ML090050331

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Notification of Inspection and Request for Information
ML090050331
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 01/05/2009
From: Thomas Farnholtz
Division of Reactor Safety IV
To: Conway J
Pacific Gas & Electric Co
References
Download: ML090050331 (12)


Text

UNITED STATES NUC LE AR RE G UL AT O RY C O M M I S S I O N R E GI ON I V 612 EAST LAMAR BLVD , SU I TE 400 AR LI N GTON , TEXAS 76011-4125 January 5, 2009 John T. Conway Senior Vice President &

Chief Nuclear Officer Pacific Gas and Electric Company P.O. Box 3 Mail Code 104/6/601 Avila Beach, CA 93424

SUBJECT:

DIABLO CANYON POWER PLANT, UNIT 1 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Keenan:

From February 9 to March 13, 2009, the NRC will perform the baseline inservice inspection at the Diablo Canyon Power Plant, Unit 1 (NRC Inspection Procedure 71111.08) and Temporary Instruction 2515/172, Reactor Coolant System Dissimilar Metal Butt Welds.

Experience has shown that this inspection is resource intensive both for the NRC inspectors and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection. These documents have been divided into two groups. The first group (Section A of the enclosure) identifies information to be provided prior to the inspection to ensure that the inspectors are adequately prepared. The second group (Section B of the enclosure) identifies the information the inspectors will need upon arrival at the site. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.

We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Steven Zawalick and Mike McCoy of your organization. Our inspection dates are subject to change based on your updated schedule of outage activities. If there are any questions about this inspection or the material requested, please contact the lead inspector Breck Henderson at (817) 276-6569 (breck.henderson@nrc.gov).

Pacific Gas and Electric Company In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room)

Sincerely,

/RA/

Thomas Farnholtz, Chief Engineering Branch 1 Division of Reactor Safety Docket No: 50-323 License No. DPR-82

Enclosure:

Inservice Inspection Document Request cc: w/enclosure Sierra Club San Lucia Chapter ATTN: Andrew Christie P.O. Box 15755 San Luis Obispo, CA 93406 Nancy Culver San Luis Obispo Mothers for Peace P.O. Box 164 Pismo Beach, CA 93448 Chairman San Luis Obispo County Board of Supervisors County Government Building 1055 Monterey Street, Suite D430 San Luis Obispo, CA 93408 Truman Burns\Robert Kinosian California Public Utilities Commission 505 Van Ness Ave., Rm. 4102 San Francisco, CA 94102-3298

Pacific Gas and Electric Company Diablo Canyon Independent Safety Committee Robert R. Wellington, Esq.

Legal Counsel 857 Cass Street, Suite D Monterey, CA 93940 Director, Radiological Health Branch State Department of Health Services P.O. Box 997414 (MS 7610)

Sacramento, CA 95899-7414 Jennifer Post, Esq.

Pacific Gas and Electric Company P.O. Box 7442 San Francisco, CA 94120 City Editor The Tribune 3825 South Higuera Street P.O. Box 112 San Luis Obispo, CA 93406-0112 James D. Boyd, Commissioner California Energy Commission 1516 Ninth Street (MS 34)

Sacramento, CA 95814 James R. Becker, Vice President Diablo Canyon Operations and Station Director, Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424 Jennifer Tang Field Representative United States Senator Barbara Boxer 1700 Montgomery Street, Suite 240 San Francisco, CA 94111 John T. Conway Site Vice President Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424

Pacific Gas and Electric Company Chief, Radiological Emergency Preparedness Section National Preparedness Directorate Technological Hazards Division Department of Homeland Security 1111 Broadway, Suite 1200 Oakland, CA 94607-4052

Pacific Gas and Electric Company Electronic distribution by RIV:

Regional Administrator (EEC)

DRP Director (ATH)

DRS Director (DDC)

DRS Deputy Director (RJC1)

Senior Resident Inspector (MSP)

Branch Chief, DRP/B (VGG)

Senior Project Engineer, DRP/E (RWD)

Team Leader, DRP/TSS (CJP)

RITS Coordinator (MSH3)

DRS STA (DAP)

V. Dricks, PAO (VLD)

A. Powell, OCA Region IV Coordinator (AXP10)

D. Pelton, OEDO RIV Coordinator (DLP)

ROPreports DC Site Secretary (AWC1)

SUNSI Review Completed: BWH ADAMS: Yes No Initials: BWH Publicly Available Non-Publicly Available Sensitive Non-Sensitive DOCUMENT NAME: R:\REACTORS\DC\2008\DC U2ISI Info Rqst Ltr. ML090050331 RI:EB1 C:EB1 BWHenderson/lar TFarnholtz

/RA/ /RA/

1/5/2009 1/5/2009 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: February 2 -13 and March 2 - 13, 2009 Inspection Procedures: IP 71111.08 Inservice Inspection (ISI) Activities TI 2515/172 Reactor Coolant System Dissimilar Metal Butt Welds Inspectors: Breck Henderson, Reactor Inspector (Lead Inspector - ISI)

Shiattin Makor, Reactor Inspector A. Information Requested for the In-Office Preparation Week The following information should be sent to the Region IV office in hard copy or electronic format (CD preferred), in care of Breck Henderson by January 26, 2009, to facilitate the selection of specific items that will be reviewed during the onsite inspection week. The inspector will select specific items from the information requested below and then request from your staff additional documents needed during the onsite inspection week (section B of this enclosure). We ask that the specific items selected from the lists be available and ready for review on the first day of inspection. Please provide requested documentation electronically if possible. If requested documents are large and only hard copy formats are available, please inform the inspectors, and provide subject documentation during the first day of the onsite inspection. If you have any questions regarding this information request, please call the inspector as soon as possible.

A.1 ISI/Welding Programs and Schedule Information a) A detailed schedule (including preliminary dates) of:

i) Nondestructive examinations (NDEs) planned for Class 1 and 2 systems and containment, performed as part of your ASME Section XI, Risk Informed (if applicable), and augmented ISI Programs during the upcoming outage.

Provided a status summary of the NDE inspection activities vs. the required inspection period percentages for this interval by category per ASME Section XI, IWX-2400 (Do not provide separately if other documentation requested contains this information).

ii) Reactor pressure vessel head (RPVH) examinations planned for the upcoming outage.

iii) Examinations planned for Alloy 82/182/600 components that are not included in the Section XI scope. (If applicable)

Enclosure

iv) Examinations planned as part of your Boric Acid Corrosion Control Program (Mode 3 walk downs, bolted connection walk downs, etc.)

v) Welding activities that are scheduled to be completed during the upcoming outage (ASME Class 1, 2, or 3 structures, systems, or components (SSCs))

b) A copy of ASME Section XI Code Relief Requests and associated NRC Safety Evaluations applicable to the examinations identified above.

c) A list of NDE reports (ultrasonic, radiography, magnetic particle, dye penetrant, visual VT-1, VT-2, and VT-3) which have identified relevant indications (geometric or flaw) on Code Class 1 and 2 systems since the beginning of the last refueling outage. Also, include in the list the NDE reports with relevant indications in the RPVH penetration nozzles which have been accepted for continued service. The list of NDE reports should include a brief description of the SSC where the relevant indication was identified.

d) A list with a brief description (e.g., system, material, pipe size, weld number, and NDE performed) of the welds in Code Class 1 and 2 systems which have been fabricated due to component repair/replacement activities since the beginning of the last refueling outage, or are planned to be fabricated this refueling outage.

e) If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the upcoming outage, provide a detailed description of the welds to be examined, and the extent of the planned examination. Please also provide reference numbers for applicable procedures that will be used to conduct these examinations.

f) Copy of any 10 CFR Part 21 reports applicable to your SSCs within the scope of Section XI of the ASME Code that have been identified since the beginning of the last refueling outage.

g) A list of any temporary non-code repairs in service (e.g., pinhole leaks).

h) Please provide copies of the most recent self-assessments for the ISI, Welding, and Alloy 600 Programs.

Enclosure

A.2 Reactor Pressure Vessel Head (RPVH) a) Provide the detailed scope of the planned NDE of the reactor vessel head which identifies the types of NDE methods to be used on each specific part of the vessel head to fulfill NRC commitments made in response to NRC Bulletin 2002-02 and NRC Order EA-03-009. Also, include examination scope expansion criteria and planned expansion sample sizes if relevant indications are identified. (If applicable) b) A list of the standards and/or requirements that will be used to evaluate indications identified during NDE of the reactor vessel head (e.g., the specific industry or procedural standards which will be used to evaluate potential leakage and/or flaw indications).

A.3 Boric Acid Corrosion Control Program (BACCP) a) Copy of the procedures that govern the scope, equipment and implementation of the inspections required to identify boric acid leakage and the procedures for boric acid leakage/corrosion evaluation.

b) Please provide a list of leaks (including code class of the components) that have been identified since the last refueling outage and associated corrective action documentation. If during the last cycle, the unit was shutdown, please provide documentation of containment walk down inspections performed as part of the BACCP.

c) Please provide a copy of the most recent self-assessment performed for the BACCP.

A.4 Additional Information Related to All ISI Activities a) A list with a brief description of ISI, BACCP, and SG ISI related issues (e.g., condition reports) entered into your corrective action program since the beginning of the last refueling outage for (Unit 2). For example, a list based upon data base searches using key words related to piping or SG tube degradation such as: ISI, ASME Code,Section XI, NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors in piping/SG tube examinations.

b) Please provide names and phone numbers for the following program leads:

ISI contacts (Examination, planning)

Containment Exams RPVH Exams Snubbers and Supports Repair and Replacement Program Manager Licensing Contact Enclosure

Site Welding Engineer Boric Acid Corrosion Control Program SG Inspection Activities (site lead and vendor contact)

B. Information to be Provided On-site to the Inspector at the Entrance Meeting February 2, 2009 B.1 ISI/Welding Programs and Schedule Information a) Updated schedules for ISI/NDE activities, planned welding activities, and schedule showing contingency repair plans, if available.

b) For ASME Class 1 and 2 welds selected by the inspector from the lists provided from Section A of this enclosure, please provide copies of the following documentation for each subject weld:

i) Weld data sheet (traveler) ii) Weld configuration and system location iii) Applicable Code Edition and Addenda for weldment iv) Applicable Code Edition and Addenda for welding procedures v) Applicable weld procedures (WPS) used to fabricate the welds vi) Copies of procedure qualification records (PQRs) supporting the WPS from B.1.b.v vii) Copies of mechanical test reports identified in the PQRs above viii) Copies of the nonconformance reports for the selected welds (If applicable) ix) Radiographs of the selected welds and access to equipment to allow viewing radiographs (If RT was performed) x) Copies of the preservice examination records for the selected welds xi) Copies of welder performance qualifications records applicable to WPS, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS (At least six months prior to date subject work) xii) Copies of NDE personnel qualifications (VT, PT, UT, RT) As applicable Enclosure

c) For the ISI related corrective action issues selected by the inspector from Section A of this enclosure, provided a copy of the corrective actions and supporting documentation.

d) For the NDE reports with relevant indications on Code Class 1 and 2 systems selected by the inspector from Section A above, provide a copy of the examination records, examiner qualification records, and associated corrective action documents.

e) A copy of (or ready access to) most current revision of the ISI Program Manual and Plan for the current interval.

f) For the NDEs selected by the inspector from Section A of this enclosure, provide a copy of the NDE procedures used to perform the examinations (including calibration and flaw characterization/sizing procedures). For ultrasonic examination procedures qualified in accordance with ASME Code,Section XI, Appendix VIII, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Also, include documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers) and NDE personnel qualification records.

B.2 Reactor Pressure Vessel Head (RPVH) a) Provide the NDE personnel qualification records for the examiners who will perform examinations of the RPVH.

b) Provide drawings showing the following: (If a visual examination is planned for the upcoming refueling outage) i) RPVH and CRDM nozzle configurations ii) RPVH insulation configuration The drawings listed above should include fabrication drawings for the nozzle attachment welds as applicable.

c) Copy of NDE reports from the last RPVH examination.

d) Copy of evaluation or calculation demonstrating that the scope of the visual examination of the upper head will meet the 95 percent minimum coverage required by NRC Order EA-03-009 (If a visual examination is planned for the upcoming refueling outage).

e) Provide a copy of the procedures that will be used to identify the source of any boric acid deposits identified on the RPVH. If no explicit procedures exist which govern this activity, provide a description of the Enclosure

process to be followed including personnel responsibilities and expectations.

f) Provide a copy of the updated calculation of effective degradation years (EDY) for the RPVH susceptibility ranking.

g) Provided copy of the vendor qualification report(s) that demonstrates the detection capability of the NDE equipment used for the RPVH examinations. Also, identify any changes in equipment configurations used for the RPVH examinations which differ from that used in the vendor qualification report(s).

B.3 Boric Acid Corrosion Program (BACCP) a) Please provided boric acid walk down inspection results, an updated list of boric acid leaks identified so far this outage, associated corrective action documentation, and overall status of planned boric acid inspections.

b) Please provide any engineering evaluations completed for boric acid leaks identified since the end of the last refueling outage. Please include a status of corrective actions to repair and/or clean these boric acid leaks.

Please specifically which known leaks, if any, have remained in service or will remain in service as active leaks.

c) In accordance with NRC Inspection Procedure 71111.08, the inspector(s) would like to conduct an independent boric acid walk down of the reactor building early in the inspection week. Please have knowledgeable BACCP staff available to accompany the inspector(s) during the walk down.

B.4 Codes and Standards a) Ready access, upon request to i) Applicable editions of the ASME Code (Sections V, IX and XI) for the inservice inspection program and the repair/replacement program.

ii) EPRI and industry standards referenced in the procedures used to perform the SG tube eddy current examination.

Enclosure

Inspector Contact Information Breck Henderson Shiattin Makor Reactor Inspector Reactor Inspector 817-276-6569 817-276-6507 breck.henderson@nrc.gov shiattin.makor@nrc.gov Mailing Address:

US NRC Region 4 ATTN: Breck Henderson 612 East Lamar Blvd., Suite 400 Arlington, TX 76011 Enclosure