ML20128M585: Difference between revisions

From kanterella
Jump to navigation Jump to search
StriderTol Bot insert
 
StriderTol Bot change
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:_ . - . _ _ _ _            ____ _ _ _ _ _ _ _ _ _ . . . _ _ . _ _ _ _ _ .                                            _      _ . _ -
{{#Wiki_filter:_. -.
NN                                                                                         h/N f/G.26~j i                      J.f) p ha
NN h/N f/G.26~j J.f) p ha i
;                      @ @ g g gv.ii.ypo..,si.iion                                                                     M /f M/[
@ @ g g gv.ii.ypo..,si.iion M / M/[
smppinoport.er iso 77-ooo4 l
f l
                                                                                                                            //
smppinoport.er iso 77-ooo4
;                      $$$nifE..w.,,                                                               october 4, 1996             j2
//
                      "::!::2hn
$$$nifE..w.,,
.                  Mr. David L. Meyer Chief, Rules Review and Directives Branch
october 4, 1996 j2
!                  U. S. Nuclear Regulatory Commission i                   Mail Stop T-6D-69 Washington, DC 20555-0001
"::!::2hn Mr. David L. Meyer Chief, Rules Review and Directives Branch U. S. Nuclear Regulatory Commission i
Mail Stop T-6D-69 Washington, DC 20555-0001


==Subject:==
==Subject:==
Beaver Valley Power Station, Unit No.1 and No. 2 i                               BV-1 Docket No. 50-334, License No. DPR-66 i                               BV-2 Docket No. 50-412, License No. NPF-73
Beaver Valley Power Station, Unit No.1 and No. 2 i
;                              Proposed Generic Communication, " Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism and Other Vessel Head j                               Penetrations"
BV-1 Docket No. 50-334, License No. DPR-66 i
BV-2 Docket No. 50-412, License No. NPF-73 Proposed Generic Communication, " Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism and Other Vessel Head j
Penetrations"


==Dear Mr. Meyer:==
==Dear Mr. Meyer:==
 
i Duquesne Light Company (DLC) is responsible for the operation of Beaver Valley Power Station Units 1 and 2. DLC has reviewed the proposed generic communication, i
i
" Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism and Other Vessel Head Penetrations," which was published in the Federal Register on August 1, 1996 (61 FR 40253). DLC hereby submits the following comments.
;                        Duquesne Light Company (DLC) is responsible for the operation of Beaver Valley i
Power Station Units 1 and 2. DLC has reviewed the proposed generic communication,
                    " Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism and Other Vessel Head Penetrations," which was published in the Federal Register on August 1, 1996 (61 FR 40253). DLC hereby submits the following comments.
DLC endorses the comments provided by the Nuclear Energy Institute (NEI). The NEI comments identify the key issues which need to be considered. DLC concurs with NEI that there is no technical or regulatoiy basis for this generic letter.
DLC endorses the comments provided by the Nuclear Energy Institute (NEI). The NEI comments identify the key issues which need to be considered. DLC concurs with NEI that there is no technical or regulatoiy basis for this generic letter.
Thank you for the opportunity to comment on this issue. If you have any questions on this submittal, please contact Mr. Roy K. Brosi, Manager, Nuclear Safety Department, (412) 393-5210.
Thank you for the opportunity to comment on this issue. If you have any questions on this submittal, please contact Mr. Roy K. Brosi, Manager, Nuclear Safety Department, (412) 393-5210.
Sincerely,                       i w Sushil C. Jain
Sincerely, i
                                                                                                                                          'M DEllVERING
w
                        %OgnG   ~
'M Sushil C. Jain DEllVERING
Q U A l l i >Y 9610160120 961004                                                                                           E ll E R G Y PDR   ADOCK 05000334 P                               peg 1}}
%OgnG Q U A l l i >Y
~
9610160120 961004 E ll E R G Y PDR ADOCK 05000334 P
peg 1}}

Latest revision as of 13:10, 12 December 2024

Comment on Proposed Generic Communication, Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism & Other Vessel Head Penetrations
ML20128M585
Person / Time
Site: Beaver Valley
Issue date: 10/04/1996
From: Jain S
DUQUESNE LIGHT CO.
To: Meyer D
NRC
References
FRN-61FR40253 61FR40253-00011, 61FR40253-11, NUDOCS 9610160120
Download: ML20128M585 (1)


Text

_. -.

NN h/N f/G.26~j J.f) p ha i

@ @ g g gv.ii.ypo..,si.iion M / M/[

f l

smppinoport.er iso 77-ooo4

//

$$$nifE..w.,,

october 4, 1996 j2

"::!::2hn Mr. David L. Meyer Chief, Rules Review and Directives Branch U. S. Nuclear Regulatory Commission i

Mail Stop T-6D-69 Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No.1 and No. 2 i

BV-1 Docket No. 50-334, License No. DPR-66 i

BV-2 Docket No. 50-412, License No. NPF-73 Proposed Generic Communication, " Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism and Other Vessel Head j

Penetrations"

Dear Mr. Meyer:

i Duquesne Light Company (DLC) is responsible for the operation of Beaver Valley Power Station Units 1 and 2. DLC has reviewed the proposed generic communication, i

" Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism and Other Vessel Head Penetrations," which was published in the Federal Register on August 1, 1996 (61 FR 40253). DLC hereby submits the following comments.

DLC endorses the comments provided by the Nuclear Energy Institute (NEI). The NEI comments identify the key issues which need to be considered. DLC concurs with NEI that there is no technical or regulatoiy basis for this generic letter.

Thank you for the opportunity to comment on this issue. If you have any questions on this submittal, please contact Mr. Roy K. Brosi, Manager, Nuclear Safety Department, (412) 393-5210.

Sincerely, i

w

'M Sushil C. Jain DEllVERING

%OgnG Q U A l l i >Y

~

9610160120 961004 E ll E R G Y PDR ADOCK 05000334 P

peg 1