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{{#Wiki_filter:December 14, 2006 MEMORANDUM TO: Michael L. Marshall, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: | {{#Wiki_filter:December 14, 2006 MEMORANDUM TO: Michael L. Marshall, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: | ||
Sunil D. Weerakkody, Chief /RA/ | |||
Fire Protection Branch Division of Risk Assessment Office of Nuclear Reactor Regulation | Fire Protection Branch Division of Risk Assessment Office of Nuclear Reactor Regulation | ||
| Line 28: | Line 29: | ||
==Enclosure:== | ==Enclosure:== | ||
As stated CONTACT: Thinh Dinh, AFPB/DRA/NRR (301) 415-2149 | As stated CONTACT: Thinh Dinh, AFPB/DRA/NRR (301) 415-2149 | ||
ML063490404 | ML063490404 NRR-106 OFFICE AFPB/DRA/NRR BC: AFPB/DRA/NRR NAME TDinh SWeerakkody DATE 12/13/06 12/14/06 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION WATTS BAR NUCLEAR PLANT - UNIT 1 LICENSE AMENDMENT, ULTIMATE HEAT SINK - 88oF MAXIMUM OPERATING TEMPERATURE EVALUATION, (TAC NO. MD1460) | ||
REQUEST FOR ADDITIONAL INFORMATION WATTS BAR NUCLEAR PLANT - UNIT 1 LICENSE AMENDMENT, ULTIMATE HEAT SINK - 88oF MAXIMUM OPERATING TEMPERATURE EVALUATION, (TAC NO. MD1460) | |||
The ultimate heat sink (UHS) is the water source for the essential raw cooling water system, which provide cooling water to various components/systems, including components required for achieving and maintaining post-fire safe shutdown. Although the expected water temperature increase from 85oF to 88oF has no direct physical impact on any safe-shutdown components/systems, the rise in cooling water temperature may adversely impact the performance characteristics of these components/systems. | The ultimate heat sink (UHS) is the water source for the essential raw cooling water system, which provide cooling water to various components/systems, including components required for achieving and maintaining post-fire safe shutdown. Although the expected water temperature increase from 85oF to 88oF has no direct physical impact on any safe-shutdown components/systems, the rise in cooling water temperature may adversely impact the performance characteristics of these components/systems. | ||
To evaluate the impact of the proposed license amendment, if any, on the fire protection program at Watts Bar Nuclear Plant, Unit 1, the Fire Protection Branch requests that the following additional information are provided: | To evaluate the impact of the proposed license amendment, if any, on the fire protection program at Watts Bar Nuclear Plant, Unit 1, the Fire Protection Branch requests that the following additional information are provided: | ||
1. | |||
Section 3.7, Fire Protection, of the license amendment report only discussed the effect of the proposed UHS maximum temperature increase on the high-pressure fire suppression system. The impact on safe-shutdown components/systems and their ability to achieve and maintain post-fire safe shutdown, which is part of the Fire Protection Program should also be discussed in this section. | |||
2. | |||
Note 9 to Table 2 indicated that emergency diesel generator load shedding is performed to reduce the electrical loading to 100%. Will this load shedding be accomplished as part of a permanent design change or as post-fire manual actions?}} | |||
Latest revision as of 04:42, 15 January 2025
| ML063490404 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 12/14/2006 |
| From: | Sunil Weerakkody NRC/NRR/ADRA/DRA/AFPB |
| To: | Marshall M NRC/NRR/ADRO/DORL/LPLII-2 |
| Dinh T, NRR/DRA, 415-2149 | |
| References | |
| TAC MD1460 | |
| Download: ML063490404 (3) | |
Text
December 14, 2006 MEMORANDUM TO: Michael L. Marshall, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Sunil D. Weerakkody, Chief /RA/
Fire Protection Branch Division of Risk Assessment Office of Nuclear Reactor Regulation
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING WATTS BAR NUCLEAR PLANT - UNIT 1 LICENSING AMENDMENT FOR INCREASING THE MAXIMUM ULTIMATE HEAT SINK TEMPERATURE TO 88oF (TAC NO. MD1460)
The Fire Protection Branch reviewed the Ultimate Heat Sink - 88oF Maximum Operating Temperature Evaluation submitted by Watts Bar Nuclear Plant, Unit 1. The analysis was reviewed in accordance with the fire protection program requirements of Title 10 of the Code of Federal Regulation, Part 50, Section 48 (10 CFR 50.48), Fire Protection, and General Design Criteria (GDC) 3, Fire Protection.
As the result of the review, we identified several areas where additional information is needed in order to determine the acceptability of the proposed change. Enclosed is the request for additional information (RAI).
Our effort on this task (TAC No. MD1460) is being continued. If you have any questions regarding the RAI, please contact us.
Enclosure:
As stated CONTACT: Thinh Dinh, AFPB/DRA/NRR (301) 415-2149
ML063490404 NRR-106 OFFICE AFPB/DRA/NRR BC: AFPB/DRA/NRR NAME TDinh SWeerakkody DATE 12/13/06 12/14/06 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION WATTS BAR NUCLEAR PLANT - UNIT 1 LICENSE AMENDMENT, ULTIMATE HEAT SINK - 88oF MAXIMUM OPERATING TEMPERATURE EVALUATION, (TAC NO. MD1460)
The ultimate heat sink (UHS) is the water source for the essential raw cooling water system, which provide cooling water to various components/systems, including components required for achieving and maintaining post-fire safe shutdown. Although the expected water temperature increase from 85oF to 88oF has no direct physical impact on any safe-shutdown components/systems, the rise in cooling water temperature may adversely impact the performance characteristics of these components/systems.
To evaluate the impact of the proposed license amendment, if any, on the fire protection program at Watts Bar Nuclear Plant, Unit 1, the Fire Protection Branch requests that the following additional information are provided:
1.
Section 3.7, Fire Protection, of the license amendment report only discussed the effect of the proposed UHS maximum temperature increase on the high-pressure fire suppression system. The impact on safe-shutdown components/systems and their ability to achieve and maintain post-fire safe shutdown, which is part of the Fire Protection Program should also be discussed in this section.
2.
Note 9 to Table 2 indicated that emergency diesel generator load shedding is performed to reduce the electrical loading to 100%. Will this load shedding be accomplished as part of a permanent design change or as post-fire manual actions?