ML19210C112

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Responds to 790913 Request for Commitment Re Implementation of NUREG-0578 Actions.Submits List of Scheduled Dates for Implementation
ML19210C112
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 11/05/1979
From: Linder F
DAIRYLAND POWER COOPERATIVE
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
LAC-6616, NUDOCS 7911130288
Download: ML19210C112 (5)


Text

DAIItYLAND 1*0WER COUI*EItATIVE Sa Grosw, Ohconan 54601 November 5, 1979 In reply, please refer to LAC-6616 DOCKET NO. 50-409 U.

S.

Nuclear Regulatory Commission ATTN:

Mr. Darrell G. Eisenhut, Acting Director Division of Operating Reactors Washington, D.

C.

20555

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 NUREG 0578 ACTIONS - IMPLEMENTATION COMMITMEtTr

Reference:

(1)

NRC Letter, Eisenhut to All Operating Nuclear Power Plant, dated September 13, 1979.

Gentlemen:

In response to Mr. Darrell Eisenhut's letter (Reference 1) which was received September 25, 1979, we are submitting our commitments to meet the requirements on the implementation schedule contained in Enclosures 6 and 8 of Reference 1 as follows: Commitments Section Abbreviated Implementation No.

Title Comments Date 2.1.1 D.tergency Power Does not apply to BWR.

NA Fupply Require-No power operated relief 1..e n t s and associated block valves.

2.1.2 Relief and Discussion of LACBWR past 1/1/80 Safety Valve and current valve test Testing program to be submitted.

2.1.3.a Direct Indi-None 1/1/80 cation of Valve Position 2.1.3.b Instrumentation Applicability discussion

~

for Inadequate required.

Core Cooling i320 128 7911180 $13 b P

Mr. Darrell G. Eisenhut, Acting Director LAC-6616 Division of Operating Reactors November 5, 1979 Commitments - (Cont'd)

Section Abbreviated Implementation No.

Title Comments Date 2.1.4 Diverse Con-None 1/1/80 tainment Isolation 2.1. 5. a Dedicated H2 None.

Equipment may not 1/1/80 Control be necessary.

Not re-Penetrations quired in accident analysis of original Safeguards Report (FSAR).

2.1.5.c Recombiners None 1/1/80 2.1.6.a System Integ-None 1/1/80 rity for righ Radioactivity 2.1.6.b Plant Shield-None.

Adequate design

./1/80 ing Review modifications unlikely.

2.1.7.a Auto lnitiation Does not apply to BWR.

NA of Auxiliary Feed 2.1.7.b Auxiliary Feed Does not apply to BWR.

NA Flew Indica-t1cn 2.1.8.a Pott Accident None.

1/1/80 Sampling Modifications 1/1/81 2.1.8.b High Range None, but containment radia-1/1/81 Rcdiation tion monitor is adequate.

Monitors 2.1.8.c Improved Iodine Have adequate sampling Instrumentation capability.

2.1.9 Transient &

Must discuss applicability Accident with NRC Technical Staff Analysis Containment Discuss applicability of 1/1/81

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Pressure installed equipment.

Monitor 1320 129 Mr. Darrell G. Eisenhut, Acting Director LAC-6616 Division of Operating Reactors November 5, 1979 Commitments - (Cont'd)

Section Abbreviated Implementation No.

Title Comments Date Containment Discuss applicability of 1/1/81 Water Level inste.lled equipment.

Monitor Containment None 1/1/81 Hydrogen Monitor RCS Venting Have manual depressuriza-NA tion system.

Discuss applicability of installed equipment.

2.2.1.a Shift Super-None 1/1/80 visor Responsi-bilities 2.2.1.b Shift Technical Alternate Plan to be 1/1/80 Advisor submitted.

2.2.1.c Shift Turnover None 1/1/80 Procedures 2.2.2.a Control Room None 1/1/80 Access Control 2.2.2.b On-Site Tech-None 1/1/80 nical Suppcrt Center 2.2.2.c On-Site Oper-None 1/1/80 ational Support Center Commitments 1

Upgrade Emer-None 1/1/80 gency Plans 1320 130 Mr. Darrell G. Eisenhut, Acting Director LAC-6616 Division of Operating Reactors November 5, 1979 Commitments - (Cont'd)

Section Abbreviated Implementation No.

Title Comments Date 2

Implement Short-Term Actions:

2.1. 8 (a) Post-Accident Sampling -

Design Review None 1/1/80 Procedures None 1/1/80 Modification None Mid/80 Discription of None 1/1/80 Modifications 2.1.8(b) High-Range Radio-activity Monitors -

Methods None 1/1/80 High Range Installation as equipment Monitors becomes available. See 2.1.8.b comments.

2.1.8(c) In-Installation as equipment proved In-Plant becomes available.

Iodine Instru-See 2.1.8.c comments.

mentation 3

Establish Emergency Operations Center:

(a) Designate None Mod /80 Location &

Alternate (b) Upgrade None 1/1/81 Emergency Operations Center 1320 131

Mr. Darrell G.

Eisenhut, Acting Director LAC-6616 Division of Operating Reactors November 5, 1979 Commitments - (Cont'd)

Section Abbreviated Implementation No.

Title Comments Date 4

Improve Off-Site None Mid/80 Monitoring 5

State / Local Plan Adequacy:

(a) Current None Mid/80 Criteria (b) Upgraded None 1/1/81 Criteria 6

Conduct Test Exercise *:

(a) Test Licensees None Mid/80 Emergency Plan (b) Test State Nore Mid/80 Emergency Plan (c) Joint Test None Within 5 Yrs.

/

  • Joint Tests Con-ducted in July 1979.

Delay in response to your letter was attributed to the recent need for preparation and attendance by key plant personnel at ACRS and staff technical meetings on other licensee technical matters.

If there are any questions concerning our commitments or proposed actions, please contact us.

Very truly yours, DAIRYLAND POWER COOPERATIVE 7

9 t

AL t & c~

Frank Linder, General Manager FL:RES:af cc:

J.

Keppler, Reg. Dir., NRC-DRO III 1320 132