ML080940624
| ML080940624 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/03/2008 |
| From: | Russ Bywater Region 4 Engineering Branch 1 |
| To: | Walsh K Entergy Operations |
| References | |
| IR-08-003 | |
| Download: ML080940624 (12) | |
See also: IR 05000382/2008003
Text
April 3, 2008
Kevin T. Walsh, Vice President
of Operations
Waterford 3
Entergy Operations, Inc.
17265 River Road
Killona, LA 70057-3093
SUBJECT:
WATERFORD 3 - NOTIFICATION OF INSPECTION (NRC INSPECTION
REPORT 05000382/2008003) AND REQUEST FOR INFORMATION
Dear Mr. Walsh,
From May 5 to May 16, 2008, reactor inspectors from the Nuclear Regulatory
Commissions (NRC) Region IV office will perform the baseline inservice inspection at
Waterford 3, using NRC Inspection Procedure 71111.08 and Temporary Instruction 2515/172,
Rector 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 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) 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. Ron Williams 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 W. Sifre at (817) 860-8193 (wcs@nrc.gov).
UNITED STATES
NUCLEAR REGULATORY COMMISSION
R E GI ON I V
612 EAST LAMAR BLVD, SUITE 400
ARLINGTON, TEXAS 76011-4005
Entergy Operations, Inc
- 2 -
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 NRC's
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/
Russell L. Bywater, Chief
Engineering Branch 1
Division of Reactor Safety
Docket: 50-382
License: NPF-38
Enclosure:
Inservice Inspection Document Request
cc: w/enclosure
Senior Vice President
Entergy Nuclear Operations
P.O. Box 31995
Jackson, MS 39286-1995
Senior Vice President and
Chief Operating Officer
Entergy Operations, Inc.
P.O. Box 31995
Jackson, MS 39286-1995
Vice President, Operations Support
Entergy Services, Inc.
P.O. Box 31995
Jackson, MS 39286-1995
Senior Manager, Nuclear Safety
and Licensing
Entergy Services, Inc.
P.O. Box 31995
Jackson, MS 39286-1995
Site Vice President
Waterford Steam Electric Station, Unit 3
Entergy Operations, Inc.
17265 River Road
Killona, LA 70057-0751
Entergy Operations, Inc
- 3 -
Director
Nuclear Safety Assurance
Entergy Operations, Inc.
17265 River Road
Killona, LA 70057-0751
General Manager, Plant Operations
Waterford 3 SES
Entergy Operations, Inc.
17265 River Road
Killona, LA 70057-0751
Manager, Licensing
Entergy Operations, Inc.
17265 River Road
Killona, LA 70057-3093
Chairman
Louisiana Public Service Commission
P.O. Box 91154
Baton Rouge, LA 70825-1697
Richard Penrod, Senior Environmental
Scientist, State Liaison Officer
Office of Environmental Services
Northwestern State University
Russsell Hall, Room 201
Natchitoches, LA 71497
Parish President Council
St. Charles Parish
P.O. Box 302
Hahnville, LA 70057
Director, Nuclear Safety & Licensing
Entergy, Operations, Inc.
440 Hamilton Avenue
White Plains, NY 10601
Louisiana Department of Environmental
Quality Radiological Emergency Planning
and Response Division
P.O. Box 4312
Baton Rouge, LA 70821-4312
Entergy Operations, Inc
- 4 -
Louisiana Department of Environmental
Quality
Office of Environmental Compliance
P.O. Box 4312
Baton Rouge, LA 70821-4312
Lisa R. Hammond, Chief
Technological Hazards Branch
National Preparedness Division
FEMA Region VI
800 N. Loop 288
Denton, TX 76209
Entergy Operations, Inc
- 5 -
Electronic distribution by RIV:
Regional Administrator (EEC)
DRP Director (DDC)
DRS Director (RJC1)
DRS Deputy Director (TWP)
Senior Resident Inspector (RVA)
Branch Chief, DRP/E (JAC)
Senior Project Engineer, DRP/E (GDR)
Team Leader, DRP/TSS (CJP)
RITS Coordinator (MSH3)
J. Adams, OEDO RIV Coordinator (JTA)
ROPreports
WAT Site Secretary (AHY)
SUNSI Review Completed: _RLB_____
ADAMS: Yes
Initials: _RLB_____
Publicly Available
Non-Sensitive
S:DRS\\REPORTS\\WT 200803 LTR-WCS.doc
SRI:EB1
RI:EB1
C:EB!
WCSifre/lmb
JHNadel
RLBywater
/RA/
/RA/
/RA/
4/2/08
4/2/08
4/3/08
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
- 1 -
Enclosure
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates:
May 5, 2008 - May 16, 2008
Inspection Procedures:
IP 71111.08 Inservice Inspection (ISI) Activities
TI 2515/172 Reactor Coolant Dissimilar Metal Butt Welds
Inspectors:
W. Sifre, Senior Reactor Inspector (Lead Inspector - ISI)
J. Nadel, 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 W. Sifre, by April 21, 2008, 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 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)
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)
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))
- 2 -
Enclosure
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 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 recorded 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 recordable 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.
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)
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.
- 3 -
Enclosure
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
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).
g)
Provide past history of the condition and issues pertaining to the secondary side of the
steam generators (including items such as bat wing issues, 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
cheduled to take place.
- 4 -
Enclosure
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
Metals Reliability (MRP-139) Program Activities
a)
A list of, with verification that, the baseline inspections of all Dissimilar Metal Butt Welds
(DMBWs)have been completed by December 31, 2007.
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
coming 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 coming 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 (SI) activities planned for the coming
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.
A.6
Additional Information Related To All ISI Activities
a)
A list with a brief description of ISI and BACCP related issues (e.g., condition reports)
entered into your corrective action program since the beginning of the last refueling
outage (for the applicable Unit). For example, a list based upon data base searches
using key words related to piping such as: ISI, ASME Code,Section XI, NDE, cracks,
wear, thinning, leakage, rust, corrosion, boric acid, or errors in piping 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)
- 5 -
Enclosure
B.
Information To Be Provided Onsite To The Inspector At The Entrance Meeting
(May 5, 2008):
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 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 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.
c)
For the ISI related corrective action issues selected by the inspector 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 documentation of the specific equipment to
be used (e.g., ultrasonic unit, cables, and transducers including serial numbers) and
NDE personnel qualification records.
- 6 -
Enclosure
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% 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 (BACCP)
a)
Please provide 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.
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.
- 7 -
Enclosure
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 to use for the duration of the
inspection at the on-site 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
SGT eddy current examination.
Inspector Contact Information:
W. Sifre
J. Nadel
Senior Reactor Inspector
Reactor Inspector
817-860-8193
817-276-6547
wcs@nrc.gov
jhn@nrc.gov
Mailing Address:
US NRC Region IV
Attn: W. Sifre
611 Ryan Plaza Drive, Suite 400
Arlington, TX 76011