ML15023A096

Notification of Conduct of a Triennial Fire Protection Baseline IR 05000483/2015007 and Request for Information

ML15023A096
Person / Time
Site:	Callaway
Issue date:	01/23/2015
From:	Greg Werner NRC/RGN-IV/DRS/EB-2
To:	Diya F Union Electric Co
J. Mateychick
References
IR-2015007
Download: ML15023A096 (14)

See also: IR 05000483/2015007

Text

January 23, 2015

Mr. Fadi Diya, Senior Vice President

and Chief Nuclear Officer

Union Electric Company

P.O. Box 620

Fulton, MO 65251

SUBJECT: CALLAWAY PLANT - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE

PROTECTION BASELINE INSPECTION (NRC INSPECTION

REPORT 05000483/2015007) AND REQUEST FOR INFORMATION

Dear Mr. Diya:

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

staff will conduct a triennial fire protection baseline inspection at the Callaway Plant in April and

May 2015. The inspection team will be comprised of four reactor inspectors and up to two

senior reactor analysts from the NRC Region IV office. The inspection will be conducted in

accordance with IP 71111.05XT, Fire Protection - NFPA 805 (Triennial).

The schedule for the inspection is as follows:

Information Gathering Visit: April 7 - 9, 2015

On-site Inspection:

April 27 - May 1, 2015

May 11 - 15, 2015

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

needed to support the inspection and to become familiar with the fire protection program, fire

protection features, post-fire safe shutdown capabilities, plant layout, and mitigating strategies

to address, Section B.5.b of NRC Order EA-02-026, Order for Interim Safeguards and Security

Compensatory Measures, dated February 25, 2002, and 10 CFR 50.54(hh)(2).

Initial lists of the documents the team will review during the conduct of the inspection are listed

in Attachments 1 and 2. The team leader will contact you with any additional specific document

requests prior to the information gathering visit.

During the information gathering visit, the team will also discuss the following inspection support

administrative details: (1) office space size and location; (2) specific documents requested to be

made available to the team in their office spaces; (3) arrangements for reactor site access

(including radiation protection training, security, safety, and fitness for duty requirements); and

(4) the availability of knowledgeable plant staff and licensing organization personnel to serve as

points of contact during the inspection.

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION IV

1600 E LAMAR BLVD

ARLINGTON, TX 76011-4511

F. Diya

- 2 -

We request that during the on-site inspection weeks you ensure that copies of analyses,

evaluations, or documentation regarding the implementation and maintenance of the station fire

protection program, including post-fire safe shutdown capability, be readily accessible to the

team for their review. Of specific interest for the fire protection portion of the inspection are

those documents which establish that your fire protection program satisfies NRC regulatory

requirements and conforms to applicable NRC and industry fire protection guidance (i.e., fire

protection compliance assessment documents). For the 10 CFR 50.54(hh)(2) portion of the

inspection, those documents implementing your mitigating strategies and demonstrating the

management of your commitments for the strategies are of specific interest. Also, personnel

should be available at the site during the inspection, who is knowledgeable regarding those

plant systems required to achieve and maintain safe shutdown conditions from inside and

outside the control room, including the electrical aspects of the relevant post-fire safe shutdown

analyses, reactor plant fire protection systems and features, and the station fire protection

program and its implementation.

This letter does not contain new or amended information collection requirements subject to the

Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection

requirements were approved by the Office of Management and Budget, under Control

Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to

respond to, a request for information or an information collection requirement unless the

requesting document displays a currently valid Office of Management and Budget control

number.

In accordance with 10 CFR 2.390 of the NRC Rules and Practices, a copy of this letter

and its attachments 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.

Your cooperation and support during this inspection will be appreciated. If you have questions

concerning this inspection, or the inspection team's information or logistical needs, please

contact John Mateychick, the team leader, in the Region RIV Office at 817-200-1560 or

John.Mateychick@nrc.gov.

Sincerely,

/RA/

Gregory E. Werner, Chief

Engineering Branch 2

Division of Reactor Safety

Docket Nos.: 50-483

License Nos.: NPF-30

Attachments:

1. Fire Protection Program Supporting Documentation

2. Mitigating Strategies Supporting Documentation

Electronic Distribution for Callaway Plant

A1-1

Attachment 1

Fire Protection Program Supporting Documentation

The documents and information requested below should generally be made available to the

inspection team during the inspection. Electronic format is the preferred media, except where

specifically noted. If electronic media is made available via the internet based inspection

management system (IMS), then the remote document access must allow inspectors to

download, save, and print the documents in the NRC's regional office.

If IMS is utilized, it recommended that a separate folder be used corresponding to each request

item listed below and that multiple documents being uploaded into a folder be combined into a

ZIP file before uploading to IMS. Electronic media on compact disc or paper records (hard

copy) are acceptable.

To allow review before the on-site information gathering visit, the following documents should be

made available to the team in the regional office no later than March 23, 2015:

Post-fire Nuclear Safety Capability, Systems, and Separation Analysis (request A.1)

Fire Hazards Analysis and/or NFPA 805 Design Basis Document (request A.2)

Fire Probabilistic Risk Assessment (PRA) Summary Document or full PRA Document

(request A.3)

NFPA 805 Transition Report, developed in accordance with NEI 04-02 (request A.4)

Fire Risk Evaluations (i.e., NFPA 805 Section 2.4.3) (request A.5)

Plant Change Evaluations (i.e., NFPA 805 Section 2.4.4) (request A.6)

Analysis that demonstrates nuclear safety performance criteria can be achieved and

maintained for those areas that require recovery actions (request A.7)

Based on review of the above seven documents, team leader should identify a preliminary list of

fire areas being considered for inspection prior to the on-site information gathering visit. During

the information gathering visit, or shortly thereafter, the fire areas selected for inspection will be

determined.

This document request is based on typical documents that a generic plant might have. As such,

this generic document request is not meant to imply that any specific plant is required to have all

of the listed documents. It is recognized that some documents listed below may not be

available for your plant. In addition, the document titles listed below are based on typical

industry document names; your plant specific document titles may vary.

To allow review before the on-site inspection weeks, the following documents should be made

available to the team in the regional office no later than April 13, 2015.

A1-2

A.

DESIGN AND LICENSING BASIS DOCUMENTS

A.1

Post-fire Nuclear Safety Capability, Systems, and Separation Analysis.

A.2

Fire Hazards Analysis and/or NFPA 805 Design Basis Document.

A.3

Fire PRA Summary Document or full PRA Document (if summary document not

available).

A.4

NFPA 805 Transition Report, developed in accordance with NEI 04-02.

A.5

Fire Risk Evaluations (i.e., NFPA 805 Section 2.4.3).

A.6

Plant Change Evaluations (i.e., NFPA 805 Section 2.4.4).

A.7

Analysis that demonstrates nuclear safety performance criteria can be achieved and

maintained for those areas that require recovery actions.

A.8

Fire Protection Program and/or Fire Protection Plan.

A.9

LIST of post-fire safe shutdown components (i.e., safe shutdown equipment list).

A.10 Fire Protection System Design Basis Document.

A.11 LIST of applicable NFPA codes and standards and issuance dates (i.e., codes of

record).

A.12 LIST of deviations from (a) NFPA codes of record, or (b) NFPA 805 fundamental fire

protection program and design elements (i.e., NFPA 805, Chapter 3).

A.13 NFPA Compliance Review Report.

A.14 Report or evaluation that compares the fire protection program to the NRC Branch

Technical Position (BTP) 9.5-1 Appendix A.

A.15 COPY of licensee submittals and NRC safety evaluation reports that are specifically

listed in the facility operating license for the approved fire protection program.

A.16 COPY of NRC Safety Evaluation Reports that form the licensing basis for:

Fire Protection Program

Post-fire Nuclear Safety Capability

A.17 COPY of NRC approved exemptions for plant fire protection and post-fire nuclear

safety capability features.

A.18 COPY of exemption requests submitted but not yet approved for plant fire protection

and post-fire nuclear safety capability features.

A1-3

A.19 LIST of nuclear safety capability design changes completed in the last three years

(including their associated 10 CFR 50.59 and NFPA 805 plant change evaluations).

A.20 Facility Operating License.

A.21 Technical Specifications (electronic format only).

A.22 Technical Requirements Manual (electronic format only).

A.23 Updated Final Safety Analysis Report (electronic format only).

B.

GENERAL PLANT DESIGN DOCUMENTS

B.1

Piping and instrumentation diagrams, (P&IDs) and legend list for components used to

achieve and maintain nuclear safety performance criteria for: (electronic format and

C-size paper drawings)

Fires outside the main control room

Fires in areas requiring recovery actions at other than primary control stations

B.2

P&IDs and legend list for fire protection systems, including fire water supply, water

suppression sprinklers, and deluge, and CO2, and Halon systems (electronic format

and C-size paper drawings).

B.3

Yard layout drawings for underground fire protection buried piping (electronic format

and C-size paper drawings).

B.4

AC and DC electrical system single line diagrams, from off-site power down to the

highest safety-related bus level (typically 4kV, EDG bus) (electronic format and C-size

paper drawings).

B.5

Single line diagrams for motor control centers (MCCs) that supply post-fire nuclear

safety component loads (only for selected fire areas) (electronic format and C-size

paper drawings).

B.6

Equipment location drawings which identify the physical plant locations of post-fire

nuclear safety capability equipment (electronic format and C-size paper drawings).

B.7

Plant layout drawings which identify: (electronic format and C-size paper drawings)

Plant fire area boundaries

Combustible control zone drawings

Areas protected by automatic fire suppression and detection

Locations of fire protection equipment

C. CLASSIC FIRE PROTECTION

C.1 COPY of fire protection program implementing procedures (e.g., administrative

controls, surveillance testing, and fire brigade).

A1-4

C.2 LIST of calculations and engineering analyses, studies, or evaluations for the fire

protection system, including the fire water system.

C.3 Hydraulic calculation or analysis for fire protection water system.

C.4 Last two completed surveillance's of fire protection features in the selected fire areas

(detection, suppression, damper inspections, damper tests, penetration inspections,

barrier inspections, etc.).

C.5 LIST of routine tests, surveillances, and preventive maintenance on fire pumps,

including pump controllers and batteries.

C.6 Last two completed annual fire pump pressure and flow tests.

C.7 Last two completed monthly and/or quarterly fire pump tests.

C.8 Last two completed fire loop flow tests and loop flushes.

C.9 CO2 and Halon initial discharge testing or calculation that determined appropriate

concentrations and soak or hold times can be achieved (only for selected fire areas).

C.10 Last five hot work permits (at power).

C.11 Last five transient combustible permits (at power).

C.12 For Fire Brigade Drills, provide the following:

Last five fire brigade drill critiques

Last drill critique for a drill with off-site fire department support

Last unannounced drill critique

Last back-shift drill critique

Dates, shifts, and locations of unannounced drills for last three years

Summary of any unsatisfactory drill performance items for last three years

Last unannounced drill critique by a qualified individual independent of the

licensee's staff

C.13 For fire brigade equipment provide the following:

• Procedure for inventory and inspection

• Most recent inspection and inventory results

C.14 Fire Brigade Qualifications, including self-contained breathing apparatus, (SCBA) and

training lesson plans.

A1-5

C.15 COPY of the mutual aid agreement for the first-due local fire department that is

currently in effect.

C.16 COPY of the evaluation or analysis of the effects of fire suppression activities on the

ability to achieve the nuclear safety performance criteria (only for selected fire areas),

including:

An automatic or manually actuated suppression system, due to a fire in a single

location, will not indirectly cause damage to the success path

inadvertent actuation or rupture of a suppression system will not indirectly cause

damage to the success path

demonstration of adequate drainage for areas protected by water suppression

systems

hydrostatic rating of any floor penetration seals installed within the fire areas that

are credited with keeping water from leaking into fire areas below

C.17 Pre-fire plans for all fire areas.

C.18 For Emergency Lighting Units (ELU), provide the following:

COPY of performance based emergency light assessments

LIST of Preventive Maintenance tasks, frequencies, and bases

Most recently performed monthly or quarterly functional test

Most recently performed battery discharge performance test or conductance

measurement test

ELU battery loading analysis

vendor manual(s) for on-site inspector use

results of black-out testing (if performed)

Maintenance Rule program information related to the ELU

Compensatory measures taken when ELU are out of service

Drawings showing emergency light locations and lamp orientation

C.19 Impairment Log (at start of inspection), for fire protection features that are out of

service.

A1-6

C.20 Three Fire Protection screening reviews for recent design changes, modifications, or

temporary modifications (i.e., an NFPA 805 plant change evaluation that screened

out).

C.21 LIST of penetration seal work, re-work, or installation activities, in the last three years.

C.22 LIST of fire wrap work, re-work, or installation activities, in the last three years.

C.23 Fire protection system health reports for the two most recent quarters.

C.24 Fire protection program health report for the two most recent quarters.

C.25 Emergency lighting system health reports for the two most recent quarters.

C.26 LIST of fire protection system design changes completed in the last three years

(including their associated 10 CFR 50.59 and NFPA 805 plant change evaluations).

C.27 LIST of fire protection system, NFPA 805 engineering equivalency evaluations

completed in the last three years.

C.28 Licensee evaluation of industry operating experience concerning fire protection

issues completed in the last three years.

D. ELECTRICAL

D.1 Identify whether the cables in the selected fire areas are predominantly Thermoset or

Thermoplastic. Specifically identify any Thermoplastic cable in the selected fire

areas.

D.2 Nuclear safety circuit coordination analysis for fuse and breaker coordination of

nuclear safety capability components (only for selected fire areas).

D.3 Administrative or configuration control procedures that govern fuse replacement (e.g.,

fuse control procedures).

D.4 Maintenance procedures that verify breaker over-current trip settings to ensure

coordination remains functional, for post-fire nuclear safety capability components.

D.5 Electrical system health reports for the two most recent quarters.

D.6 Last surveillance demonstrating operability of those components operated from the

primary control stations.

D.7 Schematic or elementary diagrams for circuits to be reviewed (samples to be

identified by the inspector) (C-size paper drawings).

D.8 Cable routing for components and equipment credited for post-fire nuclear safety

capability systems and components (only for selected fire areas).

A1-7

D.9 LIST of post-fire nuclear safety capability system and component design changes

completed, in the last three years.

D.10 LIST of identified fire induced circuit failure configurations (only for selected fire

areas).

E.

OPERATIONS

E.1

LIST of calculations and engineering analyses, studies, or evaluations for the nuclear

safety capability methodology.

E.2

LIST of licensed operator Job Performance Measures (JPMs) for operator actions

required to achieve and maintain post-fire nuclear safety performance criteria.

E.3

LIST of non-licensed operator training associated with non-licensed operator actions

to achieve and maintain post-fire nuclear safety performance criteria (including JPMs,

in-field training walkdowns, simulations, or initial qualification).

E.4

Lesson plans for post-fire nuclear safety capability training for licensed and non-

licensed operators.

E.5

For recovery actions, provide the following:

Manual Action Feasibility Study

Operator Time Critical Action Program

Time lines for time-critical recovery actions

Time line validations

E.6

Thermal hydraulic calculation or analysis that determines the time requirements for

time-critical manual operator actions.

E.7

Operating procedures to achieve and maintain nuclear safety performance criteria

from the control room, with a postulated fire in the selected fire areas.

E.8

Operating procedures to achieve and maintain nuclear safety performance criteria

from outside the control room, with a postulated fire in the control room, cable

spreading room, or any area requiring recovery actions (other than recovery actions

performed in the control room or primary control stations) and any associated

procedure basis documents.

E.9

For safe shutdown equipment and tools, provide the following:

Procedure for inventory and inspection

Most recent inspection and inventory results

E.10 LIST of procedures that implement Cold Shutdown Repairs.

A1-8

E.11 For Cold Shutdown Repairs, provide the following:

Procedure for inventory and inspection (i.e., needed tools, material, etc.)

Most recent inspection and inventory results

E.12 For Radio communications, provide the following:

Communications Plan for firefighting and post-fire safe shutdown manual actions

Repeater locations

Cable routing for repeater power supply cables

Radio coverage test results

Radio Dead Spot locations in the plant

E.13 For telephone, plant pager or sound power phone systems, if relied credited for post-

fire safe shutdown, provide the following:

Communications Plan for firefighting and post-fire safe shutdown manual actions

Locations of phone, pager units, sound powered phone jacks and sound

powered phone headsets

Cable routing including power supply cables

E.14 Environmental and habitability evaluations for post-fire operator actions (temperature,

smoke, humidity, SCBAs, etc.).

F. ADMINISTRATIVE CONTROL, OVERSIGHT, AND CORRECTIVE ACTION PROGRAMS

F.1

Corrective actions for fire-induced circuit failures (including but not limited to NRC

IN 92-18), both single and multiple spurious actuations (only for selected fire areas).

F.2

Corrective actions associated with operator actions to achieve and maintain post-fire

nuclear safety performance criteria.

F.3

Self assessments, peer assessments, and audits of fire protection activities for the

last three years.

F.4

Self assessments, peer assessments, and audits of post-fire nuclear safety capability

methodology for the last three years.

F.5

LIST of open and closed condition reports for the fire protection system for the last

three years.

F.6

LIST of fire event analysis reports for the last three years.

F.7

LIST of open and closed condition reports for emergency lighting units for the last

three years.

A1-9

F.8

LIST of open and closed condition reports for post-fire nuclear safety capability issues

for the last three years. This includes issues affecting the nuclear safety capability

analysis, fire hazards analysis, NFPA 805 design basis, fire risk evaluations, plant

change evaluations, post-fire operating procedures and/or training, timeline

evaluations for operator actions, and supporting engineering evaluations, analysis, or

calculations.

F.9 LIST of procedures that control the configuration of the fire protection program,

features, and post-fire nuclear safety capability methodology and system design.

A2-1

Attachment 2

MITIGATING STRATEGIES SUPPORTING DOCUMENTATION

G. 10 CFR 50.54(hh)(2) MITIGATING STRATEGIES DOCUMENTS

G.1 LIST of all changes to regulatory commitments made to meet the requirements of,

Section B.5.b of NRC Order EA-02-026, Order for Interim Safeguards and Security

Compensatory Measures, dated February 25, 2002, and Title 10 of the Code of

Federal Regulations (10 CFR) 50.54(hh)(2).

G.2 LIST of procedures and guidelines that were revised or generated to implement the

mitigating strategies. These could be extensive damage mitigation guidelines

(EDMGs), severe accident management guidelines (SAMGs), emergency operating

procedures (EOPs), abnormal operating procedures (AOPs), etc.

G.3 A matrix that shows the correlation between the mitigation strategies identified in

Nuclear Energy Institute, 06-12, Revision 2, B.5.b Phase 2 & 3 Submittal Guideline,

issued December 2006, and the site-specific procedures or guidelines that are used

to implement each strategy.

G.4 LIST of engineering evaluations or calculations that were used to verify the

engineering bases for the mitigating strategies.

G.5 Piping and instrumentation diagrams (P&ID) and legend list or simplified flow

diagrams for systems relied upon in the mitigating strategies. These could be the

type used for training (electronic format and C-size paper drawings).

G.6 LIST of modification packages or summary descriptions of modifications with

simplified drawings, for necessary facility changes to implement the mitigating

strategies.

G.7 LIST of routine tests, surveillances, and preventive maintenance for equipment and

tools needed to implement 10 CFR 50.54(hh)(2) strategies.

G.8 For equipment and tools needed to implement 10 CFR 50.54(hh)(2) strategies,

provide the following:

Procedures for inventory and inspection

Most recent inspection and inventory results

G.9 LIST of 10 CFR 50.54(hh)(2) strategies, if any, which have implementing details that

differ from that documented in the submittals or the safety evaluation report.

G.10 Site general arrangement drawings that show the majority of buildings and areas

referenced in 10 CFR 50.54(hh)(2) documents (electronic format and C-size paper

drawings).

G.11 Training records, training matrix, and lesson plans related to 10 CFR 50.54(hh)(2).

G.12 Copies of memoranda of understanding (MOU) (e.g., with local fire departments)

required to implement any mitigating strategies.

F. Diya

-2-

We request that during the on-site inspection weeks you ensure that copies of analyses, evaluations, or

documentation regarding the implementation and maintenance of the station fire protection program, including post-

fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest for the fire

protection portion of the inspection are those documents which establish that your fire protection program satisfies

NRC regulatory requirements and conforms to applicable NRC and industry fire protection guidance (i.e., fire

protection compliance assessment documents). For the 10 CFR 50.54(hh)(2) portion of the inspection, those

documents implementing your mitigating strategies and demonstrating the management of your commitments for the

strategies are of specific interest. Also, personnel should be available at the site during the inspection, who is

knowledgeable regarding those plant systems required to achieve and maintain safe shutdown conditions from inside

and outside the control room, including the electrical aspects of the relevant post-fire safe shutdown analyses, reactor

plant fire protection systems and features, and the station fire protection program and its implementation.

This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction

Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of

Management and Budget, under Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is

not required to respond to, a request for information or an information collection requirement unless the requesting

document displays a currently valid Office of Management and Budget control number.

In accordance with 10 CFR 2.390 of the NRC Rules and Practices, a copy of this letter

and its attachments 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.

Your cooperation and support during this inspection will be appreciated. If you have questions concerning this

inspection, or the inspection team's information or logistical needs, please contact John Mateychick, the team leader,

in the Region RIV Office at 817-200-1560 or John.Mateychick@nrc.gov.

Sincerely,

/RA/

Gregory E. Werner, Chief

Engineering Branch 2

Division of Reactor Safety

Docket Nos.: 50-483

License Nos.: NPF-30

Attachments:

1. Fire Protection Program Supporting Documentation

2. Mitigating Strategies Supporting Documentation

Electronic Distribution for Callaway Plant

DISTRIBUTION

See next page

Accession No. ML15023A096

SUNSI Review By:

JMM

ADAMS:

Yes No

Sensitive

Non-Sensitive

Non-Publicly Available

Publicly Available

Keyword

NRC-002

OFFICE

EB2/SRI

EB2/C

NAME

JMateychickltk

GWerner

SIGNATURE

/RA/

/RA/

DATE

1/20/15

1/23/15

OFFICIAL RECORD COPY

Letter to Fadi Diya from Gregory Werner dated January 23, 2015

SUBJECT: CALLAWAY PLANT - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE

PROTECTION BASELINE INSPECTION (NRC INSPECTION

REPORT 05000483/2015007) AND REQUEST FOR INFORMATION

DISTRIBUTION:

Regional Administrator (Marc.Dapas@nrc.gov)

Deputy Regional Administrator (Kriss.Kennedy@nrc.gov)

DRP Director (Troy.Pruett@nrc.gov)

Acting DRP Deputy Director (Thomas.Farnholtz@nrc.gov)

DRS Director (Anton.Vegel@nrc.gov)

DRS Deputy Director (Jeff.Clark@nrc.gov)

Senior Resident Inspector (Thomas.Hartman@nrc.gov)

Resident Inspector (Michael.Langelier@nrc.gov)

Branch Chief, DRP/B (Neil.OKeefe@nrc.gov)

Senior Project Engineer, DRP/B (David.Proulx@nrc.gov)

Project Engineer, DRP/B (Fabian.Thomas@nrc.gov)

CW Administrative Assistant (Dawn.Yancey@nrc.gov)

Public Affairs Officer (Victor.Dricks@nrc.gov)

Public Affairs Officer (Lara.Uselding@nrc.gov)

Project Manager (Fred.Lyon@nrc.gov)

Branch Chief, DRS/TSB (Geoffrey.Miller@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

ACES (R4Enforcement.Resource@nrc.gov)

Regional Counsel (Karla.Fuller@nrc.gov)

Technical Support Assistant (Loretta.Williams@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov)

RIV Congressional Affairs Officer (Angel.Moreno@nrc.gov)

RIV/ETA: OEDO (Michael.Waters@nrc.gov)