ML021020555

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Safety System Design & Performance Capability Inspection NRC Inspection Report Nos. 50-269/2002-09, 50-270/2002-09 & 50-287/2002-09
ML021020555
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 04/12/2002
From: Ogle C
NRC/RGN-II/DRS/EB
To: Mccollum W
Duke Energy Corp
References
IP 71111.21 IR-02-009
Download: ML021020555 (6)


See also: IR 05000269/2002009

Text

Duke Energy Corporation

ATTN: Mr. W. R. McCollum

Vice President

Oconee Site

7800 Rochester Highway

Seneca, SC 29672

SUBJECT:

SAFETY SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION

NRC INSPECTION REPORT NOS. 50-269/2002-09, 50-270/2002-09, and

50-287/2002-09

Dear Mr. McCollum:

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

Region II staff will conduct a safety system design and performance capability inspection at

your Oconee facility during July - August, 2002. A team of five inspectors will perform the

inspection. The inspection team will be led by Mr. J. Lenahan, a senior reactor inspector from

the NRC Region II Office. The inspection will be conducted in accordance with baseline

Inspection Procedure 71111.21, Safety System Design and Performance Capability.

The inspection objective will be to evaluate the capability of the high pressure injection system

and support systems, as well as other related systems, to perform the functions required to

mitigate a small break loss of coolant (LOCA) event.

During a telephone conversation on April 9, 2002, Mr. J. Lenahan of my staff, and

Mr. J. Smith 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: May 28 - 30, 2002

Onsite inspection: July 15 - 19 and July 29 - August 2, 2002

The purpose of the information gathering visit is to obtain information and documentation

outlined in the enclosure needed to support the inspection. Mr. W. Rogers a Region II Senior

Reactor Analyst, will accompany Mr. J. Lenahan during the information gathering visit to review

PRA data and identify risk significant components which will be examined during the inspection.

Please contact Mr. J. Lenahan 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 reactor site access; and the availability of

knowledgeable plant engineering and licensing organization personnel to serve as points of

contact during the inspection.

DEC

2

Thank you for your cooperation in this matter. If you have any questions regarding the

information requested or the inspection, please contact me at (404) 562-4605, or

Mr. J. Lenahan at (404) 562-4625.

Sincerely,

/RA/

Charles R. Ogle, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-269, 50-270, 50-287

License Nos.: DPR-38, DPR-47, DPR-55

Enclosure:

Information Request for the High

Pressure Injection System

cc w/encl:

Compliance Manager (ONS)

Duke Energy Corporation

Electronic Mail Distribution

Lisa Vaughn

Legal Department (PB05E)

Duke Energy Corporation

422 South Church Street

Charlotte, NC 28242

Anne Cottingham

Winston and Strawn

Electronic Mail Distribution

Mel Fry, Director

Division of Radiation Protection

N. C. Department of Environmental

Health & Natural Resources

Electronic Mail Distribution

Henry J. Porter, Director

Div. of Radioactive Waste Mgmt.

S. C. Department of Health and

Environmental Control

Electronic Mail Distribution

(cc w/encl contd - See page 3)

DEC

3

(cc w/encl contd)

R. Mike Gandy

Division of Radioactive Waste Mgmt.

S. C. Department of Health and

Environmental Control

Electronic Mail Distribution

County Supervisor of

Oconee County

415 S. Pine Street

Walhalla, SC 29691-2145

Lyle Graber, LIS

NUS Corporation

Electronic Mail Distribution

C. J. Thomas, Manager

Nuclear Regulatory Licensing

Duke Energy Corporation

526 S. Church Street

Charlotte, NC 28201-0006

Peggy Force

Assistant Attorney General

N. C. Department of Justice

Electronic Mail Distribution

Distribution w/encl:

L. Olshan, NRR

RIDSNRRDIPMLIPB

PUBLIC

OFFICE

RII:DRS

RII:DRS

SIGNATURE

OGLE

CARROLL

NAME

LENAHAN

HAAG

DATE

04/ 11/2002

04/12/2002

E-MAIL COPY?

YES

NO YES

NO YES

NO YES

NO YES

NO

YES

NO

OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML021020555.wpd

Enclosure

INFORMATION REQUEST FOR THE SAFETY SYSTEM DESIGN AND

PERFORMANCE CAPABILITY INSPECTION:

SMALL BREAK LOCA EVENT

Note: Electronic media is preferred if readily available (i.e., on computer disc).



Site specific administrative procedures related to standard operation, abnormal

operation, and emergency operation of the high pressure injection (HPI) system,

including support systems, and other related systems during a small break loss of

coolant accident (LOCA). Other related systems include, but may not be limited to the

emergency power source (Keowee), other portions of the emergency core cooling

system (e.g. the core flooding system, low pressure injection system, and containment

building sumps), the service water system, and the instrument air system.



Design criteria (i.e., design basis documents) for the HPI system and other related

systems.

HPI system Technical Specification requirements and a list of associated surveillance

test/calibration procedures for the HPI system and related systems.



Copies of applicable sections of the UFSAR for the HPI system, and other related

systems and copies of applicable sections of changes to the UFSAR which have yet to

be docketed.



HPI system, and other related systems piping and instrumentation drawings, one-line

diagrams; electrical schematics, and wiring and logic diagrams.



A list of engineering calculations (Electrical, Instrumentation and Controls and

Mechanical/Nuclear) applicable to the HPI system, and other related systems.



A list of plant modifications to the HPI system, and other related systems, implemented

since 1992.



List of current open temporary modifications and operator work arounds involving

operation of the HPI and the other related systems.



List of Problem Investigation Process Reports (PIPs) initiated since 1992 affecting the

HPI system, and other related systems.



Summary of corrective maintenance activities, including the maintenance rule event log,

performed on the HPI system and other related systems in the past 12 months.



An index of drawings for the HPI system, and other related systems.



Self-assessment performed on HPI system and other related systems in the last 24

months.

2

Enclosure



System description and operator training modules for the HPI system and other related

systems.

Strategy for handling a small break LOCA.

List of Operating Experience Program evaluations of industry, vendor, or NRC generic

issues related to the HPI system for the past 3 years.

List of valves in the HPI system required to change position for a small break LOCA.



List of instrument setpoint changes affecting the HPI system and related systems

initiated since 1992. Include the number and title, date, brief description, and

corresponding calculation number.



PRA Fault Tree Data for the HPI.



PRA/Risk Achievement Worth (RAW) listing for the HPI system, and related support

systems, evaluated for failure of the HPI system.



PRA Event Tree for the small break LOCA initiating event.



A list of PRA system dependencies and success criteria for HPI and its support systems