Event Notification Report for July 20, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/19/1999 - 07/20/1999
EVENT NUMBERS
35939359403594135937
Power Reactor
Event Number: 35939
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: PHILLIP SHORT
HQ OPS Officer: DOUG WEAVER
Region: 3 State: WI
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: PHILLIP SHORT
HQ OPS Officer: DOUG WEAVER
Notification Date: 07/20/1999
Notification Time: 14:44 [ET]
Event Date: 07/20/1999
Event Time: 13:09 [CDT]
Last Update Date: 07/20/1999
Notification Time: 14:44 [ET]
Event Date: 07/20/1999
Event Time: 13:09 [CDT]
Last Update Date: 07/20/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
Person (Organization):
PATRICK HILAND (R3)
PATRICK HILAND (R3)
| 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 |
OUTSIDE DESIGN BASES - CONDITION OUTSIDE OF APPENDIX R REQUIREMENTS
During an Appendix R baseline project review, a condition has been found that is considered to be outside the Appendix R Safe Shutdown design basis. During a postulated fire on the 26 foot level of the primary auxiliary building, fire related cable damage could lead to spurious opening of a single power operated relief valve (PORV) along with the inability to close its associated block valve. Presently, plant procedures direct operators to isolate air to the containment and vent the instrument air header locally in order to shut the PORV. The local valve operations that are required, however, are in the same area as the postulated fire. Failure to get the PORVs closed in adequate time would place the plant outside of the performance goals of 10CFR50, Appendix R, Paragraph III.L.
The licensee notified the NRC resident inspector.
During an Appendix R baseline project review, a condition has been found that is considered to be outside the Appendix R Safe Shutdown design basis. During a postulated fire on the 26 foot level of the primary auxiliary building, fire related cable damage could lead to spurious opening of a single power operated relief valve (PORV) along with the inability to close its associated block valve. Presently, plant procedures direct operators to isolate air to the containment and vent the instrument air header locally in order to shut the PORV. The local valve operations that are required, however, are in the same area as the postulated fire. Failure to get the PORVs closed in adequate time would place the plant outside of the performance goals of 10CFR50, Appendix R, Paragraph III.L.
The licensee notified the NRC resident inspector.
Power Reactor
Event Number: 35940
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: D.W. MCGAUGHEY
HQ OPS Officer: DOUG WEAVER
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: D.W. MCGAUGHEY
HQ OPS Officer: DOUG WEAVER
Notification Date: 07/20/1999
Notification Time: 16:50 [ET]
Event Date: 07/20/1999
Event Time: 15:05 [CDT]
Last Update Date: 07/20/1999
Notification Time: 16:50 [ET]
Event Date: 07/20/1999
Event Time: 15:05 [CDT]
Last Update Date: 07/20/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - EMERGENCY SIREN INOP
10 CFR Section:
50.72(b)(1)(v) - EMERGENCY SIREN INOP
Person (Organization):
ELMO COLLINS (R4)
ELMO COLLINS (R4)
| 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 |
EMERGENCY SIRENS
All Comanche Peak Emergency Warning Sirens are inoperable. The cause of the failure is unknown, but personnel are working to effect repairs. Hood and Somervell counties have been notified. The licensee notified the NRC Resident Inspector.
All Comanche Peak Emergency Warning Sirens are inoperable. The cause of the failure is unknown, but personnel are working to effect repairs. Hood and Somervell counties have been notified. The licensee notified the NRC Resident Inspector.
Fuel Cycle Facility
Event Number: 35941
Facility: PADUCAH GASEOUS DIFFUSION PLANT
Region: 3 State: KY
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: KEVIN BEASLEY
HQ OPS Officer: DICK JOLLIFFE
Region: 3 State: KY
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: KEVIN BEASLEY
HQ OPS Officer: DICK JOLLIFFE
Notification Date: 07/21/1999
Notification Time: 08:54 [ET]
Event Date: 07/20/1999
Event Time: 14:30 [CDT]
Last Update Date: 07/21/1999
Notification Time: 08:54 [ET]
Event Date: 07/20/1999
Event Time: 14:30 [CDT]
Last Update Date: 07/21/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
PATRICK HILAND (R3)
DON COOL (NMSS)
PATRICK HILAND (R3)
DON COOL (NMSS)
NRC BULLETIN 91-01, 24 HOUR REPORT -
At 1430 CDT on 07/20/99, the Plant Shift Superintendent was notified that during calibration of C-335 air plant moisture meter, air was added to C-335 Unit 3 Cell 7 without independently verifying that the enrichment was less than 1.0 weight percent U-235, in violation of NCSA GEN 10-01. Independent assay verification is required if the air moisture content exceeds 1300 ppm or if the moisture meter is inoperable. With the moisture meter out of service, dry air was added to C-335 Unit 3 Cell 7, which had an assay of 1.01 weight percent U-235. The cell was thought to be less than 1.0 weight percent U-235. However, a previously completed independent assay verification was not referenced. Moisture content was less than 1300 ppm prior to removing the meter from service. After placing the moisture meter back in service, it was determined that the dry air never exceeded 1300 ppm while the meter was out of service. During the period of time that the meter was out of service, the air equipment was operated in a steady state condition with no manipulations performed and no abnormal or unusual process conditions observed.
SAFETY SIGNIFICANCE OF EVENT:
Double contingency was not maintained since the independent verification of assay was not performed. Independent verification of assay is required to preclude exposure of an unsafe mass deposit with the enrichment greater than 1.0 weight percent U-235 to wet air. Removal of the moisture meter requires that the system not be pressured with air or independent verification of assay less than 1.0 weight percent U-235 prior to applying air. However, a criticality was not possible because the moisture content did not exceed 1300 ppm.
POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO OF HOW CRITICALITY COULD OCCUR):
In order for a criticality to be possible, a deposit of unsafe mass would have to be present. This deposit would then have to be exposed to sufficient air with a moisture content exceeding 1300 ppm to moderate the deposit.
CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):
Two controls on assay.
ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS LIMIT AND % WORST CASE CRITICAL MASS):
Enrichment of 1.01 weight percent U-235 as determined by Independent Assay Verification.
NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION OF THE FAILURES OR DEFICIENCIES:
Double contingency for this scenario is established by implementing two controls of assay.
The first leg of the double contingency is based on verification that the assay of the equipment that the air is being applied to is less than 1.0 weight percent U-235. It was believed the cell assay was less than 1.0 weight percent U-235. However, verification of assay was not performed. It was later determined that the cell assay exceeded 1.0 weight percent U-235. Therefore, the control was violated.
The second leg of double contingency is based on the independent verification that the assay of the equipment that the air is being applied to is less than 1.0 weight percent U-235. However, the Independent verification of assay was not performed. Therefore, this control was violated.
Since double contingency was based on two controls on assay, a loss of one or both controls would result in a loss of double contingency. In this instance, both controls were violated and double contingency was not maintained.
CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:
The moisture meter was returned to service following calibration.
This event is being categorized as a 24 hour event in accordance with Safely Analysis Report Table 6.9-1, Criteria A.4.a and NRC Bulletin 91-01, Supplement 1.
The NRC Senior Resident Inspector has been notified of this event.
PGDP Problem Report No. ATR-99-4250, PGDP Event Report No. PAD-1999-053. Responsible Division: Operations.
At 1430 CDT on 07/20/99, the Plant Shift Superintendent was notified that during calibration of C-335 air plant moisture meter, air was added to C-335 Unit 3 Cell 7 without independently verifying that the enrichment was less than 1.0 weight percent U-235, in violation of NCSA GEN 10-01. Independent assay verification is required if the air moisture content exceeds 1300 ppm or if the moisture meter is inoperable. With the moisture meter out of service, dry air was added to C-335 Unit 3 Cell 7, which had an assay of 1.01 weight percent U-235. The cell was thought to be less than 1.0 weight percent U-235. However, a previously completed independent assay verification was not referenced. Moisture content was less than 1300 ppm prior to removing the meter from service. After placing the moisture meter back in service, it was determined that the dry air never exceeded 1300 ppm while the meter was out of service. During the period of time that the meter was out of service, the air equipment was operated in a steady state condition with no manipulations performed and no abnormal or unusual process conditions observed.
SAFETY SIGNIFICANCE OF EVENT:
Double contingency was not maintained since the independent verification of assay was not performed. Independent verification of assay is required to preclude exposure of an unsafe mass deposit with the enrichment greater than 1.0 weight percent U-235 to wet air. Removal of the moisture meter requires that the system not be pressured with air or independent verification of assay less than 1.0 weight percent U-235 prior to applying air. However, a criticality was not possible because the moisture content did not exceed 1300 ppm.
POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO OF HOW CRITICALITY COULD OCCUR):
In order for a criticality to be possible, a deposit of unsafe mass would have to be present. This deposit would then have to be exposed to sufficient air with a moisture content exceeding 1300 ppm to moderate the deposit.
CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):
Two controls on assay.
ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS LIMIT AND % WORST CASE CRITICAL MASS):
Enrichment of 1.01 weight percent U-235 as determined by Independent Assay Verification.
NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION OF THE FAILURES OR DEFICIENCIES:
Double contingency for this scenario is established by implementing two controls of assay.
The first leg of the double contingency is based on verification that the assay of the equipment that the air is being applied to is less than 1.0 weight percent U-235. It was believed the cell assay was less than 1.0 weight percent U-235. However, verification of assay was not performed. It was later determined that the cell assay exceeded 1.0 weight percent U-235. Therefore, the control was violated.
The second leg of double contingency is based on the independent verification that the assay of the equipment that the air is being applied to is less than 1.0 weight percent U-235. However, the Independent verification of assay was not performed. Therefore, this control was violated.
Since double contingency was based on two controls on assay, a loss of one or both controls would result in a loss of double contingency. In this instance, both controls were violated and double contingency was not maintained.
CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:
The moisture meter was returned to service following calibration.
This event is being categorized as a 24 hour event in accordance with Safely Analysis Report Table 6.9-1, Criteria A.4.a and NRC Bulletin 91-01, Supplement 1.
The NRC Senior Resident Inspector has been notified of this event.
PGDP Problem Report No. ATR-99-4250, PGDP Event Report No. PAD-1999-053. Responsible Division: Operations.
Other Nuclear Material
Event Number: 35937
Rep Org: PROFESSIONAL SERVICE INDUSTRIES
Licensee: PROFESSIONAL SERVICE INDUSTRIES
Region: 3
City: LIMA State: OH
County:
License #:
Agreement: N
Docket:
NRC Notified By: CHRIS SMITH
HQ OPS Officer: BOB STRANSKY
Licensee: PROFESSIONAL SERVICE INDUSTRIES
Region: 3
City: LIMA State: OH
County:
License #:
Agreement: N
Docket:
NRC Notified By: CHRIS SMITH
HQ OPS Officer: BOB STRANSKY
Notification Date: 07/20/1999
Notification Time: 09:58 [ET]
Event Date: 07/20/1999
Event Time: 01:00 [EDT]
Last Update Date: 07/20/1999
Notification Time: 09:58 [ET]
Event Date: 07/20/1999
Event Time: 01:00 [EDT]
Last Update Date: 07/20/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
PATRICK HILAND (R3)
DON COOL (NMSS)
PATRICK HILAND (R3)
DON COOL (NMSS)
STOLEN TROXLER MOISTURE/DENSITY GAUGE
A Troxler Model 3430 Moisture/Density Gauge (S/N 27891) was stolen from the back of a pickup truck in Lima, Ohio. The licensee reported that both the gauge and its transport carrier were missing from the truck. The local police were contacted and responded to the scene.
A Troxler Model 3430 Moisture/Density Gauge (S/N 27891) was stolen from the back of a pickup truck in Lima, Ohio. The licensee reported that both the gauge and its transport carrier were missing from the truck. The local police were contacted and responded to the scene.