Event Notification Report for August 2, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/01/2000 - 08/02/2000
** EVENT NUMBERS **
37166 37199 37201 37202
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37166 |
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 07/14/2000|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 14:55[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 07/14/2000|
+------------------------------------------------+EVENT TIME: 13:30[CDT]|
| NRC NOTIFIED BY: JIM McKAY |LAST UPDATE DATE: 08/01/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE JORGENSEN R3 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| VEHICLE ADMITTED TO THE PROTECTED AREA WITHOUT BEING COMPLETELY SEARCHED. |
| |
| The licensee admitted a new 2-ton truck to the protected area for use as a |
| designated vehicle. They discovered 23 hours after the truck had been |
| admitted to the protected area, that two compartments on the truck had not |
| been searched. They were immediately searched with nothing found. |
| |
| The licensee intends to notify the NRC Resident Inspector and the state and |
| local authorities. |
| |
| |
| * * * UPDATE AT 1240 ON 8/1/00, BY CHRISTIAN RECEIVED BY WEAVER * * * |
| |
| This event has been retracted. Upon further review it has been determined |
| that this event does not fall into the reportable categories identified in |
| NUREG 1304 or Generic Letter 91-03. This event will continue to be tracked |
| as a logable event. The licensee will notify the NRC resident inspector. |
| The Operations center notified the R3DO (Creed). |
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|Power Reactor |Event Number: 37199 |
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| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 07/30/2000|
| UNIT: [] [2] [] STATE: AR |NOTIFICATION TIME: 18:39[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 07/30/2000|
+------------------------------------------------+EVENT TIME: 16:35[CDT]|
| NRC NOTIFIED BY: TOM MOSBY |LAST UPDATE DATE: 08/01/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BILL JONES R4 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| INDICATION OF REACTOR COOLANT LEAKAGE ON PRESSURIZER HEATER PENETRATIONS |
| |
| "Boron was discovered on the reactor coolant system (RCS) pressurizer heater |
| power cables. An inspection of the heater sleeves was performed and it |
| appears that two heaters (B2 and D2) are leaking. B2 is on backup heater |
| bank #4 and D2 is on backup heater bank #6. The leakage appears to be the |
| result of primary water stress corrosion cracking (PWSCC) of either the |
| heater sleeve or the J-groove weld between the heater sleeve and the |
| pressurizer cladding. The insulation will need to be removed to positively |
| determine which heater sleeve(s) had been leaking. Currently, Unit 2 is in |
| reduced inventory with the pressurizer empty. The pressurizer heater sleeve |
| penetrations were inspected during 2R-13 [between 1/9/99 and 2/25/99] as |
| part of the routine I-600 inspections performed each refueling outage. No |
| indication of leakage was evident during that inspection. Pressurizer |
| heater sleeve leakage is considered RCS pressure boundary leakage." |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 0052 ON 07/31/00 BY LARRY McLERRAN TO JOLLIFFE * * * |
| |
| After removing insulation from the pressurizer and RCS hot legs, the |
| licensee discovered 9 or 10 additional pressurizer heater sleeves that are |
| leaking and also a hot leg temperature element (TE) that is leaking. The |
| licensee is continuing to inspect the hot leg penetrations for evidence of |
| leakage. |
| |
| The licensee notified the NRC Resident Inspector. The NRC Operations |
| Officer notified R4DO Bill Jones. |
| |
| * * * UPDATE AT 0829 ON 07/31/00 BY WAYNE AHO TO JOLLIFFE * * * |
| |
| The licensee discovered indications on RCS hot leg TE #2TE-4710-3 that is |
| indicative of a RCS pressure boundary leak. The TE is installed above the |
| water line in the 'B' hot leg on the reactor coolant pump #2P-32C side. The |
| licensee is continuing to inspect the hot leg penetrations for evidence of |
| leakage. |
| |
| The licensee plans to notify the NRC Resident Inspector. The NRC Operations |
| Officer notified R4DO Bill Jones. |
| |
| *** UPDATE/PARTIAL RETRACTION AT 1047 ON 08/01/00 FROM WAYNE AHO TO BOB |
| STRANSKY *** |
| |
| The licensee is retracting the last update. The following text is a portion |
| of a facsimile received from the licensee: |
| |
| "This information is provided as an update to Event #37199, and applies only |
| to the update given on 07/31/00 at 0829 EDST, and only to the RCS boundary |
| at the nozzle for 2TE-4710-3. |
| |
| "The remaining information in Event #37199 remains correct at this time. |
| |
| "The nozzle for 2TE-4710-3 was re-inspected, and there was a very fine ring |
| of white material immediately around the nozzle penetration into the |
| hot-leg. No indication of leakage was observed down the side of the hot-leg |
| pipe. Chemistry personnel took a small sample of the white material for |
| analysis. The results of the analysis was conclusive that the white |
| material was not boron. Because of the location of the white material and |
| the results of the chemistry analysis, it is concluded there is high |
| confidence that 2TE-4710-3 is not leaking around this nozzle. |
| |
| "The source of the white ring was from a Component Cooling Water (CCW) |
| leaking flange located above the TE-4710-3 nozzle." |
| |
| The NRC operations officer notified the R4DO (Spitzberg). |
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|Power Reactor |Event Number: 37201 |
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| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 08/01/2000|
| UNIT: [3] [4] [] STATE: FL |NOTIFICATION TIME: 10:44[EDT]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 08/01/2000|
+------------------------------------------------+EVENT TIME: 10:20[EDT]|
| NRC NOTIFIED BY: PAUL REIMERS |LAST UPDATE DATE: 08/01/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |STEPHEN CAHILL R2 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
|4 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| - CARM ISOLATION VALVES LABELS IN CONTROL ROOM DIFFERENT THAN UFSAR |
| DESCRIPTION - |
| |
| Tables 7.5-1 and 7.5-2 of the Turkey Point UFSAR indicate that "Open/Close" |
| position indication is provided in the control room for the containment |
| atmosphere radiation monitor (CARM) isolation valves #SV-*-2911, #SV-*-2912 |
| and #SV-*-2913 (containment isolation valves) in compliance with commitments |
| related to NRC Reg Guide 1.97 (Revision 3). Contrary to this, the stated |
| containment isolation valves are provided with "Open/Not Open" position |
| indication in the control room. |
| |
| Tech Spec LCO 3.3.3.3, Action 39 requires the licensee to restore the valves |
| to operable status within 72 hours or isolate the related containment |
| penetrations within 4 hours in accordance with Tech Spec 3.6.4. |
| |
| Since the installed configuration does not meet the plant design as |
| described in the UFSAR, the condition is considered to be reportable under |
| the requirement of 10 CFR 50.72(b)(1)(ii)(B) as a condition that is outside |
| the plant design basis. |
| |
| The licensee is determining corrective actions. |
| |
| The licensee notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 37202 |
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| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 08/01/2000|
| UNIT: [2] [3] [] STATE: PA |NOTIFICATION TIME: 19:06[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 08/01/2000|
+------------------------------------------------+EVENT TIME: 18:47[EDT]|
| NRC NOTIFIED BY: BREIDENBAUGH |LAST UPDATE DATE: 08/01/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JACK MCFADDEN R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 93 Power Operation |93 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| OUTSIDE DESIGN BASIS - EDG COOLING WATER |
| |
| This report is being made pursuant to 10CFR50.72(b)(1)(ii) due to the plant |
| being in a condition outside the design basis. During initial analysis of |
| data acquired from the Emergency Diesel Generator (EDG) GL 89-13 testing, it |
| has been determined that cross flow exists between the jacket water and air |
| cooler loops on the EDGs. As a result, the air cooler heat exchanger |
| capacity may be exceeded during a LOCA / LOOP condition when heat sink |
| temperature is greater than approximately 80�F. Previous hot weather |
| conditions during the summer of 1999 and early 2000 resulted in heat sink |
| temperatures being greater than 80�F for several days. Currently, heat sink |
| temperatures are below 80�F. The EDGs are currently operable, further |
| analysis is being conducted to increase margin, and compensatory actions are |
| being developed to reduce cross flow between heat exchangers. |
| |
| The NRC resident has been notified. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021