81-------------------85%
1300, 3/25/81 - 1440, 3/16/81--------84%
(2)
The approximate fuel burnup of assemblies in a symmetrical region is depicted in Figure 2.
(3)
Cleanup Flow History Starting 48 Hours Prior to Thermal Power Change:
3 Primary Purification Flow Rate 1400, 3/14/81 - 1440, 3/16/81--------40 gpm Primary Purification Decontamination Factor (By) 1400, 3/16/81------551:1 0121, 3/19/81------631:1 (4)
Of fgas Activity Levels Starting 48 Hours Prior to Thermal PNwer Change:-
0800-1600, 3/14/81-------------------102 Ci/ day 1600-2400, 3/14/81-------------------126 Ci/ day 0000-0800, 3/15/81-------------------143 Ci/ day 0800-1600, 3/15/81-------------------137 Ci/ day 1600-2400, 3/15/81-------------------143 Ci/ day 0000-0800, 3/16/81-------------------137 Ci/ day (5). Gross Alpha Activity Starting With Sample Prior to Thermal Power Change:
- 0155, 3/16/81------------------------6.13 x 10-8 pCi/gm
- 1440, 3/16/81------------------------Thermal Power Change r
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- 0857, 3/18/81------------------------l.02 x 10-7 pCi/gm,
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AN INDICATION OF REGIONAL EXPOSURE AS OF FEBRUARY 1, 1981 TIIE AVERAGE EXPOSURE:
6.528 GWD/MTU FIGURE 1
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NI II:DICATIO!I OF REGIONAL EXPOSURE AS OF MARCII 1, 1981 TIIE AVERAGE EXPOSURE:
- 6. 966 GUD/IITU
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