ML17059C538: Difference between revisions

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Inservice Inspection Document Request cc: Distribution via Listserv
Inservice Inspection Document Request cc: Distribution via Listserv


______________                SUNSI REVIEW COMPLETE      FORM 665 ATTACHED OFFICE            RII:DRS      RII:DRS SIGNATURE        AJB1          BBD NAME              A. Butcavage  B. Desai DATE                  2/23/2016      2/23/2016 E-MAIL COPY?        YES    NO  YES      NO    YES    NO    YES    NO    YES    NO      YES    NO    YES NO
______________                SUNSI REVIEW COMPLETE      FORM 665 ATTACHED OFFICE            RII:DRS      RII:DRS SIGNATURE        AJB1          BBD NAME              A. Butcavage  B. Desai DATE                  2/23/2016      2/23/2016 E-MAIL COPY?        YES    NO  YES      NO    YES    NO    YES    NO    YES    NO      YES    NO    YES NO INSERVICE INSPECTION DOCUMENT REQUEST Site:                      V.C. Summer, Unit 1 Docket No:                50-395 Inspection Dates:          April 17 - April 21, 2017 (Inservice Inspection)
 
INSERVICE INSPECTION DOCUMENT REQUEST Site:                      V.C. Summer, Unit 1 Docket No:                50-395 Inspection Dates:          April 17 - April 21, 2017 (Inservice Inspection)
Entrance Meeting:          April 17, 2017 Inspection Procedure:      Inspection Procedure 71111.08, Inservice Inspection Activities, Effective Date, January 1, 2017 Inspector(s):              Al Butcavage, Reactor Inspector (Lead ISI Inspector)
Entrance Meeting:          April 17, 2017 Inspection Procedure:      Inspection Procedure 71111.08, Inservice Inspection Activities, Effective Date, January 1, 2017 Inspector(s):              Al Butcavage, Reactor Inspector (Lead ISI Inspector)
A. Information Requested for the In-Office Preparation Week Please provide the information requested in this section to the NRC Region II Office, in care of the lead inspector, by April 7, 2017, in order to facilitate the selection of specific items that will be reviewed during the onsite inspection week(s). The information can be provided in hard copy or electronic format; however, electronic format is preferred, either by digital data storage device (compact disk) or Web-based document management system.
A. Information Requested for the In-Office Preparation Week Please provide the information requested in this section to the NRC Region II Office, in care of the lead inspector, by April 7, 2017, in order to facilitate the selection of specific items that will be reviewed during the onsite inspection week(s). The information can be provided in hard copy or electronic format; however, electronic format is preferred, either by digital data storage device (compact disk) or Web-based document management system.

Latest revision as of 18:58, 4 February 2020

Notification of Inspection and Request for Information
ML17059C538
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 02/23/2017
From: Binoy Desai
NRC/RGN-II/DRS/PSB2
To: Lippard G
South Carolina Electric & Gas Co
References
Download: ML17059C538 (11)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 February 23, 2017 Mr. George Lippard III, Vice President Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION - UNIT 1 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Lippard:

From April 17 through April 21, 2017, the U.S. Nuclear Regulatory Commission (NRC) will perform a baseline inservice inspection at the V.C. Summer Nuclear Station, Unit 1, in accordance with NRC inspection procedure 71111.08, Inservice Inspection Activities.

Experience has shown that this inspection is resource-intensive for both 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 information. Section A of the Enclosure identifies information to be provided prior to the inspection, to ensure adequate sample selection and preparation. Section B of the Enclosure identifies additional information the inspectors will need upon arrival at the site, to complete the review of inspection samples. The inspection staff will appreciate it if all the documents requested 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 this inspection activity with your staff, and understand that our regulatory contact for this inspection will be Mr. Bruce Bennett of your 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, Alexander Butcavage at 404-997-4640, or Alexander.Butcavage@nrc.gov.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public inspections, exemptions, requests for withholding, of the NRC's "Agency Rules of Practice and Procedure," 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)

G. Lippard 2 component of NRC's Agencywide Documents Access and Management System (ADAMS);

accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Binoy Desai, Acting Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-395 License No. NPF-12

Enclosure:

Inservice Inspection Document Request cc: Distribution via Listserv

______________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE AJB1 BBD NAME A. Butcavage B. Desai DATE 2/23/2016 2/23/2016 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO INSERVICE INSPECTION DOCUMENT REQUEST Site: V.C. Summer, Unit 1 Docket No: 50-395 Inspection Dates: April 17 - April 21, 2017 (Inservice Inspection)

Entrance Meeting: April 17, 2017 Inspection Procedure: Inspection Procedure 71111.08, Inservice Inspection Activities, Effective Date, January 1, 2017 Inspector(s): Al Butcavage, Reactor Inspector (Lead ISI Inspector)

A. Information Requested for the In-Office Preparation Week Please provide the information requested in this section to the NRC Region II Office, in care of the lead inspector, by April 7, 2017, in order to facilitate the selection of specific items that will be reviewed during the onsite inspection week(s). The information can be provided in hard copy or electronic format; however, electronic format is preferred, either by digital data storage device (compact disk) or Web-based document management system.

The inspector(s) will select specific samples from the information provided for items A.1 through A.5 below, and then request additional documents needed for the onsite inspection week(s) as described in Section B of this Enclosure. The specific documents selected for Section B should be available and ready for review on the first day of inspection. If requested documents are large and only hardcopies are available, please inform the inspector(s), and provide the subject documentation during the first day of the onsite inspection. All documents requested in this section correspond to the Unit scheduled to be in a refueling outage during the onsite inspection week(s), unless an information request item explicitly states that it applies to all operating Units. Additionally, some of the information requested may not apply to the site, depending on the scope of refueling outage activities or other plant-specific conditions. If there are any questions regarding this information request, please contact the lead inspector as soon as possible.

A.1 Non-destructive Examination and Welding Activities

a. A detailed schedule (including preliminary dates) of nondestructive examinations (NDEs) planned for the structures, systems, and components (SSCs) listed below as part of the Inservice Inspection (ISI) Program required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC),Section XI, as incorporated by reference in 10 CFR 50.55a, and other augmented ISI activities:
  • ASME Code Class 1, 2, and 3 components and supports (including Risk-Informed ISI Program)
  • ASME Code Class MC and metallic liners of Class CC components (e.g., reactor building containment liner)

Enclosure

2

  • ASME Code Class MC supports
  • reactor vessel internals (e.g., Electric Power Research Institute (EPRI) MRP-227 Program)
b. A detailed schedule (including preliminary dates) of welding activities to be completed on ASME Code Class 1, 2, or 3 components and supports during the upcoming refueling outage.
c. A list of NDE reports (ultrasonic, radiographic, magnetic particle, and liquid penetrant) addressing surface or volumetric indications that were analytically evaluated and accepted for continued service in ASME Code Class 1, 2, and 3 components, since the beginning of the last refueling outage. This list should also include any evaluations for continuous service performed as a result of Section XI pressure test(s) conducted during startup from the last refueling outage.
d. A list of the welds in ASME Code Class 1, 2, and 3 systems that have been fabricated due to component repair/replacement activities since the beginning of the last refueling outage. Please include a brief description of the welds such as system, material, pipe size, weld number, and NDEs performed. Additionally, please indicate which of those welds are risk-significant.
e. If NDE of pressure retaining welds in the reactor vessel shell required by the ASME BPVC,Section XI, Subsection IWB (also known as 10-year Reactor Vessel ISI) 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 include reference numbers for applicable procedures that will be used to conduct these examinations.
f. A copy of ASME BPVC,Section XI Relief Requests, and the associated NRC Safety Evaluation Reports (SERs), applicable to the NDEs scheduled for the upcoming refueling outage.
g. A list of temporary Code or temporary non-Code repairs installed in ASME Code Class components (e.g., pinhole leaks or mechanical clamping devices).
h. A copy of the most recent program self-assessments addressing the ISI Program and welding activities.

A.2 Reactor Pressure Vessel Upper Head Penetration Inspection Activities

a. A detailed schedule (including preliminary dates) of NDEs planned for the reactor pressure vessel upper head penetrations (VUHPs) to meet the requirements of ASME Code Case N-729-1, as incorporated by reference in 10 CFR 50.55a.
b. A detailed scope of the planned NDEs for the reactor pressure VUHPs. Please identify the types of NDE methods to be used on each specific part of the vessel upper head, to

3 meet the augmented inspection requirements of ASME Code Case N-729-1, as incorporated by reference in 10 CFR 50.55a.

A.3 Boric Acid Corrosion Control Program Inspection Activities

a. A copy of the procedures governing the implementation of the Boric Acid Corrosion Control Program (BACCP), including procedures required to identify boric acid leakage, and perform boric acid leakage/corrosion evaluations.
b. A list of leaks in ASME Code Class components which have been identified since the last refueling outage, including reference to the associated corrective action program (CAP) documentation. If during the last cycle, the Unit was shutdown, please provide documentation of containment walkdown inspections performed as part of the BACCP.
c. Copy of the most recent self-assessment performed for the BACCP.

A.4 Steam Generator Tube Inspection Activities

a. A detailed schedule of steam generator (SG) tube inspection, eddy current (EC) data analyses, tube in-situ pressure testing, tube repairs, and SG secondary side inspection activities for the upcoming refueling outage.
b. A copy of the current version of the following documents:
  • Condition Monitoring Assessment
  • Operational Assessment
c. A copy of the current Technical Specifications (TSs) for the SG ISI Program, including recent NRC SERs for license amendments issued since the last refueling outage (e.g.,

alternate repair criteria as a result of the incorporation of TS Task Force activities).

d. Confirmation of whether SG primary-to-secondary leakage was identified and quantified during the previous operating cycle. If primary-to-secondary leakage was identified, please provide documentation describing the affected SG and corrective actions completed, or planned for this condition.

NOTE: The following information request items are applicable only if EC examination of the SG tubes will occur during the upcoming refueling outage.

e. A copy of the most recent Degradation Assessment.
f. A copy of the EC Examination Plan describing the scope of SG tube examinations, including examination methods such as bobbin, rotating, or array probes, and the percentage of tubes to be examined. Do not provide this information separately if it is already included in other documentation requested.
g. A copy of the SG plant-specific degradation history provided to the vendor performing EC examination of the SG tubes during the upcoming outage. Please include information on issues pertaining to the secondary side of the SGs (including items such as loose parts, fouling, top of tube sheet condition, and crud removal amounts, etc.). Do

4 not provide this information separately if it is already included in other documentation requested.

h. A copy of the following documents, as applicable:
  • SG Eddy Current Data Analyst Guidelines
  • Site Validated Eddy Current Techniques
  • Eddy Current Technique Qualification Records per EPRI Appendix H or I
i. A copy of the most recent program self-assessments for SG tube integrity, loose parts monitoring, and secondary side water chemistry control.
j. The location of the primary, secondary, and resolution analysis teams.

A.5 Other Information Related to All Inservice Inspection Activities

a. A list with a brief description of ISI-related issues entered into the CAP for all operating Units since the beginning of the last Unit 1 refueling outage, including issues related to the SG tube inspections and the BACCP. For example, provide a list of condition reports based upon database searches using keywords related to piping, vessels, and SG tube degradation such as: ISI, ASME Code,Section XI, NDE, welding, SG tube, reactor vessel, SG, reactor coolant system, crack, wear, thinning, leakage, through-wall, rust, corrosion, boric acid, or errors in piping/SG tube examinations.
b. A copy of the sites response to recent NRC generic communications, and other industry operating experience notifications, associated with the ISI and structural integrity of ASME Code Class components, issued since the beginning of the last refueling outage (e.g., Generic Letters, Information Notices).
c. Names and contact information for the following program leads:
  • ISI Program (examination, planning)
  • Reactor Containment Building ISI Program
  • Alloy 600 Program
  • VUHP Inspection Program
  • Snubbers and Supports Inspection Program
  • Repair and Replacement Program
  • Licensing
  • Site Welding
  • BACCP
  • SG Inspection Program (site lead and vendor contact)

B. Information Requested for the Onsite Inspection Week(s) (April 17, 2017)

Please provide the information requested below in hard copy or electronic (preferred) format to the lead inspector at the entrance meeting, in order to finalize the planning of inspection activities onsite. Prior to the onsite inspection, the inspector(s) will select part of the inspection samples from the information provided in response to Section A of this Enclosure, and then request additional information needed to complete the review. There

5 is a possibility that some of the inspection samples, for which direct observation is desired (e.g., planned NDEs), will not be selected until the inspector(s) arrive onsite, and confirm the current schedule of refueling outage activities for that week. All documents requested in this section correspond to the Unit scheduled to be in a refueling outage during the onsite inspection week(s), unless an information request item explicitly states that it applies to all operating Units. Additionally, some of the information requested may not apply, depending on the scope of refueling outage activities or other plant-specific conditions.

B.1 Non-Destructive Examination Activities, Welding Activities, and Schedule Information

a. Updated schedules for the planned NDE and welding activities described in the response to items A.1.a and A.1.b of this Enclosure.
b. For the NDEs selected by the inspector(s) from item A.1.a of this Enclosure, please provide a 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, please provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Please include documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers), and NDE personnel qualification records.
c. For the NDE reports with relevant indications on ASME Code Class 1, 2, and 3 components selected by the inspector(s) from item A.1.c of this Enclosure, please provide a copy of the examination records, NDE qualification records, and associated corrective action documents, including technical evaluations supporting the acceptability of the indications for continuous service.
d. For the ASME Code Class 1, 2, and 3 welds selected by the inspector(s) from item A.1.d of this Enclosure, please provide copies of the following documentation for each subject weld:
  • weld data sheet (traveler)
  • weld configuration and supporting drawings (e.g., ISI isometric drawings)
  • applicable ASME BPVC Edition and Addenda
  • Weld Procedure Specification (WPS) used to fabricate the welds
  • Procedure Qualification Records (PQRs) supporting the WPS
  • mechanical test reports supporting the applicable PQRs
  • welder performance qualifications records, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS
  • examination records for the NDEs performed during weld fabrication
  • preservice NDE record
  • personnel qualification records for both fabrication and preservice NDEs
  • nonconformance reports for the selected welds (if applicable)

B.2 Reactor Pressure Vessel Upper Head Penetration Inspection Activities NOTE: The on-site inspection week may include samples associated with the reactor vessel upper head replacement activities.

6 A copy of the latest calculation of effective degradation years (EDY) and re-inspection years (RIY) for the VUHP crack initiation and propagation susceptibility parameters.

a. A copy of NDE reports from the last visual and non-visual VUHP examinations.
b. If visual and/or non-visual NDEs of the VUHPs are planned for the upcoming refueling outage, please provide the following:
  • a copy of the procedures governing the implementation of NDEs
  • drawings showing the configuration of the VUHPs within the scope of the examinations (e.g., upper head insulation configuration, fabrication drawings of the nozzle attachments, geometrical limitations)
  • documentation demonstrating the detection capability and qualification of the NDE personnel, procedures, and equipment in accordance with 10 CFR 50.55a
  • identify any changes in equipment configurations used for the VUHPs examinations that differ from that used in the vendor qualification or demonstration report(s)

B.3 Boric Acid Corrosion Control Program Inspection Activities

a. Inspection results for boric acid walkdowns, including an updated list of boric acid leaks identified during the current refueling outage with associated corrective action documentation, and overall status of planned boric acid inspections.
b. A list of 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 specify which known leaks, if any, have remained in service, or will remain in service, as active leaks.
c. In accordance with NRC inspection procedure (IP) 71111.08, the inspector(s) would like to conduct an independent boric acid walkdown of the Reactor Building Containment early in the inspection week. Please have knowledgeable BACCP staff available to accompany the inspector(s) during the walkdown.

B.4 Steam Generator Tube Inspection Activities

a. An updated schedule of SG tube inspection activities, including potential in-situ pressure tests, tube repairs, and secondary side inspections.

NOTE: The following information request items are applicable only if EC examination of the SG tubes will occur during the upcoming refueling outage.

b. A copy of the Eddy Current Examination Technique Specification Sheets (ETSS) from the EPRI Performance Demonstration Database, that are applicable to the scheduled examinations of SG tubes.

7

c. A copy of the EC examination procedures governing the SG tube examination activities.

Specifically, provide the procedures for calibration, flaw detection, and flaw sizing.

d. Access to the training and qualification records of personnel performing EC data analysis, including training material and test results for any site-specific training provided to the data analysts.
e. Access to the certification records of EC equipment (i.e., EC instruments, probes, and calibration standards).
f. A copy of the procedures to be followed if a loose part or foreign material is identified in the SGs.
g. Documentation demonstrating that the in-situ pressure test screening criteria are in accordance with the applicable EPRI Guidelines. Please have knowledgeable staff available to discuss the analytical method used to determine the in-situ pressure test screening criteria.
h. A list of corrective action documents generated by the vendor with respect to SG tube inspection activities during the current refueling outage.

B.5 Other Information Related To All Inservice Inspection Activities

a. For the ISI-related corrective action issues selected by the inspector(s) from item A.5.a of this Enclosure, please provide copies of the corrective action documents and supporting documentation (e.g., cause evaluations, work orders, corrective action plan).
b. An updated list of ISI-related issues entered into the CAP for the current refueling outage, including issues related to the SG tube inspections and BACCP.
c. A copy of or ready access to:
  • applicable editions and sections of the ASME BPVC (e.g., Sections II, III, V, IX, and XI) for the ISI and repair/replacement activities selected for review
  • industry standards referenced in the procedures for the BACCP
  • EPRI and other industry standards referenced in the procedures used to perform the SG tube inspection activities
  • a current revision of the ISI Program Manual and Plan for the current interval Inspector(s) Contact Information:

Alexander Butcavage Reactor Inspector Mailing Address:

Engineering Branch 3 US NRC Region II Division of Reactor Safety Attn: Alexander Butcavage 404-997-4640 245 Peachtree Center Avenue, Suite 1200 Alexander.Butcavage@nrc.gov Atlanta, GA 30303

8 LIST OF ACRONYMS ASME American Society of Mechanical Engineers BACCP Boric Acid Corrosion Control Program BPVC Boiler and Pressure Vessel Code CAP Corrective Action Program EC Eddy Current EDY Effective Degradation years EPRI Electric Power Research Institute ETSS Examination Technique Specification Sheets IP Inspection Procedure ISI Inservice Inspection NDEs Non-destructive Examination PQRs Procedure Qualification Records RIY Re-inspection Years SERs Safety Evaluation Reports SG Steam Generator SSCs Systems, Structures, or Components TSs Technical Specifications VUHPs Vessel Upper Head Penetrations WPS Weld Procedure Specification