ML11108A034: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(2 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 05/15/2011
| issue date = 05/15/2011
| title = Resumption of Review of the Proposed Extended Power Uprate Amendment (TAC Nos. MD5262, MD5263, and MD5264) (TS-431)
| title = Resumption of Review of the Proposed Extended Power Uprate Amendment (TAC Nos. MD5262, MD5263, and MD5264) (TS-431)
| author name = Leeds E J
| author name = Leeds E
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name = Swafford P D
| addressee name = Swafford P
| addressee affiliation = Tennessee Valley Authority
| addressee affiliation = Tennessee Valley Authority
| docket = 05000259, 05000260, 05000296
| docket = 05000259, 05000260, 05000296
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 May 15, 2011 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 -RESUMPTION OF REVIEW OF THE PROPOSED EXTENDED POWER UPRATE AMENDMENT (TAC NOS. MD5262, MD5263, AND MD5264) (TS-431)  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 15, 2011 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
 
==SUBJECT:==
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - RESUMPTION OF REVIEW OF THE PROPOSED EXTENDED POWER UPRATE AMENDMENT (TAC NOS. MD5262, MD5263, AND MD5264) (TS-431)


==Dear Mr. Swafford:==
==Dear Mr. Swafford:==


By letter dated September 18, 2009, I informed you that, because of the containment accident pressure (CAP) credit issue, additional time was warranted to develop additional review criteria to ensure the technical adequacy of the extended power uprate (EPU) applications for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The development of these review criteria is essential to provide the technical and regulatory consistency, as well as the schedule certainty needed to complete this review. The CAP credit review criteria were developed several months ago and presented to the Commission via SECY-11-0014, "Use of Containment Accident Pressure in Analyzing Emergency Core Cooling System and Containment Heat Removal System Pump Performance in Postulated Accidents" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 102780586).
By letter dated September 18, 2009, I informed you that, because of the containment accident pressure (CAP) credit issue, additional time was warranted to develop additional review criteria to ensure the technical adequacy of the extended power uprate (EPU) applications for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The development of these review criteria is essential to provide the technical and regulatory consistency, as well as the schedule certainty needed to complete this review.
The review criteria have been endorsed by the Commission via a memo, "Staff Requirements  
The CAP credit review criteria were developed several months ago and presented to the Commission via SECY-11-0014, "Use of Containment Accident Pressure in Analyzing Emergency Core Cooling System and Containment Heat Removal System Pump Performance in Postulated Accidents" (Agencywide Documents Access and Management System (ADAMS)
-SECY-11-014  
Accession No. ML102780586). The review criteria have been endorsed by the Commission via a memo, "Staff Requirements - SECY-11-014 - Use of Containment Accident Pressure in Analyzing Emergency Core Cooling System and Containment Heat Removal System Pump Performance in Postulated Accidents," dated March 15, 2011 (ADAMS Accession No. ML110740154). Thus, the Nuclear Regulatory Commission (NRC) staff is prepared to resume the review.
-Use of Containment Accident Pressure in Analyzing Emergency Core Cooling System and Containment Heat Removal System Pump Performance in Postulated Accidents," dated March 15, 2011 (ADAMS Accession No. ML 110740154).
 
Thus, the Nuclear Regulatory Commission (NRC) staff is prepared to resume the review.
P. Swafford                                 - 2 In my letter I also stated that the NRC staff will focus on closing out the other outstanding technical issues associated with the EPU amendment applications. I trust that your staff had been in frequent contact with the BFN Project Manager, Mr. Christopher Gratton, to obtain up-to-date status of all those other issues of this EPU review.
P. Swafford -In my letter I also stated that the NRC staff will focus on closing out the other outstanding technical issues associated with the EPU amendment applications.
Should you have any questions, please feel free to contact Mr. Gratton at (301) 415-1055.
I trust that your staff had been in frequent contact with the BFN Project Manager, Mr. Christopher Gratton, to obtain up-to-date status of all those other issues of this EPU review. Should you have any questions, please feel free to contact Mr. Gratton at (301) 415-1055.
Sincerely,
Sincerely, Office of Nuclear Reactor Regulation Docket No. 50-259, 50-260, and 50-296 cc: Listserv P. Swafford -In my letter I also stated that the NRC staff will focus on closing out the other outstanding technical issues associated with the EPU amendment applications.
                                              ~:::
I trust that your staff had been in frequent contact with the BFN Project Manager, Mr. Christopher Gratton, to obtain up-to-date status of all those other issues of this EPU review. Should you have any questions, please feel free to contact Mr. Gratton at (301) 415-1055.
Office of Nuclear Reactor Regulation Docket No. 50-259, 50-260, and 50-296 cc: Listserv
Sincerely, IRA! Eric J. Leeds, Director Office of Nuclear Reactor Regulation Docket No. 50-259, 50-260, and 50-296 cc: Listserv Distribution:
 
PUBLIC LPL2-2 RtF RidsOgcRp Resource RidsNrrDorlLpl2-2 Resource RidsNrrDss RidsNrrDra RidsRgn2MailCenter Resource RidsN rrPMBrownsF erry RidsNrrDe RidsNrrDorl RidsNrrDssScvb RidsAcrsAcnw MailCTR Resource RidsNrrOd RidsNrrDraApla RidsN rrDraAfpb SBush-Goddaid, EDO Rgn II TAlexion, NRR RLobel, NRR MStutzke, NRR ADAMS Accession No.: ML11108A034 OFFICE LPL2-2/PM LPL2-2/LA LPL2*2/BC DBroaddus scvB/Be RDennig DSS/D DORUD JGiitter 05/05111 05/06/11 05/10/11 OFFICIAL RECORD COPY NRRtD ELeeds 05/15/11}}
ML11108A034 OFFICE       LPL2-2/PM       LPL2-2/LA       LPL2*2/BC         scvB/Be         DSS/D           DORUD   NRRtD DBroaddus        RDennig                          JGiitter ELeeds 05/05111         05/06/11                         05/10/11 05/15/11}}

Latest revision as of 03:39, 11 March 2020

Resumption of Review of the Proposed Extended Power Uprate Amendment (TAC Nos. MD5262, MD5263, and MD5264) (TS-431)
ML11108A034
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 05/15/2011
From: Leeds E
Office of Nuclear Reactor Regulation
To: Swafford P
Tennessee Valley Authority
Gratton C
References
TAC MD5262, TAC MD5263, TAC MD5264, TS-431
Download: ML11108A034 (3)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 15, 2011 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - RESUMPTION OF REVIEW OF THE PROPOSED EXTENDED POWER UPRATE AMENDMENT (TAC NOS. MD5262, MD5263, AND MD5264) (TS-431)

Dear Mr. Swafford:

By letter dated September 18, 2009, I informed you that, because of the containment accident pressure (CAP) credit issue, additional time was warranted to develop additional review criteria to ensure the technical adequacy of the extended power uprate (EPU) applications for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The development of these review criteria is essential to provide the technical and regulatory consistency, as well as the schedule certainty needed to complete this review.

The CAP credit review criteria were developed several months ago and presented to the Commission via SECY-11-0014, "Use of Containment Accident Pressure in Analyzing Emergency Core Cooling System and Containment Heat Removal System Pump Performance in Postulated Accidents" (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML102780586). The review criteria have been endorsed by the Commission via a memo, "Staff Requirements - SECY-11-014 - Use of Containment Accident Pressure in Analyzing Emergency Core Cooling System and Containment Heat Removal System Pump Performance in Postulated Accidents," dated March 15, 2011 (ADAMS Accession No. ML110740154). Thus, the Nuclear Regulatory Commission (NRC) staff is prepared to resume the review.

P. Swafford - 2 In my letter I also stated that the NRC staff will focus on closing out the other outstanding technical issues associated with the EPU amendment applications. I trust that your staff had been in frequent contact with the BFN Project Manager, Mr. Christopher Gratton, to obtain up-to-date status of all those other issues of this EPU review.

Should you have any questions, please feel free to contact Mr. Gratton at (301) 415-1055.

Sincerely,

~:::

Office of Nuclear Reactor Regulation Docket No. 50-259, 50-260, and 50-296 cc: Listserv

ML11108A034 OFFICE LPL2-2/PM LPL2-2/LA LPL2*2/BC scvB/Be DSS/D DORUD NRRtD DBroaddus RDennig JGiitter ELeeds 05/05111 05/06/11 05/10/11 05/15/11

Retrieved from "https://kanterella.com/w/index.php?title=ML11108A034&oldid=2551006"