ML040220344

Notification of Harris Nuclear Plant - Plant Design - Pilot Inspection

ML040220344
Person / Time
Site:	Harris
Issue date:	01/21/2004
From:	Ogle C Division of Reactor Safety II
To:	Scarola J Carolina Power & Light Co
References
IR-04-007
Download: ML040220344 (7)

Text

January 21, 2004 Carolina Power & Light Company ATTN:

Mr. James Scarola Vice President - Harris Plant Shearon Harris Nuclear Power Plant P. O. Box 165, Mail Code: Zone 1 New Hill, NC 27562-0165

SUBJECT:

NOTIFICATION OF HARRIS NUCLEAR PLANT - PLANT DESIGN - PILOT INSPECTION - NRC INSPECTION REPORT 05000400/2004007

Dear Mr. Scarola:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region II staff will conduct a plant design inspection at your Harris Nuclear Plant during the weeks of March 22 and April 12, 2004. A team of seven inspectors will perform this inspection.

The inspection team will be led by Mr. Jim Moorman, a Senior Reactor Inspector from the NRC Region II Office. This biennial inspection will be conducted in accordance with baseline inspection program Attachment 71111.DS, Plant Design - Pilot.

The inspection will evaluate the capability of installed plant equipment to detect and respond to a steam generator tube rupture event. Procedures which direct the mitigating actions for this event will also be evaluated.

During a telephone conversation on January 8, 2004, Mr. Moorman, and Mr. Mike Wallace of your staff, confirmed arrangements for an information gathering site visit and the two-week onsite inspection. The schedule is as follows:

• Information gathering visit: Week of March 1, 2004

• Onsite inspection weeks: March 22 and April 12, 2004 The purpose of the information gathering visit is to obtain information and documentation, outlined in the Enclosure, that is needed to support the inspection. Mr. Walt Rogers, a Region II Senior Reactor Analyst, may accompany Mr. Moorman during the information gathering visit to review probabilistic risk assessment data and identify risk significant components which will be examined during the inspection. Please contact Mr. Moorman prior to preparing copies of the materials listed in the Enclosure. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. During the information gathering visit, the team leader will also discuss the following inspection support administrative details: office space; specific documents requested to be made available to the team in their office space; arrangements for site access; and the availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection.

CP&L 2

Thank you for your cooperation in this matter. If you have any questions regarding the information requested or the inspection, please contact Mr. Moorman at (404) 562-4647 or me at (404) 562-4605.

In accordance with 10 CFR 2.790 of the NRCs "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 Publically Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/readingrm/

adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Charles R. Ogle, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-400 License No. NPF-63

Enclosure:

Information Request for the Plant Design - Pilot Inspection.

cc w/encl:

James W. Holt, Manager Performance Evaluation and Regulatory Affairs CPB 9 Carolina Power & Light Company Electronic Mail Distribution Robert J. Duncan II Director of Site Operations Carolina Power & Light Company Shearon Harris Nuclear Power Plant Electronic Mail Distribution Benjamin C. Waldrep Plant General Manager--Harris Plant Carolina Power & Light Company Shearon Harris Nuclear Power Plant Electronic Mail Distribution (cc w/encl contd - See page 3)

CP&L 3

(cc w/encl contd)

Terry C. Morton, Manager Support Services Carolina Power & Light Company Shearon Harris Nuclear Power Plant Electronic Mail Distribution John R. Caves, Supervisor Licensing/Regulatory Programs Carolina Power & Light Company Shearon Harris Nuclear Power Plant Electronic Mail Distribution Steven R. Carr Associate General Counsel - Legal Department Progress Energy Service Company, LLC Electronic Mail Distribution John H. O'Neill, Jr.

Shaw, Pittman, Potts & Trowbridge 2300 N. Street, NW Washington, DC 20037-1128 Beverly Hall, Acting Director Division of Radiation Protection N. C. Department of Environmental Commerce & Natural Resources Electronic Mail Distribution Peggy Force Assistant Attorney General State of North Carolina Electronic Mail Distribution Public Service Commission State of South Carolina P. O. Box 11649 Columbia, SC 29211 Chairman of the North Carolina Utilities Commission c/o Sam Watson, Staff Attorney Electronic Mail Distribution (cc w/encl contd - See page 4)

CP&L 4

(cc w/encl contd)

Robert P. Gruber Executive Director Public Staff NCUC 4326 Mail Service Center Raleigh, NC 27699-4326 Herb Council, Chair Board of County Commissioners of Wake County P. O. Box 550 Raleigh, NC 27602 Tommy Emerson, Chair Board of County Commissioners of Chatham County Electronic Mail Distribution Distribution w/encl:

C. Patel, NRR RIDSNRRDIPMLIPB PUBLIC OFFICE RII:DRS RII:DRP SIGNATURE RA RA NAME MOORMAN FREDRICKSON DATE 1/21/2004 1/21/2004 1/ /2004 1/ /2004 1/ /2004 1/ /2004 1/ /2004 E-MAIL COPY?

YES NO YES NO YES NO YES NO YES NO YES NO YES NO PUBLIC DOCUMENT YES NO OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML040220344.wpd

Enclosure INFORMATION REQUEST FOR THE PLANT DESIGN - PILOT INSPECTION HARRIS STEAM GENERATOR TUBE RUPTURE MITIGATION (Please provide the information electronically in searchable.pdf files on CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use. Information in lists should contain enough information to be easily understood by someone who has a knowledge of pressurized water reactor technology.)

1.

Piping and instrumentation drawings for Safety Injection System (SI), Auxiliary Feedwater System (AFW), Main Steam (MS), Chemical and Volume Control System (CVCS), Component Cooling Water System (CCW), Residual Heat Removal System (RHR), Reactor Coolant System (RCS) (Paper copies (2) are preferred for these) 2.

The normal operating procedures for the systems listed above. Include the procedures which specify the normal valve alignment for these systems.

3.

Surveillance procedures used to ensure the operability of equipment required by your Technical Specifications that is used during the mitigation of the SGTR event.

4.

Procedures used for the operational testing of check valves in portions of the emergency core cooling systems used during mitigation of the SGTR event.

5.

System description and operator training modules for a SGTR event.

6.

Procedures used to sample the reactor coolant system during a SGTR event.

7.

Calibration and functional testing procedures for the main steam line, steam generator blowdown, and condenser air ejector radiation monitoring instrumentation.

8.

Calibration and functional test procedures for instruments used to monitor RCS pressure, pressurizer level and pressure, SG level and pressure, RCS hot and cold leg temperature, RCS subcooling, feedwater flow, steam flow, core exit temperature, high pressure injection flow, SI flow, refueling water storage tank level, pressurizer heater status, safety relief valve position indicator, AFW flow, condensate storage tank (CST) level, makeup flow, and letdown flow.

9.

Test procedures for the primary and secondary system safety relief valves and pressurizer power operated relief valves.

10.

Test procedures for the AFW starting logic.

11.

A list of Action Requests and non-routine work requests initiated since 1999 affecting the systems used to detect and mitigate a SGTR event; including their power suplies.

12.

Emergency Operating Procedures (EOPs) and supporting procedures, EOP basis documents, step deviation document, writers guide, and users guide. Abnormal

2 Enclosure Operating Procedures that would be used during a steam generator tube leak/rupture event.

13.

Calculations used to support the setpoints in Emergency Operating Procedures for a SGTR event.

14.

A list of engineering calculations applicable to AFW, SI, CVCS, RCS, CC, and other systems used in the mitigation of the SGTR event.

15.

A list of temporary modifications and operator work-arounds since 2001.

16.

A list of operability determinations performed since 1999.

17.

A list of corrective action program documents and non-routine work requests initiated since 2001 for AFW, HPSI, MS, CCW, Radiation Monitoring, and MS systems.

18.

System Health Reports and System Performance Trends for all systems going back 2 years.

19.

A copy of the Maintenance Rule program procedure and performance criteria for all plant systems. A list of plant systems currently monitored under 50.65(a)(1) and the performance goals. A list of Maintenance Rule functional failures since 2000.

20.

Quality Assurance audits, self-assessments and third party assessments performed on AFW, SI, CVCS, RCS, CCW systems and other related systems in the last 24 months.

Quality Assurance audits, self-assessments, and third party assessments performed on engineering and maintenance department activities performed in the last 24 months..

21.

Operator training lesson plans, system descriptions, and job performance measures for the EOPs, EOP support procedures, abnormal, and normal operating procedures that would be used to mitigate an SGTR event.

22.

Key electrical single line drawings of the intermediate and low voltage alternating current (AC) and DC power systems. (Paper copies (2) are preferred for these) 23.

The electrical system load list(s).

24.

A brief description of the mitigation strategy for handling the SGTR event, including operator actions and equipment used.

25.

A list of Operating Experience Program evaluations of industry, vendor, or NRC generic issues for the past 3 years.

26.

A list of equipment and operator actions with a Risk Achievement Worth (RAW) greater than 1.02.

3 Enclosure 27.

Probabilistic Risk Assessment (PRA) Event Tree for SGTR initiating event. A List of PRA system dependencies and success criteria for AFW, SI, CVCS, MS, CCW systems, and their support systems.

28.

Design Basis Manual for major plant electrical, mechanical, and control systems.

29.

Plant Technical Specifications, Bases, and Technical Requirements Manual 30.

A current copy of the Updated Final Safety Analysis Report.

31.

A list of all plant permanent plant changes, design changes, setpoint changes, procedure changes, equivalency evaluations, suitability analyses, calculations, and commercial grade dedications since 2001 32.

Plant procedures that provide the guidelines for the following prorgams: 1) Corrective Action Program, 2) Program for the evaluation of changes, tests, and experiments

[50.59 Program] 3) Program for the incorporation of local and industry operating experience into Harris programs and procedures.

33.

A list of changes, tests, or experiments which received a 50.59 evaluation. ( i.e. were not screened out)

34.

A list; if possible; of the more significant changes, tests, or experiments which were screened out via the 50.59 process. Or, provide guidance as to availability of data bases/files on site which can be reviewed for those which were screened out.

35.

If multiple categories of modifications exist, provide a description of the types and coding scheme.

36.

A list of operations training packages which were required due to modifications, if any.

37.

A list of Action Requests which were initiated in the area of modifications and the 50.59 process.

38.

Copies of the most recent self-assessment(s) and audit(s) of the modifications process and the 50.59 process.