ML102450743

Notification of Inspection (NRC Integrated Inspection Report 05000275-10-005) and Request for Information

ML102450743
Person / Time
Site:	Diablo Canyon
Issue date:	09/01/2010
From:	Greg Werner NRC/RGN-IV/DRS/PSB-2
To:	Conway J Pacific Gas & Electric Co
References
Download: ML102450743 (13)

See also: IR 05000275/2010005

Text

UN IT E D S T A T ES

NU C LE A R R E G U L AT O R Y C O M M IS S IO N

R E G IO N IV

6 12 E AST LAM AR BL VD , S U IT E 400

A R L IN G T O N , T E X A S 7 6 0 1 1 -41 25

September 1, 2010

John T. Conway

Senior Vice President and

Chief Nuclear Officer

Pacific Gas and Electric Company

77 Beale Street, B32

San Francisco, CA

SUBJECT: DIABLO CANYON POWER PLANT UNIT 1 - NOTIFICATION OF INSPECTION

(NRC INTEGRATED INSPECTION REPORT 05000275/2010005) AND

REQUEST FOR INFORMATION

Dear Mr. Conway:

From October 4 through 22, 2010, reactor inspectors from the U.S. Nuclear Regulatory

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

Diablo Canyon Power Plant Unit 1, using NRC Inspection Procedure 71111.08, Inservice

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

NRC Inspection Procedure 71007, Reactor Vessel Head Replacement Inspection. 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 24,

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. M. McCoy 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 Ronald A. Kopriva at (817) 860-8104 (ron.kopriva@nrc.gov) or

Isaac A. Anchondo at (817) 860-8152 (Isaac.anchondo@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,

Pacific Gas and Electric Company -2-

Control 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: 50-275

License: DPR-80

Enclosure:

Inservice Inspection Document Request

cc:

Sierra Club San Lucia Chapter

ATTN: Andrew Christie

P.O. Box 15755

San Luis Obispo, CA 93406

Jane Swanson

San Luis Obispo

Mothers for Peace

P.O. Box 3608

San Luis Obispo, CA 93403

James Grant, County Administrative Officer

San Luis Obispo County Board of

Supervisors

1055 Monterey Street, Suite D430

San Luis Obispo, CA 93408

Pacific Gas and Electric Company -3-

Truman Burns\Robert Kinosian

California Public Utilities Commission

505 Van Ness Ave., Rm. 4102

San Francisco, CA 94102

Jennifer Post, Esq.

Pacific Gas & Electric Co.

77 Beale Street, Room 2496

Mail Code B30A

San Francisco, CA 94120

Gary Butner

Chief, Radiologic Health Branch

California Department of Public Health 3

P.O. Box 997414 (MS 7610)

Sacramento, CA 95899-7414

The City Editor of

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 31)

Sacramento, CA 95814

James R. Becker, Site Vice President

Pacific Gas and Electric Company

Diablo Canyon Nuclear Plant

P.O. Box 56, Mail Station 104/6/601

Avila Beach, CA 93424

Jennifer Tang

Field Representative

United States Senator Barbara Boxer

1700 Montgomery Street, Suite 240

San Francisco, CA 94111

Chief, Technological Hazards Branch

FEMA Region IX

1111 Broadway, Suite 1200

Oakland, CA 94607-4052

Pacific Gas and Electric Company -4-

Electronic distribution by RIV:

Regional Administrator (Elmo.Collins@nrc.gov)

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

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

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

DRS Director (Roy.Caniano@nrc.gov)

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

Senior Resident Inspector (Michael.Peck@nrc.gov)

Resident Inspector (Tony.Brown@nrc.gov)

Branch Chief, DRP/B (Geoffrey.Miller@nrc.gov)

Senior Project Engineer, DRP/B (Rick.Deese@nrc.gov)

Project Engineer, DRP/B (Greg.Tutak@nrc.gov)

Project Engineer, DRP/B (Nestor.Makris@nrc.gov)

Reactor Inspector, DRP/B (Christie.Denissen@nrc.gov)

DC Administrative Assistant (Agnes.Chan@nrc.gov)

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

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

Project Manager (Alan.Wang@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

ROPreports

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

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

Executive Technical Assistant (John.Giessner@nrc.gov)

R:_\REACTORS\DC\ 2010005 Unit 1 ISI RFI-RAK ADAMS ML

ADAMS: No Yes SUNSI Review Complete Reviewer Initials:

Publicly Available Non-Sensitive

Non-publicly Available Sensitive

RI:EB1 C:EB1

R. Kopriva T. Farnholtz

/RA/ /RA/

8/30/10 9/1/10

OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

INSERVICE INSPECTION DOCUMENT REQUEST

Inspection Dates: October 4 through 22, 2010

Inspection Procedures: IP 71111.08 Inservice Inspection (ISI) Activities

IP 71007 Reactor Head Replacement Inspection

TI 2515/172 Reactor Coolant System Dissimilar Metal Butt Welds

Inspectors: Ronald A. Kopriva, Senior Reactor Inspector (Lead Inspector - ISI)

Isaac A. Anchondo, 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 Ronald A. Kopriva by

September 24, 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

inspectors as soon as possible.

A.1 ISI / Welding Programs and Schedule Information

a) A detailed schedule (including preliminary dates) of:

i) Nondestructive examinations planned for Class 1 & 2 systems and

containment, performed as part of your ASME,Section XI, risk informed

(if applicable), and augmented inservice inspection programs during the

upcoming outage

Provide a status summary of the nondestructive examination 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)

-1- 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)

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 nondestructive examination reports (ultrasonic, radiography, magnetic

particle, dye penetrate, Visual VT-1, VT-2, and VT-3), which have identified

relevant conditions on Code Class 1 & 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 nondestructive examination reports

with relevant conditions in the reactor pressure vessel head penetration nozzles

that have been accepted for continued service. The list of nondestructive

examination reports should include a brief description of the structures, systems,

or components where the relevant condition was identified.

d) A list with a brief description (e.g., system, material, pipe size, weld number, and

nondestructive examinations 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 structures, systems, or

components 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 inservice

inspection, welding, and Alloy 600 programs.

A.2 New Reactor Pressure Vessel Head (If not previously provided per Inspection

Procedure 71007)

a) Updated schedule of all manufacturing and installation activities.

-2- Enclosure

b) A list of vessel welds and attachment welds on the new reactor vessel head.

c) A list of the standards and/or requirements that will be used to evaluate

indications identified during nondestructive examination of the new reactor vessel

head (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) 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 walkdown inspections performed as part of the

boric acid corrosion control program.

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

boric acid corrosion control program.

A.4 Steam Generator Tube Inspections

a) A detailed schedule of:

i) Steam generator tube inspection, data analyses, and repair activities for

the upcoming outage (If occurring)

ii) Steam generator secondary side inspection activities for the upcoming

outage. (If occurring)

b) Please provide a copy of your steam generator inservice inspection program and

plan. Please include a copy of the operational assessment from the 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 Traveler TSTF-449, Steam

Generator Tube Integrity, please provide copies of your correspondence with the

NRC regarding deviations from the standard technical specifications.

d) Copy of steam generator history documentation given to vendors performing

Eddy Current testing of the steam generators during the upcoming outage.

e) Copy of steam generator Eddy Current data analyst guidelines and site validated

Eddy Current technique specification sheets. Additionally, please provide a copy

-3- Enclosure

of EPRI, Appendix H, examination technique specification sheets qualification

records.

f) Identify and quantify any steam generator tube leakage experienced during the

previous operating cycle. Also provide documentation identifying which steam

generator 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 steam generators (including items such as loose parts, fouling, top of tube

sheet condition, crud removal amounts, etc.).

h) Please provide copies of your most recent self-assessments of the steam

generator monitoring, loose parts monitoring, and secondary side water

chemistry control programs.

i) Please also indicate where the primary, secondary, and resolution analyses are

scheduled to take place.

j) Please provide a summary of the scope of the steam generator tube

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): Primary System Piping Butt Weld Inspection

and Evaluation Guideline Activities

a) A list with verification that the baseline inspections of all applicable dissimilar

metal butt welds have been completed and any dissimilar metal butt welds that

have not been completed with justification for not having completed.

b) Verification that baseline inspection of hot leg and cold leg temperature dissimilar

metal butt welds 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 dissimilar metal butt weld

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 dissimilar metal butt

welds in the upcoming outage. If no welding will be performed then records of

previous welding on dissimilar metal butt welds and postweld nondestructive

examination documentation.

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

upcoming refueling outage. If none are scheduled, then qualification reports for

any stress improvements previously performed should be available for review.

-4- Enclosure

f) Documentation and description of how the baseline and inservice inspection

specifications in MRP-139 are satisfied at your facility.

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 Inservice Inspection Activities

a) A list with a brief description of inservice inspection, boric acid corrosion control

program, and steam generator tube inspection related issues (e.g., condition

reports) entered into your corrective action program since the beginning of the

last refueling outage (for Unit 1). For example, a list based upon data base

searches using key words related to piping or steam generator tube degradation

such as: inservice inspection, ASME Code,Section XI, nondestructive

examination, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors

in piping/steam generator tube examinations.

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

Inservice inspection contacts (examination, planning)

Containment exams

Reactor pressure vessel head exams

Snubbers and supports

Repair and replacement program manager

Licensing contact

Site welding engineer

Boric acid corrosion control program

Steam generator inspection activities (site lead and vendor contact)

B. Information to be provided onsite to the inspectors at the entrance meeting

(October 4, 2010):

B.1 ISI/Welding Programs and Schedule Information

a) Updated schedules for inservice inspection/nondestructive examination activities,

including steam generator tube inspections, planned welding activities, and

schedule showing contingency repair plans, if available.

b) For ASME, Code Class 1 and 2 welds selected by the inspectors 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

-5- Enclosure

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

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 radiographic testing 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 nondestructive examination personnel qualifications (Visual

inspection, penetrant testing, ultrasonic testing, radiographic testing), as

applicable

c) For the inservice inspection related corrective action issues selected by the

inspectors from Section A of this enclosure, provide a copy of the corrective

actions and supporting documentation.

d) For the nondestructive examination reports with relevant conditions on Code

Class 1 and 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) the most current revision of the inservice

inspection program manual and plan for the current Interval.

f) For the nondestructive examinations selected by the inspectors from Section A of

this enclosure, provide a copy of the nondestructive examination 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

-6- Enclosure

qualification documentation of the specific equipment to be used (e.g., ultrasonic

unit, cables, and transducers including serial numbers) and nondestructive

examination personnel qualification records.

B.2 Reactor Pressure Vessel Head

a) Provide the nondestructive personnel qualification records for the examiners who

will perform examinations of the reactor pressure vessel head

b) Provide drawings showing the following: (If a visual examination is planned for

the upcoming refueling outage)

i) Reactor pressure vessel head and control rod drive mechanism nozzle

configurations

ii) Reactor pressure vessel head insulation configuration

The drawings listed above should include fabrication drawings for the nozzle attachment

welds as applicable.

c) Copy of nondestructive examination reports from the last reactor pressure vessel

head 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 reactor pressure vessel head. 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 for the

reactor pressure vessel head susceptibility ranking.

g) Provide a copy of the vendor qualification report(s) that demonstrates the

detection capability of the nondestructive examination equipment used for the

reactor pressure vessel head examinations. Also, identify any changes in

equipment configurations used for the reactor pressure vessel head

examinations which differ from that used in the vendor qualification report(s).

B.3 Boric Acid Corrosion Control Program

a) Please 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.

-7- Enclosure

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 identify

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

service as active leaks.

B.4 Steam Generator Tube Inspections

a) Copies of the examination technique specification sheets 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 steam generators.

c) Please provide a copy of the Eddy Current testing procedures used to perform

the steam generator tube inspections (specifically calibration and flaw

characterization/sizing procedures, etc.). Also include documentation for the

specific equipment to be used.

d) Please provide copies of your responses to NRC and industry operating

experience communications such as Generic Letters, Information Notices, etc.

(as applicable to steam generator tube 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 steam generator inspection activities.

B.5 Codes and Standards

a) Ready access to (i.e., copies provided to the inspectors 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

inservice inspection program and the repair/replacement program.

ii) EPRI and industry standards referenced in the procedures used to

perform the steam generator tube Eddy Current examination.

-8- Enclosure

Inspector Contact Information:

Ronald A. Kopriva Isaac A. Anchondo

Senior Reactor Inspector Reactor Inspector

817-860-8104 817-860-8152

Ron.kopriva@nrc.gov Isaac.Anchondo@nrc.gov

Mailing Address:

US NRC Region IV

Attn: Ronald A. Kopriva

612 E. Lamar Blvd, Suite 400

Arlington, TX 76011

-9- Enclosure