ML102300672

Notification of Inspection (NRC Inspection Report 05000362005) and Request for Information

ML102300672
Person / Time
Site:	San Onofre
Issue date:	08/18/2010
From:	Greg Werner NRC/RGN-IV/DRS/PSB-2
To:	Ridenoure R Southern California Edison Co
References
Download: ML102300672 (13)

See also: IR 05000036/2020005

Text

August 18, 2010

Mr. Ross T. Ridenoure

Senior Vice President and

Chief Nuclear Officer

Southern California Edison Company

San Onofre Nuclear Generating Station

P.O. Box 128

San Clemente, CA 92674-0128

SUBJECT:

SAN ONOFRE NUCLEAR GENERATING STATION UNIT 3 - NOTIFICATION

OF INSPECTION (NRC INSPECTION REPORT 05000362005) AND REQUEST

FOR INFORMATION

Dear Mr.Ridenoure:

From November 29 to December 10, 2010, reactor inspectors from the U.S. Nuclear Regulatory

Commissions (NRC) Region IV office will perform the baseline inservice inspection at San

Onofre Nuclear Generating Station Unit 3, using NRC Inspection Procedure 71111.08,

Inservice Inspection Activities, and TI 2515/172, Reactor Coolant System Dissimilar Metal

Butt Welds. Experience has shown that this inspection is a resource intensive inspection both

for the NRC inspectors and your staff. In order to minimize the impact to your onsite 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, due by

September 1, 2010, (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 Mr. Dave Axeline of your licensing

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 Jim Drake, at (817) 276-6558 or (James.Drake@nrc.gov).

This letter does not contain new or amended information collection requirements subject to the

Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection

requirements were approved by the Office of Management and Budget, Control

UNITED STATES

NUCLEAR REGULATORY COMMISSION

R E GI ON I V

612 EAST LAMAR BLVD, SUITE 400

ARLINGTON, TEXAS 76011-4125

Southern California Edison Company

- 2 -

Number 3150 0011. The NRC may not conduct or sponsor, and a person is not required to

respond to, a request for information or an information collection requirement unless the

requesting document displays a currently valid Office of Management and Budget control

number.

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/

Gregory E. Werner, Chief

Plant Support Branch 2

Division of Reactor Safety

Docket: 50-362

License: NPF-15

Enclosure:

Inservice Inspection Document Request

Chairman, Board of Supervisors

County of San Diego

1600 Pacific Highway, Room 335

San Diego, CA 92101

Gary L. Nolff

Assistant Director-Resources

City of Riverside

3900 Main Street

Riverside, CA 92522

Mark L. Parsons

Deputy City Attorney

City of Riverside

3900 Main Street

Riverside, CA 92522

Gary H. Yamamoto, P.E., Chief

Division of Drinking Water and

Environmental Management

1616 Capitol Avenue, MS 7400

P.O. Box 997377

Sacramento, CA 95899-7377

Southern California Edison Company

- 3 -

Michael L. DeMarco

San Onofre Liaison

San Diego Gas & Electric Company

8315 Century Park Ct. CP21C

San Diego, CA 92123-1548

Director, Radiological Health Branch

State Department of Health Services

P.O. Box 997414 (MS 7610)

Sacramento, CA 95899-7414

The Mayor of the City of San Clemente

100 Avenida Presidio

San Clemente, CA 92672

James D. Boyd, Commissioner

California Energy Commission

1516 Ninth Street (MS 34)

Sacramento, CA 95814

Douglas K. Porter, Esquire

Southern California Edison Company

2244 Walnut Grove Avenue

Rosemead, CA 91770

Albert R. Hochevar

Southern California Edison Company

San Onofre Nuclear Generating Station

P.O. Box 128

San Clemente, CA 92674-0128

Steve Hsu

Department of Health Services

Radiologic Health Branch

MS 7610, P.O. Box 997414

Sacramento, CA 95899-7414

R. St. Onge

Southern California Edison Company

San Onofre Nuclear Generating Station

P.O. Box 128

San Clemente, CA 92674-0128

Chief, Technological Hazards Branch

FEMA Region IX

1111 Broadway, Suite 1200

Oakland, CA 94607-4052

Southern California Edison Company

- 4 -

Institute of Nuclear Power Operations (INPO)

Records Center

700 Galleria Parkway SE, Suite 100

Atlanta, GA 30339

Southern California Edison Company

- 5 -

Electronic distribution by RIV:

Regional Administrator (Elmo.Collins@nrc.gov)

Deputy Regional Administrator (Chuck.Casto@nrc.gov)

Acting DRP Director (Tony.Vegel@nrc.gov)

Acting DRP Deputy Director (Troy.Pruett@nrc.gov)

DRS Director (Roy.Caniano@nrc.gov)

Acting DRS Deputy Director (Jeff.Clark@nrc.gov)

Senior Resident Inspector (Greg.Warnick@nrc.gov)

Resident Inspector (John.Reynoso@nrc.gov)

Branch Chief, DRP/D (Ryan.Lantz@nrc.gov)

Senior Project Engineer, DRP/D (Don.Allen@nrc.gov)

SONGS Administrative Assistant (Heather.Hutchinson@nrc.gov)

Project Engineer, DRP/D (Peter.Jayroe@nrc.gov)

Project Engineer, DRP/D (Zachary.Hollcraft@nrc.gov)

Public Affairs Officer (Victor.Dricks@nrc.gov)

Public Affairs Officer (Lara.Uselding@nrc.gov)

Project Manager (Randy.Hall@nrc.gov)

Branch Chief, DRS/TSB (Michael.Hay@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

Regional Counsel (Karla.Fuller@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov)

OEMail Resource

Inspection Reports/MidCycle and EOC Letters to the following:

ROPreports

Only inspection reports to the following:

DRS/TSB STA (Dale.Powers@nrc.gov)

OEDO RIV Coordinator (Margie.Kotzalas@nrc.gov)

SUNSI Review Completed: ___Y___

ADAMS: 7 Yes

No Initials: ___JFD_

7 Publicly Available Non-Publicly Available Sensitive

7 Non-Sensitive

R:_Reactors/_SONGS/2010/2010005-LTR-JFD.docx ML

RI:EB1

C:PSB2

JDrake

GWerner

8/16/2010

8/18/2010

OFFICIAL RECORD COPY T=Telephone

E=E-mail

F=Fax

- 1 -

Enclosure

INSERVICE INSPECTION DOCUMENT REQUEST

Inspection Dates:

November 29 through December 10, 2010

Inspection Procedures:

IP 71111.08 Inservice Inspection (ISI) Activities

TI 2515/172 Reactor Coolant System Dissimilar Metal Butt Welds

Inspectors:

J. Drake, Senior Reactor Inspector (Lead Inspector - ISI)

S. Makor, Reactor Inspector

A. Fairbanks, 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 (ims.certrec.com preferred), in care of Jim Drake, by

September 1, 2010, to facilitate the selection of specific items that will be reviewed

during the onsite inspection week. The inspectors 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 & 2 systems

and containment, performed as part of your ASME,Section XI, Risk

Informed (if applicable), and augmented ISI programs during the

upcoming outage.

Provide 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 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).

- 2 -

Enclosure

iv)

Examinations planned as part of your Boric Acid Corrosion Control

Program (Mode 3 walkdowns, bolted connection walkdowns, 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 penetrate,

Visual VT-1, VT-2, and VT-3), which have identified relevant conditions on Code

Class 1 and 2 systems since the beginning of the last refueling outage. This

should include the previousSection XI pressure test(s) conducted during start up

and any evaluations associated with the results of the pressure tests. Also,

include in the list the NDE reports with relevant conditions in the reactor pressure

vessel head penetration nozzles that have been accepted for continued service.

The list of NDE reports should include a brief description of the SSC where the

relevant condition 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. 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 noncode 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.

A.2

Reactor Pressure Vessel Head

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 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 conditions are identified (if

applicable).

- 3 -

Enclosure

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

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)

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, provide

documentation of containment walkdown inspections performed as part of the

Boric Acid Corrosion Control Program.

c)

Provide a copy of the most recent self-assessment performed for the Boric Acid

Corrosion Control Program.

A.4

Steam Generator Tube (SGT) Inspections

a)

A detailed schedule of:

i)

SGT inspection, data analyses, and repair activities for the upcoming

outage (if occurring).

ii)

Steam Generator (SG) secondary side inspection activities for the

upcoming outage (if occurring).

b)

Provide a copy of your SG ISI Inspection Program and Plan. Please include a

copy of the Operational Assessment from last outage and a copy of the following

documents as they become available:

i)

Degradation Assessment

ii)

Condition Monitoring Assessment

c)

If you are planning on modifying your technical specifications such that they are

consistent with Technical Specification Task Force-449, provide copies of your

correspondence with the NRC regarding deviations from the standard technical

specifications.

d)

Copy of SG history documentation given to vendors performing Eddy Current

(ET) testing of the SGs during the upcoming outage.

- 4 -

Enclosure

e)

Copy of SG Eddy Current Data Analyst Guidelines and Site Validated Eddy

Current Technique Specification Sheets (ETSS). Additionally, provide a copy of

EPRI, Appendix H, ETSS Qualification Records.

f)

Identify and quantify any SGT leakage experienced during the previous operating

cycle. Also provide documentation identifying which SG was leaking and

corrective actions completed or planned for this condition (If applicable).

g)

Provide past history of the condition and issues pertaining to the secondary side

of the SG (including items such as loose parts, fouling, top of tube sheet

condition, crud removal amounts, etc.).

h)

Provide copies of your most recent self-assessments of the SG monitoring, loose

parts monitoring, and secondary side water chemistry control programs.

i)

Indicate where the primary, secondary, and resolution analyses are scheduled to

take place.

j)

Provide a summary of the scope of the SGT examinations, including examination

methods such as bobbin, rotating pancake, or plus point, and the percentage of

tubes to be examined. *Do not provide these documents separately if already

included in other information requested.

A.5

Materials Reliability Program (MRP-139) Activities

a)

A list of, with verification, that the baseline inspections of all applicable Dissimilar

Metal Butt Welds (DMBWs) have been completed by July 31 2010.

b)

Verification that baseline inspection of hot-leg and cold-leg temperature DMBWs

have been included in the inspection program and that the schedules for the

baseline inspections are consistent with the baseline schedules in MRP-139.

c)

A list and schedule (examination dates) of all DMBW examinations planned for

the upcoming refueling outage. If none are scheduled, then data from previous

examinations should be available for review.

d)

A list and schedule for any welding to be performed on DMBWs in the upcoming

outage. If no welding will be performed then records of previous welding on

DMBWs and post-weld NDE documentation.

e)

A list and schedule of any stress improvement activities planned for the

upcoming refueling outage. If none are scheduled then have qualification reports

for any stress improvements previously performed.

f)

Documentation and description of how the baseline and ISI specifications in

MRP-139 are satisfied at your facility.

- 5 -

Enclosure

g)

A list of weld locations controlled by MRP-139, which includes the MRP-139 weld

category, pre-mitigation volumetric examination date, type of mitigation or stress

improvement, post-mitigation volumetric examination date, and plans for future

MRP-139 required examinations.

A.6

Additional information related to all ISI activities

a)

A list with a brief description of ISI, Boric Acid Corrosion Control Program, and

SGT inspection 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/SGT examinations.

b)

Provide names and phone numbers for the following program leads:

ISI contacts (examination, planning)

Containment Examinations

RPVH Examinations

Snubbers and Supports

Repair and Replacement Program Manager

Licensing Contact

Site Welding Engineer

Boric Acid Corrosion Control Program

SG Inspection Activities (site lead and vendor contact)

B.

Information to be provided onsite to the inspector(s) at the entrance meeting

(November 29, 2010).

B.1

ISI / Welding Programs and Schedule Information

a)

Updated schedules for ISI/NDE activities, including SGT inspections, planned

welding activities, and schedule showing contingency repair plans, if available.

b)

For ASME, Code Class 1 and 2 welds selected by the inspector from the lists

provided from Section A of this enclosure, 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 used to fabricate the welds

- 6 -

Enclosure

vi)

Copies of procedure qualification records supporting the weld procedures

from B.1.b.v

vii)

Copies of mechanical test reports identified in the procedure qualification

records 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 the

selected welds, including documentation that welder maintained

proficiency in the applicable welding processes specified in the weld

procedures (at least 6 months prior to the date of subject work)

xii)

Copies of NDE personnel qualifications (VT, PT, UT, RT), as applicable

c)

For the ISI related corrective action issues selected by the inspector(s) from

Section A of this enclosure, provide a copy of the corrective actions and

supporting documentation.

d)

For the NDE reports with relevant conditions on Code Class 1 & 2 systems

selected by the inspectors 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 inspectors from Section A of this enclosure,

provide 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 qualification 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 reactor pressure vessel head

- 7 -

Enclosure

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 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)

Provide 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 Control Program

a)

Provide boric acid walkdown 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)

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 identify specifically

which known leaks, if any, have remained in service or will remain in service as

active leaks.

B.4

SGT Inspections

a)

Copies of the Examination Technique Specification Sheets (ETSS) and

associated justification for any revisions.

b)

Copy of the guidance to be followed if a loose part or foreign material is identified

in the SGs.

- 8 -

Enclosure

c)

Provide a copy of the ET procedures used to perform the SGT inspections

(specifically calibration and flaw characterization/sizing procedures, etc.). Also

include documentation for the specific equipment to be used.

d)

Provide copies of your responses to NRC and industry operating experience

communications such as Generic Letters, Information Notices, etc. (as applicable

to SGT inspections) *Do not provide these documents separately if already

included in other information requested such as the degradation assessment.

e)

List of corrective action documents generated by the vendor and/or site with

respect to SG inspection activities.

B.5

Codes and Standards

a)

Ready access to (i.e., copies provided to the inspector(s) for use during the

inspection at the onsite inspection location, or room number and location where

available):

i)

Applicable Editions of the ASME Code, Sections V, IX and XI for the ISI

program and the repair/replacement program.

ii)

EPRI and industry standards referenced in the procedures used to

perform the SGT Eddy Current examination.

Inspector Contact Information:

Jim Drake

Abin Fairbanks

Shiattin Makor

Senior Reactor Inspector

Reactor Inspector

Reactor Inspector

817-276-6558

817-860-8158

817-276-6507

James.Drake@nrc.gov

Abin.Fairbanks@nrc.gov

Shiattin.Makor@nrc.gov

Mailing Address:

US NRC Region IV

Attn: Jim Drake

612 E. Lamar Blvd, Suite 400

Arlington, TX 76011