ML083530317: Difference between revisions
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| number = ML083530317 | | number = ML083530317 | ||
| issue date = 12/08/2008 | | issue date = 12/08/2008 | ||
| title = | | title = 2.206 Petition from M. Mulligan | ||
| author name = Mulligan M | | author name = Mulligan M | ||
| author affiliation = - No Known Affiliation | | author affiliation = - No Known Affiliation | ||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:From: | {{#Wiki_filter:From: | ||
Sent: | Michael Mulligan [steamshovel2002@yahoo.com] | ||
Sent: | |||
Monday, December 08, 2008 2:39 PM To: | |||
James Kim | |||
==Subject:== | ==Subject:== | ||
| Line 27: | Line 30: | ||
This raises issues with what size Diesel Generator capacity would be necessary with the new plants. I am thinking the design accident bus load should be 25% to 40% below the continuous rating of the DG when purchasing it. | This raises issues with what size Diesel Generator capacity would be necessary with the new plants. I am thinking the design accident bus load should be 25% to 40% below the continuous rating of the DG when purchasing it. | ||
I futher think we need a IG investigation...a case study with how not to purchase DGs...how a plant(s) would be forced to live with inadiquate DG's for the whole life time of operation. | I futher think we need a IG investigation...a case study with how not to purchase DGs...how a plant(s) would be forced to live with inadiquate DG's for the whole life time of operation. | ||
OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.9 APPLICATION AND TESTING OF SAFETY-RELATED DIESEL GENERATORS IN NUCLEAR POWER PLANTS | OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.9 APPLICATION AND TESTING OF SAFETY-RELATED DIESEL GENERATORS IN NUCLEAR POWER PLANTS | ||
The below conversation thoroughly cover my issues. It occurs on page 9 and 10 ...the whole conversation discusses what we thought about the recent component inspection at VY. | The below conversation thoroughly cover my issues. It occurs on page 9 and 10...the whole conversation discusses what we thought about the recent component inspection at VY. | ||
http://www.topix.net/forum/source/brattleboro-reformer/T0TIINT9ROEGUN6D0 | http://www.topix.net/forum/source/brattleboro-reformer/T0TIINT9ROEGUN6D0 | ||
: Thanks, mike mulligan Hinsdale, NH E-mail Properties Mail Envelope Properties (376406.15656.qm) | : Thanks, mike mulligan Hinsdale, NH E-mail Properties Mail Envelope Properties (376406.15656.qm) | ||
==Subject:== | ==Subject:== | ||
Re: Vermont Yankee 2.206 Petition - PRB Teleconference (11/25-Tuesday at 10:00am)(2) | Re: Vermont Yankee 2.206 Petition - PRB Teleconference (11/25-Tuesday at 10:00am)(2) | ||
Sent Date: | Sent Date: 12/08/2008 2:39:33 PM Received Date: 12/08/2008 2:39:33 PM From: Michael Mulligan Created By: steamshovel2002@yahoo.com Recipients: | ||
James.Kim@nrc.gov (James Kim) | James.Kim@nrc.gov (James Kim) | ||
Tracking Status: None | Tracking Status: None | ||
Post Office: | Post Office: | ||
web58703.mail.re1.yahoo.com Files | web58703.mail.re1.yahoo.com Files Size Date & Time MESSAGE 11547 12/08/2008 Options Expiration Date: | ||
Priority: | Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received:}} | ||
Latest revision as of 13:56, 14 January 2025
| ML083530317 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 12/08/2008 |
| From: | Mulligan M - No Known Affiliation |
| To: | James Kim Division of Operating Reactor Licensing |
| Kim J, NRR/DORL, 415-4125 | |
| References | |
| 2.206, RG-1.009 | |
| Download: ML083530317 (3) | |
Text
From:
Michael Mulligan [steamshovel2002@yahoo.com]
Sent:
Monday, December 08, 2008 2:39 PM To:
Subject:
Re: Vermont Yankee 2.206 Petition - PRB Teleconference (11/25-Tuesday at 10:00am)(2)
- James, This might better explain why i think the VY Diesel Generators are to small.
I additionally have broader concerns that Fairbanks Morse is a unreliable service provider...the nuclear plant emergency Diesel Generator. I am thinking about recent part 21 issues.
What I get out of reg guide 1.9 is that nuclear power plants are suppose to stay within their continuous rating under all conceivable design accident load conditions...all the loads based on normal and emergency procedures are supposed to be below the continuous rating. Further, the DBA load is supposed to be 5% to 15% below the continuous rating. It is noted that many plant's operated by procedure higher than the continuous rating which is very troublesome.
VY and the NRC are just not operating conservatively.
This raises issues with what size Diesel Generator capacity would be necessary with the new plants. I am thinking the design accident bus load should be 25% to 40% below the continuous rating of the DG when purchasing it.
I futher think we need a IG investigation...a case study with how not to purchase DGs...how a plant(s) would be forced to live with inadiquate DG's for the whole life time of operation.
OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.9 APPLICATION AND TESTING OF SAFETY-RELATED DIESEL GENERATORS IN NUCLEAR POWER PLANTS
The below conversation thoroughly cover my issues. It occurs on page 9 and 10...the whole conversation discusses what we thought about the recent component inspection at VY.
http://www.topix.net/forum/source/brattleboro-reformer/T0TIINT9ROEGUN6D0
- Thanks, mike mulligan Hinsdale, NH E-mail Properties Mail Envelope Properties (376406.15656.qm)
Subject:
Re: Vermont Yankee 2.206 Petition - PRB Teleconference (11/25-Tuesday at 10:00am)(2)
Sent Date: 12/08/2008 2:39:33 PM Received Date: 12/08/2008 2:39:33 PM From: Michael Mulligan Created By: steamshovel2002@yahoo.com Recipients:
James.Kim@nrc.gov (James Kim)
Tracking Status: None
Post Office:
web58703.mail.re1.yahoo.com Files Size Date & Time MESSAGE 11547 12/08/2008 Options Expiration Date:
Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received: