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{{#Wiki_filter:January 3, 2011  
{{#Wiki_filter:January 3, 2011 MEMEORANDUM TO:           Docket File FROM:                     N. Kalyanam, Project Manager /RA/
 
Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
MEMEORANDUM TO: Docket File FROM: N. Kalyanam, Project Manager /RA/ Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation


==SUBJECT:==
==SUBJECT:==
ARKANSAS NUCLEAR ONE, UNIT 1 - VERBAL AUTHORIZATION OF REQUEST FOR ALTERNATIVE, ANO1-R&R-013 (TAC NO. ME3701)  
ARKANSAS NUCLEAR ONE, UNIT 1 - VERBAL AUTHORIZATION OF REQUEST FOR ALTERNATIVE, ANO1-R&R-013 (TAC NO. ME3701)
 
By letter dated April 5, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100950255), Entergy Operations, Inc. (the licensee), requested U.S. Nuclear Regulatory Commission (NRC) approval of a proposed alternative in Relief Request ANO1-R&R-013 to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) associated with the repair of pressurizer instrumentation penetration, RC-1001 A/B, at the Arkansas Nuclear One, Unit 1 (ANO-1). By letter dated April 12, 2010 (ADAMS Accession No. ML101050404), the licensee submitted its response to the NRC staffs request for additional information regarding the design, repair procedures, inspection, and flaw evaluations of the proposed instrumentation penetration repair.
By letter dated April 5, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100950255), Entergy Operations, Inc. (the licensee), requested U.S. Nuclear Regulatory Commission (NRC) approval of a proposed alternative in Relief Request ANO1-R&R-013 to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) associated with the repair of pressurizer instrumentation penetration, RC-1001 A/B, at the Arkansas Nuclear One, Unit 1 (ANO-1). By letter dated April 12, 2010 (ADAMS Accession No. ML101050404), the licensee submitted its response to the NRC staff's request for additional information regarding the design, repair procedures, inspection, and flaw evaluations of the proposed instrumentation penetration repair.
Due to the immediate need of this relief request, the licensee requested a verbal authorization for the use of the request for alternative, ANO1-R&R-013, to facilitate the plant restart.
Due to the immediate need of this relief request, the licensee requested a verbal authorization for the use of the request for alternative, ANO1-R&R-013, to facilitate the plant restart.
On the basis of its review, the NRC staff concluded that the proposed alternative would provide an acceptable level of quality and safety. In accordance with the Office of Nuclear Reactor Regulation procedure, and pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff granted verbal authorization for the use of Relief Request ANO1-R&R-013 for the repair of pressurizer instrumentation nozzle RC-1001 A/B at ANO-1 as of April 12, 2010, at 13:07 hours.  
On the basis of its review, the NRC staff concluded that the proposed alternative would provide an acceptable level of quality and safety. In accordance with the Office of Nuclear Reactor Regulation procedure, and pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff granted verbal authorization for the use of Relief Request ANO1-R&R-013 for the repair of pressurizer instrumentation nozzle RC-1001 A/B at ANO-1 as of April 12, 2010, at 13:07 hours.
 
The participants from the NRC staff were:
The participants from the NRC staff were:
Mike Markley, NRR/DORL Branch Chief Tim Lupold, NRR/DCI/CPNB Branch Chief John Tsao, NRR/DCI/CPNB Rezai Ali, NRR/DCI/CPNB Kaly N. Kalyanam, NRR/DORL Project Manager  
Mike Markley, NRR/DORL Branch Chief Tim Lupold, NRR/DCI/CPNB Branch Chief John Tsao, NRR/DCI/CPNB Rezai Ali, NRR/DCI/CPNB Kaly N. Kalyanam, NRR/DORL Project Manager


The participants from the licensee were:
The participants from the licensee were:
Dale James (Director, Nuclear Safety Assurance) William Sims (Manager, Major Projects)
Dale James (Director, Nuclear Safety Assurance)
David Bice (Acting Manager, Licensing) Jamie Gobell (Project Manager) Bob Clark (Licensing)
William Sims (Manager, Major Projects)
David Bice (Acting Manager, Licensing)
Jamie Gobell (Project Manager)
Bob Clark (Licensing)
The NRC staff will proceed with completion of the written safety evaluation for the subject relief request. The NRC may ask additional clarification questions to complete its written safety evaluation, if necessary. It is expected that the licensee will provide response to those questions.
The NRC staff will proceed with completion of the written safety evaluation for the subject relief request. The NRC may ask additional clarification questions to complete its written safety evaluation, if necessary. It is expected that the licensee will provide response to those questions.
All other ASME Code, Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.  
All other ASME Code, Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
 
The licensee was also informed that if additional information was required later for the NRC staff to complete the safety evaluation, it will be submitted and the staff expects satisfactory response.
The licensee was also informed that if additional information was required later for the NRC staff to complete the safety evaluation, it will be submitted and the staff expects satisfactory response.  
Docket No. 50-313
 
Docket No. 50-313  


ML103570333 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPNB NRR/LPL4/BC NRR/LPL4/PM NAME NKalyanam JBurkhardt TLupold MMarkley NKalyanam DATE 1/3/11 1/3/11 1/3/11 1/3/11 1/3/11}}
ML103570333 OFFICE   NRR/LPL4/PM       NRR/LPL4/LA       NRR/DCI/CPNB     NRR/LPL4/BC       NRR/LPL4/PM NAME     NKalyanam         JBurkhardt         TLupold           MMarkley         NKalyanam DATE     1/3/11           1/3/11             1/3/11           1/3/11           1/3/11}}

Latest revision as of 05:11, 13 November 2019

Verbal Authorization of Request for Alternative ANO1-R&R-013
ML103570333
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 01/03/2011
From: Kalyanam N
Plant Licensing Branch IV
To:
Plant Licensing Branch IV
Kalyanam N, NRR/DORL/LPL4, 415-1480
References
TAC ME3701
Download: ML103570333 (3)
v • d • e


Text

January 3, 2011 MEMEORANDUM TO: Docket File FROM: N. Kalyanam, Project Manager /RA/

Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT 1 - VERBAL AUTHORIZATION OF REQUEST FOR ALTERNATIVE, ANO1-R&R-013 (TAC NO. ME3701)

By letter dated April 5, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100950255), Entergy Operations, Inc. (the licensee), requested U.S. Nuclear Regulatory Commission (NRC) approval of a proposed alternative in Relief Request ANO1-R&R-013 to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) associated with the repair of pressurizer instrumentation penetration, RC-1001 A/B, at the Arkansas Nuclear One, Unit 1 (ANO-1). By letter dated April 12, 2010 (ADAMS Accession No. ML101050404), the licensee submitted its response to the NRC staffs request for additional information regarding the design, repair procedures, inspection, and flaw evaluations of the proposed instrumentation penetration repair.

Due to the immediate need of this relief request, the licensee requested a verbal authorization for the use of the request for alternative, ANO1-R&R-013, to facilitate the plant restart.

On the basis of its review, the NRC staff concluded that the proposed alternative would provide an acceptable level of quality and safety. In accordance with the Office of Nuclear Reactor Regulation procedure, and pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff granted verbal authorization for the use of Relief Request ANO1-R&R-013 for the repair of pressurizer instrumentation nozzle RC-1001 A/B at ANO-1 as of April 12, 2010, at 13:07 hours.

The participants from the NRC staff were:

Mike Markley, NRR/DORL Branch Chief Tim Lupold, NRR/DCI/CPNB Branch Chief John Tsao, NRR/DCI/CPNB Rezai Ali, NRR/DCI/CPNB Kaly N. Kalyanam, NRR/DORL Project Manager

The participants from the licensee were:

Dale James (Director, Nuclear Safety Assurance)

William Sims (Manager, Major Projects)

David Bice (Acting Manager, Licensing)

Jamie Gobell (Project Manager)

Bob Clark (Licensing)

The NRC staff will proceed with completion of the written safety evaluation for the subject relief request. The NRC may ask additional clarification questions to complete its written safety evaluation, if necessary. It is expected that the licensee will provide response to those questions.

All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.

The licensee was also informed that if additional information was required later for the NRC staff to complete the safety evaluation, it will be submitted and the staff expects satisfactory response.

Docket No. 50-313

ML103570333 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPNB NRR/LPL4/BC NRR/LPL4/PM NAME NKalyanam JBurkhardt TLupold MMarkley NKalyanam DATE 1/3/11 1/3/11 1/3/11 1/3/11 1/3/11

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