ML20050A802
| ML20050A802 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 03/25/1982 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737, TASK-2.F.1, TASK-TM LAC-8178, NUDOCS 8204020286 | |
| Download: ML20050A802 (2) | |
Text
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D DA/RYLAND h
[k COOPERAT/VE pO box 817 2615 EAST AV SOUTH
- t A CROsSL WlsCONslN 54601 (608) 788-4000 March 25, 1982 In reply, please refer to LAC-8178 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation ATIN:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Operating Reactors so ts U. S. Nuclear Regulatory Commission p
g Washington, D. C.
20555 GC@M A
SUBJECT:
DAIRYLAND POWER COOPERATIVE
-9 'h LA CROSSE BOILING WATER REACTOR (LACBWR)
C gpp, Q 1198F ~--
PROVISIONAL OPERATING LICENSE NO. DPR-45 C
- $$guessmus' s sert *8 8 TMI ACT11N PLAN - NUREG-0737, ITEM II.F.1.3, CONTAINMENT HIGH RANGE RADIATION MONITORS
.g' s//
REFERENCES:
(1) NRC Letter, Crutchfield to Linder,
! 4 Dated March 5, 1982.
(2) DPC Letter, Linder to Crutchfield, L AC-7983, Dated December 17, 1981.
Gentlemen:
Your letter (Reference 1) requested that we inforn you of any technical deviations that we were aware of in equipment we installed to comply with the provisions of NUREG-0737, Item II.F.1.3.
You stated that based on your review of our submittal, no technical deviations were requested. Our submittal (Reference 2) did indicate that the cable used in this monitor does not fully comply with to environmental qualifications required pursuant to NUREG-0737, Item II.F.1.3.
It further indicated that the Adnutdcturer had filed a 10CFR21 notification with the Nuclear Regulatory Commission on this equipment.
NUREG-0737, Table II.F.1.3 indicates that each detector should be source Cdlibrated f or at least one point per decade between 10 and 103 R/hr prior to initial use. Our two detectors were installed under the criteria of NUREG-0578, prior to issuance of NUREG-0737 (October 31,1980), and were source calibrated at a single point between 102 and 103 R/hr by the vendor prior to initial use, j
lt is also noted that the cables routed fraa the electrical penetration room to the control roon are in the same cable tray (though on opposite sides).
l This is not in total compliance with Regulatory Guide 1.75.
Regulatory Guide 1.75 is listed in Appendix B to NUREG-0737.
Item II.F.1.3 does not reference 8204020286 820325 PDR ADOCK 05000409
(, ' g F
r Director of Nuclear Reactor Regulation Mr. Dennis M. Crutchfield, Chief LAC-8178 Operating Reactors Branch if 5 March 25, 1982 this Appendix; however, Table II.F.1.3 references Appendix A to NUREG-0737, and we believe the commission intended to reference Appendix B.
This deviation from Regulatory Guide 1.75 has no health and safety consequences because the separation of cables was a concern from the standpoint of potential tires.
10CFR50, Appendix R does not require the license to protect equipment used in design basis accidents f rom the simultaneous effects of a loss of coolant accident and a fire.*
- 10CFR50, I.
" Safety Function - Design Basis Accidents"
" Fire Damage Limit - Both trains of equipment necessary for mitigation of consequences following design basis accidents may be danaged by a single exposure fire."
As the high range radiation monitors are used to indicate containaient conditions following a LOCA, this separation is not required to ensure functionability during the incidents the monitors are designed to be utilized for.
Contact us if you have any questions on this information.
Very truly yours, DAIRYLAND POWER COOPERATIVE 7
ef/f/146<0 fdf j[7# Frank Linder, General Manager G
FL :JUP : abs CC:
J. G. Keppler, Regional Director, NRC-DRO, Region III NRC Resident Inspectors