ML19338G035

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Forwards Special Rept 80-02 Covering Results of Sampling & Analysis Actions W/Addl Operational Info for Five Occasions When Reactor Thermal Power Changed by More than 15% of Rated Thermal Power within 1-h
ML19338G035
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 10/17/1980
From: Linder F
DAIRYLAND POWER COOPERATIVE
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
LAC-7185, NUDOCS 8010280353
Download: ML19338G035 (11)
v • d • e


Text

_

8 DAIRYL.AND

/_]

COOPERAT/VE PO BOX 8U

  • 2615 EAST AV SOUTH
  • LA CROSSE WISCONSIN S4601 hsoa)7884000 October 17, 1980 In reply, please refer to LAC-7185 Mr. James G.

Keppler, Regional Director 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 PROVISIONAL OPERATING LICENSE NO. DPR-45 SPECIAL. REPORT-80-02

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

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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-----July 19, 1980 SECTION 2-----August 8, 1980 SECTION 3-----August 31, 1980 SECTION 4-----September 5, 1980 S ECTION 5-----Oc tobe r 4, 1980 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.

S010280 N h

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L Mr. James G. Keppler, Regional Director LAC-7185 U. S. Nuclear Regulatory Commission October 17, 1980 Very truly yours, i

i Frank Linder, General Manager

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ATTACHMENTS CC:

Director, Of fice of Inspection and Enforcement (30) l U.

S. Nuclear Regulatory Commission Washing ton, D. C.

20555 Director, Office of Management, Information, and Program Control (3)

U.

S.

Nuclear Regulatory Commission Washington, D. C.

20555 Resident Inspectors BCC:

SRC i

E. Tremmel D. Milos-Shimshak Parkyn Boyd/Kelley/SS Raffety Angle j

Towsley Nowicki/ Gray /Rybarik

.Krajewski Goodman Files:

Reading Tech. Lib.

A10, P3, H1, T5N l

I L.

SPECIAL REPORT 80-02 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 report is required to contain the information datermined by the analysis plus additional information regarding reactor power history, fuel burnup, cleanup flow history, offgas activity levels, and gross alpha activit.y levels.

SECTION.1 1B Forced Circulation Pump tripped at 2214 on July 19, 1980, due to low seal inject leakoff flow.

The reactor was operating at 85% of rated thermal power (37 MWe-Net) at the time of the IB FCP trip.

The pump trip caused reactor power to drop to 49% rated thermal power.

GROSS.SV. ACTIVITY AND IODINE ANALYSIS Time of Sample:

0200, 7/20 80 f

Sample Results:

Gross sy-----1.07 pCi/gm I-131--------5.19 x 10-3 pCi/gm I-133--------2.29 x 10-2 pCi/gm I-135--------l.05 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:

0200, 7/17/80 - 2214, 7/19/80-------85%

(2)

The approximate fuel burnup of assemblies in a symmetrical core region is depicted 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:

Prima ry-Purif ica tion. Flow. Ra te 2200, 7/17/80 - 2214, 7/19/80-------41 GPM Primary. Purification Decontamination. Factors. (sy )

0025, 7/17/80---------114:1

! 0226, 7/21/80---------196:1 c

SPECIAL REPORT 80-02 (4)

Offgas. Activity Levels for 48. Hours Prior to. Thermal Power Change:

1600-2400, 7/17/80------------------------------261 Ci/ day 0000-0800, 7/18/80------------------------------261 Ci/ day 0800-1600, 7/18/80------------------------------257 Ci/ day 1600-2400, 7/18/80------------------------------266 Ci/ day 0000-0800, 7/19/80------------------------------269 Ci/ day 1

0800-1600, 7/19/80------------------------------269 Ci/ day (5)

Gross Alpha Activity Level Starting With the Last. Sample Taken Prior. to. Thermal. Power Change:

0923, 7/17/80----------------------------<2.14 x 10-8 uCi/gm
2214, 7/19/80----------------------------Thermal Power Change
0225, 7/21/80----------------------------3.82 x 10-8 uCi/gm SECTION.2 A reactor scram occurred at 0843 on August 8, 1980, when the Forced Circulation Pumps tripped due to low seal inject flow.

The reactor was operating at 85% of rated thermal power (37 MWe-Net) at the time of the scram.

GROSS. sy, ACTIVITY AND. IODINE ANALYSIS Time of Sample:

1307, 8/8/80 Sauple Results:

Gross s y -----------. 69 6 u Ci/gm I-131---------------7.408 x 10-3 uCi/gm I-133---------------5.331 x 10-3 pCi/gm I-135---------------5.559 x 10-3 uCi/gm ADDITIONAL.INFORMATION (1)

Reactr 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:

0800, 8/6/80 - 0843, 8/7/80--------85%

(2)

The approximate fuel ournup of assemblies in a symmetrical core region is depicted 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 the thermal power change:

Primary, Purification. Flow. Rate n800, 8/6/80 - 0843, 8/8/80--------41 GPM 2-

[,

SPECIAL REPORT 80-02 I

Primary. Purification Decontamination Factors (8y) 0102, 8/7/80---------134:1 0103, 8/14/80--------75:1 (4)

Of fgas. Activity. Levels for 48. Hours Prior to. Thermal Power Change 0800-1600, 8/6/80-------------------------------268 Ci/ day 1600-2400, 8/6/80-------------------------------269 Ci/ day 0000-0800, 8/7/80-------------------------------293 Ci/ day 0800-1600, 8/7/80-------------------------------272 Ci/ day 1600-2400, 8/7/80-------------------------------280 Ci/ day 0000-0800, 8/8/80-------------------------------265 Ci/ day (5)

Gross. Alpha. Activity Level Starting.With the-Last Sample.Taken Prior. to. The rmal. Power. Change:

0104, 8/7/80-----------------------------6.1 x 10-7 pCi/gm 0843, 8/ 8/ 8 0 -----------------------------The rm a l Powe r C h ang e
1307, 8/8/80-----------------------------6.96 x 10-7 pCi/gm SECTION 3 A reactor scram occurred at 1430 on August 22, 1980, when the lA Reactor Feed Pump (RFP) tripped due to water dripping onto and shorting out a portion of the RFP controls.

The reactor had achieved 55% rated thermal power during a slow escalation when the scram occurred.

GROSS.8Y ACTIVITY AND. IODINE. ANALYSIS Time of Sample:

1648, 8/22/80 Sample Results:

Gross SY-----------

.667 uCi/gm I-131---------------3.086 x 10-3 pCi/gm I-133---------------4.342 x 10-2 uCi/gm I-135---------------<8.3478 x 10-3 pCi/gm ADDITIONAL.INFORMATION (1)

Reactor taermal 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:

1400-2400, 8/20/80---------45% + 49%

0000-2400, 8/21/80---------49% + 51%

0000-1430, 8/22/80---------51% + 55%

(2)

The approximate fuel burnup of assemblies in a symmetrical core region iz depicted in Figure 2.

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SPECIAL REPORT 80-02 (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 1400, 8/20/80 - 1430, 8/22/80-------41 GPM Primary. Purification Decontamination, Factor ( 6y.)

0041, 8/21/80--------68:1 0045, 8/25/80--------181:1 (4)

Of fgas. Activity Levels for 48. Hours. Prior. to. Thermal Powe r Change 0800-1600, 8/20/80------------------------------137 Ci/ day 1600-2400, 8/20/80------------------------------150 Ci/ day 0000-Oe00, 8/21/80------------------------------149 Ci/ day 0800-1600, 8/21/80------------------------------157 Ci/ day 1600-2400, 8/21/80------------------------------144 Ci/ day 0000-0800, 8/22/80------------------------------165 Ci/ day (5)

Gross. Alpha Activity Level Starting With the Last Sample Taken Prior. to The rmal Powe r. Change:

0033, 8/21/80----------------------------2.12 x 10-7 pCi/gm 1430, 8/ 2 2/8 0----------------------------Therma l Powe r Ch ang e
1648, 8/22/80----------------------------8.54 x 10-7 pCi/gm SECTION.4 A partial, scram occurred at 0700 on September 5, 1980, when water leakage from the seal inject supply line connection to Control Rod Drive Mechanism (CRDM) No. I sprayed onto the scram solenoid area of CRDM No. 3 causing an electrical short.

The reactor had achieved 31% rated thermal power during a slow escalation prior to the scram.

GROSS.ey ACTIVITY.AND. IODINE ANALYSIS Time of Sample:

1115, 9/5/80 Sample Results:

Gross gy------------9.34 x 10-2 gCi/gm I-131---------------2.373 x 10-4 Ci/gm p

I-133---------------3.737 x 10-3 pCi/gm I-135---------------5.774 x 10-3 Ci/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: u

e SPECIAL REPORT 80-02 0700-1655, 9/ 3 /8 0 --------------Sh u td o wn 1655, 9/3/80-------------------Reactor Critical 1700, 9/3/80 - 1700, 9/4/80----10-4 + 1%

1800-1900, 9/4/80--------------l% + 14%

2000-2400, 9/4/80--------------17%

+ 20%

0100-0700, 9/5/80--------------22% + 31%

(2)

The approximate fuel burnup of assemblies in a symmetrical core region is depicted in Figure 2.

(3)

Cleanup Flow flistory 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 0700-1500, 9/3/80--------------41 GPM 1600-1900, 9/3/80--------------42 GPM

2000, 9/3/80-------------------39 GPM
2100, 9/3/80-------------------35 GPM 2200, 9/3/80 - 0700, 9/4/80----Shutdown 0800-1400, 9/4/80--------------42 GPM 1500, 9/4/80 - 0700, 9/5/80----41.5 GPM Primary. Purification Decontamination Factor (SV )

0602, 9/4/80------35.7:1 0231, 9/8/80------36.7:1 (4)

Of fgas. Activity Levels. for. 48 llours Prior. to The rmal. Power Change:

0000-0800, 9/3/80--------------No Offgas Flow 0800-1600, 9/3/80--------------No Offgas Flow 1600-2400, 9/3/80--------------No Offgas Flow 0000-0800, 9/4/80--------------No Offgas Flow l

0800-1600, 9/4/80--------------No Offgas Flow 1600-2400, 9/4/80--------------66.5 Ci/ day 0000-0700, 9/5/80--------------90.2 Ci/ day (5)

Gross. Alpha Activity. Level Starting With the Last Sample.Taken Prior. to. Thermal Power Change:

0105, 9/5/80-------------------3.07 x 10-7 uCi/gm 0700, 9/ 5/8 0-------------------Th e rma l Powe r Ch ang e 0130, 9/6/80-------------------3.54 x 10-7 pCi/gm SECTION.5 A reactor scram occurred at 0732 on October 4 when the 13 Reactor Feed Pump controller failed, increasing reactor water ltvel to the high water level setpoint.

The reactor was operating at 85% rated thermal power at the time of the scram. e

SPECIAL REPORT 80-02 GROSS; 4y. ACTIVITY, AND. IODINE. ANALYSIS Time of Sample:

0942, 10/4/80 Sample Results:

Gross S y------------

. 2 5 0 p C i/gm I-131----------------2.19 x 10-3 gCi/gm I-133----------------1.78 x 10-2 pCi/gm I-135----------------2.61 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:

0700, 10/1/80 - 0732, 10/4/80----85%

(2)

The approximate fuel burnup of assemblies in a symmetrical core region is depicted 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 to the thermal power change:

Primary. Purification Flow Rate

0700, 10/2/80--------------------43 GPM
0800, 10/2/80--------------------42.8 GPM 0900-1500, 10/2/80---------------42.5 GPM 1600, 10/2/80 - 0732, 10/4/80----43 GPM Primary. Purification Decontamination Factor (8Y)
0116, 10/2/80--------------------62:1
0109, 10/6/80--------------------4.28:1
0036, 10/9/80--------------------38.9:1 (4)

Offgas Activity Levels for 48 Hours Prior. to Thermal Power

' Change:

0000-0800, 10/2/80---------------288 Ci/ day 0800-1600, 10/2/80---------------279 Ci/ day 1600-2400, 10/2/80---------------288 Ci/ day 0000-0800, 10/3/80---------------288 Ci/ day 0800-1600, 10/3/80---------------288 Ci/ day 1600-2400, 10/3/80---------------288 Ci/ day 0000-0732, 10/4/80---------------285 Ci/ day (5)

Gross Alpha. Activity. Level Starting. With the. Last Sample Taken. Prior. to The rmal Power Change :

0115, 10/2/80--------------------l.22 x 10-7 pCi/gm 0732, 10/4/8 0--------------------The rmal Powe r Change
1257, 10/5/80--------------------7.04 x 10-7 pCi/gm l

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QUARTER CORE FUEIo EXPOSURE ESTIMATION (GWD/MTU)

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