ML20154D727

Forwards RAI Re Spent Fuel Pool & Fuel Assemblies.Response Requested within 30 Days of Date of Ltr

ML20154D727
Person / Time
Site:	Maine Yankee
Issue date:	10/02/1998
From:	Michael Webb NRC (Affiliation Not Assigned)
To:	Meisner M Maine Yankee
References
TAC-MA0069, TAC-MA69, NUDOCS 9810070315
Download: ML20154D727 (6)

Text

.

881 St M Mr. Michael J. Meisner, President Maine Yankee Atomic Power Company P.O. Box 408 Wiscasset, Maine 04578

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR MODELING SPENT FUEL -

POOL HEATUP (TAC NO. MAOO69)

Dear Mr. Meisner:

On September 3,1998, the NRC issued an exemption from certain portions of 10 CFR 50.54 (q),10 CFR 50.47 (b) and (c), and Appendix E to 10 CFR Part 50 to the Maine Yankee Atomic Power Company (MY), which allows MY to discontinue offsite emergency planning and reduce the scope of onsite emergency planning as a result of the permanently shutdown and defueled status of the facility. This exemption was based, in part, on your spent fuel pool data available to the NRC. ' In order to address future exemption requests from permanently shutdown plants in a more generic and timely manner, NRC is requesting additional information regarding your spent fuel pool and fuel assemblies. _ Please respond to the enclosed request for additional information within 30 days of the date of this letter.

If you have any questions regarding this request, please contact me at (301) 415-1347.

Sincerely, se 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

Enclosure:

As stated cc w/ enclosure: See next page 3

DISTRIBUTION: \ l E-MAIL: HARD COPY:

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Mr. Michael J. Meisner, President Maine Yankee Atomic Power Company P.O. Box 408 Wiscasset, Maine 04578

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR MODELING SPENT FUEL POOL HEATUP (TAC NO. MA0069)

Dear Mr. Meisner:

On September 3,1998, the NRC issued an exemption from certain portions of 10 CFR 50.54 (q),10 CFR 50.47 (b) and (c), and Appendix E to 10 CFR Part 50 to the Maine Yankee Atomic Power Company (MY), which allows MY to discontinue offsite emergency planning and reduce the scope of onsite emergency planning as a result of the permanently shutdown and defueled status of the facility. This exemption was based, in part, on your spent fuel pool data available to the NRC. In order to address future exemption requests from permanently shutdown plants in a more generic and timely manner, NRC is requesting additional information regarding your spent fuel pool and fuel assemblies. Please respond to the enclosed request for additionalinformation within 30 days of the date of this letter.

This information will be used to model your spent fuel pool using the COBRA-SFS computer code and evaluate the results of draining the spent fuel pool of all water.

If you have any questions regarding this request, please contact me at (301) 415-1347.

Sincerely, 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

Enclosure:

As stated cc w/ enclosure: See next page DISTRIBUTION:

E-MAIL: HARD COPY:

RBurrows MMendonca Docket File 50-309 EHylton RDudley AMarkley PDND r/f MWebb MFairtile JMinns PUBLIC TFredrichs LThonus MMasnik PHarris DWheeler SWeiss PDND:PM PDND:LA PDND:(A)SC PDND:D MWebb pHyltor MMasnik SWeiss 9 /u /98 ,

f/J/98 / /98 / /98  !

OFFICIAL RECdRD COPY DOCUMENT NAME: G:\SECY\WEBB\MYRAl.LTR

W 82 N88 Mr. Michael J. Meisner, President Maine Yankee Atomic Power Company P.O. Box 408 Wiscasset, Maine 0457G

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR MODELING SPENT FUEL POOL HEATUP (TAC NO. MA0069)

Dear Mr. Meisner:

On September 3,1998, the NRC issued an exemption from certain portions of 10 CFR 50.54 (q),10 CFR 50.47 (b) and (c), and Appendix E to 10 CFR Part 50 to the Maine Yankee Atomic Power Company (MY), which allows MY to discontinue offsite emergency planning and reduce the scope of onsite emergency planning as a result of the permanently shutdown and defueled status of the facility. This exemption was based, in part, on your spent fuel pool data available to the NRC. In order to address future exemption requests from permanently shutdown plants in a more generic and timely manner, NRC is requesting additionalinformation regarding your spent fuel pool and fuel assemblies. Please respond to the enclosed request for additionalinformation within 30 days of the date of this letter.

If you have any questions regarding this request, please contact me at (301) 415-1347.

Sincerely, ORlWME 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

Enclosure:

As stated cc w/ enclosure: See next page DISTRIBUTION:

E-MAIL: HARD COPY:

RBurrows MMendonca Docket File 50-309 EHylton RDudley AMarkley PDND r/f MWebb MFairtile JMinns PUBLIC 1 TFredrichs LThonus MMasnik PHarris DWheeler SWeiss

'SEE PREVIOUS CONCURRENCE PAGE.

PDND:PM PDND:LA* PDND:(A)SC PDND:D g

MWebb **"' EHylton" '"'" MMasnik .fWeiss

'I /#/98 9/30/98 10/ 7/98 jo/IJ08 OFFICIAL RECORD COPY DOCUMENT NAME: G:\SECY\WEBB\MYRAl.LTR

p sarouq\ UNITED STATES g j 2

NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. 20666-0001 4 . . . . . ,o Mr. Michael J. Meisner, President Maine Yankee Atomic Power Company P.O. Box 408 Wiscasset, Maine 04578

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR MODELING SPENT FUEL POOL HEATUP (TAC NO. MA0069)

Dear Mr. Meisner:

On September 3,1998, the NRC issued an exemption from certain portions of 10 CFR 50.54 (q),10 CFR 50.47 (b) and (c), and Appendix E to 10 CFR Part 50 to the Maine Yankee Atomic Power Company (MY), which allows MY to discontinue offsite emergency planning and reduce the scope of onsite emergency planning as a result of the permanently shutdown and defueled status of the facility. This exemption was based, in part, on your spent fuel pool data available to the NRC. In order to address future exemption requests from permanently shutdown plants in a more generic and timely manner, NRC is requesting additionalinformation regarding your spent fuel pool and fuel assemblies. Please respond to the enclosed request for additionalinformation within 30 days of the date of this letter.

If you have any questions regarding this request, please contact me at (301) 415-1347.

Sincerely, Q

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

Enclosure:

As stated cc w/ enclosure: See next page

Docket No. 50-309 Friends of the Coast P.O. Box 98 Edgecomb, ME 04556 Mr. William O' Dell Operations Director Maine Yankee Atomic Power Company

. P.O. Box 408 Wisessset, ME 04578 Mr. George Zinke, Director Nuclear Safety and Regulatory Affairs Maine Yankee Atomic Power Company P.O. Box 408 Wiscasset, ME 04578 Mr. Jonathan M. Block Attorney at Law P.O. Box 566 Putney, VT 05346-0566 Mr. Michael J. Meisner, President Main Yankee Atomic Power Company P.O. Box 408 Wiscasset, ME 04578 Mr. Robert Fraser, Director Engineering Maine Yankee Atomic Power Company P.O. Box 408 Wiscasset, ME 04578 Mr. Patrick J. Dostie ,

State of Maine Nuclear Safety inspector Maine Yankee Atomic Power Company P.O. Box 408 Wiseasset, ME 04578 Mr. Mark Ferri Decommissioning Director Maine Yankee Atomic Power Company P.O. Box 408 Wiscasset, ME 04578

l REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING MODELING OF MAXIMUM FUEL TEMPERATURE FOLLOWING LOSS OF WATER IN THE SPENT FUEL POOL AT MAINE YANKEE On September 3,1998, the NRC issued an exemption from certain portions of 10 CFR 50.54 (q),10 CFR 50.47 (b) and (c), and Appendix E to 10 CFR Part 50 to the Maine Yankee Atomic Power Company (MY), which allows MY to discontinue offsite emergency planning and reduce the scope of onsite emergency planning as a result of the permanently shutdown and defueled status of the facility. In an effort to establish generic conditions under which a permanently shutdown plant may eliminate offsite emergency planning, the NRC is issuing this request for additionalinformation to obtain data required for performing an analysis of the MY spent fuel pool using the COBRA-SFS computer code. The detailed information requested from MY is necessary in order to obtain a more accurate physical representation of the spent fuel pool.

Buildina

1. Provide the spent fuel pool (SFP) building dimensions. Provide a N-S and a W-E profile view of the SFP building (a simple schematic is sufficient). In addition, identify which walls or portions of walls are exterior (i.e., in contact with the ambient environment).

2. Provide the relative location of the SFP within the building (plan view of the building at the 44'6" elevation). Maine Yankee stated 6 ft as the distance from the pool edge to the SFP building walls on the E, S, and W sides of the pool, in addition, provide the dimensions of the stairwell and the fuel receipt bay.

3. Identify whether or not the new fuel storage area and the fuel receipt bay are covered to form a continuous floor at the 44' 6" elevation.

4. Provide the thickness and material of construction of the poolliner.

5. Provide the air flow rate through the 44' 6" elevation level of the SFP building.

6. Provide a schematic that shows the elevation and position of the ventilation system vents servicing the 44' 6" level. In addition, identify whether there is an air inlet vent to the building or if an air inlet is provided via building leakage.

Enclosure

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l. 2 Backa l

l 7. Referring to Figure 6-1 of Reference 1, the top of Figure 6-1 indicates the Boral pane!

has a " clad" and is attached to the cell wall via a " sheath." identify whether or not the " clad" and " sheath" are made of aluminum and stainless steel, respectively. If not, describe the material of construction.

8. Referring to Figura 6-2 of Reference 1, confirm whether or not the cell to cell pitch is the same in all Ws0tions. In either case, identify what the pitch is. In addition, identify whether or not the gap (flux trap) exists on all four sides of a cell.

9. Identify any lateral flow holes that exist on the sides of the cans. If thev do exist, identify the number of holes and where they are located.

l

10. Identify the base plate material and configuration for the Region I and Region ll racks.

l

11. Provide the configuration of the lateral cell to cell connections for the Region I racks.

12. Provide the notation for identifying individual cell locations.

Fuel / Assemblies

13. Provide the diameter of the control rods and identify whether or not they are still in place within the assembiies. If they are in place within the assemblies, identify the individual assemblies or the percentage of assemblies still containing control rods for each batch. l

14. Describe how the configuration of an assembly changes for those assemblies with less than 176 active fuel rods. Referring to Table 2, column 3 of Reference 1, the number of active rods is given as 160,164,168,171,172, and 176. Provide schematics depicting the various assembly configurations.

16. - Identify the fuel loading configuration within the individual racks and indicate the fuel by various batches or by ranges of decay heat loads.

16. Provide the decay heat load for individual batches of fuel.

17. Provide a normalized axial decay heat profile that is representative of an assembly at ,

Maine Yankee.

18. Provide the following information for the control rods:

1) The materials of construction and physical properties, and

2) Whether or not they have a sheath or cladding.

j 19. Provide the emissivity of the control rods, i

i l

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