ML101190563
| ML101190563 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/23/2009 |
| From: | Michael Brown Office of Nuclear Reactor Regulation |
| To: | Barber G, Ronald Bellamy NRC Region 1 |
| References | |
| FOIA/PA-2010-0118 | |
| Download: ML101190563 (2) | |
Text
Brn, Jal v..
r From:
Brown, Michael Sent-.
Monday, November 23, 2009 9:29 AM To:
Barber, Scott' Bellam y,ýRonald
.Cc:
Brand, Javier; Kern, David;'.Spindler, David,
Subject:
Morning Call notes affecting.Branh -6 'TMI Contamination event Scott et al, Heireis w*.ha-t Iheard on the Morning.call today regarding TMI's:Contamination event. Please take a look at it ande.
e
- ifi-is-correct, feel free to correct as.:necessary. The first part is juSt the EN that was issued and the 2ndJis :wht I. heard-on-the Morning call EN.45514-:TMi. -RADIATION RELEASE INCONTAINMENT ASSOCIATED WITH STEAM GENERATOR REMOVAL.-
"This' even'tis being reported via the ENS to theANRCOperations Center within four hours after notifications weremade to-the, ennsy'.vaniaEmergency Management Agency and local counties for an event of potential publi*i*nter-st. This notification was made at 22:45 on November 21, 2009, after the occurrence of an event related, toath safety andhealth of'onsite personnel for.which a press release has been made. Theýpress release was imade,following the event of potential public interest notifications. This report is being made under "At approximatelyý 16:00 on Saturday November 21, 2009, low levels of radiation activity, were measured on radiation, rmon"ito(rs installed in.the TMI-1 reactor building. Personnel were directed to immediately leave the react*rbuii:g untilthe Source
`of the activity"ould beidentified. Surveys directly outside of the reactor buildingdonst ructirIonopenin indicateda slight increase in activity. Levels have returned to normal. No contaihatiorsiwaS identified outside of the'reactor building. Approximately 150 workers were monitored for
."expo'sur-tthe radiation activity, No worker approached or exceeded' any exposure limits. The sources of the.
.acivitare lbeiieved to be fromomainteiance tasks related to cutting lines1in, preparation for removal of the 'B'Steam Generator."
The licensee.is still investigating the cause of the-event but indicated that the radiation release is no longer in progress.-, Containment Ventilation is established to provide an inflow into containment to the extent possible (dohsidering the openings in containment).
The.licehseeicontacted state and local authorities' and the Pennsylvania Emergency Management Agency (PEMA)? The-licensee notified the NRC Resident Inspector. The licensee has also issued a press release.
Regio'n lMorning:Call Notes`
EN 45514-TMI - RADIATION RELEASE IN CONTAINMENT ASSOCIATED WITH STEAM GENERATOR REMOVAL Approximately at 4-PM Saturday 11/21 TMI had an event involving loss of contamination control inside
,c0ntainment.,,At the time the reactor was defueled with a hole cut in the containment wall to support the ongoing-SG repla*ement outage. The licenseeý is notisure at this'time what activity inside containment led to Sthe ro~blem Their investigation is focusing on two activities (1) "A" piping loop decontamination activities or (2) som-e work on a drain line on the B" SG.
At the!tirimeeof the event 175 workers were insidebcontainment. Of these workers 151 people were selected for deai. e moitoring based on nasal smearsand :portal monitor readings. Of the 151,about 20 people have S potentially :reieived.* doses greater-than 1 mR.
The highest dose to a worker was between 30,and 40 mR.
No sitew'worker. leftthe site with,:external contamination. Airborne contamination levels insidecont'ainment have been restored to pre-event levels and cleanup of:containmentsurfaces is"in progress. The tarp ttatSwas b&m=uuon Wi fta mo W88 dekf.d in bemp*on w~ lth F o
IOf ml"nOnl Act.
2
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, I
- ,1 covering the containment opening was contaminated on its inside surface and is in the process of being replaced.
At thetime of the event there was a slight positive pressure in containment. This condition has been corrected and:there is now a slight negative pressure in containment. The licensee has performed a release calculation forthe period of time where the containment was at positive pressure and determined the maximum release was 0.04 mr. The quarterly limit for a release allowed by their ODCM is 7.5 mr. Therefore, this release is less than 1% of the quarterly limit.
The"A".SG, which was in the process of being lifted when this event occurred, is still hanging vertically inside containment. It is being deconned/encapsulated and the.licensee hopes to down-end it today onto the transfer mechanism that will eventually move it out through the SG opening. The downending process will.end up with part of the SG poking out the hole in the containment wall.
This: event has generated. a significant amount of media interest. Regional OPA and state liason officers have taken inquiries from multiple radio, print media and TV stations. They performed a press release at TMI at 2 pm on Sunday.
The PA governor's office has been notified and they understand this is a low level event. They have some con cerns about notification timeliness. The state-was notified about 9:30 pm on Saturday (event time was 4 pm). Based on the PA state notification, an event report was filed with the HOO (event number 45514). This event was.far below levels that would warrant an unusual event declaration.
TMI still 'has not determined the root cause for the event.
The Region dispatched 2 inspectors to the site on Sunday. In addition, the Residentinpector and one other inspector responded to the site for additional coverage. A Manual Chapter 0309 evaluation has performed and no reactiveinspection is warranted at this time.
The Region is closely following the licensee's response and will be evaluating their root cause determination once it is issued.
Your:help.'in this-matter is appreciated. 2 Questions - Where is Dave Kern and why did Dave Spindler respond (I'thought he.is BV's resident and going to be the SRI at VY)
- Thanks, Mike Mike Brown Reactor Systems Engineer NRR/DIRS/,IEB email -michael-brown@nrc.gov phone-3.01-415-4096.
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