IR 05000400/2014007
| ML14066A473 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/07/2014 |
| From: | Nease R L NRC/RGN-II/DRS/EB1 |
| To: | Kapopoulos E J Carolina Power & Light Co |
| References | |
| IR-14-007 | |
| Download: ML14066A473 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303
-1257 March 7, 2014 Mr. Ernie Kapop oulos Vice President Shearon Harris Nuclear Power Plant Carolina Power and Light Company P.O. Box 165, Mail Code:
Zone 1 New Hill, NC 27562
-0165
SUBJECT: NOTIFICATION OF SHEARON HARRIS NUCLEAR PLANT - COMPONENT DESIGN BASES INSPECTION
- NRC INSPECTION REPORT 05000400/2014007
Dear Mr. Kapopulous
- The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC) Region II staff will conduct a component design bases inspection (CDBI) at your Harris Nuclear Plant during the weeks of June 23 - 27, July 7
- 11, and July 21 - 25, 201 Jason Eargle, a Senior Reactor Inspector from the NRC's Region II Office, will lead the inspection tea This inspection will be conducted in accordance with Inspection Procedure 71111.21, "Component Design Bases Inspection," issued August 14, 20 1 The inspection will evaluate the capability of risk
-significant /low-margin components to function as designed and to support proper system operatio The inspection will also include a review of selected operator actions, operating experience, and modification During a telephone conversation on March 4, 20 1 4 , the staff confirmed with Mr. David Corlett of your staff, arrangements for an information
-gathering site visit and the three
-week onsite inspection
. The schedule is as follows:
Information
-gathering visit: Week of May 19 - 23 , 201 4 Onsite weeks: June 23 - 27 , July 7 - 11, and July 21 - 25, 2014 The purpose of the information
-gathering visit is to meet with members of your staff to identify risk-significant components and operator action Information and documentation needed to support the inspection will also be identifie Mr. Robert Patterson, a Reactor Inspector will be conducting all preparation activities associated with the inspection
. In addition, Mr. George McDonald , a Region II Senior Reactor Analyst, will support Mr. Patterson during the information
-gathering visit to review probabilistic risk assessment data and identify risk
-significant components, which will be examined during the inspectio The Enclosure lists documents that will be needed prior to the information
-gathering visi Please provide the referenced information to the Region II Office by May 5, 201 E. Kapopoulos 2 Additional documents may be requested during the information
-gathering visi The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparatio The additional information will need to be available to the team in the Region II office prior to the inspection team's preparation week of June 16, 201 During the information
-gathering trip, Mr. Patterson will also discuss the following inspection support administrative details:
(1) availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection, (2) method of tracking inspector requests during the inspection, (3) licensee computer access, (4) working space , (5) arrangements for site access , and (6) other applicable information
. In accordance with 10 CFR 2.390 of the NRC's "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 Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC w e bsite at http://www.nrc.gov/reading
-rm/adams.html (the Public Electronic Reading Room).
Thank you for your cooperation in this matte If you have any questions, regarding the information requested or the inspection, please contact Mr. Patterson at 404
-997-4667 or contact me at 404-997-4 53
Sincerely,RA Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety
Docket No.: 50-400 License No
.: NPF-63
Enclosure:
Information Request for Shearon Harris Nuclear Plant , Component Design Bases Inspection cc: Distribution via Listserv
___________x SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII DRS SIGNATURE RA RA NAME R. Patterson R. N ease DATE 3/07/201 4 3/07/201 4 3/ /2014 3/ /2014 3/ /2014 3/ /2014 3/ /2014 E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO YES NO YES NO Enclosur e INFORMATION REQUEST FOR SHEARON HARRIS NUCLEAR PLANT COMPONENT DESIGN BASES INSPECTION Please provide the information electronically in ".pdf" files, Excel, or other searchable format on CDROM (or FTP site, Sharepoint, etc
.). The CDROM (or website)
should be indexed and hyperlinked to facilitate ease of us . From your most recent probabilistic safety analysis (PSA) excluding external events and fires: a. Two risk rankings of components from your site
-specific PSA: one sorted by Risk Achievement Worth (RAW), and the other sorted by Birnbaum Importance b. A list of the top 500 cutsets
2. From your most recent PSA including external events and fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by RAW, and the other sorted by Birnbaum Importance A list of the top 500 cutsets 3. Risk ranking of operator actions from your site
-specific PSA sorted by RA Provide human reliability worksheets for these items
. 4. List of time
-critical operator actions with a brief description of each action
. 5. List of Emergency and Abnormal Operating Procedures revised (significant) since May 1 , 20 11 , with a brief description of each revision
.
6. List of components with low
-design margins (i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design-required output, heat exchangers close to rated design heat removal, and motor-operated valve risk-margin rankings, etc.), and associated evaluations or calculations
. List of station
-operating experience evaluations/reviews performed , and documented in the station's corrective action program , for industry events and safety
-related equipment failures/vulnerabilities (as communicated by NRC Generic Communications, Industry Communications, 10 CFR Part 21 Notifications, etc.) since May 1, 201 . List and brief description of safety
-related structures, systems, or components (SSC s) design modifications implemented since May 1, 201 . List and brief description of common
-cause component failures that have occurred since May 1, 201 . List and brief description of operability evaluations completed since May 1, 201 . List of equipment on the site's Station Equipment Reliability Issues List, including a description of the reason(s) why each component is on that list , and summaries (if available) of your plans to address the issue(s)
. 12. List and brief description of equipment currently in degraded or nonconforming status as described in Regulatory Issue Summary 05-02 . List and reason for equipment classified in maintenance rule (a)(1) status from May 1, 2011 , to present
. 14. Copies of system descriptions (or the design basis documents) for safety-related system . Copy of Updated Final Safety Analysis Repor . Copy of Technical Specification (s). 1 Copy of Technical Specifications Bases
. 1 Copy of Technical Requirements Manual(s)
. 1 List and brief description of Root Cause Evaluations performed since May 1, 201 . In-service Testing Program Procedure(s)
.
2 Corrective Action Program Procedure (s). 2 One-line diagram of electrical plan (Electronic and full size
- hard copy week of May 19-23, 201 4) 2 Index and legend for electrical plant one
-line diagrams
.
2 Primary AC calculation(s) for safety
-related buses
.
2 Primary DC calculation(s) for safety
-related buses
. 2 Piping and instrumentation diagrams (P&IDs)
for safety-related system (Electronic and 1/2 size
- hard copy week of May 19 - 23, 201 4) 2 Index and Legend for P&
I D . Copy of Operability Determination procedure(s). 3 Copies of corrective action documents (i.e. PIPs)
associated with findings from previous CDB (If applicable)
3 Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedure . Copy of any self
-assessments performed in preparation for this inspection
.
3 3 List of any condition reports generated in preparation for this inspection
. 3 Copies of condition reports generated from previous CDBI (2011).
3 5. Contact information for a person to discuss PSA information prior to the information
-gathering tri (Name, title, phone number, and e
-mail address)