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{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ | {{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ | ||
APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR | APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR | ||
^ | |||
DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copies of the requested changes to the Davis-Besse Nuclear Power Station Unit No. 1 Facility Operating License No.' NPF-3, together with the Safety Evalution for the requested change. | DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copies of the requested changes to the Davis-Besse Nuclear Power Station Unit No. 1 Facility Operating License No.' NPF-3, together with the Safety Evalution for the requested change. | ||
The proposed changes include Table 3.7-3. | The proposed changes include Table 3.7-3. | ||
A Safety Evaluation for the Steam Generator Auxiliary Feedwater lleader overall modification is included. | A Safety Evaluation for the Steam Generator Auxiliary Feedwater lleader overall modification is included. | ||
By | By /49 b Station Superintendeht For R. P. Crouse Vice President, Nuclear Sworn and subscribed before me this 30th day of July, 1982. | ||
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My Commission Expires June 30, 1987. | My Commission Expires June 30, 1987. | ||
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q' 8208050242 820730 PDR ADOCK 05000346 c. | |||
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.M Docket No.1 50-346 i 4 | |||
1 iSerial'Flo. | Licente.,KJ. h?F-3 | ||
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July 30', 1982,< | 1 iSerial'Flo. 842 i | ||
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i | July 30', 1982,< | ||
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Attachment I r g | |||
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1,nAppendix A | |||
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Char.ges to Davis' Besse Nuclear Power Station Unit j | |||
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Techijical Specifications, Table 3.7-3 | |||
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A. | |||
Time r equired to Implement. | |||
T'.11s change l's to be ef fective | T'.11s change l's to be ef fective | ||
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tryon NRC approval. | |||
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The snubbers were' removed and relocated during the modific- | B. | ||
Reason for Change (Facility Change Request d2-CW); | |||
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The snubbers were' removed and relocated during the modific- | |||
' ations to the Steam Generator Auxiliary Feedwater Header. | |||
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(6C-/FB-4-H15) at a dif ferent elevatiun. The dafety function | C. | ||
33f. sty uvaluation ' | |||
;Turine the current refueling outage (1982) at Davis-Besse | |||
~. Nuclear Power Station Unit No. 1, tht: auxiliary feedwdter | |||
< headers in the steam' generators were found damaged. As a result of this situation /an external, header way installed on teach s;. cam generator with'some rerouting,of piping,and ropports. | |||
Thq T.nalysis' of the rerouted ytpinc and header has concluded that;the relocation of one and remocal 4 tvo snubbers would neet ' the design objective to pro,1de structural integrity of the affected system during!and following al seismic or other | / | ||
,s With yhe rerouting of supports, two (2) s~nnbbers were removed (6C-E'!B-4-li6 and,6C-EBB-4-1(7) and one',(1): was relocated x | |||
event initiating dynamic loads. The reloca:ei snubber will cer.tinue to perform its intended safety fundtion and the retsoved snubbers will not adversely affect.the safety function of--the Auxiliary Feedwater systecG Therefores this is not a | (6C-/FB-4-H15) at a dif ferent elevatiun. The dafety function df' hydraulic-snubbir~s is to' ensure that the structural v 6 | ||
unreviewed safety question. | integrity of the saf' ty "related Mtees is.=dintained during e | ||
h l | and following a seismic or other' event causing initiation of | ||
4 j < | , dynamic loads.' | ||
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,1 Thq T.nalysis' of the rerouted ytpinc and header has concluded that;the relocation of one and remocal 4 tvo snubbers would neet ' the design objective to pro,1de structural integrity of the affected system during!and following al seismic or other | |||
~ | |||
event initiating dynamic loads. The reloca:ei snubber will cer.tinue to perform its intended safety fundtion and the retsoved snubbers will not adversely affect.the safety function of--the Auxiliary Feedwater systecG Therefores this is not a unreviewed safety question. | |||
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Latest revision as of 00:08, 17 December 2024
| ML20062C394 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 07/30/1982 |
| From: | Crouse R, Murray T TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20062C380 | List: |
| References | |
| TAC-48349, NUDOCS 8208050242 | |
| Download: ML20062C394 (2) | |
Text
_ _ _ _ _ _ _ _ _ _
APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR
^
DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copies of the requested changes to the Davis-Besse Nuclear Power Station Unit No. 1 Facility Operating License No.' NPF-3, together with the Safety Evalution for the requested change.
The proposed changes include Table 3.7-3.
A Safety Evaluation for the Steam Generator Auxiliary Feedwater lleader overall modification is included.
By /49 b Station Superintendeht For R. P. Crouse Vice President, Nuclear Sworn and subscribed before me this 30th day of July, 1982.
\\
q e
2s
/
/
/ !Totary Pub ^11c p
My Commission Expires June 30, 1987.
A i '
l e
q' 8208050242 820730 PDR ADOCK 05000346 c.
p PDR L
n
____________________.________m J
',. J
. /
- f. $
/
l,
/ 1 J
s-
/
/
\\
\\
t'f
}
'1 l
Y
,e
, /
- s
>~,
.1 J
f r
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5 i
h
+f
~
h
/
)l
)
l s
/
?
->.s
.l
/
.i 1
! </
j/,
', j/
.M Docket No.1 50-346 i 4
Licente.,KJ. h?F-3
/
1 iSerial'Flo. 842 i
i i
v, 9 :j ? /
r,
July 30', 1982,<
N.'
1
.g 1<>
1./
i
- T
,i 9
Attachment I r g
y-l
~
y
,, i,.
1,nAppendix A
' I. '.
Char.ges to Davis' Besse Nuclear Power Station Unit j
/
Techijical Specifications, Table 3.7-3
~
a
,r-
/
A.
Time r equired to Implement.
T'.11s change l's to be ef fective
~l'"
tryon NRC approval.
j.
j y
B.
Reason for Change (Facility Change Request d2-CW);
i i
\\
The snubbers were' removed and relocated during the modific-
' ations to the Steam Generator Auxiliary Feedwater Header.
s s.
j
/
C.
33f. sty uvaluation '
- Turine the current refueling outage (1982) at Davis-Besse
~. Nuclear Power Station Unit No. 1, tht: auxiliary feedwdter
< headers in the steam' generators were found damaged. As a result of this situation /an external, header way installed on teach s;. cam generator with'some rerouting,of piping,and ropports.
/
,s With yhe rerouting of supports, two (2) s~nnbbers were removed (6C-E'!B-4-li6 and,6C-EBB-4-1(7) and one',(1): was relocated x
(6C-/FB-4-H15) at a dif ferent elevatiun. The dafety function df' hydraulic-snubbir~s is to' ensure that the structural v 6
integrity of the saf' ty "related Mtees is.=dintained during e
and following a seismic or other' event causing initiation of
, dynamic loads.'
. I, '
,1 Thq T.nalysis' of the rerouted ytpinc and header has concluded that;the relocation of one and remocal 4 tvo snubbers would neet ' the design objective to pro,1de structural integrity of the affected system during!and following al seismic or other
~
event initiating dynamic loads. The reloca:ei snubber will cer.tinue to perform its intended safety fundtion and the retsoved snubbers will not adversely affect.the safety function of--the Auxiliary Feedwater systecG Therefores this is not a unreviewed safety question.
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