ML19318A151
| ML19318A151 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/12/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 LAC-6979, NUDOCS 8006180523 | |
| Download: ML19318A151 (2) | |
Text
.
r D DA/RYLAND COOPERAT/VE eo sox 817
- 2615 EAST AV SOUTH. LA CROSSE. WISCONSIN 51601 (606) 788 4000 June 12, 1980 In reply, please refer to L 0-6979 DOCKET NO. 50-409 Director of Nuclear. Reactor Regulation
. ATTN:
Mr. Harold Denton, Director Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission
-Washington, D. C.
20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 ADDITIONAL INFORMATION - THREE MILE ISLAND LESSONS LEARNED (NUREG-0578)
Reference:
(1)
NUREG-0578 "Three Mile Island Lessons Learned Task Force Status Report and Short Term Recommendations".
(2) 'DPC Letter, Linder to Denton, LAC-6860, dated April 14, 1980.
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Gentlemen:
1 An analysis of LACBWR shielding has been performed as outlined in Reference 2.
Reference 1 specified that following such analysis, "Each licensee
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chall provide for adequate access to -Vital Areas and protection of cafety equip. ment by design changes, increacea in permanent or tempor-ary shielding, or post accident procedural controla.
The design revicu shall determine which typea of corrective actions are needed for Vital Areas throughout the facility".
The areas requiring post accident entry were identified (Reference 2) as the' control room post accident sampling station, health physics laboratory, and the Technical Support Center.
The shielding analysis indicated that post accident radiation levels in over one-half of the control room areas were below 3 Rem for 24-hour occupancy of 100 days duration following an-event.
As NRC and DPC policies-call for maximum work tours of.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or less, the cumulative dose of any personnel assigned to this area for post
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accident work will be well below the guidelines of Reference 1.
No shielding modifications are required.
Procedures will be modified to indicate expected locations of highest exposure.
8006180I D
o Mr. Harold Denton, Director LAC-6979 Office of Nuclear Reactor Regulation June 12, 1980 The health physics laboratory and new sampling system locations are utilized for intermediate occupancy following an event.
Radiation levels in these areas would permit the sample to be collected, trans-ported and counted with an area background exposure level resulting in less than 1 Rem exposure which is well below the 3 Rem guideline of Reference 1.
The Technical Support Center will not normally be occupied in the first hour following an event even during the normal work week.
It will be occupied only after the required site evacuation is complete, personnel are accounted for and the Emergency Control Director and Duty Shift Supervisor permit such occupancy.
As the Shift Technical Advisor is present in the control room and has access to all the same information and parameters as would be available in the Technical Support Center, the function intended for the Technical Support Center will be accomplished.
The normal restrictions on personnel (i.e., rotation of personnel) will be utilized to maintain the exposure within the guidelines of NUREG-0578.
The shielding analysis results indicated the need to locate the permanent Technical Support Center in the office area of the turbine building (near the control room) instead of the interim location in the new Administration Building.
If you have any questions, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE s
c /2dALWl? L4Ubd Prank Linder, General Manager FL:JDP:af cc:
J.
Keppler, Reg. Dir., NRC-DRO III I