ML102850648

Lr -

ML102850648
Person / Time
Site:	Diablo Canyon
Issue date:	06/14/2010
From:	Office of Nuclear Reactor Regulation
To:	Division of License Renewal
References
Download: ML102850648 (7)

Text

DiabloCanyonNPEm Resource From: Ferrer, Nathaniel Sent: Monday, June 14, 2010 9:38 AM To: Grebel, Terence; Soenen, Philippe R Cc: Green, Kimberly; DiabloHearingFile Resource Attachments: Telecon Summary 06-03-10 Aging Management Programs.doc Terry & Philippe, Attached is the Teleconference Call Summary from 6/3/2010. Please review and let me know if there are any corrections/changes needed.

Please let me know if you have any questions.

Nathaniel Ferrer Project Manager Division of License Renewal Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (301)4151045 1

Hearing Identifier: DiabloCanyon_LicenseRenewal_NonPublic Email Number: 1963 Mail Envelope Properties (26E42474DB238C408C94990815A02F090A739F5E44)

Subject:

Sent Date: 6/14/2010 9:37:53 AM Received Date: 6/14/2010 9:37:54 AM From: Ferrer, Nathaniel Created By: Nathaniel.Ferrer@nrc.gov Recipients:

"Green, Kimberly" <Kimberly.Green@nrc.gov>

Tracking Status: None "DiabloHearingFile Resource" <DiabloHearingFile.Resource@nrc.gov>

Tracking Status: None "Grebel, Terence" <TLG1@PGE.COM>

Tracking Status: None "Soenen, Philippe R" <PNS3@PGE.COM>

Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 396 6/14/2010 9:37:54 AM Telecon Summary 06-03-10 Aging Management Programs.doc 70650 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

LICENSEE: Pacific Gas and Electric Company FACILITY: Diablo Canyon Nuclear Power Plant, Units 1 and 2

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON JUNE 3, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PACIFIC GAS AND ELECTRIC COMPANY CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATIONAGING MANAGEMENT PROGRAMS The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Pacific Gas and Electric Company (PG&E) held a telephone conference call on June 3, 2010, to obtain clarification on the staffs draft request for additional information (D-RAI) regarding the Diablo Canyon Nuclear Power Plant license renewal application (LRA).

By emails dated May 17, 2010 and May 20, 2010, the staff sent D-RAIs to PG&E regarding aging management programs. PG&E reviewed the information contained therein, and requested a telephone conference call. The telephone conference call was useful in clarifying the intent of the staffs D-RAIs. Enclosure 2 provides discussions on D-RAIs for which the applicant requested clarification. No changes to other D-RAIs were necessary as a result of this telephone conference call. Formal RAIs will be issued by a separate letter. provides a listing of the participants.

The applicant had an opportunity to comment on this summary.

Nathaniel Ferrer, Safety Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-275 and 50-323 Enclosure cc w/encl: See next page

OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR PM:RPB2:DLR NAME NFerrer DWrona NFerrer DATE 05/ /10 05/ /10 05/ /10 05/ /10 TELEPHONE CONFERENCE CALL DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS MAY 18, 2010 PARTICIPANTS AFFILIATIONS Kim Green U.S. Nuclear Regulatory Commission (NRC)

Nate Ferrer NRC Yogen Garud Argonne National Laboratory (ANL)

Dwight Dierks ANL Terry Grebel Pacific Gas and Electric Company (PG&E)

Philippe Soenen PG&E Chalmer Myer Strategic Teaming And Resource Sharing (STARS)

Dave Kunsemiller STARS Dave Lipinski STARS Fred Polaski STARS Enclosure 1

Diablo Canyon Nuclear Power Plant, Units 1 and 2 License Renewal Application Draft Request for Additional Information Aging Management Programs D-RAI B2.1.1-1 Generic Aging Lessons Learned (GALL) Report AMP XI.M1 scope of program element contains broad class of components for inservice inspection (ISI) with respective standards for flaw acceptance and flaw evaluation. Also, the detection of aging effects program element covers the inspections of Class 1 small-bore piping and socket welds.

In its description of the ISI program under LRA Section B2.1.1, the applicant stated that DCPP evaluates every indication. However, the acceptance standards IWD-3400 and IWD-3500 and the flaw evaluation standard IWD-3600, for Class 3 components, are not included in the program description of LRA AMP B2.1.1. Also, Class 1 small-bore piping and socket welds for the aging management program are covered under different AMPs for DCPP.

Explain how the program description includes the use of acceptance and evaluation standards for Class 3 components. Also, indicate under the detection of aging effects element in which AMPs the inspection of Class 1 small-bore piping and socket welds are covered or supplemented.

Discussion: Based on the discussion with the applicant, the staff agreed to revise this question as follows. The revised question will be sent as a formal RAI.

RAI B2.1.1-1 Generic Aging Lessons Learned (GALL) Report AMP XI.M1 scope of program element contains broad class of components for inservice inspection (ISI) with respective standards for flaw acceptance and flaw evaluation. Also, the detection of aging effects program element covers the inspections of Class 1 small-bore piping and socket welds.

In its description of the ISI program under LRA Section B2.1.1, the applicant stated that DCPP evaluates every indication. However, the acceptance standards IWD-3400 and IWD-3500 and the flaw evaluation standard IWD-3600, for Class 3 components, are not included in the program description of LRA AMP B2.1.1. Also, Class 1 small-bore piping and socket welds for the aging management program are covered under different AMPs for DCPP.

Explain how the program description includes the use of acceptance and evaluation standards for Class 3 components. Also, indicate in which AMP the inspection of Class 1 small-bore piping and socket welds are covered or supplemented, including a justification for using this program.

Enclosure 2

D-RAI B2.1.16-3 LRA Table 3.3.1, Item 3.3.1.35 refers to the aging evaluation of pump casings in auxiliary systems fabricated of steel with stainless steel cladding and exposed to treated borated water.

The aging effect identified is loss of material due to cladding breach, and the GALL Report recommends the use of a plant-specific aging management program. The applicant proposes to manage this aging effect using its Water Chemistry Program, with its One-Time Inspection Program to be used for verification of program effectiveness.

The staff notes that treated borated water is corrosive with respect to the ferritic steel underlying the stainless steel cladding in these pump casings. This means that even if proper water chemistry is maintained under the applicants Water Chemistry Program, the ferritic steel substrate will undergo corrosive attack in the event of a cladding breach. The applicant must therefore rely on its proposed One-Time Inspection Program to detect this aging effect in these components. Since loss of material in the underlying ferritic steel is not normally surface-intersecting, a volumetric inspection technique such as ultrasonic testing would normally be used for detection purposes. However, the complex microstructure and geometry of this weld-clad component makes ultrasonic inspection difficult and potentially unreliable.

Describe the details of the inspection technique to be used to perform the one-time inspection of these components and provide relevant plant or industry experience to demonstrate the effectiveness and reliability of this technique.

Discussion: The applicant referred the staff to section 3.3.2.2.14 and Table A4-1 of the LRA.

The staff determined that sufficient information is included in the LRA to address the staffs concern. Therefore, this question is withdrawn and will not be sent as a formal RAI.

Enclosure 2