ML103270349

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Lr - Draft Teleconference Sumary for November 9, 2010
ML103270349
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 11/23/2010
From:
Office of Nuclear Reactor Regulation
To:
Division of License Renewal
References
Download: ML103270349 (9)


Text

DiabloCanyonNPEm Resource From: Ferrer, Nathaniel Sent: Tuesday, November 23, 2010 11:23 AM To: Grebel, Terence Cc: DiabloCanyonNPEm Resource

Subject:

Draft Teleconference Sumary for November 9, 2010 Attachments: Telecon Summary 11-09-10 AMR and TLAA.doc

Terry, Attached is a draft of the Teleconference Summary for November 9, 2010, conference call. 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: 2197 Mail Envelope Properties (26E42474DB238C408C94990815A02F0913678A41AB)

Subject:

Draft Teleconference Sumary for November 9, 2010 Sent Date: 11/23/2010 11:22:31 AM Received Date: 11/23/2010 11:22:32 AM From: Ferrer, Nathaniel Created By: Nathaniel.Ferrer@nrc.gov Recipients:

"DiabloCanyonNPEm Resource" <DiabloCanyonNPEm.Resource@nrc.gov>

Tracking Status: None "Grebel, Terence" <TLG1@pge.com>

Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 415 11/23/2010 11:22:32 AM Telecon Summary 11-09-10 AMR and TLAA.doc 103418 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

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON NOVEMBER 9, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PACIFIC GAS AND ELECTRIC COMPANY, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION RELATED TO THE DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. ME2896 AND ME2897)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Pacific Gas and Electric Company (PG&E or the applicant) held a telephone conference call on November 9, 2010, to obtain clarification on the staffs requests for additional information (RAIs) regarding the Diablo Canyon Nuclear Power Plant, Units 1 and 2, license renewal application.

By e-mails dated October 27, 2010, November 2, 2010, and November 9, 2010, the staff emailed draft RAIs to PG&E regarding aging management review. In addition, by letter dated November 3, 2010, the staff issued RAIs regarding time limited aging analyses. PG&E reviewed the information contained therein, and requested a telephone conference call. The telephone conference call was useful in clarifying the intent of PG&Es response. Enclosure 1 provides a listing of the participants. Enclosure 2 provides discussions on draft RAIs for which the applicant requested clarification. No changes to the RAIs issued by letter dated November 2, 2010, were necessary as a result of this conference call. PG&E will submit supplemental responses, as necessary, within 30 days of the issuance of this summary.

The applicant had an opportunity to comment on this summary.

Nathaniel B. Ferrer, 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

ML103190589 OFFICE LA:RPOB:DLR PM:RPB2:DLR BC:RPB2:DLR PM:RPB2:DLR NAME SFigueroa NFerrer DWrona NFerrer (Signature)

DATE 11/16/10 11/ /10 11/ /10 11/ /10 Memorandum to Pacific Gas and Electric Company from Nathaniel B. Ferrer dated November XX, 2010

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON NOVEMBER 9, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PACIFIC GAS AND ELECTRIC COMPANY, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION RELATED TO THE DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. ME2896 AND ME2897)

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PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsOgcMailCenter Resource NFerrer KGreen AStuyvenberg DWrona AWang MPeck, RIV TBrown, RI GMiller, RIV NOKeefe, RIV ICouret, OPA VDricks, OPA WMaier, RIV JWeil, OCA EWilliamson, OGC SUttal, OGC RRihm, EDO

TELEPHONE CONFERENCE CALLS DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS NOVEMBER 9, 2010 PARTICIPANTS AFFILIATIONS Nathaniel Ferrer U.S. Nuclear Regulatory Commission (NRC)

Michelle Kichline NRC John Tsao NRC Terry Grebel Pacific Gas and Electric Company (PG&E)

Dave Miklush PG&E David Gonzalez PG&E Kevin Braico PG&E David Kunsemiller Strategic Teaming And Resource Sharing (STARS)

Stan Shepard STARS ENCLOSURE 1

Diablo Canyon Nuclear Power Plant, Units 1 and 2 License Renewal Application Draft Request for Additional Information Aging Management Review Draft Request for Additional Information (D-RAI) 3.3.2.3.5-1 (follow-up)

In License Renewal Application (LRA) Tables 3.3.2-5 and 3.4.2-1, the applicant stated that carbon steel indicators, sight glasses, piping, pumps, tanks, and valves internally exposed to sodium hydroxide (NaOH) are being managed for loss of material by the Water Chemistry and One-Time Inspection Programs. The Aging Management Review line items cite generic note G and a plant-specific note, which states The use of carbon steel up to 200°F (93°C) and 50 wt percent NaOH is common in industrial applications with no special consideration for aging. The NaOH concentration is controlled by the Water Chemistry Program.

By letter dated August 30, 2010, the staff issued RAI 3.3.2.3.5-1, and noted that Electric Power Research Institute primary and secondary water chemistry guidelines, which are the basis for Generic Aging Lessons Learned (GALL) aging management program (AMP) XI.M2 Water Chemistry, do not include control parameters for managing NaOH used in auxiliary systems.

The staff requested that the applicant describe the parameters being monitored and acceptance criteria for the sodium hydroxide solution being monitored by the Water Chemistry Program. In its response dated September 29, 2010, the applicant stated that the components exposed to NaOH are no longer in-service but have not been formally abandoned-in-place and therefore were assumed to contain liquid. The applicant did not include the parameters and acceptance criteria being monitored by the Water Chemistry Program.

Request

1. State the parameters being monitored, frequency of monitoring, and acceptance criteria for the NaOH solution.
2. Confirm that these parameters are being monitored by the Water Chemistry Program.
3. Justify the use of the One-Time Inspection Program to manage loss of material for these components given that GALL AMP XI.M32, One-Time Inspection is only to be used to verify the effectiveness of an aging management program, confirm the absence of an aging effect, or confirm that the aging effect is occurring slowly enough such that it will not affect the intended function of the component during the period of extended operation.

Discussion Pacific Gas and Electric Company (PG&E) agreed to supplement its response to the original RAI 3.3.2.3.5-1 to address the concerns noted above. This D-RAI will not be issued formally.

ENCLOSURE 2

D-RAI 3.3.2.3.3-1 (follow-up)

Background

In the response to RAI 3.3.2.3.3-1, the applicant stated that the following components will be maintained below 104°F at all times. GALL Report Chapter IX.C states that, Hardening and loss of strength of elastomers can be induced by elevated temperature (over about 95°F), and additional aging factors such as exposure to ozone, oxidation, and radiation. For the following LRA tables and line items, no aging effect and no AMP is proposed when the components are exposed to air-indoor (external).

LRA Table Component Material 3.3.2-3 & 3.3.2-5 Pipe, Valves, Strainers, Filters and PVC eye wash stations 3.3.2-18 Flow indicator, demineralizer Plexiglas 3.4.2-1 Pipe PVC 3.4.2-5 Tanks Plexiglas 3.4.2-2 Tanks Lexan Issue Given that the exposure temperature for the components exceeds the recommended threshold for hardening and loss of strength to occur in elastomeric materials, the staff does not have sufficient information to justify the applicants proposal that there is no aging effect and no AMP is required.

Request Justify why the temperatures in the vicinity of the above components would not lead to (or contribute to) aging effects during the period of extended operation.

Discussion PG&E agreed to supplement its response to the original RAI 3.3.2.3.3-1 to address the concerns noted above. This D-RAI will not be issued formally.

D-RAI B2.1.9 (follow-up)

Background

By letter dated August 26, 2010, the staff issued RAI B2.1.9, requesting that the applicant provide additional information on how cracking in titanium components will be managed by the Open-Cycle Cooling Water System Program and if visual inspection will be used. The staff also requested details on how the visual inspection will be implemented to take into consideration the tightness of cracks that can form in titanium. In its response dated September 22, 2010, the applicant stated that it would revise the External Surface Monitoring Program to include visual

inspections to detect cracking and leakage of titanium tubing. The applicants response did not provide details, as requested in the RAI, on what visual inspection techniques would be implemented to identify the tight cracks (e.g., VT-1, VT-2, VT-3).

Issue Given that the applicant did not provide the requested detail in its response to RAI B2.1.9, the staff does not know what visual examination method will be used and therefore cannot evaluate the effectiveness of this method in detecting tight cracks that may form in titanium.

Request State what type of visual inspection technique will be used in the External Surface Monitoring Program to detect cracks in titanium prior to failure (i.e., leakage).

Discussion PG&E agreed to supplement its response to the original RAI B2.1.9 to address the concerns noted above. This D-RAI will not be issued formally.