ML20063G304: Difference between revisions

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En i
Tennessee Valey Autnonty. Post Office Box 2000. &cdy-Daisy; Tennessee 3737S 2000 l
t Tennessee Valey Autnonty. Post Office Box 2000. &cdy-Daisy; Tennessee 3737S 2000 l
Robert A. Fenech
Robert A. Fenech
                %ce President. Segacyah Nacicar Plant February 7, 1994                                                                                                                                   ;
%ce President. Segacyah Nacicar Plant February 7, 1994 TVA-SQN-TS-93-11 10 CFR 50.90' U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
TVA-SQN-TS-93-11                                                                                                           10 CFR 50.90' U.S. Nuclear Regulatory Commission ATTN: Document Control Desk                                                                                                                         .
In the Matter of
Washington, D.C. 20555 Gentlemen:                                                                                                                                         ,
)
In the Matter of                                                                   )                                 Docket Nos. 50-327 Tennessee Valley' Authority                                                       )                                             50-328           ;
Docket Nos. 50-327 Tennessee Valley' Authority
1 SEQUOYAH NUCLEAR PLANT (SQN) - TFCHNICAL SPECIFICATION (TS) CHANGE 93-11,
)
                  " SNUBBER TRENDING ANALYSIS REQUIREMENTS"                                                                                                         >
50-328 1
In accordance with 10 CFR 50.'90, we are enclosing a requested amendment                                                                           !
SEQUOYAH NUCLEAR PLANT (SQN) - TFCHNICAL SPECIFICATION (TS) CHANGE 93-11,
to Licenses DPR-77 and DPR-79 to change the'TSs of.SQN. Units 1 and 2..                                                                           !
" SNUBBER TRENDING ANALYSIS REQUIREMENTS" In accordance with 10 CFR 50.'90, we are enclosing a requested amendment to Licenses DPR-77 and DPR-79 to change the'TSs of.SQN. Units 1 and 2..
The proposed change'will delete the prescriptive information contained                                                                             !
The proposed change'will delete the prescriptive information contained within the Snubber Service Life Program of TS 3.7.9 and replace the wording with that from the NRC. approved Westinghouse Electric Corporation Standard TS, Revision 4a.-
within the Snubber Service Life Program of TS 3.7.9 and replace the wording with that from the NRC. approved Westinghouse Electric Corporation                                                                         '
Additionally, changes'are being proposed based upon previously received NRC comments.
Standard TS, Revision 4a.-                           Additionally, changes'are being proposed based                                             .;
The proposed TS change is identified in. Enclosure 1.
upon previously received NRC comments.                                                                                                             !
The justification
The proposed TS change is identified in. Enclosure 1.                                                             The justification             '}
'}
for the proposed TS change is provided in Enclosure 2. A proposed determination of no significant hazards consideration performed pursuant                                                                         -;
for the proposed TS change is provided in Enclosure 2.
to 10 CFR 50.92 is'provided in Enclosure 3.:                                                                                                     j TVA requests a 45-day implementation. period for this TS change following issuance. Since'the change is expected to be a resource savings that'is                                                                           i applicable during refueling outages, TVA requests that this TS change be                                                                         3 approved as soon as possible.                                                                                                                   -l I
A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 is'provided in Enclosure 3.:
j TVA requests a 45-day implementation. period for this TS change following issuance. Since'the change is expected to be a resource savings that'is i
applicable during refueling outages, TVA requests that this TS change be 3
approved as soon as possible.
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                                                                  'm 9402150412 940207i.!?                                g;                                                                                  A PDR              ADOCK._05000327                                                                                                          /'t g p                                              PDR. m fj o:    l


                          +.                                     .
+.
+                                                                                       j U.S. - Nuclear Regulatory Comission                                   ]
j
Page 2           .                                                        i February 7, 1994                                                           >
+
i Please direct questions concerning this issue to W. C. Ludwig at.         !
U.S. - Nuclear Regulatory Comission
]
Page 2 i
February 7, 1994 i
Please direct questions concerning this issue to W. C. Ludwig at.
(615) 843-7460.
(615) 843-7460.
Sincerely,
Sincerely,
                                                                                      .}
.}
                                        ' =d                                             l Robert A. Fenech                                                           ,
' =d l
s Sworn to and subs ibed before me                                           !
Robert A. Fenech s
this M day of                 1994 h%f Nota y Public l --                                               ;
Sworn to and subs ibed before me this M day of 1994 h%f l --
1 My Comission Expires         77 1
Nota y Public 1
Enclosures                                                             .'
My Comission Expires 77 1
cc (Enclosures)                                                         .,
Enclosures cc (Enclosures)
Mr. D. E. LaBarge, Project Manager                                   i U.S. Nuclear Regulatory. Comission                               -l One White Flint, North                                               i 11555 Rockville Pike                                                 l Rockville, Maryland 20852-2739                                       :
Mr. D. E. LaBarge, Project Manager i
Mr4 Michael H. Mobley, Director (w/o Enclosures)
U.S. Nuclear Regulatory. Comission
Divieion.of Radiological Health                                   'l 3rd Y1oor L 8 C Annex 61 3hurch Street Pashv111e, Tennessee 37243-1532                                       I NRC Resident Inspector Sequoyah Nuclear Plant l                   2600 Igou. Ferry Road                                                 !
-l One White Flint, North i
b                    Soddy-Daisy, Tennessee 37379-3624                                 .i Regional Administrator U.S. Nuclear Regulatory Comission Region'II 101 Marietta. Street NW, Suite 2900.
11555 Rockville Pike l
Rockville, Maryland 20852-2739 Mr4 Michael H. Mobley, Director (w/o Enclosures)
Divieion.of Radiological Health
'l 3rd Y1oor L 8 C Annex 61 3hurch Street Pashv111e, Tennessee 37243-1532 I
NRC Resident Inspector Sequoyah Nuclear Plant l
2600 Igou. Ferry Road b
Soddy-Daisy, Tennessee 37379-3624
.i Regional Administrator U.S. Nuclear Regulatory Comission Region'II 101 Marietta. Street NW, Suite 2900.
Atlanta, Georgia 30323-2711
Atlanta, Georgia 30323-2711
                                                                                          )
)}}
l}}

Latest revision as of 21:51, 16 December 2024

Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 93-11,replacing Wording in SR 4.7.9.i, Snubber Service Life Program with Wording from Westinghouse Sts,Rev 4a
ML20063G304
Person / Time
Site: Sequoyah  
Issue date: 02/07/1994
From: Fenech R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20063G305 List:
References
NUDOCS 9402150412
Download: ML20063G304 (23)
v • d • e


Text

,

y

  • }o. * ~

, -y g

En i

t Tennessee Valey Autnonty. Post Office Box 2000. &cdy-Daisy; Tennessee 3737S 2000 l

Robert A. Fenech

%ce President. Segacyah Nacicar Plant February 7, 1994 TVA-SQN-TS-93-11 10 CFR 50.90' U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of

)

Docket Nos. 50-327 Tennessee Valley' Authority

)

50-328 1

SEQUOYAH NUCLEAR PLANT (SQN) - TFCHNICAL SPECIFICATION (TS) CHANGE 93-11,

" SNUBBER TRENDING ANALYSIS REQUIREMENTS" In accordance with 10 CFR 50.'90, we are enclosing a requested amendment to Licenses DPR-77 and DPR-79 to change the'TSs of.SQN. Units 1 and 2..

The proposed change'will delete the prescriptive information contained within the Snubber Service Life Program of TS 3.7.9 and replace the wording with that from the NRC. approved Westinghouse Electric Corporation Standard TS, Revision 4a.-

Additionally, changes'are being proposed based upon previously received NRC comments.

The proposed TS change is identified in. Enclosure 1.

The justification

'}

for the proposed TS change is provided in Enclosure 2.

A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 is'provided in Enclosure 3.:

j TVA requests a 45-day implementation. period for this TS change following issuance. Since'the change is expected to be a resource savings that'is i

applicable during refueling outages, TVA requests that this TS change be 3

approved as soon as possible.

- l I

l

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g;

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PDR ADOCK._05000327 A

p PDR.

m fj o:

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+.

j

+

U.S. - Nuclear Regulatory Comission

]

Page 2 i

February 7, 1994 i

Please direct questions concerning this issue to W. C. Ludwig at.

(615) 843-7460.

Sincerely,

.}

' =d l

Robert A. Fenech s

Sworn to and subs ibed before me this M day of 1994 h%f l --

Nota y Public 1

My Comission Expires 77 1

Enclosures cc (Enclosures)

Mr. D. E. LaBarge, Project Manager i

U.S. Nuclear Regulatory. Comission

-l One White Flint, North i

11555 Rockville Pike l

Rockville, Maryland 20852-2739 Mr4 Michael H. Mobley, Director (w/o Enclosures)

Divieion.of Radiological Health

'l 3rd Y1oor L 8 C Annex 61 3hurch Street Pashv111e, Tennessee 37243-1532 I

NRC Resident Inspector Sequoyah Nuclear Plant l

2600 Igou. Ferry Road b

Soddy-Daisy, Tennessee 37379-3624

.i Regional Administrator U.S. Nuclear Regulatory Comission Region'II 101 Marietta. Street NW, Suite 2900.

Atlanta, Georgia 30323-2711

)

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