ML20202G859
| ML20202G859 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/01/1997 |
| From: | Michael Webb NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9712100124 | |
| Download: ML20202G859 (30) | |
Text
{{#Wiki_filter:- -- - Decernber 1,1997 e FACILITY: Meine Yenkoo Atomic Power Station
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 25,1997, TO DISCUSS THE PROPOSED DEFUELED EMERGENCY PLAN FOR MAINE YANKEE ATOMIC POWER STATION On November 25,1997, NRC staff members met at NRC headquarters, Rockville, Maryland, with employees of Maine Yankee Atomic Power Company (MYAPC or the licensee) to discuss the proposed defueled emergency plan for the Maine Yankee Atomic Power Station (Maine Yankee). A list of attendees is included as Enclosure 1. The handout used by MYAPC at the meeting is included as Enclosure 2. MYAPC provided certifications of permanent cessation of operation and permanent removal of fuel from the reactor vessel on August 7,1997. On November 6,1997, MYAPC submitted the proposed defueled emergency plan for Maine Yankee along with a request for exemption from 10 CFR 50.54(q) to allow the licensee to implement the proposed defueled emergency plan. The major areas of exemption include elimination of emergency classification above the " alert" level, elimination of off site emergency response provisions, and elimination of o!! site protective measures, in its presentation, the licensee provided an overview of the regulatory framework that it used to develop the Maine Yankee defueled emergency plan, including a comparison of the license basis of the plant while it was operating versus permanently defueled. MYAPC also f described its defueled accident analyses, as well as the proposed Maine Yankee defueled emergency plan and its proposed implementation schedule. , DRIGINAL SIGNED BY: Michael K. Webb, Project Manager , Non Power Reactors and Decommissioning ' Project Directorate ' Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 50-309
Enclosures:
As stated
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., . . . . . p' Doctrnber 1,1997 FACILITY: Maine Yankee Atomic Power Station
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 25,1997. TO DISCUSS THE PROPOSED DEFUELED EMERGENCY PLAN FOR MAINE YANKEE ATOMIC POWER STATION 1 On November 25,1997, NRC staff members met at NRC headquarters, Ror:kville, Maryland, with employees of Maine Yankee Atomic Power Company (MYAPC or the licensee) to discuss the proposed defueled emergency plan for the Maine Yankee Atornic Power Station (Maine Yankee). A list of attendees is included as Enclosure 1. The handout used by MYAPC at the meeting is included as Enclosure 2. MYAPC provided certifications of permanent cessation of operation and permanent removal of fuel from the reactor vessel on August 7,1997. On November 6,1997, MYAPC submitted .he proposed defueled emergency plan for Maine Yankee along with a request for exemption from 10 CFR 50.54(q) to allow the licenses to implement the proposed defueled emergency plan. The major areas of exemption include elimination of emergency classification above the " alert" level, elimination of off-site smergency response provisions, and elimination of off site protective measures, in its presentation, the licensee provided an overview of the regulatory framework that it used to develop the Maine Yankee defueled emergency plan, including a comparison of the license basis of the plant while it was operating versus permanently defueled. MYAPC also described its defueled accident analyses, as well as the proposed Maine Yankee defueled emergency plan and its proposed implementation schedule. nL/WWJh Michael K. Webb, Project Manager Non Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 50 309
Enclosures:
As stated cc w/ enclosures: See next page
e i ENCLOSURE 1 Meeting to discuss the Maine Yankee Atomic Power Station Proposed Defueled Emergency Plan November 25,1997 i ATTENDEES NAME ORGANIZATION Michael Meisner MYAPC ! Steve Evans MYAPC Maureen Brown MYAPC Paul Eargeron Yankee Atomic Peter Uttlefield Yankee Atomic Rick Rasmussen NRC/ Senior Resident inspector Michael Mesnik NRC/NRR Michael Webb NRC/NRR Barry Zalcman NRC/NRR Dan Barss NRC/NRR Jim O'Brien NRC/NRR Elaine Chan FEMA /OGC Pat Tenorio FEMA /PT&E Peter Wiley State of Maine Alan Nelson NEl Ray Ng Bechtel t
Maine Yankee Atomic Power Station Docket No. 50 309 Cc: Mr. Chorles B. Brinkmari Friends of the Coast Manager ?A*3shington Nuclear P.O. Box 98 Operations, Edgecomb, ME 04556 l ABB Combustion Engineering i 12300 Twinbrook Parkway, Suite 330 Mr. William O' Dell Rockville, MD 20852 - Operations Director Maine Yankee Atomic Power Station Thomas G. Dignan, Jr., Esquire P.O. Box 408 Ropes & Gray - Wiscasset ME 04578 One International Place Boston, MA 02110 2624 Mr. Michael J. Molsner Vice President i Mr. Uldis Vanags Licerising and Regulatory Compliance State Nuclear Safety Advisor Maine Yankee Atomic Power Company 4 State Planning Offico 329 Bath Road State House Station #38 Brunswick, ME 04011 Augusta, ME 04333 Mr. Jonathan M. Block
- j. Mr. P. L. Anderson, Project Manager Attorney at Law Yankee Atomic Electric Company P.O. Box 566 580 Main Street Putney, VT 05346 0566 Bolton, MA 01740 1398 Mr. Michael B. Sellman, President Regional Administrator, Region l Main Yankee Atomic Power U.S. Nuclear Regulatory Commission 329 Bath Road 475 Allendale Road Brunswick, ME 04011 King of Prussia, PA 19406 Mr. Robert Fraser Director First Selectman of Wiscasset Eiigineering Municipal Building Maine Yankee Atomic Power Company U.S. Route 1 329 Bath Road Wiscasset, ME 04578 Brunswick, ME 04011 Mr. Richard Rasmussen Mr. Patrick J. Dostle Senior Resident inspector State of Maine Nuclear Safety Maine Yankee Atomic Power Station inspector U.S. Nuclear Regulatory Commission Maine Yankee Atomic Power Station P.O. Box E P.O. Box 408 Wiscasset, ME C4578 Wiscasset, ME 04578 Mary Ann Lynch, Esquire Mr. Mark Ferri Maine Yankee Atomic Power Company Decommissioning Director 329 Bath Road Maine Yankee Atomic Power Station Brunswick. ME 04011 P.O. Box 408 Wiscasset, ME 04578 Mr. George Zinke, Manager Regulatory Affairs Maine Yankee Atomic Power Company 329 Bath Road Brunswick, ME 04011
l ( ) - l Maine Yankee Defueled Emergency Plan Overview Presentation to U.S. Nuclear Regulatory Commission 1 4 i November 25,1997 . P 8 e M November 25,199
t i Briefing Topics l
. Regulatory Framework for Emergency l Preparedness Reductions 1
l
. Permanently Defueled Accident Analyses - Defueled Emergency Plan i l - Transition / Exemption Request i
l
. Implementation Schedule
! . Surr! mary , l . i
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[ . Maine Yankee: Decommissioning Safety Analysis Summary D i
> Purpose Describe preliminary analyses and Licensing Basis results for Maine Yankee in a decommissioning mode.
l
- > Operating Plant License Basis i
1 Loss of Coolant at Full Power.
- Relevant to. Decommissioning
- Spent Fuel Storage Criticality, i
Loss of Pool Cooling, Waste Handling Accidents. j > Decommissioning Plant License Basis ; i Spent Fuel Pool Accidents: Criticality, Loss of Cooling, Fuel Handling, Loss of Inventory. l Decommissioning Specific Transients: l LLW Storage, Liquid Releases, Cask Handling, Large
- Component Handling.
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{ Regulatory Framework for Emergency Prepardeness i Reductions at Permanently Defueled Nuclear Power Plants l 1 1 - Decommissioning of Nuclear Power Reactors - NRC l Final Rule, 61FR39278,7/29/96 l
- SECY-97-120, Rulemaking Plan for Emergency l Planning Requirements for Permanently Shutdown
! Nuclear Power Plant Sites - 10CFR50.54(q) and (t); 10CFR50.47 and Appendix E to 10CFR50,6/16/97. I i - 10CFR72.32 Emergency Plan for ISFSI,60FR32441, 6/22/95. i Q ~"~) ..
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- Maine Yankee: Decommissioning Safety Analysis Summary i
. Spent Fuel Storage Design Summary ! > Spent Fuel Pool Design t interior Dimensions: 37' Width, 41.5' Length, 38.5' Depth. i- 6' Concrete Walls with 1/4" Welded Stainless Steel Liner. Leakage Monitoring System. Filled with Borated Water at ~1800 ppm. -
> Spent Fuel Racks Two Region; Free Standing; 'Neided Stainless Steel with Boral Neutron Absorber; 4.5 initial W% U23s j 228 Storage Locations (Region I); 1526 Locations (Region 11).
- > Fuel Building New Fuel Receipt Area, New Fuel Storage, Spent Fuel Pool, Cooling and Support Systems.
November 25,1997 9
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Maine Yankee: Decommissioning Safety Analysis Summary Operating License Basis : Off-Site Releases > Loss of Coolant Accident at Full Power 10 CFR 50.46 Analyses Off-site Releases: 3.7 Rem (Whole Body) 160 Rem (Thyroid) > Spent Fuel Handling Accident Dropping of One Fuel Assembly 72 Hours After Reactor Shutdown Off-site Releases: 2.4 Rem (Whole Body) 17.7 Rem (Thyroid) m 2s.m7
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!j Loss of Spent Fuel Pool Cooling Analyses Provide assurance against unacceptable consequences of accidental or inadvertent overheating of spent fuel or the spent fuel pool through passive design and operational constraints.
Spent Fuel Pool Reracking Related Cooling Analyses License Amendment #144 (Issued 3/15/94) Blocked Fuel Storage Cell Loss of Forced Flow Loss of Heat Sink
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Maine Yankee: Decommissioning Safety Anahsis Summary Operating and Decommissioning License Basis
> Spent Fuel Storage Criticality Analyses Provide assurance against unacceptable consequences of i accidental or inadvertent criticality through passive design and operational constraints.
Spent Fuel Pool Reracking Calculations License Amendment #144 (Issued 3/15/94) Two Region Spent Fuel Storage Configuration Misplaced Assembly, Dropped Assembly, Placement of Assembly Adjacent to Racks, Placement of Assembly in Comer of Racks Results K-eff s 0.95 for Normal Storage Configurations (No Boron Credit). K-eff s 0.95 for Accidents (Minimum Boron Credit of 663 ppm). mome r 25. mr e
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l , . j i f Maine Yankee: Decommissioning Safety Analysis Summary i Operating and Decommissioning License Basis
- Loss of Spent Fuel Pool Cooling Analyses (cont.)
t l > Loss of Forced Flow ! Initially Analyzed for License Amendment #144 (Issued 3/15/94) l Re-analyzed for Current Fuel Decay Heat Levels Loss of Both Cooling Pumps with Subsequent Pool Heatup i No Credit for Heat Loss or Evaporation i Spent Fuel Pool Heatup Tests Indicate Substantial Conservatism
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- Results: Calculated Time to Boil (>60 hr) Allows Sufficient Time for Operator Action to Restore Cooling & Makeup.
Radiological Doses from Pool Surface Evaporation and Boiling (2 hr period): Oraan (Lunas) Whole Body l Site Boundary 0.003 mrem 0.0022 mrem l Control Room 0.04 mrem 0.02 mrem 2.56 mrem
- Fuel Building 3.60 mrem i November 25,1997 i
i [ Maine Yankee: Decommissioning Safety Analysis Summary ! Operating and Decommissioning License Basis l Loss of Spent Fuel Pool Cooling Analyses (cont.) 4 l > Blocked Fuel Storage Cell i ! License Amendment #144 (Issued 3/15/94)
- 8' x 10' B!ockage at the Top of the Racks (Multiple Cells) l Decay Heat Corresponding to 180 Days Decay,70 GWD/MTU
! 1" Rack Vent Holes Remain Operational , l Results Steady Two-Phase Cooling of Fuel. l No Fuel Cladding Heatup. ) No Calculated Radiological Consequences. ) Fuel Remains in a Coolable Geometry l i November 25,1997 i j . a
4 Maine Yankee: Decommissioning Safety Analysis Summary Operating and Decommissioning License Basis Loss of Spent Fuel Pool Cooling Analyses (cont.)
> Loss of Heat Sink Discussed as Part of License Amendment #144 (Issued 3/15/94)
Loss of Component Cooling Capacity (Secondary Side of the Spent Fuel Pool Heat Exchanger) Requires Use of Altemale Spent Fuel Pool Cooling Recovery Actions (Reference AOP 2.52) Results Bounded by Loss of Forced Flow Transient Altemate Spent Fuel Pool Cooling initiated Within Acceptable Operator Action Times. Same Transient as Loss of Forced FIF eh Aru:5< mal Recovery Options Available j i i i E
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l I h Maine Yankee: Decommissicning Satety Analysis Sammary
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, t J t i > Spent Fuel Pool Heatup Test t Designed to assess the decay heat loading of the spent fuel pool ! to validate conservatisms in the Loss of Forced Flow, Loss of l Heat Sink, and Spent Fuel Pool !nventory Boiloff calculations. i
- Test Process
[ Initial spent fuel pool temperature: 81F. j Cooling to the spent fuel pool secured for 73 hours. l Final spent fuel pool temperature: 140F. ! i l Results Non-QA'd test results: Spent fuel pool heat load: 3.5 MBtu/hr Decay heat calculation assumption based on NRC Branch Technical ! Position 9.2 (+10% uncertainty): 5.8 MBtu/hr
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Maine Yankee: Decommissioning Safety Analysis Summary Decommissioning License Basis ! > Spent Fuel Pool Accident - Fuel Handling Provide assurance that Off-site and CR doses are within a small fraction of EPA PAGs. ! Analysis 1 Release of radionuclides from one dropped fuel assembly i Worst case composite fuei assembly with 1 year decay No credit for Fuel Building ventilation; No credit for water ! scrubbing of released gases (DF=1) l Isotopic Releases: 10% (Noble Gases, lodine), 30% (K85,i29) i Limitina Results
- Whole Body Thyroid ,
Off-site Doses: 0.4 mrem 6.1 mrem CR Doses: 3.3 mrem 66 mrem NovemtMn 25,1997 i
Maine Yankee: Decommissioning Safety Analysis Summary Radiation Fields at the Top of the Spent Fuel Pool l
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1 Maine Yankee: Decommissioning Safety Analysis Summary Decommissioning License Basis l Loss of Spent Fuel Pool inventory Analyses (cont.) !
> Spent Fuel Pool Inventory Boiloff Calculated as Part of Loss of Forced Flow Analysis Spent Fuel Pool Heatup Tests indicate Substantial Conservatism Results:
Calculated Boil-off Rate (12.5 gpm) Ailows Sufficient Time for Operator Action to Restore Makeup (> 15 hours per foot of drop). Radiological Doses from Pool Surface Evaporation and Boiling are the same as the Loss of Forced Flow Analyses. Figure: Radiation Fields at the Tor of the Spent Fuel Pool as a Function of'Nater Depth Above Active Fuel Figure: Skyshine Radiation Fields at Various Horizontal Distances as a Function of' Water Depth Above Active Fuel. m ms- 25. m r
o Maine Yankee: Decommissioning Safety Analysis Summary ; I Decommissioning l_icense Basis Loss of Spent Feel Pool inventory Analyses (cont.)
> Spent Fue: Pool Syphoning Two Syphon Points in the Spent Fuel Pool:
Cooling Water Outlet Piping (~18 Feet Above Active Fuel) Cooling Water inlet Piping (~10 Feet Above Active Fuel) Results Limited Loss of Spent Fuel Pool Inventory. Bounded by Radiological inventory Loss Figures November 25,1997
Maine Yankee: Decommissioning Safety Analysis Summary Skyshine Radiation Fields at Various Horizontal Distances
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- assembees. W toest number of discfwged assembees is 1434. stweiding provided by assemedy and radt structurs erweertses was ignored.
November 25.1997 e
a Maine Yankee: Decommissioning Safe'y Analysis Summary Decommissioning License Basis i l > Decommissicaing Transients Provide assurance that Off-site and CR doses are within a small fraction of EPA PAGs. Analyses Liquid Waste System Failures Low Level Waste Storage Spent Fuel Shipping Cask Drop
~ Decommissioning Activity incidents i
November 25,1997 1
v - - ew..s - Maine Yankee: Decommissioning Safety Analysis Summary Decommissioning License Basis Loss of Spent Fuei Pool inventory Analyses (cont.) > Fuel Troasfer Tu's? Leakage Blank flanges tote instal!ed at both Spent Fuel Pool and Cavity sides of the Transfer Tube. Removal of Valve between Spent Fuel Pool and Cavity
)
Results Not Considered Credible Means of Pool Inventory Loss. i November 25,1997
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u Maine Yankee: Decommissioning Safety Analysis Summary i Decommissioning License Basis Decommissioning Transients (cont.) 1
> Low Level Waste Storage Spill of a Full Resin HIC within the LLW Storage Facility.
148 Cubic Feet of Dewatered Resin Spilled. Initial Activity at LSA Shipping Limits (49 CFR 173.403), except 8 for 1 129 at 10 CFR 61 Limit and Co > LSA Shipping Limit. Results-2 Hour Site Boundary Dose: 0.017 mrem (Whole Body) 260 mrem (Lung) i November 25,199'
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r [ ] Maine Yankee: Decommissioning Safety Analysis Summary Decommissioning License Basis Decommissioning Transients (cont.)
> Liquid Waste System Failures Full Power FSAR Analysis Primary Drain Tank (PDT) Failure PDT at 80% Capacity with Undecayed RCS Goolant at current Technical Specification Limit 100% PDT inventory Spilled Results 2 Hour Site Boundary Dose: 230 mrem (Whole Body)
Novemter 25,1997 y $
Maine Yankee: Decommissioning Safety Analysis Summary Decommissioning License Basis Decommissioning Transients (cont.)
> Decommissioning Activity incidents Removal of Major Components: Reactor Vessel, Steam Generators, Pressurizer, Reactor Coolant Pumps; RCS Loop Decontamination activities; etc.
Analysis Performed in Accordance with Component Specific Activities. Acceptance Criteria: Administratively Controlled to a Small Fraction of EPA PAGs (i.e.: Less than Liquid Waste System Failure Off-site Doses). November 25,1997
Maine Yankee: Decommissioning Safety Analysis Summary Decommissioning License Basis . oecommissioning Transients (cont.)
> . Spent Fuel Shipping Cask Drop Maine ' Yankee Technical Specifications do not allow the use of spent fuel shipping casks. Therefore, this accident is not included within the licensing basis at this time.
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Maine Yankee: Decommissioning Safety Analysis Summary Non-License Basis Decommissioning Analyses ) i f
> Spent Fuel Pool Draindown and Fuel Rod Oxidation Not considered a credible event.
Two Scenarios Considered:
- 1. Loss of all water in the spent fuel pool.
Exposure of fuel assembly to air.
- 2. Break in the spent fuel pool wall at the 11' elevation.
Draining of spent fuel pool water into the lower PAB. Both scenarios use the composite worst case fuel assembly. Methodology Scientech, Inc. use of scoping calculations and TRAC-PF1 code. TRAC is a NRC developed advanced, best estimate program to calculate transient fuel and thermal-hydraulic behavior. Relevant i models specifically qualified for i November 25,1997
Maine Yankee: Decommissioning Safety Ana!ysis Summary Non-License Basis Decommissioning Analyses 1
> Those analyses which are not part of the plant License l Basis and are not reflective of regulatory requirements.
. Voluntary'by Maine Yankee
. Would not meet Backfit Rule test
> Classified as "Beyond Design Basis" Analyses:
Spent Fuel Pool Draindown and Fuel Rod Oxidation Radiological Assessment of Fuel Assembly Exposure
> "Best estimate" analyses 1
thwTh 25,1997
Maine Yankee: Decommissioning Safety Analysis Summary Non-License Basis Decommissioning Analyses" Spent Fuel Pool Draindown and Fuel Rod Oxidation (cont.) Multidimensional flow, steam binding, metal / water oxidation reaction, natural circulation flows, transient thermal effects. Extensive industry and NRC qualification of TRAC code. ! Results Results are preliminary and based on scoping calculations. Scenario 1: With an ambient air temperature of 100F, maximum fuel assembly cladding temperature is less than 570 F (<300 C). Scenario 2: With water levels in the spent fuel pool and PAB basement, between 5.5 and 7.5 feet of the fuel assembly remains covered due to a low boiloff rate and large water reservoir. Maximum fuel assembly cladding oxidation expected to be acceptable. c_.w 2s. mr
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Major Changes of the Defueled Emergency Plan (DEP) ] (Compared to the MY Emeraency Plan for Power Operations)
- Highest event classification level an ALERT. - Emergency Planning Zones eliminated beyond the owner controlled l
area. I
- Offsite interface with State and local agencies limited to event notifications and request for specific assistance (medical, fire, etc.).
4 - Public Information programs for licensee emergency response coordinated by the public affairs staff (as necessary).
- On-shift staff reduced to include Control Room Staff (Shift Manager and Operator (s)).and Security Staff. - The augmented ERO reduced in size and scope, consistent with the reducec hazard of the permanently defueled facility.
- Onsite res aonse facilities reduced to the Control Room and the Technical Support Center.
* .Public Notification System eliminated.
4 November 25,199 _ . -__ ___ ___ ------ ---_)
Assumptions Used in Development of the Defueled Emergency Plan (DEP)
- All fuel is permanently removed from the reactor and stored in the Spent Fuel Pool ]
. Onsite emergency preparedness remains in place as long as spent fuel is stored on-site
. The Plan will be similar to the requirements of 10CFR72.32 (IFSFI) ]
- Postulated accident scenarios associated with SFP, reduced source term and significantly lower risk to the general public.
- Emergency Action Levels will be developed consistent with the safety analyses and other identified hazards.
Onsite Protective Actions will be determined based on the particular incident and will reflect general industrial precautions for hazardous materials. ( m2s. m}
Types of Accidents
- Radiological Accidents Radioactive Liquid Waste System Leaks and Failures Fuel Handling incident 4
Spent Fuel Cask Drop
. Non-Radiological Events Loss of System Monitoring Capabilities Loss of Communications Systems Fire / Explosion and Toxic / Flammable Gas Exposures Natural / Destructive Phenomena Security Compromise g
TABLE OF_C.ONTENTS Section Table of Contents
~
List of Tables List of Figures 1.0 Introduction 2.0 Facility Description 2.1 Maine Yankee Site 2.2 General Area-2.3 Spent Fuel Pool 3.0 Types of Accidents 3.1 Radiological Accidents 3.2 Non-radiological Accidents 4.0 Classification of Accidents 4.1 Definitions 4.2 Categories of Events 5.0 Detection of Accidents 5.1 Area and Process Monitors 5.2 System Status Monitors 6.0 Emergency Response and Mitigation of Consequences 1 6.1 Emergency Response Overview 6.2 Facilities and Equipment 6.3 Mitigation 7.0 Assessment of Releases 8.0 Responsibilities 8.1 Organizational Control of Emergencies 8.1.1 On Shift Organization 8.1.2 Augmented Organization 9.0 Notification, Coordination and Public Information 9.1 Initial Notifications 9.1.1 Maine Yankee Staff ( 9.1.2 Outside Organizations 9.1.3 Information to be Communicated 9.2 Notification and Communication Systems 9.3 Coordination with Offsite Agencies 9.4 Public Information 10.0 Maintaining Emergency Preparedness 10.1 Training 10.2 Review and Updating of the Defueled Emergency Plan and implementing Procedures 10.3 Drills and Exercises 11.0 Recovery 12.0 Offsite Assistance 13.0 References Appendix l- Assistance Agreements Appendix il - Supporting Plans and Documents
Categories of Events
- - S stem Degradation.
Examples: 3 - Loss of Instrumentation Loss of Spent ' Fuel Pool Cooling
- Hazards / Security /ED Judgement Examples:
Fire or Explosion Natural and Destructive Phenomena Emergency Director's Judgement . l Abnormal Radiation Levels / Release of Radioactive ' Materials Examples: l Unplanned increases in radiation levels Unplanned release of liquid or gaseous radioactive material exceeding predetermined ODCM limits November 25,199
Classification of Accidents
- Unusual Event Events are in process or have occurred which l indicate a potential degradation of the level of safety l
of the plant. (No releases of radioactive material requiring offsite response or monitoring are expected) l l
. Adert Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. (Any releases of radioactive material are expected to be a small fraction of the EPA PAGs beyond the owner controlled areas) 9
. . j
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Emergency Response and Mitigation of Consequences
. Facilities and Equipment Control Room i
TSC Area Assembly Areas Communications Equipment Radiological Monitoring Equipment
- . Mitigation /Onsite Protective Actions Evacuation, Sheltering, and Search and Rescue First Aid / Medical Response Personnel Monitoring and Decontamination .
Fire Suppression Systems November 25,199
I Detection of Accidents
- Area and Process Radiation Monitors - Monitors that provide an indication that the spent fuel has been compromised or a potential radiological hazard to workers in the facility exists 1
Examples: Spent Fuel Pool Area Monitor Primary Vent Stack (Gas and Particulate Monito.s)
- System Status Monitors - Focus has shifted from the Reactor Coolant System status to the Spent Fuel Pool status, including support areas / buildings Examples:
Spent Fuel Pool Parameters h e
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Assessment of Releases
~ . Observation of installed instrumentation - Verification of conditions Radiological surveys Air sampling i
Visual observations
. Dose Assessment t
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Technical Support Center ; TSC Equio. Cabs 7_
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l Emergency Response Organization i 1 EMERGENCY g DIRECTOR ! (ED) fj r . .,. - yo- ~ g n.ureyl
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l 8 TECI F E SECURfTY SUPPORT COORDINATOR -
---------------g CEN!ER (SEC) g '
MANAGER 8 ! (TSCM) _ , l I TSc COMMS I l COORDINATOR , g
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I i TECHNICAL & ! DAMAGE CONTROL HAZARD e shirt MANAGEF ENGINEERING l
RESPONSE
ASSESSMENT N - COORDINATOR COORDINATOR g g
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'TERC) (RIMC) [----- SUF N M e
' i TEO N &
ENGINEERING MAINTENANCE ANO ZARD l l'OPEhe6b?O k OPERA N ASSESSWENT S RESPONSE SUPPORT STAFF SUPPORT STAFF SUPPORT STAFF d 0 TECHNICAL SUPPORT CENTER g CONTROL ROOM November 25,1997 ________ _ - __ _- __ - _ _ _ q M
Emergency Organization On-shift Organization r
- Shift Manager (' Emergency Director)
Operator (s) Security Supervisor u ,
- Augmented Organization
- Emergency Director
- TSC Manager l
- Technical and Engineering Response Coordinator l
- Damage Control Response Coordinator Radiological / Hazard Assessment Coordinator
- Security Coordinator Communications Coordinator Q -2s. m} _
[ Maintaining Emargency Preparedness
. Training ERO Members Initial Training Continual Training Offsite Assistance Organizations Site Familiarization
- Plan and Procedure review and updates
. Periodic surveillances
. Communications Systems Checks
- Drills and Exercises Radiological Monitoring and Medical Drills Self Assessment (Critiques) essential element
- 2s. =
( l Notification, Coordination, and Public Information
. Maine Yankee Staff To be completed within 60 minutes of declaration Notification Methods:
Pagers
- CANS automated dialing network
. Outside Organizations Notifications to be complete as soon as practicable, but within 60 minutes of the event declaration
- Dedicated telephone to Maine State Police
- Dedicated telephone to Maine Emergency Manage' ment Agency ENS (FTS-2000) to NRC l
. Public information To be disseminated as necessary by Public Affairs Department g
O S g,
i l l [Offsite Assistance -
. Response from offsite assistance organizations not expected to be necessary, except forfire, medical emergencies or hazardous materials' incidents. ,
i t t November 25,1997
Recovery l Recovery Director is responsible for returning the l facility to pre-emergency safe condition. ! - Maintain comprehensive hazard assessment of the facility;
- Maintain access control to the facility to minimize risk exposure to workers;
. Prioritize clean-up of affected areas / equipment; l
- Isolate and repair damaged equipment / systems; )
. Document all actions taken related to the emergency and recovery operations;
- Provide offsite officials with periodic condition reports regarding impact on the general public.
( -s. .y
[ Exemption Request to 10CFR50.544q) [950.47(b) and Appendix E Standards]
- Offsite emergency response (plans, protective actions, EPZs, public notification system, public information)
- Onsite (EOF,15-minute notification)
. Basis
- Reduced risk to public
- Compliance with 10CFR50.54(q) is not necessary to achieve underlying purpose.
- Would result in undue financial and administretive hardship
- 25. m
f [ Transition to Defueled Emergency Plan ) l
~
. Plan Changes !
Implemented under 10CFR50.54(q)
- No decrease in Plan effectiveness during ~
i decommissioning ! 1
- Approval of exemption request 1
\
I November 25,199 g
.)t 4
mplementation Schedule
. Certifications of Permanent Cessation of Operations 8/7/97 and Fuel Removal from Reactor
- 1998 Biennial Exercise Exemption Request 9/25/97 (MN 97-111) ;
- Briefing for State of Maine and FEMA Region I on 10/14/97 Draft Defueled Emergency Plan
. ApprovJ (PORC) of Defueled Emergency Plan 10/23/97
- Defueled Emergency Plan and 10CFR50.54(q) 11/6/97 Exemption Request (MN 97-119)
- Defueled Emergency Action Levels (EALs) 12/5/97
. Defueled Emergency Plan implementing Procedures 1/30/98 . Training 2/28/98 . NRC Approval of Exemption Request 3/1/98 . Implement Defueled Emergency Plan ASAP after 3/1/98 . Exercise 1998
( -25. mj
[Offsite Emergency Preparedness Aspects )
. Current Program Continuity
. Strong Interface with State and Local Organizations Radiological Emergency Preparedness Com.mittee l (37-B MRSA 954)
EP Policy Group Effective Communications
. Transition plan to be formulated with State and other stakeholders contingent on NRC approval of exemption request.
n.-s. my
L . - . . 1 r-Summary l
- Existing regulatory framework permits exemptions from requirements not applicable, provided standards are met
, ( 50.12).
. Permanently shutdown plant and all spent fuel in storage ; in SFP, coupled with 1 year fuel decay poses significantly l reduced risk to public.
j - Preliminary decommissioning safety analyses demonstrates projected offsite dose consequences from postulated accidents much less than EPA PAGS. I November 25,1997
- - , ,-,.,m, - . ., .,.--- ,,- , , .m,- - -we. , - - . . . , , . . - . . , , . , . , . - - - - . . , , , , -
i b I j [ Summary (continued) i . l . DEP provides planning base for effective response to the ! range of potential emergencies at Maine Yankee site during decommissioning. I - Exemption request to 10CFR50.54(q), and by inclusion the applicable standards of 10CFR50.47 and Appendix E, l meets standards of 10CFR50.12. !
- i
. State of Maine (MEMA) endorses the managed reduction in offsite Emergency Preparedness and Response for Maine Yankee.
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