ML20216F189
| ML20216F189 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe, Maine Yankee |
| Issue date: | 08/26/1999 |
| From: | Alexis Nelson NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT & |
| To: | Dudley R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20216F193 | List: |
| References | |
| PROJECT-689 NUDOCS 9909210206 | |
| Download: ML20216F189 (2) | |
Text
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NUCLEAR ENERGY INSTITUTE l
SEN OR P OJECT MANAGER UC EARG ERATION OMSION August 26,1999 Mr. Richard Dudley U.S. Nuclear Regulatory Commission Document Control Desk Mail Stop 11 D14 Washington, DC 20555-0001
SUBJECT:
Project No. JO689
Dear Mr. Dudley:
Enclosed please find copies of the Maine Yankee and Yankee Rowe references listed below. As discussed at the recent NRC-Public Workshop on Risk Related to Spent Fuel Pool Accidents for Decommissioning Plants, this information supports the industry position that the Branch Technical Position ASB 9-2 methodology over-estimates spent fuel decay heat. At Maine Yankee the BTP ASB 9-2 over-estimated decay heat by approximately 40% *aference 2, page id 01%). At Yankee Rowe using similar ANS methodology decay heat was over-estimated by approximately 80% (Reference 3, page 9).
Please contact me at (202) 739-8110 or by e-mail at apu@nei.org.
Sincerely, I
/
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.f._NLf Alan Nel on APN:tnb V.lf" h
References:
- 1. Duke Engineering & Services Calculation MYC-2004 Rev. O, " Spent Fuel Pool Thermal-Hydraulic Calculations," dated 12/1/97.
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Mr. Richard Dudley August 26,1999 Page 2
- 2. Duke Engineering & Services Calculation MYC-2005 Rev.0, " Spent Fuel Paol Passive Cooling," dated 12/1/97.
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- 3. Duke Engineering & Services Calculation YRC-991 Rev.0, Estimation of Spent Fuel Pit Heat-Up Rate Incorporating Actual Plant Data and Thermal Losses,"
dated, G/3/92.
- 4. Duke Engineering & Services Calculation YRC-991 Rev.1, " Estimation of Spent Fuel Pit Heat Up Rate Incorporating Actual Plant Data and Thermal Losses,"
dated, 4/15/94.
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