ML20042C060
| ML20042C060 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 03/23/1982 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| LAC-8170, NUDOCS 8203300122 | |
| Download: ML20042C060 (3) | |
Text
,
k D DA/RYLAND h
[k COOPERAT/VE eO EOx8i7 2615 EAST AV SOUTH LA CROSSE. WISCONSIN 54601 March 23,1982 (608) 788 4 000 In reply, please refer to LAC-8170 DOCKET NO. 50-409 Director, of Nuclear Reactor Regulation ATIN:
Mr. Dennis M. Crutchfield, Chief p
43 Operating Reactors Brarch #5
/
Division of Operating Reactors S
I9 U. S. Nuclear Regulatory Commission EL " l C
s Washington, D. C.
20555 L
t;'
M/tR.0 91982+- 9
SUBJECT:
TMI Action Plan - Environmental Qualification of 2 "J e r n a r.::
s
- $,W 'N Safety-Related Electrical Equipment Request for gj'
/f Additional Information g
sp
REFERENCE:
(1) Letter Crutchfield to Linder, dated March 2,1982
~
Gentlemen:
Enclosed as Attachments 1 and 2 are summaries of the requested information.
DPC has previously submitted the available information which supports an 6
integrated containment building accident dose of less than 2 x 10 R.
Since your consultant finds this information inconclusive, we are submitting a Nomogram as suggested by the D0R guidelines. The proposed LOCA integrated 6
dose is approximately 8 x 10 R.
This new value does not affect any of the qualifications of existing equipment that have already been addressed in previous submittals. provides a conservative estimate of the normal operating radiation exposure over 40 year period to which an item of Environmentally Qualified Equipment could be expected to be exposed. Due to the location of the Environmentally Qualified Equipment in relation to the containment building sump, there is a negligible contribution to the normal operating radiation dose.
As requested in your letter (Reference 1) a copy of this submittal will be sent to Mr. Cyril Crane at Franklin Research Center.
Contact us if you have any questions on this information.
Very truly yours, D&IRYLAND POWER COOPERATIVE F2033OO122 820323
[f'/f[Y DR ADOCK 05000 jFrank Linder, General Manager FL:RMB:eme
Enclosures:
Attachments 1 & 2 0
cc:
J. G. Keppler, Regional Director, NRC-DRO, Region III bk c
NRC Resident Inspector l
ATTAOBETT 1 r.0M'.;3M FOR C0'iTAINMEr.T VOLU"E A'O REA _CR POWER
(
LOCA DOSE CORPECT10N5*
( OONTAINMENT LACBWR VOLUME (f t )
3 3 x 106 2 x 106 30 D AY MwTH INTEG R ATED yDOSE 4000 1 x 106 7
3000 4 x 10 2000 3 x 107 1000 5 x los 4 x 105 7
~
2 x 10 3 x 106 1'
5 2.64 x 10 2 x 105 1 x 107 6
168
-3 8 x 10 N
1 x 106 5 x 106 4 x 106 I
3 x 106 l
2.5 x 106 2.0 x 10E r
1 x 106 I
t l
l
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ATTACHMENT 2 NORMAL OPERATING EXPOSURE Containment Building Assumptions:
(1) Reactor Operates Continuously for 40 years l
(2) Measured Exposure to 8, y, Neutron radiation is.
600 mr/hr (worst dose rate for E. Q. Equipiaent).
TOTAL DOSE 2.1 x 108 24 hr/ day 365 day /yr 40 yr 600 mr/hr
=
mr 5
2.1 x 10 R I
I l
4 i
Total Accident and Normal Operating Exposure 6 (1) 5 (2) 6 8.0 x 10 R
+ 2.1 x 10 R 8.2 x 10 R
=
l 6
8.2 x 10 R-i-
i I-i i
(1)
DDR Guidelines Nomogram (2)
[
LACBWR Calculated.Value i
4
-wpl.
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