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| number = ML15362A551 | | number = ML15362A551 | ||
| issue date = 12/28/2015 | | issue date = 12/28/2015 | ||
| title = IR 05000261/2015007, October 26, 2015 Through November 19, 2015, H.B. Robinson Steam Electric Plant - NRC Evaluation | | title = IR 05000261/2015007, October 26, 2015 Through November 19, 2015, H.B. Robinson Steam Electric Plant - NRC Evaluation of Changes, Tests, and Experiments and Permanent Plant Modifications | ||
| author name = Bartley J | | author name = Bartley J | ||
| author affiliation = NRC/RGN-II/DRS/EB1 | | author affiliation = NRC/RGN-II/DRS/EB1 | ||
| addressee name = Glover R | | addressee name = Glover R | ||
| addressee affiliation = Duke Energy Corp | | addressee affiliation = Duke Energy Corp | ||
| docket = 05000261 | | docket = 05000261 | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter | {{#Wiki_filter:December 28, 2015 | ||
==SUBJECT:== | |||
H. B. ROBINSON STEAM ELECTRIC PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000261/2015007 | |||
SUBJECT: H. B. ROBINSON STEAM ELECTRIC PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000261/2015007 | |||
==Dear Mr. Glover:== | ==Dear Mr. Glover:== | ||
| Line 30: | Line 28: | ||
The NRC inspectors did not identify any findings or violations of more than minor significance. | The NRC inspectors did not identify any findings or violations of more than minor significance. | ||
In accordance with Title 10 of the Code of Federal Regulations 2.390 of the | In accordance with Title 10 of the Code of Federal Regulations 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publically Available Records component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | ||
Sincerely, | |||
/RA/ | |||
Jonathan H. Bartley, Chief | |||
Engineering Branch 1 | |||
Division of Reactor Safety | |||
Docket No.: | |||
50-261 License No.: DPR-23 | |||
===Enclosure:=== | ===Enclosure:=== | ||
Inspection Report 05000261/2015007 | Inspection Report 05000261/2015007 w/Attachment: Supplemental Information | ||
== | REGION II== | ||
Docket No: | |||
50-261 License No: | |||
DPR-23 Report No: | |||
005000261/2015007 Facility: | |||
H. B. Robinson Steam Electric Plant, Unit 2 Location: | |||
3581 West Entrance Road Hartsville, SC 29550 | |||
Dates: | |||
October 26, 2015 through November 19, 2015 Inspectors: | |||
D. Hardage, Senior Resident Inspector T. C. Su, Reactor Inspector D. Jackson, Project Engineer E. Bousquet, Trainee | |||
Approved by: | |||
Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety | |||
=SUMMARY= | =SUMMARY= | ||
| Line 49: | Line 65: | ||
Inc., H.B. Robinson Steam Electric Plant, Unit 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications. | Inc., H.B. Robinson Steam Electric Plant, Unit 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications. | ||
This report covers a two-week, on-site inspection by two regional inspectors and one resident inspector. No findings or violations were identified. The Nuclear Regulatory | This report covers a two-week, on-site inspection by two regional inspectors and one resident inspector. No findings or violations were identified. The Nuclear Regulatory Commissions (NRCs) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5, dated February 2014. | ||
=REPORT DETAILS= | =REPORT DETAILS= | ||
==REACTOR SAFETY== | ==REACTOR SAFETY== | ||
Cornerstones: | Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity {{a|1R17}} | ||
{{a|1R17}} | |||
==1R17 Evaluations of Changes, Tests Experiments, and Permanent Plant Modifications== | ==1R17 Evaluations of Changes, Tests Experiments, and Permanent Plant Modifications== | ||
{{IP sample|IP=IP 71111.17T}} | {{IP sample|IP=IP 71111.17T}} | ||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
Evaluations of Changes, Tests Experiments: | Evaluations of Changes, Tests Experiments: The team reviewed eight safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59, Changes, tests, and experiments, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 15 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if: | ||
* the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required; | * the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required; | ||
* the safety issues requiring the changes, tests or experiments were resolved; | * the safety issues requiring the changes, tests or experiments were resolved; | ||
* the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and | * the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and | ||
* the design and licensing basis documentation used to support the change was updated to reflect the change. The team used, in part, Nuclear Energy Institute (NEI) 96-07, | * the design and licensing basis documentation used to support the change was updated to reflect the change. | ||
The team used, in part, Nuclear Energy Institute (NEI) 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000. | |||
Permanent Plant Modifications: The team reviewed 10 permanent plant modifications that had been installed in the plant during the last three years. The modifications reviewed are listed below: | Permanent Plant Modifications: The team reviewed 10 permanent plant modifications that had been installed in the plant during the last three years. The modifications reviewed are listed below: | ||
* DCHG 0000275044, EDG A Voltage Regulator Replacement child EC#1 | * DCHG 0000275044, EDG A Voltage Regulator Replacement child EC#1 | ||
* DCHG 0000277390, Replace TE-410, TE-420 & TE-430 Cold leg RTDs Revision 2: Revise Torque Values for the subject RTD PATEL Conduit Seal Assembly Interface Fitting | * DCHG 0000277390, Replace TE-410, TE-420 & TE-430 Cold leg RTDs Revision 2: | ||
Revise Torque Values for the subject RTD PATEL Conduit Seal Assembly Interface Fitting | |||
* DCHG 0000280186, Replace Existing A1 and B1 Battery Chargers child EC#1 to master EC 77389 Replace Battery Charger A1 | * DCHG 0000280186, Replace Existing A1 and B1 Battery Chargers child EC#1 to master EC 77389 Replace Battery Charger A1 | ||
* DCHG 0000280351, Relocate RPS System BFD/NBFD Relays, RF0-29 Modification child EC for Rack 61 Implementation (Master EC 68034) | * DCHG 0000280351, Relocate RPS System BFD/NBFD Relays, RF0-29 Modification child EC for Rack 61 Implementation (Master EC 68034) | ||
* DCHG 0000284282, Replace RHR-744A AND RHR-744B Motors | * DCHG 0000284282, Replace RHR-744A AND RHR-744B Motors | ||
* DCHG 0000291633, Diesel Fire Pump Engine Replacement | * DCHG 0000291633, Diesel Fire Pump Engine Replacement | ||
* DCHG 0000292104, NUS Replacement for Hagan Function Generators LTAM RNP-10-359 | * DCHG 0000292104, NUS Replacement for Hagan Function Generators LTAM RNP-10-359 LRPF 428011 | ||
* DCHG 0000272331, Replace EDG FO Day Tank Solenoid Valves | * DCHG 0000272331, Replace EDG FO Day Tank Solenoid Valves | ||
* DCHG 0000279462, Replace CST Level Transmitter | * DCHG 0000279462, Replace CST Level Transmitter | ||
* DCHG 0000300624, Replace Thermal Overloads for SI-864A | * DCHG 0000300624, Replace Thermal Overloads for SI-864A | ||
The modifications were selected based upon risk significance, safety significance, and complexity. The team reviewed the modifications selected to determine if: | |||
* the supporting design and licensing basis documentation was updated; | * the supporting design and licensing basis documentation was updated; | ||
* the changes were in accordance with the specified design requirements; | * the changes were in accordance with the specified design requirements; | ||
* the procedures and training plans affected by the modification had been adequately updated; | * the procedures and training plans affected by the modification had been adequately updated; | ||
* the test documentation as required by the applicable test programs had been updated; and | * the test documentation as required by the applicable test programs had been updated; and | ||
* post-modification testing adequately verified system operability and/or functionality. The team also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications. | * post-modification testing adequately verified system operability and/or functionality. | ||
The team also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications. | |||
Documents reviewed are listed in the Attachment. | Documents reviewed are listed in the Attachment. | ||
| Line 88: | Line 111: | ||
No findings were identified. | No findings were identified. | ||
{{a|4OA6}} | {{a|4OA6}} | ||
==4OA6 Meetings, Including Exit On November 19, 2015, the team presented the inspection results to Mr. Glover and other members of the | |||
The team verified that no proprietary information was retained by the inspectors or documented in this report. | ==4OA6 Meetings, Including Exit== | ||
On November 19, 2015, the team presented the inspection results to Mr. Glover and other members of the licensees staff. The team verified that no proprietary information was retained by the inspectors or documented in this report. | |||
ATTACHMENT: | ATTACHMENT: | ||
=SUPPLEMENTARY INFORMATION= | =SUPPLEMENTARY INFORMATION= | ||
==KEY POINTS OF CONTACT== | ==KEY POINTS OF CONTACT== | ||
===Licensee personnel=== | ===Licensee personnel=== | ||
: [[contact::J. Brady]], Regulatory Affairs | : [[contact::J. Brady]], Regulatory Affairs | ||
| Line 116: | Line 139: | ||
: [[contact::L. Hall]], Senior Nuclear Emergency Preparedness Specialist | : [[contact::L. Hall]], Senior Nuclear Emergency Preparedness Specialist | ||
: [[contact::H. King]], Engineer III | : [[contact::H. King]], Engineer III | ||
: [[contact::T. Nance]], Senior Engineer | : [[contact::T. Nance]], Senior Engineer | ||
===NRC personnel=== | ===NRC personnel=== | ||
: [[contact::K. Ellis]], Senior Resident Inspector | : [[contact::K. Ellis]], Senior Resident Inspector | ||
| Line 122: | Line 146: | ||
==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | ||
===Opened=== | ===Opened=== | ||
None | None | ||
===Closed=== | ===Closed=== | ||
None | |||
===Discussed=== | ===Discussed=== | ||
| Line 133: | Line 156: | ||
==LIST OF DOCUMENTS REVIEWED== | ==LIST OF DOCUMENTS REVIEWED== | ||
}} | }} | ||
Latest revision as of 05:52, 10 January 2025
| ML15362A551 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/28/2015 |
| From: | Bartley J NRC/RGN-II/DRS/EB1 |
| To: | Glover R Duke Energy Corp |
| References | |
| IR 2015007 | |
| Download: ML15362A551 (11) | |
Text
December 28, 2015
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000261/2015007
Dear Mr. Glover:
On November 19, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your H. B. Robinson Steam Electric Plant, Unit 2. On November 19, 2015, the NRC inspectors discussed the results of this inspection with you and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.
The NRC inspectors did not identify any findings or violations of more than minor significance.
In accordance with Title 10 of the Code of Federal Regulations 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publically Available Records component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Jonathan H. Bartley, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No.:
50-261 License No.: DPR-23
Enclosure:
Inspection Report 05000261/2015007 w/Attachment: Supplemental Information
REGION II==
Docket No:
50-261 License No:
DPR-23 Report No:
005000261/2015007 Facility:
H. B. Robinson Steam Electric Plant, Unit 2 Location:
3581 West Entrance Road Hartsville, SC 29550
Dates:
October 26, 2015 through November 19, 2015 Inspectors:
D. Hardage, Senior Resident Inspector T. C. Su, Reactor Inspector D. Jackson, Project Engineer E. Bousquet, Trainee
Approved by:
Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety
SUMMARY
IR 05000261/2015007, October 26, 2015, through November 19, 2015; Duke Energy Progress,
Inc., H.B. Robinson Steam Electric Plant, Unit 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.
This report covers a two-week, on-site inspection by two regional inspectors and one resident inspector. No findings or violations were identified. The Nuclear Regulatory Commissions (NRCs) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5, dated February 2014.
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R17 Evaluations of Changes, Tests Experiments, and Permanent Plant Modifications
a. Inspection Scope
Evaluations of Changes, Tests Experiments: The team reviewed eight safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59, Changes, tests, and experiments, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 15 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if:
- the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;
- the safety issues requiring the changes, tests or experiments were resolved;
- the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
- the design and licensing basis documentation used to support the change was updated to reflect the change.
The team used, in part, Nuclear Energy Institute (NEI) 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000.
Permanent Plant Modifications: The team reviewed 10 permanent plant modifications that had been installed in the plant during the last three years. The modifications reviewed are listed below:
- DCHG 0000275044, EDG A Voltage Regulator Replacement child EC#1
- DCHG 0000277390, Replace TE-410, TE-420 & TE-430 Cold leg RTDs Revision 2:
Revise Torque Values for the subject RTD PATEL Conduit Seal Assembly Interface Fitting
- DCHG 0000280186, Replace Existing A1 and B1 Battery Chargers child EC#1 to master EC 77389 Replace Battery Charger A1
- DCHG 0000280351, Relocate RPS System BFD/NBFD Relays, RF0-29 Modification child EC for Rack 61 Implementation (Master EC 68034)
- DCHG 0000284282, Replace RHR-744A AND RHR-744B Motors
- DCHG 0000291633, Diesel Fire Pump Engine Replacement
- DCHG 0000292104, NUS Replacement for Hagan Function Generators LTAM RNP-10-359 LRPF 428011
- DCHG 0000272331, Replace EDG FO Day Tank Solenoid Valves
- DCHG 0000279462, Replace CST Level Transmitter
- DCHG 0000300624, Replace Thermal Overloads for SI-864A
The modifications were selected based upon risk significance, safety significance, and complexity. The team reviewed the modifications selected to determine if:
- the supporting design and licensing basis documentation was updated;
- the changes were in accordance with the specified design requirements;
- the procedures and training plans affected by the modification had been adequately updated;
- the test documentation as required by the applicable test programs had been updated; and
- post-modification testing adequately verified system operability and/or functionality.
The team also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications.
Documents reviewed are listed in the Attachment.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
On November 19, 2015, the team presented the inspection results to Mr. Glover and other members of the licensees staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.
ATTACHMENT:
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- J. Brady, Regulatory Affairs
- G. Eakins, Major Projects Design Engineer
- S. Connelly, Licensing
- M. Glover, Site Vice President
- D. Hoffman, Nuclear Oversight Manager
- A. Helms, Principal Engineer
- D. Hunt, Engineer III
- R. Ludwick, Lead Engineer
- A. Mallner, Lead Engineer
- E. Saunders, Engineer II
- M. Watkins, Senior Engineer
- V. Balakhnin, Lead Engineer
- K. Brown, Contract Engineer
- D. Coon, Senior Engineer
- T. Halker, Senior Engineer
- L. Hall, Senior Nuclear Emergency Preparedness Specialist
- H. King, Engineer III
- T. Nance, Senior Engineer
NRC personnel
- K. Ellis, Senior Resident Inspector
- C. Scott, Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
None
Discussed
None