ML13184A097
| ML13184A097 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/01/2013 |
| From: | Beltz T Plant Licensing Branch III |
| To: | Millen M Point Beach |
| References | |
| Download: ML13184A097 (3) | |
Text
1 NRR-PMDAPEm Resource From:
Beltz, Terry Sent:
Monday, July 01, 2013 2:00 PM To:
Millen, Michael Cc:
'harv.hanneman@nexteraenergy.com'; Carlson, Robert; Cumblidge, Stephen
Subject:
Point Beach Nuclear Plant, Units 1 and 2 - Draft Requests for Additional Information Regarding Relief Request RR-4L3 (TAC Nos. MF1144 and MF1145)
Attachments:
Point Beach Nuclear Plant, Units 1 and 2 - Draft Requests for Additional Information (EPNB)
Regarding Relief Request RR-4L3 (TAC Nos. MF1144 and MF1145).docx
Dear Mr. Millen:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 19, 2013 (Agencywide Documents Access and Management System Accession No. ML13079A144), NextEra Energy Point Beach, LLC submitted relief request RR-4L3 covering two welds from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, for the Point Beach Nuclear Plant, Units 1 and 2. The request applies to the fourth 10-year inservice inspection interval The NRC staff in the Piping & NE Branch (EPNB) of the Office of Nuclear Reactor Regulatory has identified areas where additional information is needed to complete its review. The draft requests for additional information (RAIs) are provided as an attachment to this e-mail.
You may accept the draft RAIs as a formal Request for Additional Information and provide a response by August 30, 2013. Alternatively, you may request to discuss the contents of this draft 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 U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mail Stop: O-8D15
Hearing Identifier:
NRR_PMDA Email Number:
742 Mail Envelope Properties (Terry.Beltz@nrc.gov20130701135900)
Subject:
Point Beach Nuclear Plant, Units 1 and 2 - Draft Requests for Additional Information Regarding Relief Request RR-4L3 (TAC Nos. MF1144 and MF1145)
Sent Date:
7/1/2013 1:59:51 PM Received Date:
7/1/2013 1:59:00 PM From:
Beltz, Terry Created By:
Terry.Beltz@nrc.gov Recipients:
"'harv.hanneman@nexteraenergy.com'" <harv.hanneman@nexteraenergy.com>
Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov>
Tracking Status: None "Cumblidge, Stephen" <Stephen.Cumblidge@nrc.gov>
Tracking Status: None "Millen, Michael" <Michael.Millen@nexteraenergy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1327 7/1/2013 1:59:00 PM Point Beach Nuclear Plant, Units 1 and 2 - Draft Requests for Additional Information (EPNB) Regarding Relief Request RR-4L3 (TAC Nos. MF1144 and MF1145).docx 20826 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST RR-4L3 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 NEXTERA ENERGY POINT BEACH, LLC DOCKET NUMBERS 50-266 AND 50-301 (TAC NOS. MF1144 AND MF1145)
By letter dated March 19, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13079A144), NextEra Energy Point Beach, LLC (the licensee) submitted relief request RR-4L3 covering two welds from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components for Point Beach Nuclear Power Plant, Units 1 and 2. The request for relief applies to the fourth 10-year inservice inspection (ISI) interval.
In accordance with Title 10 of the Federal Code of Regulations (10 CFR) 50.55a(g)(5)(iii), the licensee submitted the subject requests for relief for limited examinations. The ASME Code requires that 100 percent of the examination volumes, or surface areas, described in Tables IWB-2500 and IWC-2500 be performed during each interval. The licensee stated that 100 percent of the ASME Code-required volumes are impractical to obtain for the welds.
The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review of the relief request.
- 1. While PDI-UT-10 does not allow for coverage credit to be taken beyond the weld centerline, best effort coverage is often calculated and is useful in evaluating inspections where essentially 100 percent code coverage cannot be obtained.
Please discuss if the best effort coverage was calculated and, if so, what is the estimated best effort coverage for each weld?
- 2. The pipes, valves, and welds are all described as being austenitic steels.
Please discuss if any of the pipes or valves are composed of cast stainless steel?
- 3. Both welds are described as being susceptible to stress corrosion cracking. As stress corrosion cracking initiation and propagation are strongly influenced by temperature, an important factor in evaluating welds that are subject to stress corrosion cracking is the operating temperature of the weld.
Please provide the operating temperatures for each of the welds?