ML20100P954: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
| page count = 2
| project = TAC:M81758
| stage = Other
}}
}}


=Text=
=Text=
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        ~h_Q M                                 De r 'sper Power sianon Shl p nggPA 1MU.0004 JOHN D $1EBER                                                         Jantlary 27, 1992 Wes Prewtont - Nuclear Group U. S. Nuclear Regulatory Commission Attn:- Document Control Desk Washington, DC 20555
~h_Q M r 'sper Power sianon De Shl p nggPA 1MU.0004 JOHN D $1EBER Jantlary 27, 1992 Wes Prewtont - Nuclear Group U.
S. Nuclear Regulatory Commission Attn:- Document Control Desk Washington, DC 20555


==Subject:==
==Subject:==
Beaver Valley Power Station; Unit No. 2 Docket No. 50-412, License No. ilPF-73 Additional Information To Support Operating License Change Request No. 57 (TAC No. M81758)
Beaver Valley Power Station; Unit No. 2 Docket No. 50-412, License No. ilPF-73 Additional Information To Support Operating License Change Request No. 57 (TAC No. M81758)
The attached information is provided in response to a request for additional information from NRC Project Manager A. W. DeAgazio on January 16,               1992,     concerning the radiological consequences of a Locked . Rotor Accident.                   Attachment A, entitled " Assessment Of The Donos In The Unit 2 Control Room Duc To A Locked Rotor Accident At Unit 2 Assuming 18% Failed Fuel", is provided in accordance with the NRC request.                     This analysis is based on the use of new X/Q values developed in accordance with NUREG/CR-5055, and the results support our conclusion that the control room doses are within acceptable limits.
The attached information is provided in response to a request for additional information from NRC Project Manager A.
The       analysis assumes that the control room operators will
W. DeAgazio on January 16,
-manually initiate control room isolation 30 minutes after the start of the accident.                     Existing emergency procedures include steps that assure operators will take appropriate actions to perform this function within this time period.
: 1992, concerning the radiological consequences of a Locked. Rotor Accident.
Attachment B provides additional UFSAR changes to address the results obtained in Attachment A.                           These UFSAR changes are rrovided for information purposes and will be incorporated in a futace UFSAR update.
Attachment A,
Sincerely, e   >
entitled " Assessment Of The Donos In The Unit 2 Control Room Duc To A Locked Rotor Accident At Unit 2
                                                                          . D. Sieber                       >
Assuming 18% Failed Fuel", is provided in accordance with the NRC request.
cc:     Mr. J. Beall, Sr. Resident Inspector                                                             !
This analysis is based on the use of new X/Q values developed in accordance with NUREG/CR-5055, and the results support our conclusion that the control room doses are within acceptable limits.
1 Mr.-T. T. Martin, NRC Region-I Administrator                                               7 Mr. A. W. DeAgazio, Project Manager
The analysis assumes that the control room operators will
                                                                                                  % 'h jv h Mr. T. M. Gerusky, Director BRP/ DER                                                         y Mr. R. Janati, BRP/ DER                                                             -
-manually initiate control room isolation 30 minutes after the start of the accident.
I Mr. M. L. Bowling (VEPCO)
Existing emergency procedures include steps that assure operators will take appropriate actions to perform this function within this time period.
( c .~ p -
Attachment B
9202040271 920127 PDR     ADOCK05000g2 P
provides additional UFSAR changes to address the results obtained in Attachment A.
These UFSAR changes are rrovided for information purposes and will be incorporated in a futace UFSAR update.
Sincerely, e
D.
Sieber cc:
Mr. J.
Beall, Sr. Resident Inspector 1
Mr.-T.
T.
Martin, NRC Region-I Administrator 7
Mr.
A.
W.
DeAgazio, Project Manager
'h h Mr. T. M. Gerusky, Director BRP/ DER
% jv y
Mr. R. Janati, BRP/ DER I
Mr. M.
L. Bowling (VEPCO)
( c.~
p -
9202040271 920127 ADOCK05000g2 PDR P


s 4   ,
s 4
ATTACHMENT A Beaver Valley Power Station, Unit Nr.2 Additionalinformation Proposed Technical Specification Change No. 57 Assessment Of The Doses In The Unit 2 Control Room Due To A Locked Rotor Accident At Unit 2 Assuming 18% Failed Fuel l
ATTACHMENT A Beaver Valley Power Station, Unit Nr.2 Additionalinformation Proposed Technical Specification Change No. 57 Assessment Of The Doses In The Unit 2 Control Room Due To A Locked Rotor Accident At Unit 2 Assuming 18% Failed Fuel l
          .-.}}
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Latest revision as of 05:25, 13 December 2024

Forwards Rev 0 to ERS-MPD-91-035, Assessment of Doses in Unit 2 Control Room Due to Locked Rotor Accident at Unit 2 Assuming 18% Failed Fuel
ML20100P954
Person / Time
Site: Beaver Valley
Issue date: 01/27/1992
From: Sieber J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20100P955 List:
References
TAC-M81758, NUDOCS 9202040271
Download: ML20100P954 (2)


Text

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~h_Q M r 'sper Power sianon De Shl p nggPA 1MU.0004 JOHN D $1EBER Jantlary 27, 1992 Wes Prewtont - Nuclear Group U.

S. Nuclear Regulatory Commission Attn:- Document Control Desk Washington, DC 20555

Subject:

Beaver Valley Power Station; Unit No. 2 Docket No. 50-412, License No. ilPF-73 Additional Information To Support Operating License Change Request No. 57 (TAC No. M81758)

The attached information is provided in response to a request for additional information from NRC Project Manager A.

W. DeAgazio on January 16,

1992, concerning the radiological consequences of a Locked. Rotor Accident.

Attachment A,

entitled " Assessment Of The Donos In The Unit 2 Control Room Duc To A Locked Rotor Accident At Unit 2

Assuming 18% Failed Fuel", is provided in accordance with the NRC request.

This analysis is based on the use of new X/Q values developed in accordance with NUREG/CR-5055, and the results support our conclusion that the control room doses are within acceptable limits.

The analysis assumes that the control room operators will

-manually initiate control room isolation 30 minutes after the start of the accident.

Existing emergency procedures include steps that assure operators will take appropriate actions to perform this function within this time period.

Attachment B

provides additional UFSAR changes to address the results obtained in Attachment A.

These UFSAR changes are rrovided for information purposes and will be incorporated in a futace UFSAR update.

Sincerely, e

D.

Sieber cc:

Mr. J.

Beall, Sr. Resident Inspector 1

Mr.-T.

T.

Martin, NRC Region-I Administrator 7

Mr.

A.

W.

DeAgazio, Project Manager

'h h Mr. T. M. Gerusky, Director BRP/ DER

% jv y

Mr. R. Janati, BRP/ DER I

Mr. M.

L. Bowling (VEPCO)

( c.~

p -

9202040271 920127 ADOCK05000g2 PDR P

s 4

ATTACHMENT A Beaver Valley Power Station, Unit Nr.2 Additionalinformation Proposed Technical Specification Change No. 57 Assessment Of The Doses In The Unit 2 Control Room Due To A Locked Rotor Accident At Unit 2 Assuming 18% Failed Fuel l

-.