Event Notification Report for August 07, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/06/2001 - 08/07/2001
EVENT NUMBERS
38193381893819038204
General Information or Other
Event Number: 38193
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: GREEN BAY PACKAGING
Region: 4
City: MORRILTON State: AR
County:
License #: ARK197BP01-98
Agreement: Y
Docket:
NRC Notified By: JARED THOMPSON (fax)
HQ OPS Officer: LEIGH TROCINE
Licensee: GREEN BAY PACKAGING
Region: 4
City: MORRILTON State: AR
County:
License #: ARK197BP01-98
Agreement: Y
Docket:
NRC Notified By: JARED THOMPSON (fax)
HQ OPS Officer: LEIGH TROCINE
Notification Date: 08/09/2001
Notification Time: 14:22 [ET]
Event Date: 08/07/2001
Event Time: 00:00 [CDT]
Last Update Date: 08/09/2001
Notification Time: 14:22 [ET]
Event Date: 08/07/2001
Event Time: 00:00 [CDT]
Last Update Date: 08/09/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
CHARLES MARSCHALL (R4)
FRED BROWN (NMSS)
CHARLES MARSCHALL (R4)
FRED BROWN (NMSS)
AGREEMENT STATE REPORT REGARDING A DAMAGED NDC GAUGE CONTAINING AMERICIUM-241 AT
GREEN BAY PACKAGING IN MORRILTON, ARKANSAS
The following text is a portion of a facsimile received from the Arkansas Department of Health:
"The Department received notified on August 8, 2001, that a gauge containing radioactive material was damaged during maintenance operations at Green Bay Packaging in Morrilton, Arkansas. The gauge is licensed under Arkansas Radioactive Material License Number ARK-197-BP-01-98."
"The incident occurred on August 7, 2001, when the gauge became caught in the conveyor wire and was pulled away from the mounting bracket, falling and striking a roller. The impact tore the shutter from the gauge. The gauge was retrieved without exposure to personnel. Temporary shielding was added to the gauge, and the gauge was placed in storage by the Radiation Safety Officer."
"It was determined that the source was intact, and a leak test was performed. The gauge is to be returned to the manufacturer."
"The gauge is [an] NDC Model Number 104F, Serial Number 12605, containing 0.93 gBq (21 mCi) of Americium-241."
"The Department is conducting an investigation of the incident."
(Call the NRC operations officer for contact information.)
GREEN BAY PACKAGING IN MORRILTON, ARKANSAS
The following text is a portion of a facsimile received from the Arkansas Department of Health:
"The Department received notified on August 8, 2001, that a gauge containing radioactive material was damaged during maintenance operations at Green Bay Packaging in Morrilton, Arkansas. The gauge is licensed under Arkansas Radioactive Material License Number ARK-197-BP-01-98."
"The incident occurred on August 7, 2001, when the gauge became caught in the conveyor wire and was pulled away from the mounting bracket, falling and striking a roller. The impact tore the shutter from the gauge. The gauge was retrieved without exposure to personnel. Temporary shielding was added to the gauge, and the gauge was placed in storage by the Radiation Safety Officer."
"It was determined that the source was intact, and a leak test was performed. The gauge is to be returned to the manufacturer."
"The gauge is [an] NDC Model Number 104F, Serial Number 12605, containing 0.93 gBq (21 mCi) of Americium-241."
"The Department is conducting an investigation of the incident."
(Call the NRC operations officer for contact information.)
Power Reactor
Event Number: 38189
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: BRIAN BLANCHE
HQ OPS Officer: STEVE SANDIN
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: BRIAN BLANCHE
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/07/2001
Notification Time: 23:11 [ET]
Event Date: 08/07/2001
Event Time: 20:15 [CDT]
Last Update Date: 08/08/2001
Notification Time: 23:11 [ET]
Event Date: 08/07/2001
Event Time: 20:15 [CDT]
Last Update Date: 08/08/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
CHARLES MARSCHALL (R4)
CHARLES MARSCHALL (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
UNIT 1 EXPERIENCED AN AUTOMATIC REACTOR SCRAM FOR REASONS UNKNOWN
"At 2015, Grand Gulf Unit 1 had an automatic RPS actuation. This is a 4-hour notification per 10 CFR 50.72 (b)(2)(iv)(B). All systems performed as expected, except that Feedwater/Condensate were not available due to hotwell level problems. RCIC was manually started for level control. At the time of the scram, a local generating station was experiencing switchyard problems (Baxter Wilson Electric Station). Also at the time, significant lightning strikes were noticed in the area. Scram initiation event analysis is in progress."
All rods fully inserted. The licensee is in the process of restoring the condensate system. Offsite power is stable and available. All safety equipment is available. The main condenser is available for decay heat removal.
The licensee informed the NRC resident inspector.
* * * UPDATE 1756EDT ON 8/8/01 FROM WALTER CADE TO S. SANDIN * * *
"This is supplemental to event number 38189 reported on 8/7/01.
" During Post Trip analysis of Reactor Scram, it was determined that the EOC-RPT circuits required by GGNS Technical Specifications did not function as expected. There were no consequences to the failure as a non-tech spec vendor supplied load reject circuit operated properly. This is being reported per 10 CFR 50.72 (b)(3)(v)(A). Details will be available in the LER to follow. This circuit [is] not required below 40% Reactor Power."
The unit is currently in mode 3 making preparations for restart. Corrective actions will be determined following completion of a fuels analysis. This issue and a possible TS change request has been discussed with NRR. The licensee informed the NRC resident inspector. Notified R4DO(Marschall).
"At 2015, Grand Gulf Unit 1 had an automatic RPS actuation. This is a 4-hour notification per 10 CFR 50.72 (b)(2)(iv)(B). All systems performed as expected, except that Feedwater/Condensate were not available due to hotwell level problems. RCIC was manually started for level control. At the time of the scram, a local generating station was experiencing switchyard problems (Baxter Wilson Electric Station). Also at the time, significant lightning strikes were noticed in the area. Scram initiation event analysis is in progress."
All rods fully inserted. The licensee is in the process of restoring the condensate system. Offsite power is stable and available. All safety equipment is available. The main condenser is available for decay heat removal.
The licensee informed the NRC resident inspector.
* * * UPDATE 1756EDT ON 8/8/01 FROM WALTER CADE TO S. SANDIN * * *
"This is supplemental to event number 38189 reported on 8/7/01.
" During Post Trip analysis of Reactor Scram, it was determined that the EOC-RPT circuits required by GGNS Technical Specifications did not function as expected. There were no consequences to the failure as a non-tech spec vendor supplied load reject circuit operated properly. This is being reported per 10 CFR 50.72 (b)(3)(v)(A). Details will be available in the LER to follow. This circuit [is] not required below 40% Reactor Power."
The unit is currently in mode 3 making preparations for restart. Corrective actions will be determined following completion of a fuels analysis. This issue and a possible TS change request has been discussed with NRR. The licensee informed the NRC resident inspector. Notified R4DO(Marschall).
Power Reactor
Event Number: 38190
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ROBINSON
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ROBINSON
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 08/08/2001
Notification Time: 11:37 [ET]
Event Date: 08/07/2001
Event Time: 18:10 [EDT]
Last Update Date: 08/08/2001
Notification Time: 11:37 [ET]
Event Date: 08/07/2001
Event Time: 18:10 [EDT]
Last Update Date: 08/08/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DANIEL HOLODY (R1)
DANIEL HOLODY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 99 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 99 | Power Operation |
POTENTIAL OPERATION OUTSIDE OF LICENSE LIMITS
On 8/7/2001, with Unit 1 and Unit 2 operating in Mode 1 at 100% power, during a review of the Core Thermal Power calculation, Engineering discovered that a constant for the Moisture Fraction input into the calculation was non-conservative. Due to the identified non-conservatism in the constant, actual core thermal power could have been as much as 6 MWth higher than indicated (~0.2% of Rated Thermal Power). This condition resulted in both Units having potentially operated above their Maximum Power Level License Limits (Reference NPF-14, 2.C(1) and NPF-22, 2.C(1)).
Both Units have been administratively de-rated 7 MWth until this issue is resolved.
There is a potential that this condition has existed since the startup of both Units.
This event meets the License Conditions requiring a 24 Hour report in accordance with 10CFR50.72.
The NRC Resident Inspector was notified.
On 8/7/2001, with Unit 1 and Unit 2 operating in Mode 1 at 100% power, during a review of the Core Thermal Power calculation, Engineering discovered that a constant for the Moisture Fraction input into the calculation was non-conservative. Due to the identified non-conservatism in the constant, actual core thermal power could have been as much as 6 MWth higher than indicated (~0.2% of Rated Thermal Power). This condition resulted in both Units having potentially operated above their Maximum Power Level License Limits (Reference NPF-14, 2.C(1) and NPF-22, 2.C(1)).
Both Units have been administratively de-rated 7 MWth until this issue is resolved.
There is a potential that this condition has existed since the startup of both Units.
This event meets the License Conditions requiring a 24 Hour report in accordance with 10CFR50.72.
The NRC Resident Inspector was notified.
General Information or Other
Event Number: 38204
Rep Org: SCIENTECH, INC.
Licensee: NUS INSTRUMENTS, INC.
Region: 1
City: GAITHERSBURG State: MD
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MARTIN BOOSKA
HQ OPS Officer: JOHN MacKINNON
Licensee: NUS INSTRUMENTS, INC.
Region: 1
City: GAITHERSBURG State: MD
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MARTIN BOOSKA
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/13/2001
Notification Time: 17:14 [ET]
Event Date: 08/07/2001
Event Time: 00:00 [EDT]
Last Update Date: 08/13/2001
Notification Time: 17:14 [ET]
Event Date: 08/07/2001
Event Time: 00:00 [EDT]
Last Update Date: 08/13/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
RONALD BELLAMY (R1)
VERN HODGE, FAX (NRR)
RONALD BELLAMY (R1)
VERN HODGE, FAX (NRR)
POTENTIAL DEFECT
SCIENTECH, Inc.'s subsidiary NUS Instruments, Inc. (NUSI) has determined that a Basic Component, supplied to Rochester Gas and Electric Ginna Station Nuclear Plant under RG&E purchase order 5000002014, contains a potential defect that is reportable under 10CFR21. NUSI determined that the potential defect was reportable under the provisions of 10CFR21 on August 07, 2001. SCIENTECH, Inc. President was informed August 13, 2001. RG&E is aware of this problem and the affected component is being modified to restore this item to an acceptable status by August 17.
A formal written report will be provided within 30 days of this notification. The component, delta T Time Domain Module, M/N: TMD500-08/08/08/08-08-08-1/2, P/N: MBA-E063PA-1, Rev. 0 (1ea.), S/N:9800771, was originally manufactured as P/N: MBA-E062PA-1 (voltage output) by NUSI. NUSI performed a conversion of this item to P/N: MBA-E063PA-1 (current output) resulting in a defect. A total of six items were converted under this purchase order for use in Safety Related Systems. NUSI has opened a 10CFR21 file concerning this component and has numbered it as 21-01-01.
SCIENTECH, Inc.'s subsidiary NUS Instruments, Inc. (NUSI) has determined that a Basic Component, supplied to Rochester Gas and Electric Ginna Station Nuclear Plant under RG&E purchase order 5000002014, contains a potential defect that is reportable under 10CFR21. NUSI determined that the potential defect was reportable under the provisions of 10CFR21 on August 07, 2001. SCIENTECH, Inc. President was informed August 13, 2001. RG&E is aware of this problem and the affected component is being modified to restore this item to an acceptable status by August 17.
A formal written report will be provided within 30 days of this notification. The component, delta T Time Domain Module, M/N: TMD500-08/08/08/08-08-08-1/2, P/N: MBA-E063PA-1, Rev. 0 (1ea.), S/N:9800771, was originally manufactured as P/N: MBA-E062PA-1 (voltage output) by NUSI. NUSI performed a conversion of this item to P/N: MBA-E063PA-1 (current output) resulting in a defect. A total of six items were converted under this purchase order for use in Safety Related Systems. NUSI has opened a 10CFR21 file concerning this component and has numbered it as 21-01-01.