NUREG/CR-0255, Forwards NUREG/CR-0255 Re Contempt Program for Predicting Containment Pressure & Temp response,NUREG/CR-0009,TID-14844 & ORNL-TM-2412,in Response to Request for Info on Containment Analysis.W/O Encls
| ML20210G993 | |
| Person / Time | |
|---|---|
| Issue date: | 09/18/1986 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Salem E AFFILIATION NOT ASSIGNED |
| References | |
| RTR-NUREG-CR-0009, RTR-NUREG-CR-0255, RTR-NUREG-CR-255, RTR-NUREG-CR-9 NUDOCS 8609260029 | |
| Download: ML20210G993 (3) | |
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%*****) SEP Ig 1986 Mr. Ehab Assayed Salem 18 St. Akaba Kleopatra, Alexandria Egypt
Dear Mr. Salem:
This is in response to your letter requesting information on containment analysis and the analysis of offsite doses following a loss-of-coolant accident (LOCA). The enclosures provide guidance in perfoming these analyses.
Enclosure 1 is NUREG/CR-0255, the CONTEMPT program for predicting containment pressure and temperature response following a postulated high energy line
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break.
Enclosure 2 contains TID-14844. TID-14844 provides information on (1) radioactivity buildup in containment following a LOCA, (2) leakage, decay and dispersion of this radioactivity to offsite boundaries and (3) the methodology for calculating doses. The enclosure also contains Regulatory Guides 1.3 (for Boiling Water Reactors) and 1.4 (for Pressurized Water Reactors). These Regulatory Guides are currently used in the licensing of nuclear power plants in the United States. The meteorological portion of these two Regulatory Guides has been replaced by the methodology of Regulatory Guide 1.145, which is also enclosed.
Enclosure 3 provides information on spray characteristics, spray configuration, and containment spray system design.
Enclosure 4 is NUREG/CR-009. This NUREG provides the technical bases for fission product removal from a containment atmosphere by both the containment spray system and plateout on containment surfaces. Also included is a description of the SPIRT code which is used to evaluate the effectiveness of the containment spray system.
Enclosure 5 is ORNL-TM-2412 which provides information on the heatup of spray droplets in a steam atmosphere. This is used in determining the heat removal capability of the containment spray system. It is noted that the design of the containment spray system is influenced more by fission product removal considerations than containment heat removal requirements. Reference SRP Section 6.2.2, pages 6 and 7 (The SRP Sections were sent to you in NRC's previous response).
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. I believe that the enclosures will provide the information you requested.
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. Sincerely, i
Orig'inal signed by:
ThohasT N6falyakActing Director
- Division of PWR' Licensing - A Office of Nuclear Reactor Regulation 4
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Enclosures:
- As stated Encl' (T) NUREG/CR-0255 TREE-1279 Encl (2) TID-14844 Enci (3) SHNPP FSAR 6.5.2-1 Amend. No. 25 Enc 1 (4) NUREG/CR-0009 Encl (5) ORNL-Tri-24T2 Part VI 1 DISTRIBUTION
- Central File PDR w/o encls
T. Novak
- H. Denton R. Vollmer PPAS D. Mossburg C. E. Rossi J. Milhoan T. Quay R. Licciardo i R. Ballard Pat / Alma j
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j DATE :8/21/86 :8/21/86 :8/21/86 :8/ /86 :8/ /86 :8/ /86 :
- 0FFICIAL RECORD COPY
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I believe that the enclosures will provide the information you requested.
Sincerely, Thomas M Novak, Acting Director Division of PWR Licensing - A
Enclosures:
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DATE_ :8/25/86
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- 8/23/86 __:____________:____ :
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0FFICIAL RECORD COPY
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