ML053290141: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:}} | {{#Wiki_filter:Page 1 NRC FORM 699 U.S. NUCLEAR REGULATORY COMMlSSlOh DATE (9-2003) 11/21/2OO5 CONVERSATION RECORD TIME 10:15am | ||
~ ~ | |||
NAME OF PERSON(S) CONTACTED OR IN CONTACT WITH YOU TELEPHONE NO. TYPE OF CONVERSATION Donald Warren 0 VISIT u CONFERENCE TELEPHONE | |||
~~~ ~ | |||
SUBJECT Response to questions from November 1,2005 Oyster Creek License Renewal Public Meeting 0 INCOMING | |||
@/ OUTGOING | |||
==SUMMARY== | |||
(Continue on Page 2) | |||
BACKGROUND During a licensee renewal public meeting on Novemeber 1,2005, a public stakeholder (Donald Warren) asked the NRC a question concerning an excessive cooldown that occurred in November 2000 (ref. NRC inspection report 05000219/2000-008, dated December 20,2000). The Senior Resident Inspector (Marc S. Ferdas) committed to provide Mr. Warren a response to his question. | |||
CONVERSATION RECORD I contacted Mr. Warren at his home and discussed his question with him. I informed him that Oyster Creek has exceeded the technical specification requirement (cooldown rate of 100 degrees per hour) on 2 occassions, December 29,1972 and November 15,2000. I also informed Mr. Warren that Oyster Creek has NOT exceeded the technical specification bases fatigue limit assumption of 10 cooldowns of 300 degrees per hour. | |||
Mr. Warren asked additional questions concerning: | |||
: 1. Where he could find information on the December 29,1972 event; and | |||
: 2. What inspections and/or testing has Oyster Creek performed on the drywell liner? | |||
}SISP Review Complete: MSF (Reviewer@ Initials) | |||
After declaring this document CAn Official Agency RecordC it wilYwill not be released to the Public. | |||
Continue on Paae 2 ACTION REQUIRED | |||
: 1. Provide NRC reference which documents December 29,1972 event. | |||
: 2. Provide information concerning Oyster Creek drywell liner. | |||
NAME OF PERSON DOCUMENTING CONVERSATION I SIGNATURE I DATE ACTION TAKEN On November 17,2005 at 12:30 pm Mr. Ferdas and Andrew Rosebrook (RVDRPBranch 7Project Engineer) provided M r Warren wl the reference number to an NRC report which documents the 1972 event (Inspection Report 50-219/73-01, Accession Number 9604160473, Microfiche Address 885751198-212). | |||
also informed Mr. Warren that the NRC plans to review information related to the drywell liner during its license renewal inspection scheduled for 2006, and the review will be documented following the inspection. | |||
UTLE OF PERSON TAKING ACTION SIGNATURE OF PERSON TAKING ACTION DATE Senior Resident Inspector 11/17/2OO5}} |
Latest revision as of 16:52, 11 January 2020
ML053290141 | |
Person / Time | |
---|---|
Site: | Oyster Creek |
Issue date: | 11/17/2005 |
From: | Marc Ferdas Division of Reactor Safety I |
To: | Warren D - No Known Affiliation |
References | |
%dam200604, IR-73-001 NUDOCS 9604160473 | |
Download: ML053290141 (1) | |
Text
Page 1 NRC FORM 699 U.S. NUCLEAR REGULATORY COMMlSSlOh DATE (9-2003) 11/21/2OO5 CONVERSATION RECORD TIME 10:15am
~ ~
NAME OF PERSON(S) CONTACTED OR IN CONTACT WITH YOU TELEPHONE NO. TYPE OF CONVERSATION Donald Warren 0 VISIT u CONFERENCE TELEPHONE
~~~ ~
SUBJECT Response to questions from November 1,2005 Oyster Creek License Renewal Public Meeting 0 INCOMING
@/ OUTGOING
SUMMARY
(Continue on Page 2)
BACKGROUND During a licensee renewal public meeting on Novemeber 1,2005, a public stakeholder (Donald Warren) asked the NRC a question concerning an excessive cooldown that occurred in November 2000 (ref. NRC inspection report 05000219/2000-008, dated December 20,2000). The Senior Resident Inspector (Marc S. Ferdas) committed to provide Mr. Warren a response to his question.
CONVERSATION RECORD I contacted Mr. Warren at his home and discussed his question with him. I informed him that Oyster Creek has exceeded the technical specification requirement (cooldown rate of 100 degrees per hour) on 2 occassions, December 29,1972 and November 15,2000. I also informed Mr. Warren that Oyster Creek has NOT exceeded the technical specification bases fatigue limit assumption of 10 cooldowns of 300 degrees per hour.
Mr. Warren asked additional questions concerning:
- 1. Where he could find information on the December 29,1972 event; and
- 2. What inspections and/or testing has Oyster Creek performed on the drywell liner?
}SISP Review Complete: MSF (Reviewer@ Initials)
After declaring this document CAn Official Agency RecordC it wilYwill not be released to the Public.
Continue on Paae 2 ACTION REQUIRED
- 1. Provide NRC reference which documents December 29,1972 event.
- 2. Provide information concerning Oyster Creek drywell liner.
NAME OF PERSON DOCUMENTING CONVERSATION I SIGNATURE I DATE ACTION TAKEN On November 17,2005 at 12:30 pm Mr. Ferdas and Andrew Rosebrook (RVDRPBranch 7Project Engineer) provided M r Warren wl the reference number to an NRC report which documents the 1972 event (Inspection Report 50-219/73-01, Accession Number 9604160473, Microfiche Address 885751198-212).
also informed Mr. Warren that the NRC plans to review information related to the drywell liner during its license renewal inspection scheduled for 2006, and the review will be documented following the inspection.
UTLE OF PERSON TAKING ACTION SIGNATURE OF PERSON TAKING ACTION DATE Senior Resident Inspector 11/17/2OO5