NRC Generic Letter 1982-32: Difference between revisions
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WATER REACTOR PLANT LICENSEES Gentlemen: | -I ______ - | ||
SUBJECT: POTENTIAL | - | ||
STEAM GENERATOR | .U_tp ri ! r 0 0 19 82 I TO ALL PRESSURIZED WATER REACTOR PLANT LICENSEES | ||
RELATED GENERIC REQUIREMENTS (GENERIC LETTER NO. 82-32)The NRC staff has identified potential steam generator related generic requirements and is currently subjecting them to a value impact analysis | Gentlemen: | ||
SUBJECT: POTENTIAL STEAM GENERATOR RELATED GENERIC REQUIREMENTS | |||
(GENERIC LETTER NO. 82-32) | |||
The NRC staff has identified potential steam generator related generic requirements and is currently subjecting them to a value impact analysis. | |||
Any comments you may care to make, either individually or through Owners Groups, on the SAI report and on the probability and consequences of multiple tube rupture scenarios would be considered in the staff's final value impact analysis if they can be provided within 30 days of the date of this letter.Sincerely, Original signedbV Darrell G. Eisenhut Darrell G. Elsenhut, Director Division of Licensing Enclosure: | A major element of the staff's value Impact will be an analysis being prepaeed by our contractor, Science Applications, Inc. A copy of this draft report is provided for your information and use. This report is currently under staff review and will be modified to consider multiple steam generator tube ruptures in combination with other events along with single tube rupture scenarios. | ||
SAI Report | |||
,)' | Any comments you may care to make, either individually or through Owners Groups, on the SAI report and on the probability and consequences of multiple tube rupture scenarios would be considered in the staff's final value impact analysis if they can be provided within 30 days of the date of this letter. | ||
...... ........................ | |||
....... ..................... | Sincerely, Original signedbV | ||
....... ..................... | Darrell G. Eisenhut Darrell G. Elsenhut, Director Division of Licensing Enclosure: 0a ,- | ||
DATE Ip .1.2JT.I.8 | SAI Report | ||
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NRC FORM 318 (10-80) NRCM 0240 O FFICIA L R EC O RD C OP Y USGPO. 1981-335s960}} | |||
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NRC FORM 318 (10-80) NRCM 0240 O FFICIA L R EC O RD C OP Y USGPO. 1981-335s960}} | |||
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Latest revision as of 02:07, 24 November 2019
| ML031210726 | |
| Person / Time | |
|---|---|
| Issue date: | 12/09/1982 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| GL-82-032, NUDOCS 8208190263 | |
| Download: ML031210726 (1) | |
m- it iMh
-I ______ -
-
.U_tp ri ! r 0 0 19 82 I TO ALL PRESSURIZED WATER REACTOR PLANT LICENSEES
Gentlemen:
SUBJECT: POTENTIAL STEAM GENERATOR RELATED GENERIC REQUIREMENTS
(GENERIC LETTER NO. 82-32)
The NRC staff has identified potential steam generator related generic requirements and is currently subjecting them to a value impact analysis.
A major element of the staff's value Impact will be an analysis being prepaeed by our contractor, Science Applications, Inc. A copy of this draft report is provided for your information and use. This report is currently under staff review and will be modified to consider multiple steam generator tube ruptures in combination with other events along with single tube rupture scenarios.
Any comments you may care to make, either individually or through Owners Groups, on the SAI report and on the probability and consequences of multiple tube rupture scenarios would be considered in the staff's final value impact analysis if they can be provided within 30 days of the date of this letter.
Sincerely, Original signedbV
Darrell G. Eisenhut Darrell G. Elsenhut, Director Division of Licensing Enclosure: 0a ,-
SAI Report
8208190263 ,)
'JP1 ~ '
I 1
^~P.
OFFICE
a )
n...
URNAMwo ...
Th -D.
of.I
....... .Q
....
a.l.i~. ..... I.... .................... ...... ........................ ....... ............................ .....................
~ ....
DATE Ip .1.2JT.I.8 ..i2X2....
...124182 ......... ....1 -- z....... ....... ....... ........... ............. ....... ..... ................... ....... .........................
NRC FORM 318 (10-80) NRCM 0240 O FFICIA L R EC O RD C OP Y USGPO. 1981-335s960