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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
	ML15362A551
Person / Time
Site:	Robinson
Issue date:	12/28/2015
From:	Bartley J H; NRC/RGN-II/DRS/EB1
To:	Glover R M; Duke Energy Corp
References
	IR 2015007
	Download: ML15362A551 (11)
	v • d • e

December 28, 2015

Mr. Richard Michael Glover Site Vice President H. B. Robinson Steam Electric Plant Duke Energy 3581 West Entrance Road, RNPA01 Hartsville, South Carolina 29550

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 NRC's "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 NRC's 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

cc Distribution via Listserv December 28, 2015 Mr. Richard Michael Glover Site Vice President H. B. Robinson Steam Electric Plant Duke Energy 3581 West Entrance Road, RNPA01 Hartsville, South Carolina 29550

SUBJECT: H. B. ROBINSON STEAM ELECTRIC PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000261/2015007 Dear M

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 Commission's (NRC's) 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

Main article: IP 71111.17T

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 licensee's 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

LIST OF DOCUMENTS REVIEWED

10

CFR 50.59 Evaluations:

REG-NGGC-0010, Attachment 11 - 10

CFR 50.59 Evaluation,

EC 69883, Install RCS Zinc Injection Skid

REG-NGGC-0010, Attachment 11 - 10

CFR 50.59 Evaluation, DCHG

0000275690, Delete

Steam Flow Feed Flow Mismatch into Rx Trip on low SG Level

REG-NGGC-0010, Attachment 11 - 10

CFR 50.59 Evaluation, DCHG

0000279037, Safe

Shutdown Analysis Update for Appendix R Administrative Revision

REG-NGGC-0010, Attachment 11 - 10

CFR 50.59 Evaluation, DCHG

0000280767, Correct

LOCA Containment Analysis Errors

REG-NGGC-0010, Attachment 11 - 10

CFR 50.59 Evaluation,

EC 83803, RCP Safe Shutdown

Seals

REG-NGGC-0010, Attachment 11 - 10

CFR 50.59 Evaluation,

EC 86806, Permanent Canal

Seal Plate

REG-NGGC-0010, Attachment 11 - 10

CFR 50.59 Evaluation, DCHG

0000729915, Robinson

Nuclear Plant Cycle 30 Reload

REG-NGGC-0010, Attachment 11 - 10

CFR 50.59 Evaluation, DCHG

0000280836, EQ

Pressure Profile Update

CFR 50.59 Screening: