ML20199C102: Difference between revisions
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| number = ML20199C102 | | number = ML20199C102 | ||
| issue date = 11/04/1997 | | issue date = 11/04/1997 | ||
| title = Forwards Proprietary Rept, Assessment of Ex-Vessel Steam Explosions in AP600 Advanced Pressurized Water Reactor, Which Will Be Included in | | title = Forwards Proprietary Rept, Assessment of Ex-Vessel Steam Explosions in AP600 Advanced Pressurized Water Reactor, Which Will Be Included in Staffs Final Ser.Proprietary Rept Withheld | ||
| author name = Sebrosky J | | author name = Sebrosky J | ||
| author affiliation = NRC (Affiliation Not Assigned) | | author affiliation = NRC (Affiliation Not Assigned) | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:__- | {{#Wiki_filter:__- | ||
f ~% | f ~% | ||
4Mc/Dcf0%0 4h UNITE 3 STATES il NUCLEAR REGULATORY COMMISSION I' | |||
IE | IE WAECINGTON, D.C. 30MH001 f" | ||
Nuclear Safety and Regulatory Analysis | November 4,}%q Mr. Nicholas J, L"parulo, Manager | ||
~ | |||
Nuclear Safety and Regulatory Analysis HOV 101997 Nuclear and Ad',anced Technology Division 41 g (ian A. Mc Intyre Westinghouse Electric Corporation Br P.O. Box 355 Pittsburgh, PA 15230 | |||
==SUBJECT:== | ==SUBJECT:== | ||
| Line 27: | Line 29: | ||
==Dear Mr.-Liparulo:== | ==Dear Mr.-Liparulo:== | ||
The staff has asked a contractor to perform analyses of ex-vessel steam explosions for the AP600. A brief discussion of these analyses will be i~luded in the staff's final safety evaluation report. The report from the sontractor is enclosed for your information. | |||
The staff has asked a contractor to perform analyses of ex-vessel steam explosions for the AP600. A brief discussion of these analyses will be i~luded in the staff's final safety evaluation report. The report from the sontractor is enclosed for your information. If you have any questions concerning this report please contact Michael Snodderly of the Containment Systems and Severe Accident Branch at (301) 415-2047. | If you have any questions concerning this report please contact Michael Snodderly of the Containment Systems and Severe Accident Branch at (301) 415-2047. | ||
You have requested that portions of the information submitted in the June 1992, application for design certification be exempt from mandatory public disclosure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staff's final determination. The staff concludes that the enclosed report does not contain those portions of the information for which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify the staff's conclusions. If, after that time, you do not request that all or portions of the information in the enclosure be withheld from publir disclosure in accordance with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission Public Document Room. | You have requested that portions of the information submitted in the June 1992, application for design certification be exempt from mandatory public disclosure. | ||
While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staff's final determination. | |||
The staff concludes that the enclosed report does not contain those portions of the information for which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify the staff's conclusions. | |||
If, after that time, you do not request that all or portions of the information in the enclosure be withheld from publir disclosure in accordance with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission Public Document Room. | |||
If you have any questions regarding this matter, you may contact me at (301) 415-1132. | If you have any questions regarding this matter, you may contact me at (301) 415-1132. | ||
Sincer y, | Sincer y, | ||
/ | |||
h M. Se rosky, | h M. Se rosky, | ||
[Nk o | ' ject Manager dlindardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 52-003 Enclot,ure: As stated cc w/ encl: See next page | ||
[Nk o 3}} | |||
Latest revision as of 08:28, 10 December 2024
| ML20199C102 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 11/04/1997 |
| From: | Joseph Sebrosky NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| Shared Package | |
| ML19313D080 | List: |
| References | |
| NUDOCS 9711190219 | |
| Download: ML20199C102 (1) | |
Text
__-
f ~%
4Mc/Dcf0%0 4h UNITE 3 STATES il NUCLEAR REGULATORY COMMISSION I'
IE WAECINGTON, D.C. 30MH001 f"
November 4,}%q Mr. Nicholas J, L"parulo, Manager
~
Nuclear Safety and Regulatory Analysis HOV 101997 Nuclear and Ad',anced Technology Division 41 g (ian A. Mc Intyre Westinghouse Electric Corporation Br P.O. Box 355 Pittsburgh, PA 15230
SUBJECT:
REPORT ENTITLED 'AN ASSESSMENT OF EX-VESSEL STEAM EXPLOSIONS IN THE AP600 ADVANCED PRESSURIZED WATER REACTOR'
Dear Mr.-Liparulo:
The staff has asked a contractor to perform analyses of ex-vessel steam explosions for the AP600. A brief discussion of these analyses will be i~luded in the staff's final safety evaluation report. The report from the sontractor is enclosed for your information.
If you have any questions concerning this report please contact Michael Snodderly of the Containment Systems and Severe Accident Branch at (301) 415-2047.
You have requested that portions of the information submitted in the June 1992, application for design certification be exempt from mandatory public disclosure.
While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staff's final determination.
The staff concludes that the enclosed report does not contain those portions of the information for which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify the staff's conclusions.
If, after that time, you do not request that all or portions of the information in the enclosure be withheld from publir disclosure in accordance with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission Public Document Room.
If you have any questions regarding this matter, you may contact me at (301) 415-1132.
Sincer y,
/
h M. Se rosky,
' ject Manager dlindardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 Enclot,ure: As stated cc w/ encl: See next page
[Nk o 3