ML19309C376
| ML19309C376 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/01/1980 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 605, TAC-12453, NUDOCS 8004080514 | |
| Download: ML19309C376 (4) | |
Text
0 0
TOTE 00
%mm EDISON Docket No. 50-346 a.ec P C-cue c
License No. NPF-3 l1'l7
Serial No. 605 April 1, 1980 Director of Nuclear Reactor Regulation Attention:
Mr. Robert N. Reid, Gilef Operating Reactors Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington D.C.
20555 Dea r Mr. Reid:
On February 25 and 26, 1980 Mr. C.
Long of your staff led an NRC team visit to the Davis-Besse Nuclear Power Station Unit 1 facility to review the Toledo Edison implementation of short-term recommendations of your Lessons Learned Task Force.
These recommendations were documented in your letter of October 30, 1979. On March 21, 1980 (Serial No. 601), Toledo Edison partially responded to requests and questions raised during the site visit. The attachment to this letter provides additional responses.
Very truly yours, b; ;==&
RPC:TJM: cts s qi THE TCLECC ECISCN COMPANY ECISCN PLAZA 300 MAC!SCN AVENUE TOLECO. OKO 43552 8 0 04 0 80Sitt
a J
]
. Docket b!o. 50-346 License No. NPF-3 Serial No. 605 April 1, 1980 i
l Davis-Besse Unit 1 I
NRC Lessons Learned Site Visit Documentation February 25-26, 1980 2.1.6.b i
l 2.
Document of feet of Auxiliary Building radiation levels on environmental
)
qualification of ESF equipment. Provide schedule (3/31/80).
RESPONSE
f On January 31,1980 (Serial No. 585) Toledo Edison submitted " Design Review of Plant Shielding for Spaces outside Containment Which May Be Used In Post-Accident Operations For Davis-Besse Nuclear Power Station, Unit 1".
This evaluation pro-t duced post-accident radiation zone maps consistent with the assumed source terms
{
requested in your letter of October 30, 1979 (Log No. 454).
Copies of the accident radiation zone maps and revision 1 of the design review were forwarded to you as Attachment D of Toledo Edison's March 31, 1980 letter (Serial No. 601). This study is being utilized as the basis for documenting the radiation effects on environmental qualification of safety grade equipment.
As discussed during the site visit,this request duplicates a detailed study already J
in progress in response to IE Bulletin 79-01B. The evaluation methodology uses an i
integrated 180 day dose that has been determined for each room based on the shielding 5 rads are identified.
revie w.
Rooms that result in a 180 day dose greater than 10 They include room numbers:
105 227 113 2 36 115 303 208 304 l
209 314 1he ongoing review of IE Bulletin 79-01B will cross-ccrrelate the equipment locations with the high radiation dose areas. On a case-by-ca,e basis the safety grade equipment will be:
l 1)
Evaluated to determine what post-accident functioning is required, if any.
2)
Identified as to the conditions it has been qualified to.
3)
Reanalyzed, if necessary, to provide a realistic integrated radiation dose, i
~
- 4) Shielded, if necessary, to reduce the radiation effects.
5)
Requalified, if necessary, for the radiation conditions required.
6)
Replaced, if necessary, with equipment qualified for the radiation condition.
_ This will ensure that safety grade equipment in the auxiliary building will be able -
l to perform its intended function in a post-accident condition consistent with the results of the DB-1 shielding review. A copy of this evaluation being done in response l
to IE Bulletin 79-01B will be forwarded to your staf f.
It is expected to be submitted
[
-August. 15, 1980.
l l
L-
~ - - -
- -_ = - -
. - ~.
r 7
o.
1
\\
r,'. '
r:
Docket No. 50-346 License No. NPF-?
Serial No. 605
[
April 1,1980 i
t 2.1.8.a 3.
Describe the proposal for long term containment air / liquid sample analysis capability and schedule.
t I
RESP 0NS E I
L A.
Reactor Coolant Liquid Sampling j
In order to improve the reactor coolant liquid sample location DB-1 will be f
modified to add a sample line directly off a reactor coolant loop drain.
This line will join with an existing pressurizer sample line to allow sample loca-
[
j tion selection remotely from the control room.
F Reactor coolant analytical capability will be provided through the use of on-site evaluation of grab samples. This analytical capability is presently planned to include:
1)
Radiological isotopic quantification
- 2) Boron concentration determination
The current target date for completion of this capability is the 1981 DB-1 refueling outage.
l B.
Containment Vessel Atmosphere Sampling j
i 4
i-Hydrogen concentration of the containment vessel is currently provided by a f
i hydrogen analyzer with a 0-5 percent range.
This capability will be maintained and the current system modified to include a 0-10 percent range capability.
j This conversion is presently scheduled to be completed by January 1,1981.
l Toledo Edison will install a containment vessel atmosphere gross monitor with i
grab sample capability for particulate, iodine and noble gases. Current plans i
identify this modification to be installed during the 1981 ' refueling outage.
[
i i
l 1
i
. +
... _ ~ _. -.
Docket No. 50-346 2
License No. NPF-3 Serial No. 605 April 1,1980 i
i 1
2.1.8.b l
i l
4.
Document position on installing high acr.ivity effluent monitors /in-containment 7
j monitors.
l
RESPONSE
Toledo Edison will modify the plant to provide high range noble gas and radioiodine i
effluent monitors for the containment vessel atmosphere and the station vent. Subj ect t
to equipment availability these monitors shall meet the requirements of Table' 2.1.8.b.2 of your October 30, 1979 letter with the exception of ANSI N320-1979.
i l
Toledo Edison will also modify the plant to provide high range in-containment vessel e
j radiation monitors. Subj ect to equipment availability these will =eet the requirements of Table 2.1.8.b.3 of your October 30, 1979 letter with the exception of ANSI N320-1979.
i s
i i
The current schedule is projected to have these monitors installed at DB-1 during
(
the 1981 refueling outage.
)
1 i
t l
i 1
t l
l i
i i
i I
2 i
i d
i i
i j
1...
__ -