ML102780188: Difference between revisions

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| number = ML102780188
| number = ML102780188
| issue date = 10/04/2010
| issue date = 10/04/2010
| title = Fort Calhoun Unit 1 - Email, Draft Request for Additional Information, Relief Request RR-12, from Requirements of ASME Code Case N-722 for Fourth 10-Year Inservice Inspection Interval (ME4541)
| title = Email, Draft Request for Additional Information, Relief Request RR-12, from Requirements of ASME Code Case N-722 for Fourth 10-Year Inservice Inspection Interval (ME4541)
| author name = Wilkins L E
| author name = Wilkins L
| author affiliation = NRC/NRR/DORL/LPLIV
| author affiliation = NRC/NRR/DORL/LPLIV
| addressee name = Hansher B R
| addressee name = Hansher B
| addressee affiliation = Omaha Public Power District
| addressee affiliation = Omaha Public Power District
| docket = 05000285
| docket = 05000285
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=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:From:                      Wilkins, Lynnea Sent:                      Monday, October 04, 2010 5:45 PM To:                        HANSHER, BILL R Cc:                        Burkhardt, Janet; Lent, Susan
 
==Subject:==
DRAFT RAI for Fort Calhoun Station, Unit 1 Relief Request (TAC No. ME4541)
Attachments:                ME4541 RAI.docx
: Bill, By letter dated August 16, 2010, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102300641), Omaha Public Power District (OPPD or the licensee) proposed an alternative to 10 CFR 50.55a(g)(6)(ii)(E) for the Fort Calhoun Station, Unit 1. This requirement defines the inservice inspection frequency of visual examination of the reactor vessel hot leg nozzle to safe end welds in accordance with American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials, and with Nuclear Regulatory Commission (NRC) conditions. The duration of request is for the fourth 10-year ISI interval which ends on September 25, 2013.
The NRC staff has reviewed your submittal and has determined that the information specified in the attached draft Request for Additional Information (RAI) is needed for the staff to complete its evaluation.
In order for the staff to complete its review, we request that you submit your response to the enclosed RAI within 30 days of receipt. Based on previous conversations, I understand that no teleconference is needed to discuss this draft RAI. Please contact me if this is no longer correct.
Thank You Lynnea Wilkins, Project Manager Fort Calhoun Station, Unit 1 Cooper Nuclear Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377}}

Latest revision as of 13:29, 13 November 2019

Email, Draft Request for Additional Information, Relief Request RR-12, from Requirements of ASME Code Case N-722 for Fourth 10-Year Inservice Inspection Interval (ME4541)
ML102780188
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 10/04/2010
From: Lynnea Wilkins
Plant Licensing Branch IV
To: Hansher B
Omaha Public Power District
Wilkins, L E, NRR/DORL/LPL4, 415-1377
References
TAC ME4541
Download: ML102780188 (1)


Text

From: Wilkins, Lynnea Sent: Monday, October 04, 2010 5:45 PM To: HANSHER, BILL R Cc: Burkhardt, Janet; Lent, Susan

Subject:

DRAFT RAI for Fort Calhoun Station, Unit 1 Relief Request (TAC No. ME4541)

Attachments: ME4541 RAI.docx

Bill, By letter dated August 16, 2010, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102300641), Omaha Public Power District (OPPD or the licensee) proposed an alternative to 10 CFR 50.55a(g)(6)(ii)(E) for the Fort Calhoun Station, Unit 1. This requirement defines the inservice inspection frequency of visual examination of the reactor vessel hot leg nozzle to safe end welds in accordance with American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials, and with Nuclear Regulatory Commission (NRC) conditions. The duration of request is for the fourth 10-year ISI interval which ends on September 25, 2013.

The NRC staff has reviewed your submittal and has determined that the information specified in the attached draft Request for Additional Information (RAI) is needed for the staff to complete its evaluation.

In order for the staff to complete its review, we request that you submit your response to the enclosed RAI within 30 days of receipt. Based on previous conversations, I understand that no teleconference is needed to discuss this draft RAI. Please contact me if this is no longer correct.

Thank You Lynnea Wilkins, Project Manager Fort Calhoun Station, Unit 1 Cooper Nuclear Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377