ML20211P380
| ML20211P380 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 10/08/1997 |
| From: | Raddatz M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Haughney C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9710200178 | |
| Download: ML20211P380 (16) | |
Text
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l October 8, 1997 MEMORANDUM T0:
Charles J. Haughney. Acting Director Spent fuel Project Office. NMSS FROM:
Michael G. Raddatz. Sr. Project Manager Spent Fuel Licensing Section Spent Fuel Pro,1ect Office. NMSS
SUBJECT:
MEETING WITH MAINE YANKEE A10MIC POWER COMPANY On September 11. 1997, a meeting was held between representatives of the Nuclear Regulatory Commission and Maine Yankee Atomic Power Company (Maine Yankee) to discuss the options available for storage of its spent fuel. is a list of attendees. Attachment 2 is a copy of the meeting handout. The meeting was noticed on September 3. 1997.
The meeting, requested by Maine Yankee, was an information gathering session fausing on options for the storage of the spent fuel currently at the site.
NRC staff presented a brief overview of the licensing process for independent spent fuel storage installations under both the site specific and general license processes. Maine Yankee informed NRC of its intent to continue discussions with various vendors and will decide on future milestones in fall 1997.
The Maine Yankee reactor shutdown in December 1996 and commenced core offloading in June 1997.
By 2003 Maine Yankee intends to empty the fuel pool and complete the initial decommissioning.
No proprietary information was disseminated or presented at this meeting.
No regulatory decisions were requested or made.
Docket 50-309 Attachments:
1.
Attendee List 2.
Meeting Handout Di st ribution-HbG1TTgattiACenter_
-PUBlic, NMSS R/F sFP0 R/f SfLs R/F NR Fil Inctot __
s PEng EEaston fsturz WReamer. 0GC i
sshankman l
REaton DDorman JYerokun CAnderson. R1 SGaoner, nPA l
lOFC SFP0
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SFPQk
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SFP0 E/
fJLeed [
lNAME MRadhatY:dd V pe i
lDATE' 10/$ /97 10/o } /97 10kEd97 C = COVER E = COVE 1 & LNCLO5URL N = NO COPi OfgCIALRECORDcoPY G:\\MAINEY\\9 29 97.mtg -
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ATTENDANCE LIST i
MEETING BETWEEN U.S. NUCLEAR REGULATORY COMMISSION AND MAINE YANKEE ATOMIC POWER COMPANY-SEPTEMBER 11. 1997
&Lme Oraanization Fritz Sturz NRC/NMSS/SFP0-Eric Leeds NRC/NHSS/SFP0 David Tang NRC/NMSS/SFP0 l
Kim Gruss NRC/NMSS/SFP0__
Sherry Wu NRC/NMSS/SFP0 Rick Rasmussen NRC/RGN-1 Paul Harris NRC/NRR/DRPM Michael.Webb NRC/NRR/DRPM Dan Dorman NRC/NRR Sue Gagner NRC/0PA.
R. P. Jordan Maine Yankee Paul J. Plante-Maine Yankee David A. Rivard Maine Yankee Pat Dostie (by telephone)
State of Maine Uldis Vanags (by telephone)
State of Maine Steve Schulin The IBEX Group James Doman Booz Allen (DOE)
Ray N Bechtel Power Corp.
Alan elson NEI ATTACHMENT 1
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Licensing of Independent l
Spent Fuel Storage Installations I,
l Michael G. Raddatz, Senior Project Manager Licensing i
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Spent Fuel Licensing Section Spent Fuel Project Office l
United States iJuclear Regulatory Commission w
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j ATTACHMENT 2
i 10 CFR Part 72 Regulations 3
= Technical Requirements l
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- Siting Criteria i
- Design Criteria
- Design Basis Accidents l
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- Quality Assurance i
- Emergency Planning i
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Procedural Aspects i
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= One-Step Licensing i
= 20 Years
- lSFSI
= 40 Years
- MRS
= Licensing Terms
- Renewable
= Environmental Review
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The Regulations Consider l
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Accidents l
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- Explosions
- Fires l
- Drops / Tipovers j
- Airplane Events Sabotage
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I General Li.;ense I
Advantages
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- No Application Process
- Pre-Approval of Designs a Disadvantages
- Cask availability
- Restrictive
- Must retain 10 CFR Part 50 license
- Reliance upon vendors L
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D The General License Safety requirements of 10 CFR Part 72
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remain in effect Current safeguards requirements for 10 CFR
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Part 73 for fixed sites remain applicable Ruie approved several cask designs
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- New Casks are added by rulemaking em
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Licensee Requirements Under the General License
= NRC Notifications:
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- 90 days prior to first storage under the General l
License
- Register use of a cask design within 30 days of use
- Provide a preoperational test report at least 30 days prior to receipt of spent fuel j
- Maintain a copy of the Certificate of Compliance and other vendor supplied documents l
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i Site Specific Licensing i
= Direct Review of an Application
= Approval of a Storage System's Topical Safety Analysis Report
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= Combination of the Above t_
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Site Specific Licensing l
Review of the Application
= Review of the Environmental Report
- Prepare an Environmental Assessment
= Review Safety Analysis Report
- Q&A's to resolve issues
- Supplementary Information
- Confirmatory Calculations
= Publish a Safety Evaluation Report 1
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The Safety Review Major Areas of a Review l
= Confinement Barriers a Criticality
= Testing & Maintenance
- Pre-Operational l
- Operational h
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l-Certificate of Compliance I
i What do you get ?
= 20 year renewable certificate l
= Casks must be manufactured per a l
Certificate of Compliance j
= Description of cask and references to l
appropriate drawings l
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= Technical Specifications t
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c Certificate of Compliance 4
What does it Contain ?
l Functional and Operating Limits
=
- Surveillance / maintenance requirements
-Inert gas pressure I
- Leak tightness
- Surface dose rates and contamination limits l
Type of fuel
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- Cooling time
- Burnup / heat loads
-Initial Enrichment Lift height restrictions
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NRC Expectations
= Utilities
- Early involvement l
- Frequent communications with NRC and Public l
- Early notification essential
- Aggressive QA oversight l
- Aggressive self assessments
= Fabricators l
- Adhere strictly to QA program i
- Document all deviations thoroughly
- Justify all changes in detail
- Communicate often with vendor and utility 4
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Dry Storage issues l
= Overall inconsistent performance
= Utility oversight essential l
= QA programs and principles not observed
- FabricatorsNendors
= Engineering safety evaluations
- Poorly Documented
= NRC expectations not clearly communicated
= Public Confidence Jeooardized i
.