ML13350A098

12/16/13 E-mail from B.Shingleton to R.Guzman Clarification of Upper Shelf Energy Values for ONS Pressure-Temperature Curve 54 EFPY LAR

ML13350A098
Person / Time
Site:	Oconee
Issue date:	12/16/2013
From:	Shingleton B Duke Energy Carolinas
To:	Guzman R V Plant Licensing Branch II
Guzman R V
References
TAC MF0763, TAC MF0764, TAC MF0765
Download: ML13350A098 (5)

Text

From:Shingleton, Boyd To:Guzman, Richard Cc:Wasik, Christopher J

Subject:

ONS 54 EFPY PT Curve LAR - additonal information.

Date:Monday, December 16, 2013 9:18:36 AM Attachments:Response for NRC on Unirrad USE Values-ONS RPV Lower Regions.pdf Rich, Information requested by the NRC staff attached. Boyd ShingletonONS Regulatory Affairs864-873-4716 From: Guzman, Richard [1]

Sent: Wednesday, December 11, 2013 8:28 AM To: Shingleton, Boyd

Subject:

RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals Boyd, Just to clarify my previous message-the specific information that the staff is requesting is the initial USE and the 54 EFPY USE for the RPV lower head materials having fluences greater than 10 17 n/cm 2.

Thanks, Rich From: Shingleton, Boyd [mailto:Boyd.Shingleton@duke-energy.com

] Sent: Wednesday, December 11, 2013 7:50 AM To: Guzman, Richard

Subject:

RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals OK Boyd ShingletonONS Regulatory Affairs864-873-4716 From: Guzman, Richard

[2]

Sent: Wednesday, December 11, 2013 7:43 AM To: Shingleton, Boyd

Subject:

RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals Boyd, A call is not necessary.

You can provide me the initial USE value based on material reports for the RPV lower head materials having fluences greater than 10 17 n/cm 2 - via email is fine. Please confirm the value is non-proprietary and I can then add the associated email response to ADAMS as an official agency record; the reviewer can then reference it in the staff's SE. Thanks, Rich

Rich GuzmanSr. Project Manager NRR/DORL US NRC301-415-1030

From: Shingleton, Boyd [mailto:Boyd.Shingleton@duke-energy.com

] Sent: Tuesday, December 10, 2013 3:50 PM To: Guzman, Richard

Subject:

RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals Rich, Talked to AREVA. The USE at 54 EFPY will be above 50 ft-lbs. They did not use Options 1 and 2 (described below), they used the material report. Let's set up a call with the reviewer and confirm we are not missing the point. Also, need to determine whether the response will need to be docketed.

Boyd ShingletonONS Regulatory Affairs 864-873-4716 From: Guzman, Richard

[3]

Sent: Thursday, December 05, 2013 4:33 PM To: Newman, Stephen; Shingleton, Boyd

Subject:

RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals

• • • This is an EXTERNAL email. Exercise caution. DO NOT open attachments or click links from unknown senders or unexpected email. ***Boyd, As we discussed, based on his preliminary review of the 11/29/13 supplemental response, the technical reviewer has determined that the information regarding the upper-shelf energy evaluation for the RPV lower head is not complete.

Below is a description of thefollow-on information request. We can support a teleconference to discuss in more detail if needed. The November 29, 2013, upper-shelf energy (USE) evaluation for the RPV lower head materials having fluences greater than 10 17 n/cm 2 is incomplete.

The licensee states that only USE decreases.

Without referencing the initial USE values for the RPV lower head materials, it is not known whether or not the USE at 54 EFPY (considering USE decreases) will be above 50 ft-lbs. The technical reviewer notes that there are two options to consider if the initial USE values associated with the lower head materials cannot be located: (1) using generic initial USE values applicable to Oconee RPV lower heads, or (2) using the equivalent margins analysis of ASME Code,Section XI, Appendix K, supplemented by RG 1.161, "Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 ft-lb." We can also discuss these approaches, if applicable, during the teleconference call.

Thanks, Rich Rich GuzmanSr. Project Manager NRR/DORL US NRC301-415-1030

From: Newman, Stephen [mailto:Stephen.Newman@duke-energy.com

] Sent: Friday, November 29, 2013 5:05 AM To: Guzman, Richard Cc: Wasik, Christopher J; Shingleton, Boyd; Severance, Sandra N

Subject:

Oconee Nuclear Station _ NRC Commitment and RAI Submittals Richard, Please find attached two submittals associated with a reactor vessels internals inspection program LAR commitment and a PT Limit Curve LAR RAI. Both letters are dated 11/29/13.

Please let me know that you received them intact.

Best Regards, Stephen C. NewmanSr. Engineer, Regulatory AffairsOconee Nuclear Station(864) 873-4388

NRC email information request received by Duke Energy: Further clarification Boyd Shingleton From: Guzman, Richard [mailto:Richard.Guzman@nrc.gov

] Sent: Wednesday, December 11, 2013 8:28 AM To: Shingleton, Boyd

Subject:

RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals Boyd, Just to clarify my previous message-the specific information that the staff is req uesting is the initial USE and the 54 EFPY USE for the RPV lower head materials having fluences greater than 10 17 n/cm 2. Thanks, Rich From: Shingleton, Boyd [mailto:Boyd.Shingleton@duke-energy.com

] Sent: Wednesday, December 11, 2013 7:50 AM To: Guzman, Richard

Subject:

RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals OK Boyd Shingleton From: Guzman, Richard [4]

Sent: Wednesday, December 11, 2013 7:43 AM To: Shingleton, Boyd

Subject:

RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals Boyd, A call is not necessary. You can provide me the initial USE value based on material reports for the RPV lower head materials having fluences greater than 10 17 n/cm 2 - via email is fine. Please confirm the value is non-proprietary and I can then add the associated email response to ADAMS as an official agency record; the reviewer can then reference it in the staff's SE.

Thanks, Rich Rich Guzman Sr. Project Manager NRR/DORL US NRC 301-415-1030

Response: In response to the NRC email above sent to Duke Energy, the following Tables with the unirradiated CvUSE values and the 54 EFPY CvUSE per Regulatory Guide 1.99 Revision 2 for the Oconee Nuclear Stations (ONS) RPV lower region materials having fluences greater than 10 17 n/cm 2 are provided. The information is considered non-proprietary.

ONS-1 Non-Traditional Beltline RPV Material CvUSE Values Non-Traditional Beltline RPV Materials Unirradiated CvUSE (ft-lbs) Method for Determining CvUSE CvUSE at 54 EFPY (ft-lbs) Dutchman Forging 58.5 Measured (65% Long. CVN data)* 53.5 Lower Shell to Dutchman Forging Circ. Weld 64 Generic** 53.8 ONS-2 Non-Traditional Beltline RPV Material CvUSE Values Non-Traditional Beltline RPV Materials Unirradiated CvUSE (ft-lbs) Method for Determining CvUSE CvUSE at 54 EFPY (ft-lbs) Dutchman Forging 67.3 Measured (65% Long. CVN data)* 61.5 Lower Shell to Dutchman Forging Circ. Weld 64 Generic** 52.3 ONS-3 Non-Traditional Beltline RPV Material CvUSE Values Non-Traditional Beltline RPV Materials Unirradiated CvUSE (ft-lbs) Method for Determining CvUSE CvUSE at 54 EFPY (ft-lbs) Dutchman Forging 59.2 Measured (65% Long. CVN data)* 51.3 Lower Shell to Dutchman Forging Circ. Weld 64 Generic** 55.6

• Data taken from actual RPV material test report where limited CVN test data were performed at a single test temperature to confirm that at least 30 ft-lbs was obtained for the material. CVN test data does not represent the impact energy upper-shelf (i.e., >95% shear), a mean value taken at a reduced percent shear fracture is a conservative estimate of the CvUSE in that the impact energy will increase as the percent shear fracture increases.

• • Charpy impact test data not available; conservative generic value for that class of material is used. The class of material is determined for base metals by the material specification and for weld metal by the type of welding flux (i.e., Linde 80 or others).