ML111530244
| ML111530244 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/02/2011 |
| From: | Jesse M Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML111530244 (8) | |
Text
10 CFR 50.55a June 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
Response to Request for Additional Information - Relief Request 14R-52 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)
References:
1)
Letter from D. P. Helker to U.S. Nuclear Regulatory Commission, "Submittal of Relief Request 14R-52 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702),"
dated January 24, 2011 2)
Letter from J. D. Hughey (U.S. Nuclear Regulatory Commission) to M.
Pacilio (Exelon Generation Company, LLC), "Peach Bottom Atomic Power Station, Units 2 and 3 - Request for Additional Information Regarding Relief Request 14R-52 Concerning Alternatives to Reactor Vessel Weld Examinations (TAC NOS. ME5394 and ME5395)," dated May 23,2011 In the Reference 1 letter, Exelon Generation Company, LLC (Exelon) requested relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components." Relief Request 14R-52 proposed an alternative to the requirements contained in Table IWB-2500-1 concerning nozzle-to-vessel weld and nozzle inner radii examination requirements. In the Reference 2 letter, the U.S. Nuclear Regulatory Commission requested additional information.
Attached is our response to this request.
No regulatory commitments are contained in this letter.
Response to Request for Additional Information Relief Request 14R*52 Concerning Nozzle*to*Vessel Weld and Inner Radii Examinations June 2011 Page 2 Should you have any questions concerning this letter, please contact Tom Loomis at (610) 765*5510.
Michael D.
Director* Licl:msing Exelon Generation Company, LLC
Attachment:
Response to Request for Additional Information* Relief Request 14R*52 cc:
USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, PBAPS USNRC Project Manager, PBAPS R. R. Janati, Bureau of Radiation Protection S. T. Gray, State of Maryland
ATTACHMENT Response to Request for Additional Information - Relief Request 14R-52
Response to Request for Additional Information Relief Request 14R-52 Page 1 Question:
RAI-01
Clarify whether all the inspection results for the life of each unit are included or only those conducted in accordance with Appendix VIII to the ASME Code,Section XI, "Performance Demonstration for Ultrasonic Examination Systems."
Response
As noted in the attached Tables 1 and 2, the inspection results provided do not include all the inspection results for the life of each unit. The tables include the completed examinations for the third and fourth Inservice Inspection (lSI) intervals at Peach Bottom Atomic Power Station, Units 2 and 3. The third interval for Unit 2 began on November 5, 1998 and concluded on November 4, 2008. The third interval for Unit 3 began on August 15, 1998 and ended on November 4, 2008 (see ML090430052).
The fourth interval for Peach Bottom Atomic Power Station, Units 2 and 3 began on November 5, 2008. See the response to RAI-02 below for discussion on Appendix VIII.
Question:
RAI-02
Indicate which examinations listed in Enclosure 3 were conducted in accordance with Appendix VIII to the ASME Code,Section XI, "Performance Demonstration for Ultrasonic Examination Systems."
Response
The attached Tables 1 and 2 indicate which examinations were performed in accordance with Appendix VIII to the ASME Code,Section XI, "Performance Demonstration for Ultrasonic Examination Systems." The examinations performed after the 2R14 refueling outage (2002) for Unit 2 and after the 3R13 refueling outage (2001) for Unit 3 were conducted in accordance with Appendix VIII.
Response to Request for Additional Information Relief Request 14R~52 Page 2 Table 1 PBAPS, Unit 2 Nozzle-to-Vessel and Nozzle Inner Radius Inspection Results As provided in 14R~52, the following tables identify the inspection results (Recordable Indications (RI) and No~Recordable Indications (NRI)). An additional column has been added to identify the examinations performed in accordance with Appendix VIII to the ASME Code,Section XI, "Performance Demonstration for Ultrasonic Examination Systems." This column is identified as "App. VIII."
As stated in 14R~52, all the indications were evaluated as acceptable per ASME Section XI.
3 1
4 1
3 1
No 4
1 Yes 3
1 No 3
1 No 3
1 No 3
1 No 3
1 No 3
1 No 3
1 No 3
1 No 3
2 Yes 3
2 Yes 3
3 Yes 3
3 es 3
2 NRt Yes 3
2 NRI Yes 3
3 NRI Yes 3
3 NRI Yes 3
2 NRI Yes 3
2 NRI Yes 3
3 NRI Yes 3
3 NRI Yes 2
3 3
NRI Yes 2
3 3
NRI Yes 2
3 3
NRI Yes 2
3 3
NRI Yes 2
3 3
NRI Yes 2
3 3
NRI Yes 2
3 3
2 3
3 NRI Yes 2
3 3
NRI Yes 2
3 3
NRI Yes 2
3 3
NRI Yes
Response to Request for Additional Information Relief Request 14R~52 Page 3
Response to Request for Additional Information Relief Request 14R-52 Page 4 Table 2 PBAPS Unit 3, Nozzle-to-Vessel and Nozzle Inner Radius Inspection Results As provided in 14R-52, the following tables identify the inspection results (Recordable Indications (RI) and No-Recordable Indications (NRI)). An additional column has been added to identify the examinations performed in accordance with Appendix VIII to the ASME Code,Section XI, "Performance Demonstration for Ultrasonic Examination Systems." This column is identified as "App. VIII." As stated in 14R-52, all the indications were evaluated as acceptable per ASME Section XI.
3 3
1 NRI No 3
CH-NC (N6B) 3R13 3
1 NRI No 3
CH-NC-IRS (N6B) 3R13 3
1 No 3
N2A 3R14 3
2 Yes 3
N2A-IRS 3R14 3
2 NRI Yes 3
N2B 3R14 3
2 RI Recordable indications identified - acceptable per ASME Section XI.
Yes 3
N2B-IRS 3R14 3
2 NRI Yes 3
N2C 3R14 3
2 NRI Yes 3
N2C-IRS 3R14 3
2 NRI Yes 3
N2D 3R13 3
1 NRI No 3
N2D-IRS 3R13 3
1 NRI No 3
N2E 3R13 3
1f!
No 3
N2E-IRS 3R13 3
1 No 3
N2F 3R13 3
1 No 3
N2F-IRS 3R13 3
1 NRI No 3
N2G 3R14 3
2 RI Recordable indication identified acceptable per ASME Section XI.
Yes 3
N2G-IRS 3R14 3
2 NRI Yes 3
N2H 3R16 3
3 NRI Yes 3
N2H-IRS 3R16 3
3 NRI Yes 3
N2J 3R16 3
3 NRI Yes 3
N2J-IRS 3R16 3
3 NRI Yes 3
N2K 3R16 3
3 NRI Yes 3
N2K-IRS 3R16 3
3 NRI Yes 3
N3A 3R13 3
1 NRI No 3
N3A-IRS 3R13 3
1 NRI No 3
N3B 3R13 3
1 NRI No 3
N3B-IRS 3R13 3
1 NRI No 3
N3C m
3 3
NRI Yes 3
N3C-IRS 3
3 NRI Yes 3
N3D 3
3 NRI Yes 3
N3D-IRS 3R16 3
3 NRI Yes
N5A N5A-IRS N5B N5B-IRS N8A N8A-IRS N8B N8B*IRS Response to Request for Additional Information Relief Request 14R-52 Page 5