Event Notification Report for December 15, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/14/2014 - 12/15/2014
Part 21
Event Number: 50681
Rep Org: ASCO VALVE INCORPORATED
Licensee: STERIS ISOMEDIX SERVICES
Region: 1
City: AIKEN State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BOB ROYER
HQ OPS Officer: JOHN SHOEMAKER
Licensee: STERIS ISOMEDIX SERVICES
Region: 1
City: AIKEN State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BOB ROYER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/16/2014
Notification Time: 09:01 [ET]
Event Date: 12/15/2014
Event Time: 00:00 [EST]
Last Update Date: 08/19/2015
Notification Time: 09:01 [ET]
Event Date: 12/15/2014
Event Time: 00:00 [EST]
Last Update Date: 08/19/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
JOHN ROGGE (R1DO)
KATHLEEN O'DONOHUE (R2DO)
AARON MCCRAW (R3DO)
NEIL OKEEFE (R4DO)
PART 21 GROUP (EMAI)
JOHN ROGGE (R1DO)
KATHLEEN O'DONOHUE (R2DO)
AARON MCCRAW (R3DO)
NEIL OKEEFE (R4DO)
PART 21 GROUP (EMAI)
INTERIM REPORT - POTENTIAL PART 21 NOTIFICATION
The following report was received via fax:
ASCO reviewed a Part 21 notification, received from Steris Isomedix Services, to see if the reported non conformance would impact qualification levels. Based on this review, ASCO determined that even if the radiation levels, applied to components, were lower than reported on the original certifications, the additional radiation dose added to meet the 10% margin suggested by IEEE 323 would envelope this variation. Therefore, the qualification levels listed in ASCO qualification reports would not be impacted. Based on this review, ASCO determined that it was not necessary to implement 10 CFR part 21 notifications since the reported qualification levels remain unchanged.
If you have any questions, you can contact Michael Adase at Michael.adase@emerson.com or 803-641-9345.
Note: The NRC has received reports from four (4) other Steris Isomedix customers concerning this issue; EN #50253, #50285, #50359, and #50434.
* * * UPDATE AT 1507 EDT ON 8/19/2015 * * *
The following, in part, was received from Asco Valve, Inc. via fax:
"On December 15, 2014, ASCO Valve Inc. (ASCO) issued an interim report to the USNRC. The interim report was issued because ASCO was awaiting additional information from Steris and was not able to complete their evaluation of Ref B within the 60 day time limit. A December 19, 2014 update from Steris contained no additional substantive information. Although further information from Steris was not received, ASCO has since received the 'Industry Guidance Position Paper Responding to the 2014 Steris 10 CFPR Part 21', from the NUGEQ [Nuclear Utility Group on Equipment Qualification].
"ASCO has completed the review and calculated the minimum radiation exposure applied during qualification of ASCO nuclear qualified products at Steris. Based on this review, ASCO has determined that the minimum dose is less than what was originally reported in the ASCO qualification reports. ASCO is in the process of updating our reports and revising our certifications.
"Since ASCO is not able to determine what, if any impact these reduced radiation dose levels will have on the qualification testing of safety related equipment, we are forwarding this information to allow for a review of applicable qualification documentation and reports."
Notified R1DO (DeFrancisco), R2DO (Heisserer), R3DO (Riemer), R4DO (Hay), and Part 21 Group (email).
The following report was received via fax:
ASCO reviewed a Part 21 notification, received from Steris Isomedix Services, to see if the reported non conformance would impact qualification levels. Based on this review, ASCO determined that even if the radiation levels, applied to components, were lower than reported on the original certifications, the additional radiation dose added to meet the 10% margin suggested by IEEE 323 would envelope this variation. Therefore, the qualification levels listed in ASCO qualification reports would not be impacted. Based on this review, ASCO determined that it was not necessary to implement 10 CFR part 21 notifications since the reported qualification levels remain unchanged.
If you have any questions, you can contact Michael Adase at Michael.adase@emerson.com or 803-641-9345.
Note: The NRC has received reports from four (4) other Steris Isomedix customers concerning this issue; EN #50253, #50285, #50359, and #50434.
* * * UPDATE AT 1507 EDT ON 8/19/2015 * * *
The following, in part, was received from Asco Valve, Inc. via fax:
"On December 15, 2014, ASCO Valve Inc. (ASCO) issued an interim report to the USNRC. The interim report was issued because ASCO was awaiting additional information from Steris and was not able to complete their evaluation of Ref B within the 60 day time limit. A December 19, 2014 update from Steris contained no additional substantive information. Although further information from Steris was not received, ASCO has since received the 'Industry Guidance Position Paper Responding to the 2014 Steris 10 CFPR Part 21', from the NUGEQ [Nuclear Utility Group on Equipment Qualification].
"ASCO has completed the review and calculated the minimum radiation exposure applied during qualification of ASCO nuclear qualified products at Steris. Based on this review, ASCO has determined that the minimum dose is less than what was originally reported in the ASCO qualification reports. ASCO is in the process of updating our reports and revising our certifications.
"Since ASCO is not able to determine what, if any impact these reduced radiation dose levels will have on the qualification testing of safety related equipment, we are forwarding this information to allow for a review of applicable qualification documentation and reports."
Notified R1DO (DeFrancisco), R2DO (Heisserer), R3DO (Riemer), R4DO (Hay), and Part 21 Group (email).
Power Reactor
Event Number: 50678
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: JAMES COX
HQ OPS Officer: JOHN SHOEMAKER
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: JAMES COX
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/15/2014
Notification Time: 13:58 [ET]
Event Date: 12/15/2014
Event Time: 07:30 [CST]
Last Update Date: 12/15/2014
Notification Time: 13:58 [ET]
Event Date: 12/15/2014
Event Time: 07:30 [CST]
Last Update Date: 12/15/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
AARON MCCRAW (R3DO)
AARON MCCRAW (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
CONTROL ROOM EMERGENCY VENTILATION SYSTEM INOPERABLE
"On December 15, 2014, at 0730 hours [CST] the Control Room Emergency Ventilation (CREV) system was declared inoperable due to a partially stuck open main control room door. The door was unable to be closed to establish the boundary of the control room envelope. As a result, Technical Specification 3.7.4, Condition C, was entered. A repair plan and schedule is being developed.
"The CREV system maintains a habitable control room environment and ensures the operability of components in the control room emergency zone during accident conditions as well as protection of the operators from a high dose environment assumed during a design basis accident.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(D) because the CREV system is a single train system, and loss of the CREV system could impact the plant's ability to mitigate the consequences of an accident as stated in Chapter 6 of the UFSAR. This event is also reportable under 10 CFR 50.72(b)(3)(xiii) since this condition also impacts the control room as an Emergency Response Facility.
"At 0910 [CST] exited Tech Spec 3.7.4, Condition C, for CREV System Inoperable due to inoperable Control Room Envelope (CRE). The Control Room door is now closed. Completed post maintenance smoke test, satisfactory.
"The NRC Resident Inspector has been notified."
"On December 15, 2014, at 0730 hours [CST] the Control Room Emergency Ventilation (CREV) system was declared inoperable due to a partially stuck open main control room door. The door was unable to be closed to establish the boundary of the control room envelope. As a result, Technical Specification 3.7.4, Condition C, was entered. A repair plan and schedule is being developed.
"The CREV system maintains a habitable control room environment and ensures the operability of components in the control room emergency zone during accident conditions as well as protection of the operators from a high dose environment assumed during a design basis accident.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(D) because the CREV system is a single train system, and loss of the CREV system could impact the plant's ability to mitigate the consequences of an accident as stated in Chapter 6 of the UFSAR. This event is also reportable under 10 CFR 50.72(b)(3)(xiii) since this condition also impacts the control room as an Emergency Response Facility.
"At 0910 [CST] exited Tech Spec 3.7.4, Condition C, for CREV System Inoperable due to inoperable Control Room Envelope (CRE). The Control Room door is now closed. Completed post maintenance smoke test, satisfactory.
"The NRC Resident Inspector has been notified."
Agreement State
Event Number: 50683
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: COVANTA
Region: 1
City: NEWARK State: NJ
County:
License #: 506859
Agreement: Y
Docket:
NRC Notified By: CATHY BIEL
HQ OPS Officer: JOHN SHOEMAKER
Licensee: COVANTA
Region: 1
City: NEWARK State: NJ
County:
License #: 506859
Agreement: Y
Docket:
NRC Notified By: CATHY BIEL
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/16/2014
Notification Time: 15:36 [ET]
Event Date: 12/15/2014
Event Time: 15:00 [EST]
Last Update Date: 12/16/2014
Notification Time: 15:36 [ET]
Event Date: 12/15/2014
Event Time: 15:00 [EST]
Last Update Date: 12/16/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHN ROGGE (R1DO)
NMSS EVENTS NOTIFICA (EMAI)
JOHN ROGGE (R1DO)
NMSS EVENTS NOTIFICA (EMAI)
AGREEMENT STATE REPORT - DAMAGED GAUGE
The following report was received from the State of New Jersey via fax:
"Event Description: [The licensee] is a trash-to-steam facility and uses generally and specifically - licensed fixed gauges as level indicators. One of their registered, generally licensed gauges was found to be damaged during the 6-month shutter check. The damage appears to be a result of impact and the plunger needed to close the shutter is inoperable. The gauge is a Berthold Model LB 7440 L, S/N 838-3-90, containing 50 mCi of Cs-137. The gauge is in a fairly inaccessible area of the plant, and personnel do not work in the area. No overexposures are thought to have occurred at this time. An investigation is being performed and a 30-day report will be provided."
The following report was received from the State of New Jersey via fax:
"Event Description: [The licensee] is a trash-to-steam facility and uses generally and specifically - licensed fixed gauges as level indicators. One of their registered, generally licensed gauges was found to be damaged during the 6-month shutter check. The damage appears to be a result of impact and the plunger needed to close the shutter is inoperable. The gauge is a Berthold Model LB 7440 L, S/N 838-3-90, containing 50 mCi of Cs-137. The gauge is in a fairly inaccessible area of the plant, and personnel do not work in the area. No overexposures are thought to have occurred at this time. An investigation is being performed and a 30-day report will be provided."