ML20153G951
| ML20153G951 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/22/1988 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| 4537K, NUDOCS 8805120066 | |
| Download: ML20153G951 (3) | |
Text
1
', Commonwoalth Edison
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One First Natonal Plaza. Cheago, Ilhnos Address Reply 12 Post OfEe bot 7C
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Chcago, Ilhnos 60690 0767 April 22, 1988
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Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Braidwood Unit 1 and 2 Limitorque Operator Lubrication NRC Docket Nos. 50-456 and 50-457
Reference:
(a)
L.O. DelGeorge letter to T.E. Murley, dated April 21, 1988 (b)
L.O. DelGeorge letter to T.E. Murley, dated April 4, 1988
Dear Mr. Murley:
Reference (a) provided supplemental information in response to an April 20, 1988 teleconference to discuss reference (b).
Upon the completion of the NRC staff's review of reference (a) it is our understanding that four valves were identified that will potentially 7
see radiation values that are higher than the 2x10.
(The qualification value for the SUN EP 50)
We understand these valves to be ICVll2B, ICV 112C, 10G057A and 1RY8000A as listed in Attachment 2 to reference (a).
To show that the valve operators for these valves will function as intended, Commonwealth Edison will perform a qualification test of a representative grease sample, that will be completed within 60 days from the date Braidwood Unit 2 enters Mode 2, currently scheduled for April 23, 1988.
It is our understanding per D. Muller of NRR, that an additional option existe, whereby if we can show that the specific radiation values seen by these valves is lower than presented in Attachment 2 that th's information may resolve this matter in lieu of testing.
Please address any questions you may have regarding this matter to this office.
Very truly yours,
'A/
8805120066 880422 PDR ADOCK 05000456 S. C. Ilunsader P
DCD Nuclear Licensing Administrator 0'
cc: S Sands (NRR)
W. Forney (RIII)
BWD Resident Inspector gs/4537K l
l
I C} One Fird Natonal Plaza. CNeago. (Enoes.
Commonwealth Edison i
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- e V. Address Reply to: Post Omc2 Box 76F i
CNeago,lanos 60690 C767 3
i April 22, 1988 j
l (corrected copy dated April 25, 1988) i f
f Mr. Thomas E. Murley, Director L
Office of Nuclear Reactor Regulation
[
U.S. Nuclear Regulatory Commission l
3 Washington, DC 20555
- k l
subject: Braidwood Unit 1 and 2
)
Limitorque Operator Lubrication I
NRC Docket Nos. 50-456 and 50-457 I
Reference:
(a)
L.O. DelGeorge letter to T.E. Murley,
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dated April 21, 1988
)
(b)
L.O. DelGeorge letter to T.E. Murley, I
i dated Aptil 4, 1988 i
j
]
Dear Mr. Murley:
I a
i Reference (4) provided supplemental information in response to an I
April 20, 1988 teleconference to discuss reference (b).
l d
)
Upon the completion of the NRC staff's review of reference (a) it l
is our understanding that four valves were identified that will potentially 4
i see radiation values that are higher than the 2x10.
(The qualification 7
j value for the SUN EP 50)
]
We understand these valves to be ICV 112B, ICV 112C, IOG057A and 1RY8000A as listed in Attachment 2 to reference (a).
i l
I To show that the valve operators for these valves will function as intended, Commonwealth Edison will perform a qualification test of a representative grease sample, that will be completed within 60 days from the i
date Braidwood Unit 1 enters Mode 2, currently scheduled for April 23, 1988. l It is our understanding per D. Muller of NRR, that an additional d
option exists, whereby if we can show that the specific radiation values i
seen by these valves is lower than presented in Attachment 2 that this j
information may resolve this matter in lieu of testing.
l please address any questions you may have regarding this matter to j
this office.
l Very truly yours.
b wM4 i
. C.
unsader j
Nuclear Licensing Administrator i
)
cc: S Sands (NRR) l W. Forney (RIII) l BWD Resident Inspector yp 9a453x
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