ML102310526

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8/17/10 Summary of Telephone Conference Call Held Between the NRC and Pacific Gas and Electric Company Concerning D-RAI Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA - Metal Fatigue
ML102310526
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 08/27/2010
From: Ferrer N
License Renewal Projects Branch 2
To:
Ferrer, N B, NRR/DLR, 415-1045
References
Download: ML102310526 (5)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 August 27,2010 LICENSEE: Pacific Gas and Electric Company FACILITY: Diablo Canyon Nuclear Power Plant, Units 1 and 2

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 17, 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 APPLICATION - METAL FATIGUE 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 August 17, 2010, to obtain clarification on the staff's draft request for additional information (D-RAI) regarding the Diablo Canyon Nuclear Power Plant license renewal application (LRA).

Bye-mail dated August 4,2010, the staff sent D-RAls to PG&E regarding metal fatigue time limited aging analysis review. 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 staff's D-RAls. Enclosure 1 provides a listing of the participants. Enclosure 2 provides discussions on D-RAls for which the applicant requested clarification. No changes to other D-RAls were necessary as a result of this telephone conference call. Formal RAls will be issued by a separate letter.

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

Enclosures:

As stated cc w/encls: Distribution via Listserv

TELEPHONE CONFERENCE CALL DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS AUGUST 17, 2010 PARTICIPANTS AFFILIATIONS Nate Ferrer U.S. Nuclear Regulatory Commission (NRC)

James Medoff  !\IRC Todd Mintz Center for Nuclear Waste Regulatory Analyses Philippe Soenen Pacific Gas and Electric Company (PG&E)

Michelle Albright PG&E Kevin Braico PG&E Dave Kunsemiller Strategic Teaming And Resource Sharing (STARS)

Brett Lynch STARS ENCLOSURE 1

Diablo Canyon Nuclear Power Plant, Units 1 and 2 License Renewal Application Draft Request for Additional Information Metal Fatigue D-RAI4.3-8

Background:

In the license renewal application (LRA) Table 4.3-1, the applicant credits the "Global" monitoring (i.e., cycle count monitoring) of aging management program (AMP) B3.1 as the 10 CFR 54.21 (c)(1)(iii) aging management monitoring basis for dispositioning the cumulative usage factor (CUF) analyses for the reactor pressure vessel (RPV) Core Support Pads, Pressurizer Spray Nozzle, and Pressurizer Heater Penetration.

Issue:

The LRA Table 4.3-1 or LRA Table 4.3-6 indicated that the RPV Core Support Pads, Pressurizer Spray Nozzle, and Pressurizer Heater Penetration in Unit 1 have a maximum limiting design basis CUFs of -0.89, -0.95, and -0.94 respectively and limiting 60-year projected CUFs of -1.07, -1.14, and -2.97.

Reguest:

Justify your basis using the "Global" monitoring method of AMP B3.1 to monitor these components during the period of extended operation in accordance with 10 CFR 54.21 (c)(1)(iii),

and why it would not be more appropriate to monitor for these components using the cycle based fatigue (CBF) monitoring method.

Discussion: Based on discussion with the applicant, the staff determined that the Unit 1 pressurizer heater penetration 60-year projected CUF value was 0.9391, not 2.97, as indicated in LRA Table 4.3-6. The staff will revise the question as follows. The revised question will be sent as a formal RAI.

RAI4.3-8

Background:

In the LRA Table 4.3-1, the applicant credits the "Global" monitoring (Le. cycle count monitoring) of AMP 83.1 as the 10 CFR 54.21 (c)(1)(iii) aging management monitoring basis for dispositioning the CUF analyses for the RPV Core Support Pads, Pressurizer Spray Nozzle, and Pressurizer Heater Penetration.

Issue:

The LRA Table 4.3-1 or LRA Table 4.3-6 indicated that the RPV Core Support Pads, Pressurizer Spray Nozzle, and Pressurizer Heater Penetration in Unit 1 have a maximum limiting design basis CUFs of -0.89, -0.95, and -0.94 respectively and limiting 60-year projected CUFs of -1.07, -1.14, and -0.9391.

Request:

Justify your basis for using the "Global" monitoring method of AMP B3.1 to monitor these components during the period of extended operation in accordance with 10 CFR 54.21 (c)(1)(iii), and why it would not be more appropriate to monitor for these components using the CBF monitoring method.

ENCLOSURE 2

August 27.2010 LICENSEE: Pacific Gas and Electric Company FACILITY: Diablo Canyon Nuclear Power Plant, Units 1 and 2 SUB..IECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 17, 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 APPLICATION - METAL FATIGUE 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 August 17, 2010, to obtain clarification on the staff's draft request for additional information (D-RAI) regarding the Diablo Canyon Nuclear Power Plant license renewal application (LRA).

Bye-mail dated August 4, 2010. the staff sent D-RAls to PG&E regarding metal fatigue time limited aging analysis review. 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 staff's D-RAls. Enclosure 1 provides a listing of the participants. Enclosure 2 provides discussions on D-RAls for which the applicant requested clarification. No changes to other D-RAls were necessary as a result of this telephone conference call. Formal RAls will be issued by a separate letter.

The applicant had an opportunity to comment on this summary.

IRA!

Nathaniel Ferrer, Safety Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-275 and 50-323

Enclosures:

As stated cc w/encls: Distribution via Listserv DISTRIBUTION:

See next page ADAMS Accession No.: ML102310526 OFFICE ~DLR PM:RPB2:DLR BC:RPB2:DLR PM:RPB2:DLR NAME IKing NFerrer DWrona NFerrer DATE 08/25/10 08/25/10 08/26/10 08/27/10 OFFICIAL RECORD COpy

Letter to John Conway from Nathaniel B. Ferrer dated August 27, 2010

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 17, 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 APPLICATION - METAL FATIGUE DISTRIBUTION:

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