ML13036A300

NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Draft Request for Additional Information (Second Round) Reactor Vessel Internals Inspection Plan Review (TAC Nos. ME8235 & ME8236)

ML13036A300
Person / Time
Site:	Point Beach
Issue date:	01/31/2013
From:	Beltz T Plant Licensing Branch III
To:	Millen M Point Beach
References
TAC ME8235, TAC ME8236
Download: ML13036A300 (4)

Text

NRR-PMDAPEm Resource From: Beltz, Terry Sent: Thursday, January 31, 2013 11:02 AM To: 'Millen, Michael' Cc: 'Hanneman, Harv'; Carlson, Robert; Purtscher, Patrick

Subject:

Point Beach Nuclear Plant, Units 1 and 2 - Draft Request for Additional Information (Second Round) re: Reactor Vessel Internals Inspection Plan Review (TAC Nos. ME8235 & ME8236)

Attachments: Request for Additional Information - Second Round (ME8235 & ME8236).docx

Dear Mr. Millen:

By letter dated December 19, 2011 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML11354A301), NextEra Energy Point Beach, LLC (the licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC) a reactor vessel internals (RVI) inspection plan for the Point Beach Nuclear Plant, Units 1 and 2. In a letter dated August 16, 2012 (ADAMS Accession No. ML12229A580), the licensee responded to the NRC staffs first round of requests for additional information (RAIs).

The NRC staff from the Vessel and Internals Integrity Branch of the Office of Nuclear Reactor Regulation has reviewed the responses to the first round of RAIs and requests additional information as described in the attached document.

You may accept this as a formal request for additional information and respond to the questions by March 15, 2013. Alternatively, you may request to discuss the content of this RAI with the NRC staff in a conference call, including any change to the proposed response date.

Please let me know if you have any questions or concerns.

Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov 1

Hearing Identifier: NRR_PMDA Email Number: 599 Mail Envelope Properties (87B1F1BDFE5A554CA9DC5EAA75EB6D0DC63D8738ED)

Subject:

Point Beach Nuclear Plant, Units 1 and 2 - Draft Request for Additional Information (Second Round) re: Reactor Vessel Internals Inspection Plan Review (TAC Nos. ME8235 &

ME8236)

Sent Date: 1/31/2013 11:02:11 AM Received Date: 1/31/2013 11:02:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients:

"'Hanneman, Harv'" <Harv.Hanneman@nexteraenergy.com>

Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov>

Tracking Status: None "Purtscher, Patrick" <Patrick.Purtscher@nrc.gov>

Tracking Status: None

"'Millen, Michael'" <Michael.Millen@nexteraenergy.com>

Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 1349 1/31/2013 11:02:00 AM Request for Additional Information - Second Round (ME8235 & ME8236).docx 34531 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION (SECOND ROUND)

REGARDING THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 REACTOR VESSEL INTERNALS INSPECTION PLAN REVIEW NEXTERA ENERGY POINT BEACH, LLC DOCKET NOS. 50-266 AND 50-301 (TAC NOS. ME8235 AND ME8236)

By letter dated December 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11354A301), NextEra Energy Point Beach, LLC (the licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC) a reactor vessel internals (RVI) inspection plan for the Point Beach Nuclear Plant (PBNP), Units 1 and 2. In a letter dated August 16, 2012 (ADAMS Accession No. ML12229A580), the licensee responded to the NRC staffs first round of requests for additional information (RAIs).

The NRC staff from the Vessel and Internals Integrity Branch of the Office of Nuclear Reactor Regulation has reviewed the responses to the first round of RAIs and requests additional information as described below.

RAI-1a In response to RAI-1, Item 4, the licensee stated:

The PBNP RVI components are bounded by the typical Westinghouse PWR internals components outlined in MRP-227-A and the applicable referenced documents, including MRP-191 and MRP-232. The PBNP reactor vessel internals inspection program was written to comply with MRP-227-A. No changes in the inspection requirements are being proposed at this time in that the PBNP inspection program complies with MRP-227-A as indicated above.

The licensee did not mention that an extended power uprate (EPU) for each unit was approved by the NRC on May 5, 2011. The MRP has stated that the inspection recommendations are applicable to all U.S. PWR [pressurized water reactor] operating plants as of May 2007. In discussions with the MRP, the MRP indicated that EPUs after 2007 were not considered during the development of the MRP-227 recommendations.

The NRC staff reviewed the licensees 2009 submittal for the EPU (ADAMS Accession No. ML091250566) and noted several instances for which the stress, fatigue usage, and neutron fluence values provided in the EPU evaluation appear to exceed the screening values of MRP-191 and, therefore, may not be bounded by the assumptions made in development of MRP-227-A. The following examples are noted:

1. Table 2.2.3-3 of the 2009 EPU submittal lists the stresses and fatigue usage factors (CUF) of different core support structures. For the upper core plate alignment pins, the

document includes values of 51.48 ksi for stress and 0.30 for the CUF before the EPU, and 38.507 ksi for stress and 0.583 for the CUF after the EPU with an ASME Code-allowable stress intensity of 34.44 ksi.

The licensees August 16, 2012, response to RAI-1, Item 2, lists that component as having an effective stress < 30 ksi, matching the stress for that component in MRP-191.

2. Section 2.1.4.2.2 of the 2009 EPU submittal lists the maximum fast neutron fluence (E >

1.0 MeV) for 54 EFPY as 8.83E+22 n/cm2 for Unit 1 and 8.77E+22 n/cm2 for Unit 2, whereas MRP-191 states that the maximum fluence values for any internal component is 5E+22 n/cm2.

Requested Information The NRC staff requests the licensee review its current licensing basis (CLB), including the 2009 EPU submittal, and list all components that are not bounded by the assumptions on stress, temperature, and fluence contained in MRP-191, MRP-232, and MRP-227-A.

Evaluate the need for changes to the inspection requirements and/or inspection frequency for any components that are not bounded by the screening values of fluence, temperature, and stress. Describe the process used to perform these evaluations. Provide a technical justification for either changing or not changing the inspection requirements and/or inspection frequency.

RAI-8

In the December 19, 2011, submittal, there is no discussion of Action Item 7 from MRP-227-A. In Section 3.3.7 of the SE for MRP-227, the NRC staff stated that the licensee shall develop a plant-specific analysis to demonstrate that components manufactured from CASS materials will maintain their functions during the period of extended operation. This requirement applies to all susceptible components for which the licensee has determined aging management is required, which includes components designated as expansion and existing as well as the primary category.

Requested Information The NRC staff requests that the licensee provide a list of all reactor vessel internal components manufactured from CASS materials for Point Beach, Units 1 and 2, along with the plant-specific analysis required by Action Item 7. Provide plant-specific aging management requirements for any components that are not already covered by the Primary, Expansion, or Existing Programs, categories under MRP-227-A.