ML092430473
| ML092430473 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 08/31/2009 |
| From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
| To: | Conway J Pacific Gas & Electric Co |
| References | |
| IR-09-005 | |
| Download: ML092430473 (14) | |
See also: IR 05000323/2009005
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
August 31, 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 2 - NOTIFICATION OF INSPECTION
(NRC INSPECTION REPORT 05000323/2009005) AND REQUEST FOR
INFORMATION
Dear Mr. Keenan:
From October 13-23, 2009, reactor inspectors from the U. S. Nuclear Regulatory
Commissions (NRC) Region IV office will perform the baseline inservice inspection at Diablo
Canyon, using NRC Inspection Procedure 71111.08, Inservice Inspection Activities, Inspection
Procedure 71007, Reactor Vessel Head Replacement, 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 (Section A of the enclosure) identified 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
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 Shiattin Makor (817) 276-6507
(shiattin.makor@nrc.gov) or Gerond George at (817) 276-6562 (gerond.george@nrc.gov).
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).
Pacific Gas and Electric Company -2-
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
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
Pacific Gas and Electric Company -3-
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
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 -4-
Electronic distribution by RIV:
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
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
Diablo Canyon Independent Safety Committee
Attn: 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
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 31)
Sacramento, CA 95814
Pacific Gas and Electric Company -5-
James R. Becker, Site Vice President &
Station Director
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
Chief, Technological Hazards Branch
FEMA Region IX
1111 Broadway, Suite 1200
Oakland, CA 94607-4052
Pacific Gas and Electric Company -6-
Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov)
Deputy Regional Administrator (Chuck.Casto@nrc.gov)
DRP Director (Dwight.Chamberlain@nrc.gov)
DRP Deputy Director (Anton.Vegel@nrc.gov)
DRS Director (Roy.Caniano@nrc.gov)
DRS Deputy Director (Troy.Pruett@nrc.gov)
Senior Resident Inspector (Michael.Peck@nrc.gov)
Resident Inspector (Tony.Brown@nrc.gov)
Branch Chief, DRP/B (Vincent.Gaddy@nrc.gov)
Senior Project Engineer, DRP/B (Rick.Deese@nrc.gov)
DC Site Secretary (Agnes.Chan@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
Regional Counsel (Karla.Fuller@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
OEMail Resource
OEDO RIV Coordinator (Leigh.Trocine@nrc.gov)
SUNSI Review Completed: ___Y___ ADAMS: 7 Yes No Initials: ___STM_
7 Publicly Available Non-Publicly Available Sensitive 7 Non-Sensitive
RI:EB1 RI:EB1 C:EB1
STMakor GAGeorge TFarnholtz
/RA/ /RA/ /RA/
8/31/09 8/31/09 8/31/09
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: October 13 - 23, 2009
Inspection Procedures: IP 71111.08 Inservice Inspection (ISI) Activities
TI 2515/172 Reactor Coolant System Dissimilar Metal Butt Welds
Inspectors: Shiattin Makor, Reactor Inspector (Lead Inspector - ISI)
Gerond George, 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 Shiattin Makor, by October 5,
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 inspector(s), 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) Examinations planned for Alloy 82/182/600 components that are not
included in the Section XI scope (If applicable).
iii) Examinations planned as part of your Boric Acid Corrosion Control
Program (Mode 3 walkdowns, bolted connection walkdowns, etc.).
-1- Enclosure
iv) 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 & 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 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 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. 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.
A.2 New Reactor Pressure Vessel Head (RPVH) (If not previously provided per IP 71007)
a) Updated schedule of all manufacturing and installation activities.
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 NDE of the new reactor vessel head (flaw
indications).
-2- Enclosure
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 walkdown inspections performed as part of the
BACCP.
c) Please provide a copy of the most recent self-assessment performed for the
BACCP.
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) SG secondary side inspection activities for the upcoming outage (If
occurring).
b) Please 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 TSTF-449, please provide copies of your correspondence with
the NRC regarding deviations from the STS.
d) Copy of SG history documentation given to vendors performing eddy current (ET)
testing of the SGs during the upcoming outage.
e) Copy of SG Eddy Current Data Analyst Guidelines and Site Validated Eddy
Current Technique Specification Sheets (ETSS). Additionally, please 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).
-3- Enclosure
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 SG
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 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 (MRP-139) Program Activities
a) A list of all applicable Dissimilar Metal Butt Welds (DMBWs) that were completed
by December 31, 2008.
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 postweld NDE documentation.
e) A list and schedule of any stress improvement (SI) activities planned for the
upcoming refueling outage. If none are scheduled then have qualification reports
for any SIs previously performed.
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.
-4- Enclosure
A.6 Additional information related to all ISI activities
a) A list with a brief description of ISI, BACCP, 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) 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
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
(October 13, 2009):
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, 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 the
selected welds, including documentation that welder maintained
-5- Enclosure
proficiency in the applicable welding processes specified in the WPS (at
least six 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 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
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 New Reactor Pressure Vessel Head (RPVH) (If not previously provided per IP 71007)
a) All non-conformance reports associated with the new reactor vessel head, from
initial manufacturing to installation.
b) Certified Milling Test Reports for CRDM nozzle welds and weld material rods.
c) Cladding weld records and welder qualifications.
d) Weld inspection records for CRDM nozzle welds and cladding welds.
e) NDE procedures, NDE records of welds, and NDE personnel qualifications.
f) Weld records, inspection records, and welder qualifications for attachment welds
on the new reactor pressure vessel head.
g) A list of the standards and/or requirements that will be used to evaluate
indications identified during NDE of the new reactor vessel head (flaw
indications).
h) Provide drawings showing the following: (If a visual examination is planned for
the upcoming refueling outage).
-6- Enclosure
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.
B.3 Boric Acid Corrosion Control Program (BACCP)
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.
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 (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.
c) Please 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) Please 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
inservice inspection program and the repair/replacement program.
-7- Enclosure
ii) EPRI and industry standards referenced in the procedures used to
perform the SGT eddy current examination.
Inspector Contact Information:
Reactor Inspector Reactor Inspector
817-276-6507 817-276-6562
shiattin.makor@nrc.gov gerond.george@nrc.gov
Mailing Address:
US NRC Region IV
Attn: Shiattin Makor
612 E. Lamar Blvd, Suite 400
Arlington, TX 76011
-8- Enclosure