ML030910183
| ML030910183 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Watts Bar, Sequoyah  |
| Issue date: | 03/28/2003 |
| From: | Burzynski M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EPIP-13, Rev 9 | |
| Download: ML030910183 (24) | |
Text
Tennessee Valley Authonty, 1101 Market Street, Chattanooga, Tennessee 37402-2801 March 28, 2003 10 CFR 50, Appendix E Section V U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
In the Matter of
)
Docket Nos.
50-259 50-390 Tennessee Valley Authority
)
50-260 50-391 50-296 50-327 50-328 TVA CENTRAL EMERGENCY CONTROL CENTER (CECC) -
EMERGENCY PLAN IMPLEMENTING PROCEDURE (EPIP) REVISIONS In accordance with the requirements of 10 CFR Part 50, Appendix E, Section V, enclosed are copies of the Effective Page Listing and revisions to CECC EPIPs.
PROCEDURE EFFECTIVE DATE EPIP EPL 3/19/03 EPIP-13 Rev. 9 3/19/03 If you have any questions, please contact Terry Knuettel at (423) 751-6673.
Sincerely, Mark J. Burzynski Manager Nuclear Licensing Enclosures cc:
See page 2 Pnnted en recyoed paper
U.S. Nuclear Regulatory Commission Page 2 March 28, 2003 cc (Enclosures):
U.S. Nuclear Regulatory Commission (Enclosures 2)
Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector
[Enclosures provided Browns Ferry Nuclear Plant by site DCRM]
10833 Shaw Road Athens, Alabama 35611-6970 NRC Senior Resident Inspector
[Enclosures provided Sequoyah Nuclear Plant by site DCRM]
2600 Igou Ferry Road Soddy Daisy, Tennessee 37379-3624 NRC Senior Resident Inspector
[No enclosures, by request Watts Bar Nuclear Plant of site resident]
1260 Nuclear Plant Road Spring City, Tennessee 37381
DOCUMENT RELEASE AND FILING INSTRUCTIONS Page 1
of Release No To:
Management ServiceslRIMIEDM Prepared By:
Gail White Other Address:
Extension 751-2108 Date Submitted to Management Organization.
AS&P Services/RIMIEDM:
Address:
.T Attached are: (select one)
Z QA Records/Documents al Non-QA Records/Documents Release and Submitted for:
Z Distribution Z
Retention DOCUMENT NUMBER CECC-EPIP I1 List of Effective Pas I
CECC EPIP-13, cover sheet I
CECC EPIP-13, rev. log CECC EPIP-13
.1 Acceptance, Date Sqgnature 3-1'j-03 Date Contact Ext TVA 40074 B (8-97) (08-97]
Page 1 of I TVA 40074B (8-97) [08-97]
Page 1 Of 1 SPP-2 3-3 [08-29-97]
CECC-EPIP EPL Page 1 of 9 03/19/03 TENNESSEE VALLEY AUTHORITY CENTRAL EMERGENCY CONTROL CENTER EMERGENCY PLAN IMPLEMENTING PROCEDURES LIST OF EFFECTIVE PAGES This list of effective pages must be retained with the CECC-EPIPs.
Procedure No.
Subdivision List of Effective Pages Page No.
1 of 9 2 of 9 3 of 9 4 of 9 5 of 9 6 of 9 7 of 9 8 of 9 9 of 9 Rev. No.
03/19/03 03/19/03 03119/03 03/19/03 03/19/03 03/19/03 03/19/03 03/19/03 Table of Contents 1 of 2 2 of 2 10/17/02 10/17/02 EPIP-1 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G Appendix H Cover Sheet Rev. Log 1 of 30 2 of 30 3 of 30 4 of 30 5 of 30 6 of 30 7 of 30 8 of 30 9 of 30 10 of 30 11 of 30 12 of 30 13 of 30 14 of 30 15 of 30 16 of 30 17 of 30 18 of 30 19 of 30 20 of 30 21 of 30 22 of 30 23 of 30 24 of 30 25 of 30 26 of 30 27 of 30 28 of 30 29 of 30 30 of 30 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36
CECC-EPIP EPL Page 2 of 9 03/19/03 List of Effective Pages (Continued)
Page No.
- Procedure No.
EPIP-2 Subdivision Appendix A Appendix B EPIP-3 Page No.
Cover Sheet Rev. Log 1 of 5 2 of 5 3 of 5 4 of 5 5 of 5 Cover Sheet Rev. Log 1 of 8 2 of 8 3 of 8 4 of 8 5 of 8 6 of 8 7 of 8 8 of 8 Rev. No.
29 29 29 29 29 29 29 30 30 30 30 30 30 30 30 30 30 Appendix A Appendix B Appendix C EPIP-4 Appendix A Appendix B Appendix C Cover Sheet Rev. Log 1 of 8 2 of 8 3 of 8 4 of 8 5 of 8 6 of 8 7 of 8 8 of 8 Cover Sheet Rev. Log 1 of 8 2 of 8 3 of 8 4 of 8 5 of 8 6 of 8 7 of 8 8 of 8 31 31 31 31 31 31 31 31 31 31 33 33 33 33 33 33 33 33 33 33 EPIP-5 Appendix A Appendix B Appendix C EPIP-6 Cover Sheet Rev. Log 1 of 23 2 of 23 3 of 23 4 of 23 5 of 23 6 of 23 7 of 23 8 of 23 9 of 23 23 23 23 23 23 23 23 23 23 23 23 Appendix A Appendix B Appendix C
CECC-EPI P EPL Page 3 of 9 03/19/03 List of Effective Pages (Continued)
Procedure No.
EPIP-6 (Continued)
Subdivision Appendix D Appendix E Appendix F Appendix G Appendix H Appendix I Appendix J Appendix K Page No.
10 of 23 11 of 23 12 of 23 13 of 23 14 of 23 15 of 23 16 of 23 17 of 23 18 of 23 19 of 23 20 of 23 21 of 23 22 of 23 23 of 23 Rev. No.
23 23 23 23 23 23 23 23 23 23 23 23 23 23 EPIP-7 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Cover Sheet Rev. Log 1 of 15 2 of 15 3 of 15 4 of 15 5 of 15 6 of 15 7of 15 8of 15 9 of 15 10 of 15 11 of 15 12 of 15 13 of 15 14 of 15 15 of 15 Cover Sheet Rev. Log 1 of 30 2 of 30 3 of 30 4 of 30 5 of 30 6 of 30 7 of 30 8 of 30 9 of 30 10 of 30 11 of 30 12 of 30 13 of 30 14 of 30 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 EPIP-8 Appendix A Appendix B Appendix C Appendix D Appendix E
CECC-EPIP EPL Page 4 of 9 03/19/03 List of Effective Pages (Continued) v
- Procedure No.
EPIP-8 (Continued)
Subdivision Appendix F Appendix G Appendix H Appendix I Appendix J Page No.
15 of 30 16 of 30 17 of 30 18 of 30 19 of 30 20 of 30 21 of 30 22 of 30 23 of 30 24 of 30 25 of 30 26 of 30 27 of 30 28 of 30 29 of 30 30 of 30 Rev No 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 EPIP-9 Cover Sheet Rev. Log 1 of 47 2 of 47 3 of 47 4 of 47 5 of 47 6 of 47 7 of 47 8 of 47 9 of 47 10 of 47 11 of 47 12 of 47 13 of 47 14 of 47 15 of 47 16 of 47 17 of 47 18 of 47 19 of 47 20 of 47 21 of 47 22 of 47 23 of 47 24 of 47 25 of 47 26 of 47 27 of 47 28 of 47 29 of 47 30 of 47 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 I
Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G
CECC-EPIP EPL Page 5 of 9 03/19/03 List of Effective Pages (Continued)
Procedure No.
EPIP-9 (Continued)
Subdivision Appendix H Appendix I Appendix J Appendix K Appendix L Appendix M Appendix N Page No.
31 of 47 32 of 47 33 of 47 34 of 47 35 of 47 36 of 47 37 of 47 38 of 47 39 of 47 40 of 47 41 of 47 42 of 47 43 of 47 44 of 47 45 of 47 46 of 47 47 of 47 Rev. No.
26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 26 EPIP-11 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G Appendix H Appendix I Appendix J Cover Sheet Rev. Log 1 of 17 2 of 17 3of 17 4 of 17 5 of 17 6of 17 7 of 17 8 of 17 9 of 17 10 of 17 11 of 17 12 of 17 13 of 17 14 of 17 15of 17 16 of 17 17 of 17 Cover Sheet Rev. Log 1 of 19 2 of 19 3 of 19 4 of 19 5of 19 6 of 19 7 of 19 8 Of 19 9 of 19 loof 19 11 of 19 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 18 18 18 18 18 18 18 18 18 18 18 18 18 EPIP-12
CECC-EPIP EPL Page 6 of 9 03/19/03 List of Effective Pages (Continued)
- Procedure No.
EPIP-12 (Continued)
Subdivision 0 0 Page No.
12 of 19 13 of 19 14 of 19 15 of 19 16 of 19 17 of 19 18 of 19 19 of 19 Rev. No.
18 18 18 18 18 18 18 18 EPIP-13 Appendix A Appendix B Appendix C EPIP-14 Cover Sheet Rev Log 1 of 10 2 of 10 3 of 10 4 of 10 5 of 10 6 of 10 7 of 10 8 of 10 9 of 10 10 of 10 Cover Sheet Rev. Log 1 of 25 2 of 25 3 of 25 4 of 25 5 of 25 6 of 25 7 of 25 8 of 25 9 of 25 10 of 25 11 of 25 12 of 25 13 of 25 14 of 25 15 of 25 16 of 25 17 of 25 18 of 25 19 of 25 20 of 25 21 of 25 22 of 25 23 of 25 24 of 25 25 of 25 9
9 9
9 9
9 9
9 9
9 9
9 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G Appendix H
CECC-EPIP EPL Page 7 of 9 03/19/03 List of Effective Pages (Continued)
Drnnnrl-.rr KMr
{qi ihdivmion EPIP-15 Appendix A Appendix B EPIP-17 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G Appendix H Appendix I Appendix J Appendix K Appendix L Appendix M Appendix N Page No.
Cover Sheet Rev. Log 1 of 5 2 of 5 3 of 5 4 of 5 5 of 5 Cover Sheet Rev. Log 1 of 27 2 of 27 3 of 27 4 of 27 5 of 27 6 of 27 7 of 27 8 of 27 9 of 27 10 of 27 11 of 27 12 of 27 13 of 27 14 of 27 15 of 27 16 of 27 17 of 27 18 of 27 19 of 27 20 of 27 21 of 27 22 of 27 23 of 27 24 of 27 25 of 27 26 of 27 27 of 27 Rev. No.
0 0
0 0
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0 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 EPIP-18 Cover Sheet Rev. Log 1 of 6 2 of 6 3 of 6 4 of 6 5 of 6 6 of 6 9
9 9
9 9
9 9
9 Appendix A Appendix B EPIP-19 Cover Sheet Rev. Log 1 of 11 2 of 11 12 12 12 12
CECC-EPIP EPL Page 8 of 9 03/19/03 List of Effective Pages (Continued)
- Procedure No.
EPIP-19 (Continued)
Subdivision Appendix A Appendix B Page No.
3 of 11 4 of 11 5 of 11 6 of 11 7 of 11 8 of 11 9 of 11 10 of 11 11 of 11 Rev. No.
12 12 12 12 12 12 12 12 12 EPIP-21 Appendix A Appendix B EPIP-22 Cover Sheet Rev. Log 1 of 4 2 of 4 3 of 4 4 of 4 Cover Sheet Rev. Log 1 of 7 2 of 7 3 of 7 4 of 7 5 of 7 6 of 7 7 of 7 13 13 13 13 13 13 19 19 19 19 19 19 19 19 19 Attachment A Attachment B EPIP-23 Attachment A Attachment B Attachment C Attachment D Attachment E Attachment F Cover Sheet Rev. Log 1 of 24 2 of 24 3 of 24 4 of 24 5 of 24 6 of 24 7 of 24 8 of 24 9 of 24 10 of 24 11 of 24 12 of 24 13 of 24 14 of 24 15 of 24 16 of 24 17 of 24 18 of 24 19 of 24 20 of 24 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18
CECC-EPIP EPL Page 9 of 9 03/19/03 List of Effective Pages (Continued)
Prnoeprirp No Subdivision Pace No.
Rev. No.
EPIP-23 (Continued)
Attachment G 21 of 24 22 of 24 23 of 24 24 of 24 18 18 18 18 Attachment H Attachment I
P=-tO
=n1 tJAt09At LstcLt r-rir U0VUersnteeL I ^crfr r nlnr 1
Title REV. 9 Tennessee Valley Authority CENTRAL EMERGENCY I CONTROL CENTER EMERGENCY PLAN IMPLEMENTING PROCEDURES TERMINATION AND RECOVERY Effective Date:
3-I
- D
.1 _
A _
__I WRITTEN BY:
Signature REVIEWED BY:
Date PLAN EFFECTIVENESS DETERMINATION:
3/W5?L23IDate Signature CONCURRENCES Concurrence Signature Date E3naer, EP Pro:
Planning and Implementation 3 /rn;Oo03 M Manager yergency Prep redness 7//
g Mdager, Radiological and Chemistry Services 3l1 4{o3 C\\w~~d~
CECC-EPIP-13 TERMINATION AND RECOVERY REVISION LOG Rev. No.
0 1
2 3
4 5
6 7
8 9
Date 3/22/88 7/8/88 12/12/88 7/13/89 6/20/90 5/15/92 9/27/95 10/30/96 7/10/00 3/19/03 Revised Pages All (Formerly IP-16, changed from IPD to EPIP)
Page 1 All All All--*formerIy EPIP-23 (former EPIP-13 transferred to EPIP-14)
Pgs. 2 & 3 revised. New coversheet and rev. log added.
All pages issued.
All pages revised.
Pg. 3 remove reference to Appendix C. Procedure put in new format. All pages issued.
Annual review and self-assessment items. All pages issued.
Annual review. Add information for NRC Administrative Letter 97-03 All pages issued.
1.0 PURPOSE This procedure gives guidance on terminating an incident for which onsite and offsite emergency centers were activated by the Site Emergency Director and transition from the Emergency Response Organization to the Recovery organization if necessary. It identifies the required actions, responsibilities, and interfaces for reentering evacuated onsite areas. It identifies the interface with the state to provide onsite recovery information as well as offsite recovery reentry information.
2.0 SCOPE This procedure describes the criteria for termination of a REP event which required activation of onsite and offsite emergency centers and actions for reentry and recovery activities required to restore the plant to normal operating condition and to provide assistance to state and local organizations.
3.0 REFERENCE NP Radiological Emergency Plan NRC Administrative Letter 97-03 CECC EPIP 4.0 ABBREVIATIONS WARL - Western Area Radiological Laboratory.
NP - Nuclear Power.
LRC - Local Recovery Center.
CECC - Central Emergency Control Center.
SED - Site Emergency Director.
5.0 RESPONSIBILITIES 5.1 The Senior Vice President, NP Operations, or his designee will direct the overall recovery effort.
If expected to be a long-term process, he may establish a recovery organization to be responsible for continuous direction and control of the recovery operation. This organizational structure would be contingent upon the emergency situation and required actions for recovery.
Staffing of the CECC may remain in whole or in part as necessary. The LRC is also available to provide additional office space near the site to support the recovery operation.
5.2 The CECC Director is responsible for coordinating with the Site Emergency Director in determining when to enter the recovery phase. Once that decision has been made, the CECC Director will notify the Senior Vice President, NP Operations, or his designee. He will ensure all the activities are performed as identified in Appendix A, "CECC Director Checklist." The CECC Director will obtain a description of any deviations to plant technical specifications necessary to restore the plant and how these deviations shall be controlled (procedurally), along with an estimate of the time such deviation shall be required to be in effect.
If the event was associated with an emergency off-site either natural or manmade which impacted the off-site (State and local) emergency response, the NRC regional administrator will inform the affected license when the condition of the off-site emergency preparedness infrastructure can support a safe reactor restart. NRC Administrative Letter 97-03 which provides information for plant restart discussions following natural disasters is provided as Appendix C.
- Revision
TERMINATION AND CECC EPIP-13 Page 2 of 10 RECOVERY CC EP Revision 9 5 3 The CECC Public Information Manager acts as an interface between TVA and the news media.
He assists the Senior Vice President, NP Operations, CECC Director, or their designees in drafting news releases concerning progress of the recovery operation. He coordinates all news releases with TVA management and State and Federal officials as required He coordinates all press briefings and interviews concerning the incident 5.4 Radiological Assessment Manager (RAM) provides radiological support as contained in Appendix B, "Radiological Assessment Manager Checklist".
5.4.1 The RAM shall provide to the CECC Director an estimate of radioactive materials, either gaseous or liquid, which may be released to the environment during recovery operations and the impact of such releases on the population in the vicinity of the plant.
5.4.2 He shall provide the CECC Director a description of the radiation exposure and contamination control measures to be employed during the recovery including the disposition of radioactive and contaminated waste generated during the emergency or postulated to be generated during recovery operations.
5 4.3 He shall also interface with the state to provide onsite plant information as well as offsite assistance as needed.
5 5 The Vice President, Engineering and Technical Services, will provide required technical support to the site 5 6 The Manager, Nuclear Fuels, will provide needed technical services to the site. Technical services available include fuel management and core analysis, core performance, nuclear fuel control and accountability, and startup support.
6.0 PROCEDURES 6.1 Termination The decision to terminate an incident for which onsite and offsite emergency centers have been activated will be made by the Site Emergency Director after consultation with the plant technical and operations staffs and coordinated with the CECC Director. Proposals for termination of an emergency and entry into recovery will be coordinated with the State and NRC, if appropriate, through the CECC. This decision will be based upon a comprehensive review of plant system parameters These shall include, but not be limited to, the following:
6 1 1 Stability of the reactor shutdown condition, i e., successful progress toward a cold shutdown condition 6.1 2 Integrity of the reactor containment building
6 1.3 Operability of engineered safety systems and decontamination facilities.
6.1.4 The availability and operability of a heat sink.
6.1.5 The integrity of power supplies and electrical equipment.
6.1.6 The operability and integrity of instrumentation including radiation monitoring equipment (also including portable equipment assigned during the emergency.)
6.1.7 Availability of trained personnel and support services.
6.1.8 The State's needs in coping with the offsite situation.
6.2 Recovery The decision to enter the recovery phase will be made by the SED with concurrence from the CECC Director. The Senior Vice President, NP Operations, or his designee, will direct the overall recovery effort and the plant manager is responsible for inplant recovery operations. All major post-incident recovery measures shall be performed in accordance with written procedures. Procedures must be developed when not available before a recovery activity can be performed.
Recovery/Reentry Operations 6.2.1 A sequence of events before and during the emergency will be documented for review and evaluation.
6.2.2 Valve alignments, system alignments, and other pertinent information will be gathered and assessed for current plant configuration.
6.2.3 A recovery plan will be developed with all procedures required to implement the plan and make assignments to carry out the plan.
6.2.4 Establish organization to carry out plan.
6.2.5 Reentry team personnel exposures in excess of TVA limits must be approved by the Radiological Assessment Manager and Plant Manager.
6.2.6 The reentry teams will be organized for the purpose of locating and marking the radiation areas to facilitate recovery in a safe manner.
6.2.7 The designated manager responsible for onsite recovery efforts will ensure teams are organized with appropriate supervisors, crafts, and safety personnel for each specific operation.
- 6 2.8 Confirm any required NRC approvals are obtained prior to restart of a unit.
- Revision
TERMINATION AND CECC EPIP-13 Page 4 of 10 RECOVERY Revision 9 7.0 LOCAL RECOVERY CENTER (LRC) 7.1 The purpose of the LRC is to provide a nearsite facility for TVA recovery management as well as NRC emergency response personnel and other emergency and/or recovery personnel.
7 2 The LRC provides adequate space for TVA and others who may locate there to support the site should additional office space near the site become necessary during the recovery phase 7 3 The LRC will provide space for NRC personnel. Adequate supplies, communications, and data necessary for them to carry out appropriate functions is available.
8.0 ENVIRONMENTAL SAMPLE COLLECTION AND ANALYSIS 8.1 The TVA emergency field monitoring vans will be used to collect appropriate samples. This sample collection will be coordinated with the State. Samples will be divided and delivered to the State and the appropriate TVA laboratory.
8.2 Western Area Radiological Laboratory (WARL) staffs the EP screening van for screening and analyzing environmental samples near the site. Final analysis of samples will be performed at the WARL Information concerning the samples will be provided to the State and the RAM
APPENDIX A Page 1 of 1 CECC DIRECTOR'S TERMINATION/RECOVERY CHECKLIST Check box Action when action complete 1
El Determine when to initiate recovery/reentry operations.
2 Coordinate the termination of the event or establishing the Recovery Organization with the SED and the State.
3 Ensure the NRC is notified when terminating the event or establishing Recovery Organization 4
l Ensure that the detailed sequence of events around the emergency is reconstructed.
5 El Ensure that there is reconstruction of the operations activities during the events (i.e.,
system alignments, valves, pumps).
6 Ensure that a recovery organization is established and direction and control are
.provided.
7 Coordinate assessment of current conditions and planned recovery activities for l
potential Tech. Spec. impact.
8 al Ensure that a Recovery Plan including procedures for special operations is prepared.
9 Ensure authorization as appropriate for reentry personnel exposures in excess of 10 al CFR 20 limits 10 Authorize funds and the utilization of manpower and equipment for recovery operations.
11 As appropriate, assess offsite effects and keep the NRC and State informed.
- 12
- Coordinate with the State that the offsite emergency preparedness infrastructure a
- can support safe restart of the reactors.
- 13
- Consult with the NRC the status of the offsite emergency preparedness infrastructure l
- in support of a safe restart of the reactors.
Completed by Name:
Date:
- Revision
TERMINATION AND CECC EPIP-13Page 6 of 10 RECOVERY CE CE I-3Revision 9
APPENDIX B Page 1 of 1 RADIOLOGICAL ASSESSMENT MANAGER CHECKLIST Check box Action when action complete 1
LI Ensure that personnel entries into radiological areas utilize the HIS-20 system 2
El Ensure that personnel exposure in excess of 10 CFR 20 limits is authorized by the Plant Manager or Site Emergency Director.
3 C]
Ensure that standard procedures for processing, sampling, or controlling liquid, gaseous, and solid wastes are used.
4 El Direct offsite sampling programs, dose assessments, dose management, and radiation
_.protection programs.
5 Notify the offsite authorities concerning offsite sampling programs and dose assessments.
6 E
Calculate the total maximum individual exposure periodically.
Completed by IName:
I Date:
TERMINATION AND CEOC EPIP 3 Page 7 of 10 RECOERYCECCEPI-13Revision 9
APPENDIX C Page 1 of 4 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001 March 28, 1997 NRC ADMINISTRATIVE LETTER 97-03: PLANT RESTART DISCUSSIONS FOLLOWING NATURAL DISASTERS Addressees All holders of operating licenses or construction permits for nuclear power reactors Purpose The U.S. Nuclear Regulatory Commission (NRC) is issuing this administrative letter to inform addressees about a recently adopted internal practice. This practice involves coordinating the assessment of offsite recovery and onsite restart activities following a natural disaster (hurricane, tornado, flood, storm, earthquake, etc.) where offsite damage may be substantial or undetermined. This administrative letter does not transmit or imply any new or changed requirements or staff positions. No specific action or written response is required.
Background
Numerous events have occurred in recent years in which natural disasters have affected power reactor facilities. Most notable of these is Hurricane Andrew and its impact on the Turkey Point Station. The licensee for the Turkey Point plant shut the reactors down in anticipation of the storm. Onsite damage from the hurricane was extensive. After that event, the licensee repaired the damage and was ready to restart the plant before the offsite emergency preparedness infrastructure was ready to support the restart. An assessment of offsite conditions and infrastructure prior to restart was necessary to assure emergency preparedness in the event of a subsequent reactor accident.
Events have also occurred in which plants have shut down in anticipation of hurricane damage, which turned out to be minimal. Despite the absence of onsite damage, either some off site damage occurred that affected the state of offsite emergency preparedness, or some damage occurred offsite such that the state of offsite emergency preparedness could not be determined immediately.
For these cases, the NRC coordinated with the Federal Emergency Management Agency (FEMA) and the licensees involved to ensure that the restarts occurred after the offsite emergency preparedness infrastructure could safely support them.
TERMINATION AND Page 8 of 10 RECOVERY CECC EPI9P-13 Rev8son 9 APPENDIX C Page 2 of 4 Discussion Although the overall responsibility for confirming the adequacy of radiological emergency preparedness of commercial nuclear power plants is vested with the NRC, it relies on FEMA's assessment of offsite emergency planning and response activities when carrying out this responsibility.
Section III of the Memorandum of Understanding (MOU) Between FEMA and the NRC, dated June 17, 1993, lists responsibilities for both agencies for cooperating in the recovery from a disaster that affects the offsite emergency preparedness infrastructure surrounding power reactors. FEMA's headquarters (HQ) in Washington, D.C, is responsible for providing findings and determinations to the NRC concerning the adequacy of offsite preparedness in the areas surrounding power reactor sites following a severe natural event FEMA HQ bases its assessment on information from State and local governmental authorities, as well as from the affected FEMA regional office and the NRC.
In two recent instances (Hurricane Bertha, July 1996 and Hurricane Fran, September 1996), FEMA HQ chartered special evaluation teams to assess whether the offsite emergency preparedness infrastructure could support the restart of plants that had shut down in anticipation of hurricanes that affected the sites These teams consisted of FEMA and NRC regional representatives, State and local emergency management representatives, and, in a limited capacity, power reactor licensee personnel. These teams provided assessments to FEMA HQ for its ultimate determinations that offsite emergency preparedness could support plant restart in both cases. The chartering of these special evaluation teams helped ensure a timely assessment of the condition of the offsite infrastructure and was based on experience gained with Hurricane Opal (October 1995) and the Quad Cities tornado (May 1996).
In some cases, a natural disaster may occur where onsite damage is minimal, but offsite damage may be substantial or undetermined. In these cases, the plant may be ready to start up shortly after the event. Communications in these cases between the licensee and NRC, the NRC and FEMA, and FEMA and offsite officials will be aggressive; however, stringent protocols will be observed to ensure that FEMA and the NRC operate within the guidelines of the MOU The NRC uses FEMA's determinations to inform power reactor licensees when the condition of the offsite emergency preparedness infrastructure can support a reactor restart. The Office of Nuclear Reactor Regulation (NRR), as well as NRC regional offices, have adopted a communication protocol that links key personnel in the two agencies and the affected licensee organization. An overview of this protocol is attached. Some of the key points of this protocol are 1 NRC regional office personnel maintain close contact with the affected power reactor licensee to determine the state of onsite emergency preparedness and the plans for restart. The NRC regional office communicates this information rapidly to NRR.
TERMINATION AND CEOC EPIP-1 3 Page 9 of 10 RECOVERY CECEI-3Revision 9
APPENDIX C Page 3 of 4
- 2. FEMA regional office personnel maintain close contact with their evaluators in the field, the affected State and local emergency management officials, and the affected NRC regional office to determine the state of offsite emergency preparedness. The FEMA regional office communicates this information rapidly to FEMA HQ.
- 3. The final assessment that offsite emergency preparedness can support a power reactor restart originates from FEMA HQ.
- 4. A single individual in NRR serves as the point of contact with FEMA HQ to receive this assessment. The individual communicates this information rapidly to NRR management and the cognizant NRC regional office.
- 5. After the assessment from FEMA is received and discussed with NRR management, the NRC regional administrator informs the affected licensee that the condition of the offsite emergency preparedness infrastructure can support a safe reactor restart.
The NRC has developed this protocol as a result of discussions with FEMA, as well as lessons learned from Hurricane Andrew and other events The objective of this protocol is to ensure that aggressive and rapid information flow occurs between the involved organizations following natural disasters at power reactors. The NRC expects that the use of this protocol will ensure that the determination that the condition of the offsite emergency preparedness infrastructure can support a reactor restart will be made before the licensee is actually ready to restart the reactor plant(s). In the event that the determination is not made before the licensee is ready to restart the plant(s), the NRC will evaluate the need to delay the restart through the issuance of an order or confirmatory action letter. By accomplishing this protocol, the licensee, FEMA, and NRC can provide for safe and rapid restarts of power reactors in the wake of these disasters and assure that the offsite emergency preparedness infrastructure can function as expected if called upon in an emergency.
This administrative letter requires no specific action or written response.
If you have any questions about this letter, please contact the contact listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
signed by
- Thomas T. Martin, Director Division of Reactor Program Management Office of Nuclear Reactor Regulation
Contact:
W. Maier, NRR (301) 415-2926 E-mail: wam @ nrc.gov Attachments:
- 1. Information Flow for Restart Considerations Following Natural Disasters at Power Reactors
TERMINATION AND CECC EPIP-1 3 Page 10 of 10 RECOVERY Revision 9 APPENDIX C Page 4 of 4 Attachnceft 1 AL 97-03 March 28, 1997 Page 1 of 1 V