DCL-13-121, ASME Code Section XI Inservice Inspection Program Request for Alternative NDE-SFW-13 to Allow Use of Alternate Examination Requirements

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ASME Code Section XI Inservice Inspection Program Request for Alternative NDE-SFW-13 to Allow Use of Alternate Examination Requirements
ML13353A475
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 12/18/2013
From: Allen B
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-13-121
Download: ML13353A475 (6)


Text

Pacific Gas and Electric Company Barry S. Allen Diablo Canyon Power Plant Site Vice President Mail Code 104/6 P. O. Box 56 Avila Beach, CA 93424 805.545.4888 December 18,2013 Internal: 691.4888 Fax: 805.545 .6445 PG&E Letter DCL-13-121 U.S. Nuclear Regulatory Commission 10 CFR 50.55a ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-323, OL-DPR-82 Diablo Canyon Power Plant (DCPP) Unit 2 ASME Code Section XI Inservice Inspection Program Request for Alternative NDE-SFW-13 to Allow Use of Alternate Examination Requirements

Dear Commissioners and Staff:

Pursuant to 10 CFR 50.55a(a)(3)(i), Pacific Gas and Electric Company (PG&E) hereby requests NRC approval of Inservice Inspection (lSI) Request for Alternative NDE-SFW-13 for the Diablo Canyon Power Plant Unit 1 and Unit 2 third lSI intervals.

An alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code is requested for examination of reactor vessel shell-to-flange welds. The details of the proposed request are enclosed.

PG&E requests approval of NDE-SFW-13 by December 23,2014.

PG&E makes no regulatory commitments (as defined by NEI 99-04) in this letter.

If you have any questions regarding the information enclosed, or other lSI program activities, please contact Mr. Tom Baldwin at (805) 545-4720.

Sincerely, 07 s. Aa-Barry S. Allen rntU4231/SAPN 50033145-84 Enclosure cc: Diablo Distribution cc/enc: Brian J. Benney, NRR Project Manager Marc L. Dapas, NRC Region IV Administrator Thomas R. Hipschman, NRC Senior Resident Inspector State of California, Pressure Vessel Unit A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

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Enclosure PG&E Letter DCL-13-121 10 CFR 50.55a Request for Alternative NDE-SFW-13 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)

Enclosure PG&E Letter DCL-13-121 10 CFR SO.SSa Request for Alternative NDE-SFW-13 Proposed Alternative in Accordance with 10 CFR SO.SSa(a)(3)(i)

--Alternative Provides Acceptable Level of Quality and Safety--

1. ASME Code Component(s) Affected The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Class 1, Diablo Canyon Power Plant (DCPP), Units 1 and 2, reactor vessel shell-to-flange welds:

Code Cat/Item Description Weld Number B-AlB1.30 Shell-to-Flange Weld 7 -442 (Unit 1)

B-AlB1.30 Shell-to-Flange Weld 7-201 (Unit 2)

2. Applicable Code Edition and Addenda The DCPP Units 1 and 2 third interval Inservice Inspection (lSI) Program Plan is based on the ASME Section XI, 2001 Edition with 2003 Addenda. ASME Code Section XI, 2001 Edition without Addenda applies to ultrasonic (UT) examinations performed per ASME Code Section XI, Appendix VIII requirements.
3. Applicable Code Requirements ASME Code Section XI, Table IWB-2500-1, Category B-A, Item B1.30, requires that reactor vessel shell-to-flange welds be volumetrically examined once during each lSI interval. ASME CODE Section XI, Subsection IWA-2232, requires that the UT examination of reactor pressure vessel (RPV) shell-to-flange welds to be performed per the requirements of ASME Code,Section V, Article 4, as supplemented by Appendix I of Section XI. The examination volume extent is identified in the ASME Code,Section XI, Figure IWB-2500-4, "Shell-To-Flange Weld Joint."

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Enclosure PG&E Letter DCL-13-121

4. Impracticality of Compliance Pursuant to 10 CFR SO.SSa(a)(3)(i), an alternative is requested to the requirements of Subsection IWA-2232 since the vendor performing the inspection has qualified their equipment, procedures and personnel per the Performance Demonstration Initiative (PDI) implementation of ASME Code,Section XI, Appendix VIII, Supplements 4 and 6, as amended by 10 CFR SO.SSa.

ASME Code Section XI, Appendix VIII requirements apply to all DCPP reactor vessel shell welds with the exception of the shell-to-flange weld.

Performing the shell-to-flange weld examination in accordance with the requirements of ASME Code,Section XI, IWA-2232 would require the examination vendor to use a different procedure and process than that used for all other shell welds in the reactor vessel. Reactor vessel examination processes qualified to Appendix VIII have been demonstrated to be effective in detecting and sizing flaws.

Background

Both DCPP Units 1 and 2 reactor vessel shell-to-flange welds have received two previous ISis, with the second examination on each unit performed per the PDI implementation of ASME Code,Section XI, Appendix VIII rules (Precedent 2).

No service related flaws have been detected in either weld.

The upper shell course material in both DCPP reactors is A-S33 Grade B, Class 1, while the flanges are A-S08-64 material. The sections are joined with a narrow groove weld with a fit-up opening of approximately 1.37S inches. A general outline of the weld configuration is shown in Figure 1.

5. Proposed Alternative and Basis for Use Pursuant to 10 CFR SO.SSa(a)(3)(i), PG&E requests authorization to use the alternate requirements of ASME Code Section XI, 2001 Edition with no Addenda, Appendix VIII, Supplements 4 and 6, as amended by 10 CFR SO.SSa and implemented by the PDI for examination of the shell-to-flange weld when examined from the vessel shell. The Appendix VIII requirements will be implemented in lieu of ASME Code,Section XI, IWA-2232 that requires UT examination of the RPV shell-to-flange weld to be in accordance with ASME Code,Section V, Article 4, as supplemented by Appendix I of Section XI.

The proposed alternate ASME Code Section XI, Appendix VIII requirements were established to improve the effectiveness of UT examinations by means of a rigorous, item specific, performance demonstration. The performance demonstration process verifies the capability of personnel, procedures, and equipment to detect and characterize flaws that could be detrimental to the 2

Enclosure PG&E Letter DCL-13-121 structural integrity of the RPV. Since implementation, this process has shown improved performance as compared to the prescriptive requirements of ASME Code,Section V, Article 4.

As stated in Reference 1, "There is clear evidence that the performance demonstration requirements adopted by Section XI of the ASME Code for Boiler and Pressure Vessels has resulted in a positive impact on the reliability of ultrasonic examinations that are performed on piping and pressure vessels."

Although an ASME Code,Section XI, Appendix VIII qualified exam process is not required for the examination of the reactor vessel shell-to-flange welds, the use of Appendix VIII, Supplements 4 and 6 process for detection and sizing of flaws in this weld has been shown to exceed the performance of the ASME Code Section V, Article 4 prescriptive examination process. Therefore, the use of the proposed alternative will continue to provide an acceptable level of quality and safety, and approval is requested pursuant to 10 CFR 50.55a(a)(3)(i).

6. Duration of Proposed Alternative The proposed alternative will apply through the end of the DCPP third lSI interval for each unit. The Unit 1 third interval began on January 1, 2006, and is nominally scheduled to end on May 6, 2015. The Unit 2 third interval began on July 1, 2006, and is nominally scheduled to end March 12, 2016.
7. Precedents Similar requests have been previously approved:
1. Indian Point Unit 2; NRC letter dated April 25. 2011 (ADAMS Accession No. ML11109A016).
2. Diablo Canyon Units 1 and 2; NRC letter dated October 26, 2005 (ADAMS Accession No. ML052660331)
8. References
1. NUREG/CR-7165, PNNL-19014, Revision 2, "The Technical Basis Supporting ASME Code,Section XI, Appendix VIII: Performance Demonstration for Ultrasonic Examination Systems."

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Enclosure PG&E Letter DCL-13-121 Flange Forging Upper Shell Course Figure 1 Sketch of DCPP Unit 1 and Unit 2 RPV Flange Weld Configuration 1