05000409/LER-1982-014, Forwards LER 82-014/01T-0.Detailed Event Analysis Submitted

Forwards LER 82-014/01T-0.Detailed Event Analysis Submitted

ML20054F104
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	06/09/1982
From:	Linder F DAIRYLAND POWER COOPERATIVE
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20054F097	List: 05000409/LER-1982-014, Forwards LER 82-014/01T-0.Detailed Event Analysis Submitted 05000409/LER-1982-014-01, /01T-0:on 820605,gross Alpha Activity Exceeded Tech Spec Limitation During Startup from Refueling Outage. Caused by Degraded Fuel Cladding Experience Contributing to Irradiated Fuel Particles in RCS ML20054F096
References
LAC-8338, NUDOCS 8206150218
Download: ML20054F104 (5)

LER-1982-014, Forwards LER 82-014/01T-0.Detailed Event Analysis Submitted

Event date:
Report date:
4091982014R00 - NRC Website

text

.O D DA/RYLAND h

k COOPERAT/VE Po BOX 817 LA CROSSE. WISCONSIN S4601 2615 EAST AV SOUTH a

(608) 788-4000 June 9, 1982 In reply, please refer to LAC-8338 DOCKET NO. 50-409 Mr. James G.

Keppler, Regional Director U.

S.

Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 REPORTABLE OCCURRENCE NO. 82-14

REFERENCES:

(1)

LACBWR Technical Specifications, Section 6.9.1.8.b.

(2)

DPC Letter, Linder to Keppler, LAC-8330, dated June 7, 1982 (3)

LACBWR Technical Specifications, Section 4.2.2.22

Dear Mr. Keppler:

In accordance with Reference 1, this is the required follow-up report for the event initially reported in Reference 2, in which the primary coolant alpha activity exceeded the Technical Specification limit of < 5.0 x 10-6 pCi/gm gross alpha activity (Reference 3).

At 0030 on June 5, 1982, with the reactor in Operating Condition 2, at 50 x 10-6% power, a review of the shift supervisor's log revealed that the results of a sample taken the previous day indicated primary water alpha activity to be 7.46 x 10-6 pCi/gm.

Further investigation showed a sample of the primary coolant taken at 1058 on June 3, 1982 had an alpha activity of 9.98 x 10-6 pCi/gm.

The alpha activity of the primary coolant sample analyzed previous to June 3 on May 7, 1982, was 3.63 x 10-3 pCi/ml.

The iodine and gross 8-y activities were well within the specified limits for all three samples.

The reactor was in a cold shutdown condition when the samples had been taken.

Another primary coolant sample was taken at 0045 on June 5, 1982.

The alpha activity was 3.46 x 10-5 pCi/gm.

A four hour sampling frequency was initiated in accordance with Reference 3, Section 4.2.2.22.f.

The sampling was continued until 2035 on June 5, when the alpha activity fell within the Technical Specification limit.

The results of the sample analyses are listed in Attachment 1.

@206150218 820610 PDR ADOCK 05000409 p PDR

?

Mr. James G.

Keppler, Regional Director June 9, 1982 U.

S.

Nuclear Regulatory Commission LAC-8338 A reactor shutdown was conducted at 0205 on June 5, 1982 in accordance with Technical Specification Action Statement 4.2.2.22.a.3.

The plant had been shutdown since April 9, 1982 for a refueling outage.

At 1723 on June 4, the initial post-refueling startup commenced from Operating Condition 4, Cold Shutdown.

The reactor achieved criticality at 1924 on June 4.

The observed increase in alpha activity is not considered attributable to post-refueling fuel failure.

This is supported by the relatively low 8-y and iodine activities measured and that the alpha activity increase was seen prior to first criticality following refueling.

The contribution to the temporary increase in gross alpha activity of the primary coolant system is believed to be attributable to residual irradiated fuel material which entered the system as a esult of degraded fuel pin cladding primarily experienced during Cycle 4 and to a much lesser degree during Cycles 5 and 7 and to subsequent handling of the irradiated fuel assemblies during refueling.

Handling of core components during refueling and initial post-refueling operation of the forced circulation pumps, resulted in a more general distribution of suspended alpha bearing material in the coolant.

This effect has been observed in the past.

(Refer to RL's 81-03, 80-07, 80-06, and 79-10).

Recirculation of the primary coolant had initially commenced for the purpose of conducting a primary system hydrostatic test on May 30, 1982.

The recirculation pumps were stopped on June 1 and restarted on June 3 and operated for less than three hours.

On June 4 the forced circulation system was placed in operation in preparation for starting up the reactor.

Repetitive starting and stopping of the pumps following an outage has resulted in resuspension of crud in the past due to agitation of the primary coolant.

Operation of the primary purification system reduced the amount of alpha-emitting material suspended in the primary coolant.

A confirmatory sample was taken at 0134 on June 6 to ensure the alpha activity was within the limit, as the sample at 2035 on June 5 had shown.

Modifications to the LACBWR Water Chemical and Radiochemical Analyses Report form will be made to specify the Technical Specification limits for the primary system.

All Health and Safety and Operations Department personnel have been informed of this incident to focus their attention on the application of Technical Specification limits for primary system activity and the action requirements if a limit is exceeded.

WP1.

a Mr. James G.

Keppler, Regional Director June 9, 1982 U.

S.

Nuclear Regulatory Commission LAC-8338 The Additional Information required by Reference 3 is enclosed as.

A Licensee Event Report (Reference:

Appendix A, Regulatory Guide 1.16, Rev. 4) is enclosed.

Prompt notification of the event was made by L. Goodman, LACBWR Operations Engineer, to the NRC Operations Center at 0202 on June 5, 1982.

Very truly yours, DAIRYLAND POWER COOPERATIVE

&h 0 es_.

Frank Linder, General Manager FL:LSG:eme Attachments (2) cc:

NRC Resident Inspector Document Control Desk (1)

U.

S.

Nuclear Regulatory Commission Washington, D.

C.

20555 Institute of Nuclear Power Operation Records Center 1820 Water Place Atlanta, Ga 30339 WP1 June 9, 1982 LAC-8338 ATTACHMEt1T_1 PRIMARY _ COOLANT SAMPLE ANALYSE _S TIME DATE SAMPLE ACTIVITY (pCi/ml)

Alpha S-y I-131 I-133 I-135 1058 06/03/82 9.88 x 10-6 1.50 x 10-2 5.81 x 10-3 0100 06/04/82 1405 06/04/82 7.64 x 10-6 1.24 x 10-2 0045 06/05/82 3.46 x 10-5 4.23 x 10-2

<7.18 x 10-5

<1.12 x 10-4

<2.79 x 10-4 0445 06/05/82 2.00 x 10-5 2.05 x 10-2

<4.96 x 10-5

<7.50 x 10-5

<1.73 x 10-4 0835 06/05/82 1.74 x 10-5 1.51 x 10-2

<1.43 x 10-5

<1.12 x 10-5

<6.96 x 10-6 1234 06/05/82 1.92 x 10-5

1. '/ 7 x 10-2

<1.56 x 10-5

<1.24 x 10-5

<7.46 x 10-6 1635 06/05/82 6.57 x 10-6 5.81 x 10-3

<6.21 x 10-6

<5.2 x 10-6

<3.28 x 10-6 2035 06/05/82 4.18 x 10-6 3.96 x 10-3

<5.38 x 10-6

<4.51 x 10-6

<2.57 x 10-6 0134 06/06/82 2.08 x 10-6 2.03 x 10-3

<1.12 x 10-5

<2.426 x 10-5

<2.46 x 10-5 WP-1 1

^

9' June 9, 1982 LAC-8338 ATTACliMENT 2

)

ADDITIONAL INFORMATION

(1)

Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to sample in which the limit was exceeded:

The reactor was shutdown.

(2)

Fuel burnup by core region (See attached figure).

(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 sample in which limit was exceeded:

1000-1720, 06/01/82 Purification System Shutdown 1720, 06/01/82 Purification Pump Started 1800, 06/01/82 40 gpm 1900, 06/01/82 36 gpm 2000, 06/01/82 34 gpm 2100, 06/01/82 - 0800, 06/03/82 40 gpm 0900, 06/03/82 - 0900, 06/06/82 39 gpm

.(4)

Off-gas level starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to sample in which limit was exceeded.

No off-gas was generated.

(5)

Gross alpha activity level starting with the last sample taken prior to sample in which limit was exceeded.

~

1404, 05/07/82 ----- 3.63 x 10-8 pCi/ml.

See Attachment i for subsequent samples.

WP1