Event Notification Report for December 23, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/20/2002 - 12/23/2002
** EVENT NUMBERS **
39457 39465 39466 39467
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|General Information or Other |Event Number: 39457 |
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| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 12/17/2002|
|LICENSEE: SCHLUMBERGER |NOTIFICATION TIME: 18:00[EST]|
| CITY: DALLAS FT WORTH APT REGION: 4 |EVENT DATE: 12/15/2002|
| COUNTY: STATE: TX |EVENT TIME: [CST]|
|LICENSE#: L01833 AGREEMENT: Y |LAST UPDATE DATE: 12/17/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA HOWELL email R4 |
| |ROBERT PIERSON email NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HELEN WATKINS | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| PACKAGE AT DALLAS FORT WORTH (DFW) AIRPORT EXCEEDS RADIATION LIMITS BASED ON |
| LABELING |
| |
| "The package exceeded the package limits based on the labeling and the |
| container. Radiation readings were about 17 mR/hr. at one meter. The limit |
| was 10 mR/hr. at one meter. A yellow Ill and Yellow II label provided |
| inconsistent radiation information. The package was held at a cargo bay by |
| US Customs. The TDH/BRC responded to a call for assistance to survey the |
| package and help determine its contents. The inspector responded on site |
| performed a survey and notified the Licensee's RSO. The Licensee planned to |
| send a representative to repackage and relabel the package prior to the |
| package being released for shipment to Houston, TX. The information provided |
| is preliminary and based on telephone conversations with involved parties." |
| |
| The package was air cargo on an international flight being shipped from |
| Schumberger in Singapore to Schlumberger in Houston, TX. |
| |
| The Texas Department of Health, Bureau of Radiation Control has notified NRC |
| R4, US Customs, DFW, and the licensee. |
| |
| The Texas Department of Health, Bureau of Radiation Control incident number |
| is I-7962 |
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|Power Reactor |Event Number: 39465 |
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| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 12/20/2002|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 20:04[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 12/20/2002|
+------------------------------------------------+EVENT TIME: 19:15[EST]|
| NRC NOTIFIED BY: SHARON DAVIS |LAST UPDATE DATE: 12/20/2002|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PAUL FREDRICKSON R2 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| UNANALYZED CONDITION |
| |
| "Inspection of the Harris Nuclear Plant (HNP) Safe Shutdown Analysis (SSA) |
| in Case of Fire identified that for postulated fires in three fire areas, |
| the design and compensatory actions assumed by the Safe Shutdown Analysis |
| would not ensure a protected train of equipment would remain available. This |
| condition constitutes noncompliance with the HNP FSAR and is reportable as |
| an unanalyzed condition as described in 10CFR50.72. |
| |
| "The inspection identified that postulated fires could cause spurious |
| actuation of components potentially resulting in loss of the Charging/Safety |
| Injection Pump (CSIP) assumed to be protected by the Safe Shutdown Analysis. |
| The fires were postulated to cause spurious closure of valves in the suction |
| and/or discharge flowpaths for the protected CSIP prior to implementation of |
| the preplanned actions designed to preserve these flowpaths. The protected |
| CSIP could be lost if it was in service at the time of the postulated fire. |
| |
| "The plant is instituting several interim compensatory measures to minimize |
| the impact of the postulated fires. These measures include aligning the |
| Charging System and de-energizing certain valves to minimize susceptibility |
| to mal-operation of components, and posting a fire watch in fire areas of |
| concern." |
| |
| The three areas of concern for the postulated fires are in the 261 RAB |
| elevation north-south hallway. The cable spreaders in this area constitute |
| the susceptible equipment. |
| |
| The NRC Resident Inspector was notified. |
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|Power Reactor |Event Number: 39466 |
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| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 12/22/2002|
| UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 00:18[EST]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 12/21/2002|
+------------------------------------------------+EVENT TIME: 20:35[EST]|
| NRC NOTIFIED BY: DAN FORRY |LAST UPDATE DATE: 12/22/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |J. BRADLEY FEWELL R1 |
|10 CFR SECTION: |DAVID MATTHEWS NRR |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|ACCS 50.72(b)(2)(iv)(A) ECCS INJECTION | |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR SCRAM AFTER EHC FAILURE |
| |
| At 2035, an EHC failure occurred that caused multiple bypass valves to open. |
| Reactor pressure dropped resulting in a Group 1 isolation (closure of |
| MSIV's) which caused a reactor scram. Lowest pressure was approximately |
| 850#. Level dropped through Lo Level (1"), resulting in Group 2/3 PCIS |
| isolation. Level continued to Lo Lo Level (-48"), resulting in ECCS |
| actuation and injection (HPCI & RCIC). ARI also initiated resulting in trip |
| of both Recirculation pumps. Plant is stabilized and preceding to cold |
| shutdown. |
| |
| The Licensee has notified the NRC Resident Inspector. |
| |
| The plant currently has MSIV's shut due to 3 Bypass valves open and are |
| maintaining pressure control with HPCI & RCIC. |
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|Power Reactor |Event Number: 39467 |
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| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 12/23/2002|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 02:53[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 12/23/2002|
+------------------------------------------------+EVENT TIME: 01:59[EST]|
| NRC NOTIFIED BY: BARRY DOE |LAST UPDATE DATE: 12/23/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |J. BRADLEY FEWELL R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 A/R Y 100 Power Operation |0 Hot Standby |
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EVENT TEXT
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| AUTOMATIC REACTOR TRIP CAUSED BY MAIN GENERATOR TRIP |
| |
| Automatic reactor trip caused by main generator backup relay protection |
| trip. The plant currently is stable in mode 3 with Auxiliary Feedwater in |
| service for decay heat removal. All control rods fully inserted, no primary |
| relief valves lifted and no ECCS actuation occurred. The Licensee reports |
| that the electrical grid is stable and all emergency diesels are available. |
| |
| |
| The Licensee has notified the NRC Resident Inspector. |
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