ML040220367

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Notification of Surry Power Station Safety System Design & Performance Capability Inspection NRC IR 05000280-04-006 & 05000281-04-006
ML040220367
Person / Time
Site: Surry  Dominion icon.png
Issue date: 01/21/2004
From: Ogle C
NRC/RGN-II/DRS/EB
To: Christian D
Virginia Electric & Power Co (VEPCO)
References
IR-04-006
Download: ML040220367 (7)


See also: IR 05000280/2004006

Text

January 21, 2004

Virginia Electric and Power Company

ATTN: Mr. David A. Christian

Senior Vice President and

Chief Nuclear Officer

Innsbrook Technical Center

5000 Dominion Boulevard

Glen Allen, VA 23060

SUBJECT:

NOTIFICATION OF SURRY POWER STATION SAFETY SYSTEM DESIGN

AND PERFORMANCE CAPABILITY INSPECTION - NRC INSPECTION

REPORT 05000280/2004006 AND 05000281/2004006

Dear Mr. Christian:

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 Surry Power Station during the weeks of March 22-26, 2004, and April 5-9, 2004. A team

of six inspectors will perform this inspection. The inspection team will be led by

Mr. Robert Schin, a Senior Reactor Inspector from the NRC Region II Office. This biennial

inspection will be conducted in accordance with baseline inspection program Attachment

71111.21, Safety System Design and Performance Capability. This inspection will focus on

the prevention and mitigation of internal flooding events.

During a telephone conversation on January 20, 2004, Mr. R. Schin and Ms. C. Lovett 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 1-5, 2004

Onsite inspection weeks: March 22-26, 2004, and April 5-9, 2004

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

outlined in the Enclosure, that are needed to support the inspection. Mr. W. Rogers, a

Region II Senior Reactor Analyst, may accompany Mr. Schin 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. Schin 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.

VEPCO

2

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

information requested or the inspection, please contact Mr. Schin at (404) 562-4629 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/reading-

rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA: James H. Moorman, III For:/

Charles R. Ogle, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-280, 50-281

License Nos.: DPR-32, DPR-37

Enclosure:

Information Request for the Safety System Design and Performance Capability

Inspection Focusing On Internal Flooding Events

cc w/encl:

Chris L. Funderburk, Director

Nuclear Licensing and

Operations Support

Virginia Electric & Power Company

Electronic Mail Distribution

Richard H. Blount, II

Site Vice President

Surry Power Station

Virginia Electric & Power Company

Electronic Mail Distribution

Virginia State Corporation Commission

Division of Energy Regulation

P. O. Box 1197

Richmond, VA 23209

Lillian M. Cuoco, Esq.

Senior Counsel

Dominion Resources Services, Inc.

Electronic Mail Distribution

(cc w/encl contd - See page 3)

VEPCO

3

(cc w/encl contd)

Attorney General

Supreme Court Building

900 East Main Street

Richmond, VA 23219

Distribution w/encl:

C. Gratton, NRR

L. Slack, RII EICS

RIDSNRRDIPMLIPB

PUBLIC

OFFICE

RII:DRS

RII:DRS

RII:DRP

SIGNATURE

RA

RA

RA

NAME

RSchin

JMoorman

KLandis

DATE

01/21/2004

01/21/2004

01/21/2004

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\\ML040220367.wpd

Enclosure

INFORMATION REQUEST

FOR THE SAFETY SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION

FOCUSING ON INTERNAL FLOODING EVENTS

Note: Electronic media is preferred if readily available. (The preferred file format is

searchable .pdf files on CDROM. The CDROM should be indexed and hyperlinked to

facilitate ease of use. Please provide 6 copies of each CDROM submitted. Information

in lists should contain enough information to be easily understood by someone who

has a knowledge of pressurized water reactor technology.)

1.

Design basis documents for the engineered safety features and other systems that

could initiate internal flooding events or that are used to mitigate internal flooding events

(e.g., circulating water, stop logs / seal plates, door seals, service water, fire water,

charging / high pressure injection, auxiliary feedwater, primary and secondary power

operated relief valves). Include design basis documents for the high, intermediate, and

low voltage electrical systems that power and control these components.

2.

Piping and instrumentation drawings (P&IDs) for the circulating water, service water, fire

water, charging/high pressure injection, safety injection, reactor coolant system,

auxiliary feedwater, main steam, and other systems used to mitigate internal flooding

events. (Two paper copies are preferred for these.)

3.

Key electrical one-line drawings depicting the high, intermediate, and low voltage

alternating current systems and of the direct current power systems that provide power

for the pumps, valves, and instrumentation and control circuits associated with the

systems that accomplish the internal flooding mitigation strategy. (Two paper copies are

preferred.)

4.

All procedures used to implement the mitigation strategy for internal flooding events.

Include alarm response procedures as well as normal, abnormal, and emergency

operating procedures (EOPs) as appropriate. Please include or have available on site

the EOP users guide, EOP setpoint document, and EOP step deviation document.

Also, please describe how Procedure 0-FCA-6.01, Uncontrollable Turbine Building

Flooding, differs from your EOPs in procedural controls (e.g., verification and validation,

step deviation document) and in rapidly cooling down and depressurizing the reactor

coolant system. Please include an explanation of why implementation of this procedure

involves 10 CFR 50.54(x).

5.

Procedures / programs used for the operational testing / inspection / preventive

maintenance of valves and other active components that could initiate flooding or are

relied upon to mitigate flooding (e.g., circulating water, service water, and fire water

valves, including circulating water valve components whose failure could initiate a water

hammer; stop logs / seal plates; sump pumps). Include the turbine building sump pump

reliability program. Also, procedures used for operational testing / inspection /

preventive maintenance of check valves / backflow preventers in the floor drain systems

that are relied upon to prevent floor drain flooding (e.g. of charging pump rooms or

switchgear rooms). Include frequency of testing / inspection / preventive maintenance,

2

Enclosure

performance history, and maintenance history of these components for the past 10

years.

6.

Procedures for preventive maintenance or inspection of expansion joints, piping,

manways, flood dikes and other passive components that could initiate or are relied

upon to mitigate internal flooding. Also, design drawings for the flood dikes. Include

frequency of preventive maintenance / inspection, performance history, and

maintenance history of these components for the past 10 years.

7.

Surveillance procedures used to ensure the operability of equipment required by your

Technical Specifications that is used during the mitigation of internal flooding events.

8.

Calibration and functional testing procedures for instrumentation used to detect an

internal flooding event or to provide an automatic actuation to mitigate an internal

flooding event.

9.

Calculations used to support the set points for alarms and automatic actuations that are

relied upon for detection or mitigation of internal flooding events. Also, calculations

used to support the operator action setpoints in procedures for mitigation of internal

flooding events (e.g., 0-AP-13.0 and 0-FCA-6.01).

10.

A list of all temporary modifications and operator work-arounds (for the past 3 years).

11.

A list of major modifications completed in the past 5 years to components or systems

that could initiate or are required for detection or mitigation of internal flooding events.

12.

A list of deferred modifications for any components or systems that could initiate or are

required for detection or mitigation of internal flooding events.

13.

System descriptions and operator training modules for internal flooding events and the

systems used to mitigate the events.

14.

A list of operating experience program evaluations of industry, vendor, or NRC generic

issues related to internal flooding events.

15.

Probabilistic risk assessment (PRA) event trees for internal flooding events. A list of

PRA identified system dependencies and success criteria for systems used to mitigate

internal flooding events. Provide internal flooding cutsets and risk achievement worths

for those basic events (only assuming an internal flooding initiating event).

16.

A brief description of the mitigation strategy for handling internal flooding events,

including operator actions and equipment used.

17.

System health reports and/or other performance monitoring information for systems

used to detect and mitigate internal flooding events and their power supply systems.

3

Enclosure

18.

A list of condition reports and non-routine work requests initiated since 1998 related to:

1) the systems used to detect and mitigate internal flooding events, and 2) the systems

and components that could initiate internal flooding.

19.

Quality Assurance audits, self-assessments, and third party assessments performed on

the systems that could initiate or are used to detect and mitigate internal flooding

events.

20.

Maintenance Rule performance criteria for systems used to detect and mitigate internal

flooding events and their electrical power systems. A list of maintenance rule failures of

equipment and their power supplies that are used to detect or mitigate internal flooding

events.

21.

A list of equipment used to mitigate internal flooding events that changes state or is

manually manipulated during implementation of the internal flooding mitigation strategy

and the indications used by plant operators to make decisions during the event.

22.

Plant Technical Specifications, Bases, and Technical Requirements Manual.

23.

A current copy of the Updated Final Safety Analysis Report (UFSAR).

24.

Current engineering / safety analyses for internal flooding events other than those in the

UFSAR.

25.

Procedures that provide implementation guidance for the following programs:

Corrective Action Program, Maintenance Rule Program, and Operating Experience

Program.