ML20095D935: Difference between revisions
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{{#Wiki_filter:3Q | {{#Wiki_filter:3Q | ||
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DSM M COIYgisif B'o*CaHey Power Station | .s DSM M COIYgisif B'o*CaHey Power Station gy} p Sh pp ng ort PA 15077-0004 (412) 643-8069 FAX December 7,1995 GEORGE S. THOMAS u a S rvices Nuclear Power Dwision | ||
(412) 643-8069 FAX December 7,1995 GEORGE S. THOMAS u a S rvices Nuclear Power Dwision | /U. S. Nuclear Regulatory Commission 5 | ||
Chief, Rules Review and Directives Branch Mail Stop T-6D-69 yj Washington, DC 20555-0001 p | |||
Chief, Rules Review and Directives Branch Mail Stop T-6D-69 | n | ||
Washington, DC 20555-0001 | |||
n | |||
==Subject:== | ==Subject:== | ||
P.roposed Generic Communication; Boraflex Degradation in Spent Fuel, Paiol Storage Racks | P.roposed Generic Communication; Boraflex Degradation in Spent Fuel, d | ||
Paiol Storage Racks | |||
.e: | |||
.-w Duquesne Light Company (DLC) is responsible for the operation of Beaver Valley Power Station Units 1 and 2. DLC has reviewed the proposed generic letter and would like to submit the below comment. | |||
The purpose of the proposed generic letter is to request that licensees who use Boraflex as a neutron absorber in their spent fuel storage racks (1) assess the capability of the Boraflex to maintain a 5 percent subcriticality margin and (2) submit a plan of action if this suberiticality margin cannot be maintained by the Boraflex material because of current or projected degradation. The Nuclear Regulatory Commission requests a | The purpose of the proposed generic letter is to request that licensees who use Boraflex as a neutron absorber in their spent fuel storage racks (1) assess the capability of the Boraflex to maintain a 5 percent subcriticality margin and (2) submit a plan of action if this suberiticality margin cannot be maintained by the Boraflex material because of current or projected degradation. The Nuclear Regulatory Commission requests a | ||
" description of the physical condition of the Boraflex, including any deterioration, on the basis of current as well as future projected accumulated gamma exposure." | |||
The physical condition of the Boraflex in a spent fuel rack resulting from " future projected accumulated gamma exposure" cannot be determined. Design of the rack is an integral part of the degradation process (i.e., some rack designs retard the degradation process more than others). Therefore, unless specific testing based on rack design is performed, current technologies are inadequate to determine the future physical condition of the Boraflex. It is more practical to periodically monitor the condition of the Boraflex material using existing neutron absorber surveillance programs. Therefore, DLC suggests that the words "as well as future projected" be deleted from the above sentence. | The physical condition of the Boraflex in a spent fuel rack resulting from " future projected accumulated gamma exposure" cannot be determined. Design of the rack is an integral part of the degradation process (i.e., some rack designs retard the degradation process more than others). Therefore, unless specific testing based on rack design is performed, current technologies are inadequate to determine the future physical condition of the Boraflex. It is more practical to periodically monitor the condition of the Boraflex material using existing neutron absorber surveillance programs. Therefore, DLC suggests that the words "as well as future projected" be deleted from the above sentence. | ||
9512140060 951207 | 9512140060 951207 l | ||
h PDR ADOCK 05000334 P | |||
pyg | |||
1 A-Proposed G:neric Communication; | 1 A-Proposed G:neric Communication; Boraflex Degradation in Spent Fuel Pool Storage Racks Page 2 Thank you for the opponunity to comment on this issue. If you have any questions on this submittal, please contact Mr. R. A. Hruby, Director, Materials and Standards Section, (412) 393-5705. | ||
Sincerely, cb rge S. Thomas i | |||
Sincerely, cb rge S. Thomas | l l | ||
l | |||
1}} | 1}} | ||
Latest revision as of 08:43, 13 December 2024
| ML20095D935 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/07/1995 |
| From: | George Thomas DUQUESNE LIGHT CO. |
| To: | NRC |
| References | |
| FRN-60FR56359 60FR56359-00004, 60FR56359-4, NUDOCS 9512140060 | |
| Download: ML20095D935 (2) | |
Text
3Q
~~'
~M g3 O
y m S b Lf'f k W y,/
.s DSM M COIYgisif B'o*CaHey Power Station gy} p Sh pp ng ort PA 15077-0004 (412) 643-8069 FAX December 7,1995 GEORGE S. THOMAS u a S rvices Nuclear Power Dwision
/U. S. Nuclear Regulatory Commission 5
Chief, Rules Review and Directives Branch Mail Stop T-6D-69 yj Washington, DC 20555-0001 p
n
Subject:
P.roposed Generic Communication; Boraflex Degradation in Spent Fuel, d
Paiol Storage Racks
.e:
.-w Duquesne Light Company (DLC) is responsible for the operation of Beaver Valley Power Station Units 1 and 2. DLC has reviewed the proposed generic letter and would like to submit the below comment.
The purpose of the proposed generic letter is to request that licensees who use Boraflex as a neutron absorber in their spent fuel storage racks (1) assess the capability of the Boraflex to maintain a 5 percent subcriticality margin and (2) submit a plan of action if this suberiticality margin cannot be maintained by the Boraflex material because of current or projected degradation. The Nuclear Regulatory Commission requests a
" description of the physical condition of the Boraflex, including any deterioration, on the basis of current as well as future projected accumulated gamma exposure."
The physical condition of the Boraflex in a spent fuel rack resulting from " future projected accumulated gamma exposure" cannot be determined. Design of the rack is an integral part of the degradation process (i.e., some rack designs retard the degradation process more than others). Therefore, unless specific testing based on rack design is performed, current technologies are inadequate to determine the future physical condition of the Boraflex. It is more practical to periodically monitor the condition of the Boraflex material using existing neutron absorber surveillance programs. Therefore, DLC suggests that the words "as well as future projected" be deleted from the above sentence.
9512140060 951207 l
h PDR ADOCK 05000334 P
pyg
1 A-Proposed G:neric Communication; Boraflex Degradation in Spent Fuel Pool Storage Racks Page 2 Thank you for the opponunity to comment on this issue. If you have any questions on this submittal, please contact Mr. R. A. Hruby, Director, Materials and Standards Section, (412) 393-5705.
Sincerely, cb rge S. Thomas i
l l
1