ML102180285
| ML102180285 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/08/2009 |
| From: | Jerry Dozier Office of Nuclear Reactor Regulation |
| To: | Division of License Renewal |
| References | |
| FOIA/PA-2010-0116 | |
| Download: ML102180285 (3) | |
Text
Ku!Robert
',(unt-.r" From:
Dozier, Jerry Sent:
Thursday, October 08, 2009 7:12 AM To:
NRR DLR RER1 Distribution; NRR DLRRER2 Distribution; Hiser, Allen; Pelton, David; Lee, Samson; Banic, Merrilee; 'nrcoip6@earthlink.net'; Kuntz, Robert; Wrona, David; Pham, Bo
Subject:
Internal use only...... FW: OpE Item on Crystal River Containment - update From: Bernardo, Robert Sent: Thursday, October 08, 2009 7:09 AM To: Lee, Samson; Dozier, Jerry; Medoff, James
Subject:
FW: OpE Item on Crystal River Containment - update Latest info that OpE has on Crystal River containment.
Bob BeAna'rdo Reactor Systems Engineer US Nuclear Regulatory Commission NRR/ADRO/DIRS/IOEB Mail Stop: O-7C02A 301-415-2621 Robert.Bernardo )nrc.gov From: Bernardo, Robert Sent: Wednesday, October 07, 2009 3:08 PM To: Bernardo, Robert; Bagchi, Goutam; Lee, Brian
Subject:
OpE Item on Crystal River Containment - update
- NOTE. THIS
SUMMARY
IS OFFICIAL USE ONLY -- MAY C IN SENSITIVE INTER DO NOT ORW D ANYP 10 TSID RC OUT FIR INING PERMISSION FR M OR ATOR The following updated OpE item is being passed along from the OpE Clearinghouse Screening Summary for October 6, 2009 Crystal River - Crack on Exterior Containment Wall (1015) - Update The plant remains in mode 6. Reactor head is removed and the water level is 158 feet (23 feet above RV flange) and 101 F. Fuel is still in the vessel with time to boil at 367 minutes. The equipment hatch is open.
Defueling will commence today at 1100. Schedule shows 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for complete defueling. Hydro-demolition of containment concrete is completed. Licensee planning to perform a modification to support outside lift system to account for cracks identified in containment concrete. A root cause investigation is in progress.
Sargent and Lundy is involved with the investigation and corrective actions. Licensee conference call scheduled for tomorrow (10/8) to discuss the lift system modification with the NRC as well as a status update of their efforts. Currently an NDE inspection is being performed to quantify the crack to determine what needs to be done for containment to be declared operable. Containment needs to be operable by Mode 4 which is scheduled for December 2009.
Informatlon in this record was deleted In Bob 8e.n*do eaiordance with the Freedom of Infomaiain ACt.
Reactor Systems Engineer pA
_9
US,Nuclear Regulatory Commission NRR/ADRO/DIRS/IOEB Mail Stop: O-7C02A 301-415-2621 Robert. Bernardo@nrc.gov From: Bernardo, Robert Sent: Tuesday, October 06, 2009 2:34 PM To: Bagchi, Goutam; Lee, Brian; Lee, Samson; Dozier, Jerry; Medoff, James; Burnell, Scott
Subject:
OpE Item on Crystal River Containment
'NOTE:
THI M
Y IS OFFICIAL USE L
- MAY CONTAIN SENSITIVE INTERNAL DO NOT FO ARD ANY PORTI IDE OF NRC WI OTIISO Xyd FROM ORIGINATOR The following OpE item is being passed along from the OpE Clearinghouse Screening Summary for October 6, 2009 Crystal River - Crack on Exterior Containment Wall (10/5) - Update The plant is in mode 6, admin Yellow risk. Head is removed and level is approximately 134.5 feet (6" below RV flange) and 101F. Fuel in vessel with time to boil.at 16 minutes. The equipment hatch is closed. Repairs were completed on the NI plate seals. Cavity fill schedule to start tonight at 22:00. Plant risk will remain Yellow until the refueling cavity is filled.
Hydro-demolition for the containment opening continues. Licensee will perform a modification to support outside lift system as a result of the crack identified in concrete. A root cause investigation is in progress.
Sargent and Lundy is involved with the investigation and corrective actions, as well as operability and f, inr, fi~nnlih, rAnirminnfirnnc (b)(5)
I(b)(5)
I Crack was forl
- whil, maleinr nn
,nrrryitnax/
ft Y 9rý ft rrnrrata r-it f the Steam Generator Replacement project. (b)(5) t (b)(5)
Crack is a. out 1/2 inch wide and 10 inches in from outside edge of concrete -
running around the containment - located just at the layer of horizontal tendons. Licensee is assessing and evaluating implications (polar crane support, S/G lift device support, as well as operability of containment).
NOTE: Crystal River - License Renewal Application received by the NRC on December 18, 2008. Click on the link to view the status.
The licensee was contacted by the State of Florida DEP Coordinator and asked whether they were in an unusual event due to contaminated water leaking from a crack in containment. The licensee corrected the misinformation and MAY contact the local press to inform them of the RB crack issue to preclude any further misunderstandings.
Bob Betnardo Reactor Systems Engineer US Nuclear Regulatory Commission NRR/ADRO/DIRS/IOEB Mail Stop: O-7C02A 301-415-2621 Robert.Bernardo@nrc.gov 2