Event Notification Report for September 30, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/27/2002 - 09/30/2002
** EVENT NUMBERS **
39009 39202 39213 39217 39219 39220 39221 39222 39223 39224 39225 39226 39227 39228 39229 39230
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 39009 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: BUREAU OF INDIAN AFFAIRS |NOTIFICATION DATE: 06/22/2002|
|LICENSEE: BUREAU OF INDIAN AFFAIRS |NOTIFICATION TIME: 13:00[EDT]|
| CITY: FAIRFAX REGION: 4 |EVENT DATE: 06/21/2002|
| COUNTY: OSAGE STATE: OK |EVENT TIME: 09:00[CDT]|
|LICENSE#: 35-15239-02 AGREEMENT: Y |LAST UPDATE DATE: 09/27/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES MARSCHALL R4 |
| |JOHN GREEVES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BOB FAVORS | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STOLEN TROXLER MOISTURE DENSITY GAUGE |
| |
| On 9:00 a.m. CDT on 6/22/02, the licensee discovered that their storage shed |
| had been broken into and a Troxler moisture density gauge was stolen. The |
| model number is 3440, which contains 8 millicuries of CS-137 and 40 |
| millicuries of Am-Be 241, and serial numbers 18746 and 18745. The licensee |
| contacted the local police, Fairfax City Police and Osage County Sheriffs |
| office. The storage shed is located 2 miles east of Highway 20 and Highway |
| 18 in Osage County, Oklahoma. |
| |
| |
| * * * UPDATE ON 9/27/02 @ 1528 BY FAVORS TO GOULD * * * |
| |
| The licensee has recovered the Troxler gauge. It was returned to them |
| undamaged with the source lock intact by the Fairfax, Ok. Police Dept. on |
| 9/25/02. |
| |
| HOO notified MNSS EO(Brown) and REG 4 RDO(Pellet) |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39202 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 09/20/2002|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 04:12[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/20/2002|
+------------------------------------------------+EVENT TIME: 01:12[EDT]|
| NRC NOTIFIED BY: TIM JOHNSON |LAST UPDATE DATE: 09/27/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PAUL FREDRICKSON R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INADVERTENT ACTUATION OF BLACKOUT SIGNAL ON UNIT 1 DURING SURVEILLANCE |
| TESTING |
| |
| "Inadvertent Actuation of B Train Blackout Signal on Unit 1. Actuation |
| occurred during testing of the 1B Diesel Generator sequence panel. The |
| actuation caused the B Train Nuclear Service Water System to realign to the |
| standby Nuclear Service Water Pond on both Unit 1 and Unit 2. Unit 2 was not |
| affected due to the realignment. The Unit 1 Boric Acid pump transfer pump |
| automatically secured and various containment and Auxiliary Building |
| Ventilation components were affected due to the actuation. The procedure |
| used for testing the sequencer simulated an undervoltage signal on the B |
| Train Emergency Bus. Plans are being evaluated to restore the sequencer from |
| the test alignment and realign all affected equipment." |
| |
| Neither reactor residual heat removal cooling or spent fuel pool cooling |
| were affected by this event. Electrical buses remained energized and no EDG |
| autostart occurred since the blackout signal was simulated and not based on |
| an actual undervoltage condition. The licensee is attributing the cause |
| preliminarily to an inadequate procedure. |
| |
| The licensee will notify the NRC Resident Inspector. |
| |
| |
| * * * UPDATE ON 9/27/02 @ 1437 BY JOHNSON TO GOULD * * * RETRACTION |
| |
| Further evaluation determined that the blackout signal which automatically |
| aligned RN to the SNSWP was not in response to actual plant conditions or |
| parameters satisfying the requirements for initiation of a blackout signal |
| or the SNSWP safety function. Since alignment of RN to the SNSWP was not in |
| response to a valid signal, this represented an invalid actuation which is |
| not reportable per 10 CER 50.72(b) (3) (iv) (A). In addition, 10 CFR |
| 50.72(b) (3) (iv) (B) does not identify the ultimate heat sink portion of RN |
| systems as a system applicable to 10 CFR 50.72(b) (3) (iv) (A). Therefore, |
| McGuire is retracting Event Report 39202. |
| |
| Note: McGuire will report this event in accordance with the requirements of |
| 10 CFR 50.73. (see event # 39223) |
| |
| The licensee will notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39213 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: OR DEPT OF HEALTH RAD PROTECTION |NOTIFICATION DATE: 09/24/2002|
|LICENSEE: GEOPACIFIC TESTING |NOTIFICATION TIME: 11:43[EDT]|
| CITY: REGION: 4 |EVENT DATE: 09/23/2002|
| COUNTY: STATE: OR |EVENT TIME: [PDT]|
|LICENSE#: ORE-90987 AGREEMENT: Y |LAST UPDATE DATE: 09/24/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN PELLET R4 |
| |DOUG BROADDUS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TERRY LINDSEY | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MOISTURE DENSITY GAUGE LOST DURING TRANSPORT |
| |
| A Troxler gauge, model # 3440, serial # 19495 was lost while being |
| transported from Beverton, OR to North Portland, OR. The gauge is an 8 |
| millicurie Cs-137, 40 millicurie Am-Be 241 source and is licensed to |
| GeoPacific Testing Inc, Tigard, OR 97224. The licensee discovered the lost |
| gauge on 9/23/02 at approximately 1700 PDT and notified the State of Oregon |
| on 9/23/02 at 1858 PDT. The gauge was lost north of Highway 26 between the |
| intersection of Emily Lane and Northwest Bethany Blvd and Northwest |
| Germantown Rd. A search is being conducted to recover the lost gauge. A |
| press release is planned. The Oregon State Police, Oregon Emergency Response |
| System, Washington County Sheriff, Beaverton Police and the Portland Police |
| have been notified. The State of Oregon also intends to notify NRC Region |
| 4. |
| |
| * * * UPDATE ON 9/24/02 AT 2138 EDT FROM TERRY LINDSEY TO GERRY WAIG * * * |
| |
| The Troxler moisture density gauge lost during transit was discovered by a |
| passing volunteer fireman from Scapoose, OR. The fireman happened by the |
| gauge, picked up the gauge and case, and secured it at the fire house. The |
| gauge was found on 185th Ave., along the original route traveled when lost, |
| approximately 15 minutes after it was lost. The gauge was reported found |
| after news of the missing gauge was aired today on local media. The gauge is |
| currently being stored by the Scapoose Fire Dept. and will be returned to |
| GeoPacific Testing tomorrow. |
| |
| Notified R4DO (John Pellet) and NMSS (John Greeves) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39217 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 09/26/2002|
|LICENSEE: CONSTRUCTION TESTING AND ENGINEERING,|NOTIFICATION TIME: 00:26[EDT]|
| CITY: REGION: 4 |EVENT DATE: 09/24/2002|
| COUNTY: STATE: CA |EVENT TIME: 07:30[PDT]|
|LICENSE#: CA 5309-37 AGREEMENT: Y |LAST UPDATE DATE: 09/26/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN PELLET R4 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: | |
| HQ OPS OFFICER: | |
+------------------------------------------------+ |
|EMERGENCY CLASS: | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STOLEN AND RECOVERED MOISTURE DENSITY GAUGE |
| |
| "The facility [Construction Testing and Engineering, Inc.] reported a stolen |
| gauge this morning and within an hour called back to report that the gauge |
| had been recovered [by police]. |
| |
| "The gauge had been picked up from the storage location around 4:30 AM that |
| morning and was transported by the user to his home. The gauge remained |
| locked by chain in the vehicle. When the user returned to his vehicle |
| between 7:30 - 8 AM he discovered the chain had been cut and the case with |
| the gauge was missing. He contacted the police and the Alternate Radiation |
| Safety Officer for his region." |
| |
| CA Rad Health Branch will follow-up with the licensee to obtain the make, |
| model, and serial number of the stolen/recovered gauge and will forward that |
| information to the Headquarters Operations Officer. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 39219 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ARCTIC PIPE INPSECTIONS |NOTIFICATION DATE: 09/26/2002|
|LICENSEE: ARCTIC PIPE INSPECTIONS |NOTIFICATION TIME: 17:06[EDT]|
| CITY: HOUSTON REGION: 4 |EVENT DATE: 09/26/2002|
| COUNTY: STATE: TX |EVENT TIME: 09:00[CDT]|
|LICENSE#: 50-17314-02 AGREEMENT: Y |LAST UPDATE DATE: 09/27/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN PELLET R4 |
| |JOHN GREEVES NMSS |
+------------------------------------------------+ANIELLO DELLA GRECA R1 |
| NRC NOTIFIED BY: JIM HILDEBRENDT |RICHARD WESSMAN IRO |
| HQ OPS OFFICER: MIKE NORRIS |JOHN DAVIDSON NSIR |
+------------------------------------------------+DWIGHT CHAMBERLAND R4 |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST I-192 RADIOGRAPHY SOURCE DURING SHIPMENT |
| |
| A 20.3 Curie Ir-192 radiography camera SN# 94 was being shipped from Kenin, |
| AK to AEA Technologies in Burlington, MA by Federal Express. The shipment |
| arrived in Newark, NJ on 9/21/02 at 0257 and was scanned to leave on 9/24/02 |
| at 0022 EDT. The Licensee reported that the camera has not arrived in MA, |
| and that Federal Express could not account for the source's location. The |
| source was being shipped in it's shipping container and the Licensee |
| believed that it had a combination lock on it. |
| |
| ***UPDATE CHUCK CAIN TO MIKE NORRIS 1800 9/27/02*** |
| |
| The missing Arctic Pipe source changer has been found at the FedEx Newark |
| terminal. The shipping container was not damaged, but had it's paperwork |
| missing. Notified R4DO (Pellet), R1DO (Della Greca), DIRO (Wessman), NSIR |
| IAT (Davidson) and OHS (Brahm). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39220 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 09/27/2002|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 09:11[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/27/2002|
+------------------------------------------------+EVENT TIME: 08:50[EDT]|
| NRC NOTIFIED BY: RICK O'REARS |LAST UPDATE DATE: 09/28/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |WALTER RODGERS R2 |
|10 CFR SECTION: |MICHAEL JOHNSON NRR |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |RICHARD WESSMAN IRO |
| |DAN SULLIVAN FEMA |
| |DAVE ANDERSON OHS |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NOUE DECLARED DUE TO LOSS OF OFFSITE POWER SUPPLY |
| |
| The licensee declared a notice of unusual event (NOUE),in accordance with |
| EAL 3.1, due to the loss of two offsite electrical power supplies to the |
| station for greater than 15 minutes. The cause of the loss of offsite power |
| was a fire at a local hydro electric station. All systems functioned as |
| required. All emergency diesels responded and supplied electrical power to |
| the station shutdown electrical boards. The loss of two offsite power |
| supplies places the station in a technical specification (TS 3.8.1 D) |
| limiting condition for operation (LCO). |
| |
| The licensee notified the NRC Resident Inspector, the State of Tennessee, |
| and the local fire department. |
| |
| At 0955 NRC entered Monitoring for Normal Phase Mode. |
| |
| * * * UPDATE ON 09/28/02 AT 0311 FROM RICKY STOCKTON TO GERRY WAIG * * * |
| |
| The licensee terminated the NOUE at 0308 after the second offsite electrical |
| power supply was restored to the site at 0300 and exited technical |
| specifications 3.8.1 limiting conditions for operation. The first offsite |
| power supply was restored at 0125. |
| |
| At 0311 NRC exited monitoring for the Unusual Event |
| |
| Notified IRO (Wessman), R2DO (W. Rogers ), PAO (R. Virgilio ), NRR EO (M. |
| Johnson), FEMA (K.C.), OHA Ron Brahm |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39221 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 09/27/2002|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 11:01[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/27/2002|
+------------------------------------------------+EVENT TIME: 10:40[EDT]|
| NRC NOTIFIED BY: PAUL PACE |LAST UPDATE DATE: 09/27/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WALTER RODGERS R2 |
|10 CFR SECTION: |MICHAEL JOHNSON NRR |
|ADEV 50.72(b)(1) DEVIATION FROM T SPEC |RICHARD WESSMAN IRO |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DEVIATION FROM TECHNICAL SPECIFICATIONS PER 10 CFR 50.54(x) |
| |
| The licensee reported a deviation from license condition 2 F, which requires |
| compliance with the Watts Bar Fire Protection Report, part 2, section 9.1, |
| per 10 CFR 50.54(x). This section requires the minimum fire brigade staffing |
| to be restored within two hours. The Watts Bar fire brigade was dispatched |
| to a fire at the nearby Watts Bar Hydro Generation Station (see NRC Event |
| Number 39220) and replacement fire brigade members had not yet arrived |
| on-site. The licensee stated that the fire brigade can respond to a fire at |
| Watts Bar Nuclear but response time would be greater than normal. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 39222 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GLOBAL NUCLEAR FUEL - AMERICAS |NOTIFICATION DATE: 09/27/2002|
| RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 11:04[EDT]|
| COMMENTS: LEU CONVERSION (UF6 TO UO2) |EVENT DATE: 09/27/2002|
| LEU FABRICATION |EVENT TIME: 07:30[EDT]|
| LWR COMMERICAL FUEL |LAST UPDATE DATE: 09/27/2002|
| CITY: WILMINGTON REGION: 2 +-----------------------------+
| COUNTY: NEW HANOVER STATE: NC |PERSON ORGANIZATION |
|LICENSE#: SNM-1097 AGREEMENT: Y |WALTER RODGERS R2 |
| DOCKET: 07001113 |TOM ESSIG NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: PAULSON | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FOUR HOUR 91-01 BULLETIN RESPONSE |
| |
| At approximately 7:30 a.m. on September 27, 2002, a UO2 furnace operator |
| reported an overload alarm condition at the Line 1 UO2 sintering furnace. |
| Subsequent visual inspection of the furnace indicated a pellet boat "jam" |
| had occurred inside the sintering furnace chamber. An estimated 4-5 boats |
| are involved in the localized area in which the jam occurred. The stacking |
| of the boats inside the furnace constitutes a loss of geometry control. |
| |
| The independent control on moderation remained intact, thus no unsafe |
| condition existed, or currently exists. The UO2 sintering furnace |
| temperature is in excess of 1700 degrees C. |
| |
| Following procedure, operations promptly notified nuclear safety. Safe |
| recovery of the material and re-establishment of the geometry control will |
| require a 2 week cool down. This condition is reported pursuant to NRC |
| bulletin 91-01 (within 4 hours) due to a loss of geometry that requires in |
| excess of 4 hours to re-establish. Implementation of corrective actions is |
| pending completion of incident investigation, |
| |
| SAFETY SIGNIFICANCE OF EVENTS: |
| Low safety significance - localized loss of safe slab geometry, moderation |
| control remained intact. |
| |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW |
| CRITICALITY COULD OCCUR): |
| Multiple failure modes required before a criticality accident could occur. |
| |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): |
| Geometry and moderation. |
| |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST BASE CRITICAL MASS): |
| |
| Estimated 4-5 pellet boats involved in actual jam represent [ . . .] kgs |
| UO2 in the form of dry fuel pellets, enriched to [ . . . ] |
| |
| wt% U235. Under a loss of geometry, our analyses have demonstrated a fully |
| reflected hemisphere mass of UO2 pellets at [ . . . ] enrichment containing |
| 5% water is ~[. . . ]kgs. Thus, a large safety margin exists for this loss |
| of geometry Condition. |
| |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: |
| The geometry control provided by safe slab height of 3 was lost because of |
| jam inside UO2 sintering furnace. |
| |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: |
| Controlled shutdown of sintering furnace (requires 2 weeks to cool down), |
| recovery of material into favorable geometry containers under NSE approved |
| procedure. |
| |
| |
| Investigation of event and evaluation of additional corrective actions |
| pending. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39223 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 09/27/2002|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 14:37[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/20/2002|
+------------------------------------------------+EVENT TIME: 01:12[EDT]|
| NRC NOTIFIED BY: JOHNSON |LAST UPDATE DATE: 09/27/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WALTER RODGERS R2 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INADVERTENT ALIGNMENT OF THE NUCLEAR SERVICE WATER TO STANDBY NUCLEAR |
| SERVICE WATER POND |
| |
| On September 20, 2002, McGuire Nuclear Station experienced an inadvertent |
| alignment of the Nuclear Service Water (EN) system to the Standby Nuclear |
| Service Water Pond (SNSWP). This event occurred when a Unit 1 "B" Train |
| blackout signal was inadvertently generated during surveillance testing of |
| the 13 Diesel Generator sequencer panel. |
| |
| Further evaluation determined that the blackout signal which automatically |
| aligned RN to the SNSWP was not in response to actual plant conditions or |
| parameters satisfying the requirements for initiation of a blackout signal |
| or the SNSWP safety function. Since alignment of RN to the SNSWP was not in |
| response to a valid signal, this represented an invalid actuation reportable |
| per the requirements of 10 CFR 50.73(a)(2)(iv)(A). However, as per 10 CFR |
| 50.73(a) (1), McGuire is providing a telephone notification of this invalid |
| actuation instead of submitting a written LER. |
| |
| The following additional information is being provided as part of the |
| telephone notification of this event: |
| |
| "B" Train of RN actuated to align Unit 1 and Unit 2 RN to the SNSWP. |
| |
| "B" Train actuation of Unit 1 and 2 RN to the SNSWP functioned successfully |
| and was complete. |
| |
| The NRC Resident Inspector will be notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39224 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 09/27/2002|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 15:58[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/27/2002|
+------------------------------------------------+EVENT TIME: 08:24[EDT]|
| NRC NOTIFIED BY: PAUL PACE |LAST UPDATE DATE: 09/27/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WALTER RODGERS R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VALID ENGINEERED SAFETY FUNCTION ACTUATION DUE TO PARTIAL LOSS OF OFF SITE |
| POWER |
| |
| "While operating at 100% power on September 27, 2002, Watts Bar experienced |
| a loss of one off-site power source, followed about 15 minutes later by the |
| loss of the second off-site power source. These two off-site power sources |
| are fed from the Watts Bar Hydro plant, and are the primary power source for |
| the 6900 V shutdown boards, via Common Station Service Transformers (CSST's) |
| C & D. CSST C feeds shutdown bds[boards] 1A-A & 2A-A, CSST D feeds shutdown |
| bds 1B-B & 2B-B. A fire at the hydo plant was the cause of the off-site |
| power supply breakers opening. The breaker for the supply to the CSST C |
| opened at 0824 (EDT). This deenergized shutdown bds 1A-A & 2A-A, initiating |
| a valid engineered safety function (ESF) actuation that started all four |
| standby diesel generators (DG's), two of which reenergized these shutdown |
| bds. When the other off-site source was lost, the remaining 2 DG's then |
| loaded onto their respective shutdown bds. The plant remain at full power |
| since one train of shutdown power was always available. As designed, AFW |
| started coincident with the EDG start. At this time, the 2 lines have been |
| reenergized and the A, B, C and D Common Station Service Transformers are |
| also energized. Preparations are being made to re-power nonsafety related |
| loads from off-site power." |
| |
| The Licensee has notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39225 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 09/27/2002|
| UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 17:00[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 09/16/2002|
+------------------------------------------------+EVENT TIME: 16:15[EDT]|
| NRC NOTIFIED BY: BEACH |LAST UPDATE DATE: 09/27/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANIELLO DELLA GRECA R1 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INVALID PRIMARY CONTAINMENT ISOLATION OF GROUP 2 AND 3 OUTBOARD VALVES |
| |
| |
| This 60-day optional report, as allowed by 10 CFR 50.73(a)(1), is being made |
| under the reporting requirement in |
| 10CFR50.73(a)(2)(iv)(A) to describe an unplanned, invalid actuation of a |
| specified system, specifically Primary |
| Containment Isolation Valve (PCIV) Group 2 and 3 outboard valves. |
| |
| On September 16, 2002, an over-voltage on the power supply to "B" Reactor |
| Protection System (RPS) bus resulted |
| in a loss of power to the bus. The loss of power resulted in an invalid |
| isolation of the outboard Secondary Containment Isolation Valves (SCIV) and |
| outboard Group 2 and 3 PCIVs. Additionally, "B" Standby Gas Treatment (SGT) |
| started due to an invalid auto initiation signal and RPS received an invalid |
| half scram signal. |
| |
| The affected systems responded as expected for the given conditions and were |
| subsequently returned to a normal configuration when power was restored to |
| the B RPS bus. No deficiencies or abnormalities were noted during the |
| event. |
| |
| This event has been entered into the site-specific corrective action program |
| for resolution. |
| |
| The NRC resident has been informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39226 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 09/27/2002|
| UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 18:52[EDT]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 09/27/2002|
+------------------------------------------------+EVENT TIME: 15:00[MST]|
| NRC NOTIFIED BY: STROUD |LAST UPDATE DATE: 09/27/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN PELLET R4 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 99 Power Operation |99 Power Operation |
|2 N Y 99 Power Operation |99 Power Operation |
|3 N Y 99 Power Operation |99 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFF-SITE NOTIFICATION |
| |
| On September 27, 2002 at approximately 15:00 Mountain Standard Time, Palo |
| Verde Nuclear Generating Station |
| (PVNGS) notified the Environmental Protection Agency (EPA) that a INITIAL |
| NOTIFICATION OF CONTINUOUS RELEASE was being reported. |
| |
| The following information was provided to the National Response Center and |
| State of Arizona: |
| |
| "Palo Verde Nuclear Generating Station is calling to make an initial |
| notification of a continuous release in accordance |
| with CERCLA Section 103(f)(2). 40CFR 302.8 (d). This is not an accidental |
| or episodic release. |
| |
| Palo Verde Nuclear Generating Station will be performing a scheduled steam |
| generator cleaning activity as part of its routine refueling outage for Unit |
| 1. The steam generator cleaning activity will begin on Saturday, September |
| 28 at |
| approximately 18:00. During this activity, Palo Verde Nuclear Generating |
| Station will exceed the Reportable Quantities for the release of ammonia and |
| hydrazine. The same activity is scheduled to occur during the Unit 3 |
| refueling outage, spring of 2003. The activity occurs approximately once |
| per every five to seven years on each unit. The hazardous substances |
| released are ammonia (CAS #7684-41-7) and hydrazine (GAS #302-01-2). PVNGS |
| expects no adverse effects to health and welfare of the general public, nor |
| to the environment. |
| |
| The NRC Resident Inspector was notified along with the State. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39227 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 09/28/2002|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 15:36[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/28/2002|
+------------------------------------------------+EVENT TIME: 13:45[CDT]|
| NRC NOTIFIED BY: PRINTZ |LAST UPDATE DATE: 09/28/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KENNETH RIEMER R3 |
|10 CFR SECTION: | |
|DDDD 73.71(b)(1) SAFEGUARDS REPORTS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNESCORTED ACCESS GRANTED INAPPROPRIATELY |
| |
| IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY |
| |
| CONTACT HOO FOR ADDITIONAL DETAILS |
| |
| THE NRC RESIDENT INSPECTOR WAS INFORMED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39228 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 09/28/2002|
| UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 20:45[EDT]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 09/28/2002|
+------------------------------------------------+EVENT TIME: 14:10[MST]|
| NRC NOTIFIED BY: DON STRAKA |LAST UPDATE DATE: 09/28/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN PELLET R4 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N Y 99 Power Operation |99 Power Operation |
|3 N Y 99 Power Operation |99 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SPURIOUS ACTUATION OF ONE OFFSITE EP SIREN |
| |
| "At 14:10 on 09128/2002, the Palo Verde Unit 1 Control Room was notified of |
| a spurious actuation of one siren. The siren is located near Southern and |
| Palo Verde Roads. This siren provides emergency notification to |
| approximately 39 Members of the Public. |
| |
| "No press release is planned at this time, however, the event is being |
| reported due to inquiries from the Maricopa |
| County Department of Emergency Management to troubleshoot the siren and |
| notification of the siren actuation to the |
| Maricopa County Sheriffs Office. |
| |
| "Personnel have been dispatched to turn off the siren. |
| |
| "There is no event in progress and no risk to the health and safety of the |
| public. Members of the public within audible |
| range of the siren may have a concern for their radiological health and |
| safety. |
| |
| "Unit 1 is at approximately 0% power In Mode 5 at the start of its scheduled |
| refueling outage. Unit 2 is at approximately 99% power in Mode 1 at normal |
| operating temperature and pressure. Unit 3 is at approximately 99% power in |
| Mode 1 at normal operating temperature and pressure. |
| |
| "The NRC Resident Inspector has been informed of the siren actuation and |
| this ENS notification. Note: The checkbox for OTHER GOV AGENCIES is |
| referring to the Maricopa County agencies discussed above." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39229 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 09/29/2002|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 13:11[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/29/2002|
+------------------------------------------------+EVENT TIME: 05:02[EDT]|
| NRC NOTIFIED BY: HOFFMAN |LAST UPDATE DATE: 09/29/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WALTER RODGERS R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR TRIP SIGNAL DUE TO LOW-LOW STEAM GENERATOR LEVEL. |
| |
| While draining the 1"D" steam generator, a reactor trip signal was generated |
| due to a low-low steam generator level. One train of the reactor protection |
| system was being tested, so one trip breaker opened in response to the trip |
| signal. The low-low steam generator level was due to a planned evolution |
| and was a valid signal. There was no safety significance because all |
| control rods were already inserted into the fuel assemblies, the control |
| rods were not latched to the control rod drive system, and the motor |
| generator sets were shutdown by procedure. Although the reactor trip |
| breaker was closed during testing, at no point was control rod withdrawal |
| possible. They are investigating the cause. |
| |
| The NRC Resident Inspector will be notified |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39230 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 09/29/2002|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 20:20[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/10/2022|
+------------------------------------------------+EVENT TIME: 17:32[EDT]|
| NRC NOTIFIED BY: PETE SENA |LAST UPDATE DATE: 09/29/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANIELLO DELLA GRECA R1 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INADVERTENT START OF A STANDBY SERVICE WATER PUMP DURING RESTORATION FROM A |
| CALIBRATION ACTIVITY |
| |
| "On September 10, 2002 at 1732 hrs, a pressure transmitter in the Service |
| Water System was being returned to service after the performance of an |
| instrument calibration procedure. The transmitter was being vented in order |
| to return the transmitter to service. During the venting evolution, an |
| inadvertent start of 2SWE-P21B, B Standby Service Water Pump, occurred. The |
| pump start was due to low pressure as seen by a second transmitter, which |
| shares a common sensing line with the transmitter that was being vented. |
| This second transmitter provides an input to the auto start feature for the |
| B Standby Service Water Pump. Venting the transmitter caused low pressure in |
| the common sensing line which activated the auto start feature. Since the |
| low pressure was only seen locally at the transmitter and not throughout the |
| system, this was an invalid actuation. Low service water system header |
| pressure is the parameter which would activate this feature and low service |
| water system header pressure was not experienced during this event. A |
| complete actuation of the B train of the Standby Service Water System |
| occurred and the system functioned properly. |
| |
| "This event is reportable pursuant to 10 CFR 50.73(a)(2)(iv)(A) since it |
| involved an automatic actuation of an emergency service water system that |
| does not normally run and that serves as an ultimate heat sink as per 10 CFR |
| 50.73(a)(2)(iv)(B)(9). This actuation was not part of a pre-planned sequence |
| and did not occur with this system properly removed from service. |
| |
| "However, pursuant to 10 CFR 50.73(a)(1), this event is being reported via |
| this telephone notification instead of submitting a written Licensee Event |
| Report since the automatic actuation of the Standby Service Water pump was |
| not generated by a valid actuation." |
| |
| The NRC Resident was notified. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021