ML061040590
| ML061040590 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/04/2006 |
| From: | Bauer S Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-05457-SAB/TNW/RJR, WCAP-16524-NP | |
| Download: ML061040590 (3) | |
Text
10 CFR 50.55a LiA4 L A
suabsidiar of Pinnacle l} test Capital corporation Scott A. Baueri Department Leader Regulatory Affairs Tel. 623-393-5978 Mail Station 7636 Palo Verde Nuclear Fax 623-393-5442 P0 Box 52034 Generating Station e-mail: Scott.Bauer@aps.com Phoenix, Arizona 85072-2034 I 02-05457-SABITNW/RJR April 4, 2006 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Docket No. STN 50-529 Reactor Vessel Material Surveillance Capsule at 2300 Pursuant to 10 CFR 50, Appendix H, this letter transmits the attached report of the analysis of a PVNGS Unit 2 reactor vessel material surveillance capsule. The report presents the results of the examination of the Unit 2 surveillance capsule removed from the 2300 location. This is the second capsule to be removed from the reactor in accordance with the reactor vessel material surveillance program identified in Technical Requirements Manual Surveillance Requirement TSR 3.4.200.1 and the PVNGS Updated Final Safety Analysis Report (UFSAR), Section 5.3.1.6.6.
The 230° capsule was removed from the reactor vessel during Unit 2's 1 1th refueling outage after 14.35 effective full power years (EFPY) of plant operation (exposure).
Westinghouse Science and Technology Center Hot Cell Facility performed the post irradiation mechanical testing of the Charpy V-notch impact, tensile and precracked Charpy V-notch surveillance specimens. The removal of the capsule was performed in accordance with the PVNGS UFSAR Table 5.3-19, which lists capsule number 5, vessel location 2300, as having a withdrawal time of between 12 and 15 EFPY.
The surveillance results presented in the enclosed report do not change the value c~f RT(PTS;) calculated for Palo Verde pursuant to 10 CFR 50.55a and IWA-6230 of Section Xl of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 1992 Edition, 1992 Addenda. APS completed Unit 2's Refueling Outage A member of the STAiRS (Strategic Teaming and Resource Sharing) Alliance Ctllaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- South Texas Project
- Wolf Creek
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Reactor Vessel Material Surveillance Capsule at 2300 Page 2 on May 20, 2005. No changes to the current PVNGS Technical Specification are required as a result of this analysis.
This letter does not make any commitments to the NRC. Please contact Thomas N.
Weber at (623) 393-5764 if you have any questions or require additional information.
Sincerely, SAB/TNW/RJR/ca
Attachment:
WCAP-16524-NP, "Analysis of Capsule 2300 from Arizona Public Service Company Palo Verde Unit 2 Reactor Vessel Radiation Surveillance Program", dated February 2006.
This attachment may be included as a CD. 10 CFR 171.9, Appendix A, Section 4.0 required information:
File: WCAP-16524-NP.pdf, 14,680,000 bytes, publicly available
Contact:
Richard J. Rogalski Regulatory Affairs PVNGS MS 7636 P.O. Box 52034 Phoenix, AZ 85072-2034 Tel 623.393.5806 Fax 623.393.5442 E-mail rrogalskeapsc.com Fedx 5801 S. Wintersburg Rd Tonopah, AZ 85354-7529 cc:
B. S. Mallett M. B. Fields G. G. Warnick
ATTACHMENT WCAP-1 6524-NP, "Analysis of Capsule 2300 from Arizona Public Service Company Palo Verde Unit 1 Reactor Vessel Radiation Surveillance Program," dated February 2006