05000409/LER-1981-015, Forwards LER 81-015/01T-0.Detailed Event Analysis Encl

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Forwards LER 81-015/01T-0.Detailed Event Analysis Encl
ML20039G131
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 01/06/1982
From: Linder F
DAIRYLAND POWER COOPERATIVE
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20039G132 List:
References
LAC-8007, NUDOCS 8201150316
Download: ML20039G131 (3)
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LER-1981-015, Forwards LER 81-015/01T-0.Detailed Event Analysis Encl
Event date:
Report date:
4091981015R00 - NRC Website
v • d • e

text

,.

D DA/RYLAND h

COOPERAT/VE eo sox 817 2615 EAST AV SOUTH LA CROSSE. WISCONSIN S4601 (608) 788-4000 January 6, 1982 In reply, please refer to LAC-8007 DOCKET e 50-409 Mr. James G. Keppler, Regional Director r, N A

U.

S. Nuclear Regulatory Commission V

Directorate of Regulatory Operations OECEjVgg B

Region III

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1 M 1319825 9 799 Roosevelt Road f %aa; mtrga Me Glen Ellyn, Illinois 60137 t

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SUBJECT:

DAIRYLAND POWER COOPERATIVE 9r, b

LA CROSSE BOILING WATER REACTOR (LACBWR h

\\

~

dI PROVISIONAL OPERATING LICENSE NO. DPR-45 REPORTABLE OCCURRENCE NO. 81-15

References:

(1)

DPC Letter, LAC-7993, Lindar to Keppler, dated December 28, 1981.

(2)

LACBWR Technical Specifications, Section 4.2.2.4.a.

Dear Mr. Keppler:

This letter constitutes the written followup to the event reported to you in Reference 1.

Our letter discussed an occurrence on December 24, 1981, in which the temperature of the 1B Forced Circulation (FC) Loop decreased below 130 F, while primary pressure was greater than 280 psig.

Following a reactor scram, which occurred at 2115 December 23, 1981, the temperature of the piping in the 1B Forced Circulation (FC)

Loop decreased to a minimum of 86*F as measured by the 1B FC Pump Suction thermocouple.

The temperature of the 1B FC Loop was below 130 F from 0017 to 0433 on December 24, 1981.

Reactor pressure varied during this period between a maximum of 1145 psig and a minimum of 680 psig (Refer to attached table).

is Reference 2 states the Main Coolant System chrome piping RTN The 1B FC Loop temperature did not decrease b low fixed at 70 F.

the RT at anytime during this incident.

NDT An independent analysis of this incident was performed by Nuclear Energy Services.

The NES analysis also concluded the 1B FC Loop temperature did not decrease below the NDT.

A report covering this independent analysis will be docketed within the next few days. 9201150316 820106 gDRADOCKOSOOOg Y}d o22

O

. Mr. James G.;Keppler,. Regional-Director January 6, 1982 U. S. Nuclear Regulatory Commission LAC-8007 A Licensee Event Report (Reference:

Regulatory Guide 1.16, Revision 4).is enclosed.

~ If-there are any questions, please contact us.

Very truly yours, DAIRYLAND POWER COOPERATIVE Frank Linder, General Manager FL:LSG:af Attachment cc:

Director, Office of Inspection and En.forcement (30)

U.

S._ Nuclear Regulatory Commission Washington, D.

C.

20555 Director, Office of Management Information and (3)

Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555 NRC Resident Inspector LAC-8007'- 1/6/82 1B FORCED CIRCULATION LOOP TEMPERATURE RATE OF TEMPERATURE

  • TEMPERATURE PRESSURE CHANGE.BY. HOUR TIME

(*F)

(PSIG)

AFTER SCRAM 2115 551 1240 2215 384 1215

- 167*/HR 2315 234 1140.
- 150*/HR 0015 138 1080
- 96*/HR 0017 132 0115' 101 1065
- 37*/HR 0215 91 1145 (Max. Press. -

2 /HR below 130*F) 0223

'90 1100 3*/HR 0315 88 940 0341.

86 720

+

87 0345 86 0346 680

(-4*/HR 0315-0345)

+

'87 0354 86 735 0356 87 l

0415 90 820

+

2*/HR 0427 93 0430 109 820 j

0433 182 820 0435 212 i-0444 284 815 0515 263 780

+173*/HR

  • 2*F was added to chart reading up until 0403 when chart paper returned to track.

The chart was off up to 4*F.

1 l-L

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