ML060400250
| ML060400250 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/08/2006 |
| From: | Lesser M NRC/RGN-II/DRS/EB3 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| References | |
| Download: ML060400250 (10) | |
Text
February 8, 2006 Virginia Electric and Power Company ATTN: Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060
SUBJECT:
SURRY NUCLEAR STATION, UNIT 1 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Christian:
On or about May 1 - 12, 2006, the NRC will perform the baseline inservice inspection (ISI) at the Surry Nuclear Station, Unit 1 (NRC Inspection Procedure 71111.08). Experience has shown that this inspection is resource intensive both for the NRC inspector and your staff. In order to minimize the impact to your on-site 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 identifies information to be provided prior to the inspection to ensure that the inspector is adequately prepared. The second group identifies the information the inspector 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 contacts for this inspection will be Dan Jensen and Joe Eastwood. 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 Justin Fuller at (404) 562-4655.
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/
Mark S. Lesser, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-280 License No. DPR-32
Enclosure:
See next page
VEPCO 2
Enclosure:
INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl:
Chris L. Funderburk, Director Nuclear Licensing and Operations Support Virginia Electric & Power Company Electronic Mail Distribution Donald E. Jernigan Site Vice President Surry Power Station Virginia Electric & Power Company Electronic Mail Distribution Virginia State Corporation Commission Division of Energy Regulation P. O. Box 1197 Richmond, VA 23209 Lillian M. Cuoco, Esq.
Senior Counsel Dominion Resources Services, Inc.
Electronic Mail Distribution Attorney General Supreme Court Building 900 East Main Street Richmond, VA 23219
OFFICE RII:DRS RII:DRS RII:DRP SIGNATURE /RA/ /RA/ /RA/
NAME JFuller:pmd MLesser KLandis DATE 2/9/06 2/8/06 2/9/06 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: May 1 - 12, 2006 Inspection Procedures: IP 7111108 Inservice Inspection (ISI) Activities Inspector: Justin Fuller A. Information Requested for the In-Office Preparation Week The following information should be sent to the Region II office in hard copy (or electronic format CD - preferred), in care of Justin Fuller by April 10, 2006, 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.
We ask that the specific items selected from the lists be available and ready for review on the first day of inspection. All information requests relate to Unit 1 unless otherwise stated. *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.
In accordance with NRC inspection procedure 71111.08, the inspector would like to conduct an independent boric acid walk down of the Reactor Building early in the inspection week. Please have knowledgeable BACCP staff available to accompany the inspector during the walk down.
A.1 ISI / Welding Programs and Schedule Information a) A detailed schedule of:
i) Nondestructive examinations (NDE) 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 vessel head (RPVH) examinations planned for the upcoming outage. (If applicable) iii) Examinations planned for Alloy 82/182/600 components that are not included in the Section XI scope. (If applicable)
Enclosure
2 iv) Examinations performed 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))
vi) NDE inspections (visual and/or non-visual) of the Pressurizer Penetrations (safety valve and relief valve nozzles, spray line nozzle, instrumentation and/or sample lines, surge line, heater bundles, etc.) (If Applicable) b) A copy of ASME Section XI, Code Relief Requests and associated NRC Safety Evaluations applicable to the examinations identified above. Additionally, please provide documentation associated with ASME Code Cases that are being incorporated in work activities being performed this outage.
c) A list of NDE reports (ultrasonic, radiography, magnetic particle, dye penetrant, visual VT-1, VT-2, and VT-3) which have identified recordable indications (geometric or flaw) on Code Class 1 & 2 systems since the beginning of the last refueling outage. Also, include the NDE reports with recorded indications in the RPVH penetration nozzles which have been accepted for continued service.
d) A list with a brief description 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. Please identify the system, weld number, and reference applicable documentation.
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.
i) A copy of the most current revision of the ISI Program Manual and Plan for this Interval.
(Or last revision available electronically) j) If NDE procedures are available electronically, please provide most current revision (UT for austenitic and ferritic piping welds, VT-1,2,and 3, PT, and any special procedures qualified for work described in A.1.a)
A.2 Reactor Pressure Vessel Head (RPVH) (If Applicable)
3 No information required prior to the inspection week 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 and the 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 Information related to Steam Generator (SG) inspections a) A detailed schedule of:
i) SG tube inspection 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 have modified 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. Additionally, please provide a copy of EPRI Appendix H Eddy Current Technique Qualification Records.
f) Identify and quantify any SG tube 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.)
4 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 and secondary analysis is scheduled to take place.
A.5 Additional information related to all ISI activities a) A list with a brief description of ISI and SG related issues (e.g., condition reports) entered into your corrective action program since the beginning of the last refueling outage (for Units 1 and 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/SG tube examinations.
b) Please provide names and phone numbers for the following program leads:
ISI contacts (Examination, planning)
Containment 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 on-site to the inspector at the entrance meeting (May 1, 2006):
B.1 ISI / Welding Programs and Schedule Information a) Updated schedules for ISI / NDE activities, including SG ISI, 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 part A of this enclosure, please provide copies of the following documentation for each subject weld:
i) The 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)
5 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 WPS, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS (At least six months prior to date subject work completed) xii) Copies of Inspector Certifications (VT, PT, UT, RT) As applicable c) For the ISI related corrective action issues selected by the inspector from part A of this enclosure, provide a copy of the corrective actions and supporting documentation.
d) For the nondestructive examination reports with recordable indications 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) Copy of the NDE procedures used to perform the examinations selected by the inspector from the activities identified in section A of this enclosure (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).
B.2 Reactor Pressure Vessel Head (RPVH) (If Applicable) a) Provide a list which identifies the NDE personnel who will perform inspections of the RPVH. Also, provide the qualification and certification records for these personnel. (If a visual examination is planned for the upcoming refueling outage) b) Provide drawings showing the following: (If a visual examination is planned for the upcoming refueling outage) a) RPVH and CRDM nozzle configurations b) RPVH insulation configuration The drawings listed above should include fabrication drawings for the nozzle attachment welds as applicable.
c) 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.
B.3 Boric Acid Corrosion Control Program (BACCP)
6 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 indicate which known leaks, if any, have remained in service or will remain in service as active leaks.
B.4 Information related to Steam Generator (SG) inspections a) Copy of the 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 SG ISI (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 SG 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 SG tube eddy current examination.
Inspector(s) Contact Information:
Justin Fuller Reactor Inspector (404) 562-4655 jdf@nrc.gov Mailing Address
7 US NRC Region 2 Attn: Justin Fuller 61 Forsyth Street, SW Suite 23T85 Atlanta, GA 30303