Letter Sequence Acceptance Review |
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MONTHYEARML15103A2882015-04-0909 April 2015
Presentation on Potential Relief Request About Pressure Boundary Leakage on Reactor Coolant Pump 2A Pipe Nozzle
Project stage: Request
ML15104A8102015-04-14014 April 2015
NRR E-mail Capture - Palo Verde, Unit 3 - Request for Information Regarding Pressure Boundary Leakage in RCP 2A Pressure Instrumentation Nozzle (MF6083)
Project stage: RAI
ML15110A4792015-04-15015 April 2015
NRR E-mail Capture - Palo Verde, Unit 3 - Information Regarding Pressure Boundary Leakage in Reactor Coolant Pump 2A Pressure Instrumentation Nozzle for April 15, 2015 Phone Call (MF6083)
Project stage: Other
ML15113A6362015-04-22022 April 2015
Acceptance of Relief Request 53
Project stage: Acceptance Review
ML15113A4972015-04-23023 April 2015
Request for Additional Information Regarding Relief Request 53
Project stage: RAI
ML15117A0422015-04-29029 April 2015
Memorandum to File Summarizing 4/24/15 Telephone Conference Granting Verbal Relief for Relief Request 53, Request for Approval of an Alternative to ASME Code, Section XI, Requirements for Flaw Removal
Project stage: Approval
ML15198A2422015-07-15015 July 2015
Transmittal of Updated Proprietary Documents for Relief Request 53
Project stage: Request
ML15198A2242015-07-15015 July 2015
Transmittal of Non-Proprietary Documents for Relief Request 53
Project stage: Request
ML15198A2262015-07-15015 July 2015
Attachment 3: Calculation CN-PAFM-15-20-NP, Rev. 2, Palo Verde Unit 3 RCS Cold Leg Alloy 600 Small Bore Nozzle Repair Transient Stress and Fracture Mechanics Evaluation for One Cycle Operation
Project stage: Request
ML15198A2272015-07-15015 July 2015
Attachment 4: Calculation TR-FSE-15-2-NP, Rev. 1, Palo Verde Nuclear Generating Station Unit 3 Evaluation of Potential Loose Part - Reactor Coolant Pump Instrument Nozzle Weld Fragment
Project stage: Request
ML15198A2252015-07-15015 July 2015
Attachment 2: Calculation CN-MRCDA-15-13-NP, Qualification of Palo Verde Unit 3 Reactor Coolant Pump Replacement Instrumentation Nozzle
Project stage: Request
ML15209A6662015-08-10010 August 2015
Request for Withholding Information from Public Disclosure - 7/10/15 Affidavit Executed by J. Gresham, Westinghouse, Re Five Proprietary Documents in Support of Relief Request 53 - Approval of an Alternative to Flaw Removal (TAC No
Project stage: Withholding Request Acceptance
ML15238B6612015-09-15015 September 2015
Relief Request 53, Alternative to ASME Code Section XI Requirements Related to Flaw Removal
Project stage: Approval
2015-04-29
[Table View] |
Text
From:
Watford, Margaret To:
Thomas.N.Weber@aps.com Cc:
Carl.stephenson@aps.com; Delbert.Elkinton@aps.com
Subject:
Palo Verde Nuclear Generating Station, Unit 3 - Acceptance of Relief Request 53 (TAC No. MF6083)
Date:
Wednesday, April 22, 2015 5:08:00 PM
- Tom,
By letter dated April 17, 2015, Arizona Public Service Company submitted Relief Request 53 for the repair of the differential pressure instrumentation nozzle on the suction side of the 2A reactor coolant pump at Palo Verde Nuclear Generating Station, Unit 3. The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the request has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The NRC staff has reviewed your request and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence.
If you have any questions, please contact me.
Margaret M. Watford, Project Manager Plant Licensing Branch IV 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
