ML092720921
| ML092720921 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 09/29/2009 |
| From: | Ray Kellar Region 4 Engineering Branch 1 |
| To: | Kowalewski J Entergy Operations |
| References | |
| IR-09-005 | |
| Download: ML092720921 (12) | |
See also: IR 05000382/2009005
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
September 29, 2009
Joseph Kowalewski, Vice President, Operations
Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3
17265 River Road
Killona, LA 70057-3093
SUBJECT: WATERFORD STEAM ELECTRIC STATION, UNIT 3 - NOTIFICATION OF
INSPECTION (NRC INSPECTION REPORT 05000382/2009005) AND
REQUEST FOR INFORMATION
Dear Mr. Kowalewski:
From November 2-13, 2009, reactor inspectors from the U. S. Nuclear Regulatory
Commissions (NRC) Region IV office will perform the baseline inservice inspection at the
Waterford Steam Electric Station, Unit 3, using NRC Inspection Procedure 71111.08, "Inservice
Inspection Activities," and Temporary Instruction 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 and information required for these inspection activities with
your staff and understand that our regulatory contact for this inspection will be Mr. Jim Pollock 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 Ramon Azua at (817) 319-4376
(ray.azua@nrc.gov) or Michael Bloodgood at (817) 276-6544 (michael.bloodgood@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).
Entergy Operations, Inc. -2-
Sincerely,
/RA/
Ray Kellar, P.E., Chief
Engineering Branch 1
Division of Reactor Safety
Docket: 50-382
License: NPF-38
Enclosure:
Inservice Inspection Document Request
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
Director
Nuclear Safety Assurance
Entergy Operations, Inc.
17265 River Road
Killona, LA 70057-0751
Entergy Operations, Inc. -3-
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 70821-9154
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
Chief, Technological Hazards
Branch
FEMA Region VI
800 North Loop 288
Federal Regional Center
Denton, TX 76209
Entergy Operations, Inc. -4-
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 (Mark.Haire@nrc.gov)
Resident Inspector (Dean.Overland@nrc.gov)
Branch Chief, DRP/E (Jeff.Clark@nrc.gov)
Senior Project Engineer, DRP/E (Ray.Azua@nrc.gov)
WAT Site Secretary (Linda.Dufrene@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
Inspection Reports/MidCycle and EOC Letters to the following:
ROPreports
OEDO RIV Coordinator (Leigh.Trocine@nrc.gov)
SUNSI Review Completed: ___Y___ ADAMS: 7 Yes No Initials: _RVA
7 Publicly Available Non-Publicly Available Sensitive 7 Non-Sensitive
R:\REACTORS\W3 ISI RFI - RVA ML09270921
SPE:DRP/PBE RI:DRS/EB1 C:DRS/EB1
RVAzua MRBloodgood RLKellar
/RA/ /RA/ /RA/
09/29/09 09/29/09 09/29/09
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: November 2-13, 2009
Inspection Procedures: IP 71111.08 "Inservice Inspection (ISI) Activities"
TI 2515/172 "Reactor Coolant System Dissimilar Metal Butt Welds"
Inspectors: Ramon Azua, Senior Project Engineer (Lead Inspector - ISI)
Michael Bloodgood, 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 Ramon Azua, by October 26,
2009, to facilitate the selection of specific items that will be reviewed during the onsite
inspection week. The inspector will select specific items from the information requested
below and then request from your staff additional documents needed during the onsite
inspection week (Section B of this enclosure). We ask that the specific items selected
from the lists be available and ready for review on the first day of inspection. *Please
provide requested documentation electronically if possible. If requested documents are
large and only hard copy formats are available, please inform the 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.)
-1- Enclosure
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 & 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 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 commitments made in response to NRC Bulletin 2002-02
and NRC Order EA-03-009 or ASME Code Case N-729-1. Also, include
examination scope expansion criteria and planned expansion sample sizes if
relevant conditions 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
-2- Enclosure
industry or procedural standards which will be used to evaluate potential leakage
and/or flaw indications).
A.3 Boric Acid Corrosion Control Program (BACCP)
a) Copy of the procedures that govern the scope, equipment and implementation of
the inspections required to identify boric acid leakage and the procedures for
boric acid leakage/corrosion evaluation.
b) Please provide a list of leaks (including Code class of the components) that have
been identified since the last refueling outage and associated corrective action
documentation. If during the last cycle, the Unit was shutdown, please provide
documentation of containment 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.
-3- Enclosure
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 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, with verification, that the baseline inspections of all applicable Dissimilar
Metal Butt Welds (DMBWs) have been completed by September 30, 2009.
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 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 (November
2, 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.
-5- Enclosure
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 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 Reactor Pressure Vessel Head (RPVH)
a) Provide the NDE personnel qualification records for the examiners who will
perform examinations of the RPVH.
b) Provide drawings showing the following: (If a visual examination is planned for
the upcoming refueling outage)
i) RPVH and CRDM nozzle configurations
ii) RPVH insulation configuration
The drawings listed above should include fabrication drawings for the nozzle attachment
welds as applicable.
c) Copy of NDE reports from the last RPVH examination.
d) Copy of evaluation or calculation demonstrating that the scope of the visual
examination of the upper head will meet the 95 percent minimum coverage
required by NRC Order EA-03-009 or ASME Code Case N-729-1 (If a visual
examination is planned for the upcoming refueling outage).
-6- Enclosure
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 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.
-7- Enclosure
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.
ii) EPRI and industry standards referenced in the procedures used to
perform the SGT eddy current examination.
Inspector Contact Information:
Ramon Azua Michael Bloodgood
Senior Project Engineer Reactor Inspector
817-319-4376 817-276-6544
ray.azua@nrc.gov michael.bloodgood@nrc.gov
Mailing Address:
US NRC Region IV
Attn: Ramon Azua
612 E. Lamar Blvd, Suite 400
Arlington, TX 76011
-8- Enclosure