05000409/LER-1979-014, Forwards LER 79-014/03L-0

Forwards LER 79-014/03L-0

ML19259C802
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	08/06/1979
From:	Linder F DAIRYLAND POWER COOPERATIVE
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 7908150193
Download: ML19259C802 (2)

LER-1979-014, Forwards LER 79-014/03L-0

Event date:
Report date:
4091979014R00 - NRC Website

text

%

e D.tIItYIanND 1*0WEli C00PEftATIVE Ba Crosu, 0%,isirr 54601 August 6, 1979 In reply, please re f e r to LAC-6 4 41 DOCKET NO.40-409 Mr. James G.

Keppler, Regional Director U.

S.

Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, IL 60137 SUBJ ECT:

DAIhYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 REPORTABLE OCCURRENCE NO. 79-14 REFE RENCES :

(1)

LACBWR Technical Specificati.ons, Section 3. 9. 2.b. (2 )

(2)

LACBWR Technical Specifications, Section 4.2.4.2.3 (3)

LACBWR rechnical Specifications, Section 4.2.4.2.1 (4)

LACBWR Technical Spacifications, Section 4.2.4.2.4

Dear Mr. Kepple r :

In accordance with Re fe rence (1), this is to notify you of conditions leading to operation which conservative surveillance specifications indicated would be a degraded mode permitted oy a limiting condition for operation.

Reference (2) establishes Minimum Critical Power Ratio (NCPR) values as a function of core flow and fuel assembly type for

> 15% of ra ted thermal power.

operation at The surveillance specification 5.2.17.3 conservatively reouires that MCPR shall be determined to be equal to or greater U ar. the limit

-- by verifying that each control rod is within the control rod pattern and withdrawal sequence requirements - -.

65G039

_ 1 _

7 908150 / E

I Mr. James G.

Kepaler, Regional Director LAC-6441 U.

5.

Nuclear Regulatory Commission Aucust 6, 1979 The specified control rod withdrawal sequence for the startup of LACuWR requires that after the Group C rods are fully withdrawn, and all other rods are at 16 dial inches, rods 8 and 12 will be withdrawn as a 2-rod bank.

During the reactor startup on July 8, 1979, control rod 10 was inadvertantly withdrawn instead of rod 12.

When this ou t-o f-se quen ce condition was recognized at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />, the reactor power was 22% of Rated Thermal Power, control rods 8 and 10 were at 27 dial inches, and control rod 12 was at 16 dial inches.

The action requirements of T.S.

4.2.4.2.3 were followed -

adjus tments were initiated immediately and the control rods were re tu rned to the required pattern within approximately 20 minutet.

Subsequent conservative calculations of the reactor thermal-hydraulic conditions during this event showed that the limiting MCPR was not violated (actual MCPR was at least 2.1 times greater than the LCO value for each fual type).

Conservatively calculated values of APLHGR and LHGR were also compared with the LCO values of their respective Technical Specifications (References (3) and (4)) even though these specifications are not applicable

> 25% of rated thermal power.

The until the reactor power is calculated maximum APLHGR was 32.5% of the LCO value, and the maximum LHGR was 36.3% of the LCO value.

The importance of maintaining control rod position within the requirements of the control rod program will be emphasized to all opcrations personne1. No further corrective action is deared necessary.

A Licensee Event Report (Reference:

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

If you have any questior.s concerning this report, please contact us.

Very truly yours, DAIRYLAND POWER COOPERATIVE Prank Linder, General Manager FL: SJ R: abs Encloscres CC:

Director, Office of Inspection and Enforcement (30)

U.

S.

Nuclear Regulatory Commission Washington, D.

C.

20555 Director, Office of Management Information and Progran Control (1)

U.

S.

Nuclear Regulatory Commission Washington, D.

C.

20555 U56MO