IR 05000321/2017007
| ML17286A528 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/13/2017 |
| From: | Sandra Walker NRC/RGN-II/DRS/EB1 |
| To: | Vineyard D Southern Nuclear Operating Co |
| References | |
| IR 2017007 | |
| Download: ML17286A528 (13) | |
Text
October 13, 2017
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT - NRC DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) REPORT NUMBER 05000321/2017007 AND 05000366/2017007
Dear Mr. Vineyard:
On September 1, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Edwin I. Hatch Nuclear Plant, Units 1 and 2, and discussed the results of this inspection with Mr. Spring and other members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
This letter and its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Shakur A. Walker, Chief Engineering Branch 1 Division of Reactor Safety
Docket Nos.: 50-321, 50-366 License Nos.: DPR-57, NPF-5
Enclosure:
Inspection Report 05000321/2017007 and 05000366/2017007, w/Attachment:
Supplemental Information
REGION II==
Docket Nos.: 50-321, 50-366
Report Nos.: 05000321/2017007, 05000366/2017007
Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Edwin I. Hatch Nuclear Plant
Location:
11028 Hatch Parkway North, Baxley, GA 31513
Dates:
August 14 - September 1, 2017
Inspectors:
T. Su, Reactor Inspector (Lead)
M. Greenleaf, Reactor Inspector C. Franklin, Reactor Inspector
Approved by: Shakur A. Walker, Chief
Engineering Branch 1
Division of Reactor Safety
SUMMARY
IR 05000321/2017-007, 05000366/2017-007; 08/14/2017 - 09/01/2017; Edwin I. Hatch Nuclear
Plant, Units 1 and 2; Design Bases Assurance Inspection (Programs)
The inspection activities described in this report were performed between August 14, 2017, and September 1, 2017, by three Nuclear Regulatory Commission (NRC) inspectors from Region II.
The significance of inspection findings are indicated by their color (i.e., greater than Green, or Green, White, Yellow, or Red) and determined using Inspection Manual Chapter (IMC) 0609,
Significance Determination Process, (SDP) dated April 29, 2015. Cross-cutting aspects are determined using IMC 0310, Aspects Within the Cross-Cutting Areas, dated December 4, 2014. All violations of NRC requirements were dispositioned in accordance with the NRCs Enforcement Policy dated November 1, 2016. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6.
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Mitigating Systems, Barrier Integrity
1R21 Design Bases Assurance Inspection (Programs)
a. Inspection Scope
The team performed an inspection conducted as outlined in NRC Inspection Procedure (IP) 71111.21N, Attachment 1, Environmental Qualification (EQ) under 10 CFR 50.49 Programs, Processes, and Procedures. The team assessed Plant Hatchs implementation of the site environmental qualification program as required by 10 CFR 50.49, Environmental qualification of electric equipment important to safety for nuclear power plants. The team evaluated whether Plant Hatch staff properly maintained the EQ of electrical equipment important to safety throughout plant life, established and maintained required EQ documentation records, and implemented an effective corrective action program to identify and correct EQ related deficiencies.
The inspection included review of EQ program procedures, component EQ files, test records, equipment maintenance and operating history, maintenance and operating procedures, vendor documents, design documents, and calculations. The team interviewed program owners, engineers, maintenance staff, and warehouse staff. The team performed in-plant walkdowns (where accessible) to verify equipment was installed as described in Plant Hatchs EQ component documentation files; and that the components were installed in their tested configuration. Additionally, the team performed in-plant walkdowns to determine whether equipment surrounding the EQ component could fail in a manner that could prevent the safety function of the components, and to verify that components located in areas susceptible to a high energy line break were properly evaluated for operation in a harsh environment. The team reviewed and inspected the storage of replacement parts and associated procurement records to verify EQ parts approved for installation in the plant were properly identified and controlled, and that storage and environmental conditions did not adversely affect the components qualified lives. Documents reviewed are listed in the Attachment.
The inspection procedure requires the team to select six to ten components to assess the adequacy of the EQ program. The team selected ten components for this inspection. Component samples selected for this inspection are listed below:
==1R24 S011 AMC, 600 V MCC 1C. (Birnbaum sample)
- ==
2E51-N003 FT, RCIC Discharge Flow Transmitter
- 1T48-F319 LS, Drywell Vent V/V Namco limit switch
- Okonite Power and Control Cable package, Unit 1 QDP 17
- 1T52-X100G, Containment Penetration (Partial Inside Containment)
- 2E11-C002B, RHR 2B Pump Motor
- Raychem new formula splice for 2B31F019 coil, Unit 2 QDP 7. (Inside Containment )
- 2E41-N056B, HPCI Turbine Exhaust Barton Pressure Transmitter
b. Findings
.1 Unresolved Item (URI) 05000321, 366/2017007-01, Potential Failure to Adequately
Justify the Activation Energies by Licensee
Introduction:
The NRC opened an URI to review the adequacy of the licensees justification for the activation energies for the 600 V MCC fuses and scram solenoid pilot valve (SSPV) per Reg. Guide 1.89 section C.5.c.
Description:
The inspectors reviewed qualification binders 1-QDP06 for the 600VAC MCC and 1-QDP71 for the Control Rod Drive Scram Solenoid Pilot Valve (SSPV). The activation energies used for calculating the qualified lives for the most limiting components were not properly defined and justified as required by Reg. Guide 1.89.
RG 1.89, Section C, Regulatory Position, 5.c, requires in part that, Theactivation energies used during qualification testing and the basis upon which theactivation energy [was] established should be defined, justified, and documented.
The team identified that during the licensees initial evaluation of the activation energies, the use of non-conservative values may have potentially extended the qualified life of the affected SSC required by 10CFR 50.49 without adequate justification.
The subcomponents associated with this URI are:
o Bussman/Gould Fuses
- SSPV sup-components affected:
o Zytel 103
This URI is necessary so that further review of the EQ binders and related information can be conducted to determine whether the failure to define, justify, and document the basis for the activation energies used is a performance deficiency of minor or more than minor significance, in accordance with IMC 0612, Appendix B, Issue Screening.
.2 Unresolved Item (URI) 05000321, 366/2017007-02, Potential Failure to Adequately
Justify the Activation Energies Determined by 10 CFR 50 Appendix B Vendors
Introduction:
The NRC opened an URI to review the adequacy of the licensees acceptance of vendors justification for the activation energies for the 600 V MCC and SSPV) per Reg. Guide 1.89 section C.5.c.
Description:
The inspectors reviewed qualification binder 1-QDP06 for the 600 VAC MCC and 1-QDP71 for CRD SSPV. The activation energies used for calculating the qualified lives for the most limiting components were not properly defined and justified as required by Reg. Guide 1.89.
RG 1.89, Section C, Regulatory Position, 5.c, requires in part that, Theactivation energies used during qualification testing and the basis upon which theactivation energy [was] established should be defined, justified, and documented.
The team identified that during the licensees initial evaluation of the activation energies provided by the Appendix B vendor, the use of non-conservative values may have potentially extended the qualified life of the affected SSC required by 10CFR 50.49 without adequate justification.
The subcomponents addressed by this URI are:
o HFB, HFD & HMCP Molded Case Circuit Breakers o Westinghouse Overload Relays, Models AA23X and AA21P o Westinghouse AA and AN Thermal Overload Relays with FH Series Heater o Alis-Chalmers Motor Control Centers and Local Starters
- SSPV sup-components affected:
o Viton 515AB
This URI is necessary so that further review of the EQ binders and related information can be conducted to determine whether the failure to define, justify, and document the basis for the activation energies used by the licensee and provided by the vendor is a performance deficiency of minor or more than minor significance, in accordance with IMC 0612, Appendix B, Issue Screening.
OTHER ACTIVITIES
4OA6 Meetings, Including Exit
On September 1, 2017, the team presented the inspection results to Mr. Spring and other members of the licensees staff. On October 12, 2017, a re-exit meeting was conducted via teleconference to present the final inspection results to Mr. Vonier and other members of the licensees staff. Proprietary information that was reviewed during the inspection was returned to the licensee or destroyed in accordance with prescribed controls.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- J. Collins, Licensing Supervisor
- G. Johnes, Reg. Affairs Manager
- P. Burns, Corp. Licensing
- K. McKinnery, CMO Manager
- Z. Daideth, EQ Program Engineer
- D. Edenfield, Risk Informed Engineer
- L. Capeles, Maintenance Engineer
- J. Cash, Program Engineer
- T. Brimson, Warehouse Support
- M. Peterson, HQ CGD Supervisor
- R. Winfred, Maintenance Planner
- Z. Betsill, Procurement Supervisor
NRC personnel
- D. Hardage, Senior Resident Inspector
- A. Ruh, Senior Resident Inspector
- D. Retterer, Resident Inspector
- C. Jones, Senior Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened &
Closed
- 05000321, 366/2017007-01
URI Potential Failure to Adequately Justify the Activation Energies by Licensee (Section 1R21.b.1)
- 05000321, 366/2017007-02
URI Potential Failure to Adequately Justify the Activation Energies Determined by 10 CFR 50 Appendix B Vendors (Section 1R21.b.2)