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Event Notification Report for March 25, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/24/1999 - 03/25/1999

                              ** EVENT NUMBERS **

35434  35464  35468  35501  35503  35504  35505  35506  35507  35508  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35434       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 03/02/1999|
|    UNIT:  [] [2] []                 STATE:  WI |NOTIFICATION TIME: 18:21[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        03/02/1999|
+------------------------------------------------+EVENT TIME:        16:45[CST]|
| NRC NOTIFIED BY:  SHORT                        |LAST UPDATE DATE:  03/24/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(1)(ii)     DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       1        Startup          |1        Startup          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUXILIARY FEEDWATER LEAKING BACK INTO MAIN FEEDWATER SYSTEM                  |
|                                                                              |
| THE LICENSEE DISCOVERED THAT THE AUXILIARY FEEDWATER SYSTEM WAS LEAKING BACK |
| INTO THE MAIN FEED SYSTEM ("B" FEED LINE) PAST TWO IN-SERIES CHECK VALVES.   |
| THESE CHECK VALVES ARE CONSIDERED CONTAINMENT ISOLATION VALVES.  LEAKAGE IS  |
| IN EXCESS OF THEIR ALLOWABLE LIMITS.  AUXILIARY FEEDWATER IS CURRENTLY       |
| FEEDING THE STEAM GENERATORS.  THE LEAKAGE HAS BEEN ISOLATED USING MANUAL    |
| VALVES.  THE UNIT WAS IN STARTUP FOLLOWING A REFUELING OUTAGE WHEN THE       |
| CONDITION WAS FOUND.                                                         |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
|                                                                              |
|                                                                              |
| ***RETRACTION ON 03/24/99 AT 1132ET BY RANDY HASTINGS TAKEN BY MACKINNON***  |
|                                                                              |
| Subsequent evaluation has clarified that only one of the series check valves |
| performs a containment isolation function, 2CS-476AA (Reference PBNP FSAR    |
| Figure 5.2-3).  The main steam and feed water system are considered a closed |
| system inside containment and the piping is part of the containment          |
| boundary.  That boundary remained intact during this event.  Accordingly,    |
| the integrity of the containment boundary was never in question and this     |
| condition did not result in a principal safety barrier being seriously       |
| degraded.                                                                    |
|                                                                              |
| An engineering evaluation has also been completed to assess whether the      |
| leakage observed past these check valves would have resulted in less than    |
| the required auxiliary feed water flow to be available for decay heat        |
| removal.  This evaluation concluded that even with check valve leakage in    |
| excess of that observed during this event, the auxiliary feed water system   |
| was capable of providing sufficient flow to the steam generators to meet the |
| design basis for decay heat removal. R3DO (Pat Hiland) notified.             |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35464       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 03/12/1999|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 15:08[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        03/12/1999|
+------------------------------------------------+EVENT TIME:        13:14[CST]|
| NRC NOTIFIED BY:  PHIL SHORT                   |LAST UPDATE DATE:  03/24/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD GARDNER       R3      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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          Y       73       Power Operation  |73       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - AUXILIARY FEEDWATER SYSTEM FOR BOTH UNITS INOPERABLE FOR 4 MINUTES -       |
|                                                                              |
| UNIT 1 IS OPERATING AT 100% POWER, AND UNIT 2 IS OPERATING AT 73% POWER.     |
|                                                                              |
| ON 03/12/99, DURING AN ENGINEERING EVALUATION, LICENSEE ENGINEERING          |
| DEPARTMENT PERSONNEL DETERMINED THAT THE UNIT 2 TURBINE-DRIVEN (TD)          |
| AUXILIARY FEEDWATER (AFW)                                                    |
| PUMP FLOW RATE HAD BEEN SET INCORRECTLY DURING A PREVIOUSLY PERFORMED TEST.  |
| LICENSEE PERSONNEL DETERMINED THAT THIS CONDITION AFFECTED THE ENTIRE AFW    |
| SYSTEM.  (PORTIONS OF THE AFW SYSTEM ARE SHARED BY BOTH UNITS.)              |
|                                                                              |
| AT 1314 CST ON 03/12/99, THE LICENSEE ADMINISTRATIVELY DECLARED THE UNIT 1   |
| TD AFW PUMP, THE UNIT 2 TD AFW PUMP, AND THE TWO SHARED MOTOR-DRIVEN (MD)    |
| AFW PUMPS INOPERABLE (AND THUS, THE ENTIRE AFW SYSTEM) AND ENTERED TECHNICAL |
| SPECIFICATION LIMITING CONDITION FOR OPERATION ACTION STATEMENT 15.3.0.B     |
| (a.k.a. 3.0.3).  ALL FOUR AFW PUMPS REMAINED FUNCTIONAL.  THIS CONDITION IS  |
| CONSIDERED TO BE OUTSIDE THE DESIGN BASES OF THE PLANT.                      |
|                                                                              |
| AT 1318 CST ON 03/12/99, THE LICENSEE TRIPPED THE UNIT 2 TD AFW PUMP AND     |
| DECLARED IT INOPERABLE, ENTERED TECH SPEC LCO A/S 15.3.4.C.1 (72 HOUR        |
| SHUTDOWN LCO), DECLARED THE OTHER THREE AFW PUMPS OPERABLE, AND EXITED TECH  |
| SPEC LCO A/S 15.3.0.B.  THUS, ONLY THE UNIT 2 PORTION OF THE AFW SYSTEM IS   |
| INOPERABLE.                                                                  |
|                                                                              |
| THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS.                              |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
|                                                                              |
|                                                                              |
| ***RETRACTION ON 03/24/99 AT 1128ET BY RANDY HASTINGS TAKEN BY MACKINNON***  |
|                                                                              |
| An engineering evaluation has subsequently been completed to assess whether  |
| the error in adjustment of the 2P-29 discharge throttle valves, which could  |
| have accelerated the drain down of supply water to the AFW pumps in the      |
| event of an external event induced break in the AFW suction line from the    |
| condensate storage tanks, could have resulted in the AFW pumps being         |
| inoperable once the pumps were switched to the alternate source of water     |
| (service water).  This evaluation concludes that the postulated air          |
| entrainment mechanism does not result in operation of the AFW pumps outside  |
| their design basis before, during or after the pump's suctions are switched  |
| to service water.  Accordingly, it was not necessary to declare the AFW      |
| system out of service and this condition was not reportable pursuant to 10   |
| CFR 50.72.  R3DO (Pat Hiland) notified.                                      |
|                                                                              |
| The NRC  Resident Inspector was notified of this event by the licensee.      |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35468       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 03/12/1999|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 17:39[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        03/12/1999|
+------------------------------------------------+EVENT TIME:        17:31[EST]|
| NRC NOTIFIED BY:  JOE RUTTAR                   |LAST UPDATE DATE:  03/24/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TOM MOSLAK           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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| -Control room personnel access door latch mechanism may not withstand HELB   |
| pressure in the turbine building-                                            |
|                                                                              |
| A licensee preliminary review of an error in an analysis assumption for the  |
| pressure applied to a control room personnel access door (#C-49-1) due to a  |
| high energy line break (HELB) in the turbine building indicates that the     |
| door latch mechanism might not withstand the applied pressure.               |
|                                                                              |
| The control room door has been latched with an alternative latching          |
| mechanism and will remain closed against this pressure so there are no       |
| current operability concerns.                                                |
|                                                                              |
| This situation results in a historical condition where Unit 3 may have       |
| operated outside its design basis.  Engineering evaluation is continuing.  A |
| conservative decision has been made to report this condition as a condition  |
| outside the design basis of Unit 3 pursuant to 10CFR50.72(b)(1)(ii)(B)       |
| pending the results of this evaluation.                                      |
|                                                                              |
| The Licensee informed the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE at 1237 on 03/24/99 by DALE BRODSKY to JOLLIFFE * * *           |
|                                                                              |
| A mockup test of the door latch and hinges was conducted on 03/19/99 at the  |
| door manufacturer's facility.  This test determined that the door hinges and |
| latch will withstand a total pressure in excess of that resulting from a     |
| HELB in the turbine building.  Additionally, the pressure on this door will  |
| actually be less than the pressure in the turbine building due to its remote |
| location and tortuous path.                                                  |
|                                                                              |
| Therefore, this condition is not reportable to the NRC pursuant to           |
| 10CFR50.72(b)(1)(ii)(B) as a condition outside the design basis of Unit 3    |
| and thus, the Licensee desires to retract this event.                        |
|                                                                              |
| The Licensee informed the NRC Resident Inspector.                            |
|                                                                              |
| The NRC Operations Officer notified the R1DO Jack McFadden.                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35501       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FLORIDA BUREAU OF RADIATION CONTROL  |NOTIFICATION DATE: 03/23/1999|
|LICENSEE:  J & M TESTING, INC                   |NOTIFICATION TIME: 13:01[EST]|
|    CITY:  CHIPLEY                  REGION:  2  |EVENT DATE:        03/10/1999|
|  COUNTY:                            STATE:  FL |EVENT TIME:        14:15[EST]|
|LICENSE#:  1763-1                AGREEMENT:  Y  |LAST UPDATE DATE:  03/24/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MARK LESSER          R2      |
|                                                |DON COOL, NMSS       EO      |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHARLES ADAMS                |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - AGREEMENT STATE REPORT - TWO LOST PORTABLE NUCLEAR SOIL MOISTURE DENSITY   |
| GAUGES -                                                                     |
|                                                                              |
| At 1415 on 03/10/99, during a Florida state inspection of J & M Testing,     |
| Inc., two portable nuclear soil moisture density gauges were determined to   |
| be missing.  These are old gauges that were not being used and were last     |
| seen during an inventory taken on 12/28/98.   The Chipley, FL police         |
| department has been notified.                                                |
|                                                                              |
| Specifications of the gauges are as follows:                                 |
| 1.  Manufacturer: CPN, Model: BRC (1977); Serial No C7304NE147; Isotopes: 8  |
| mCi Cs-137; 50 mCi Am-241/Be                                                 |
| 2.  Manufacturer: CPN, Model: BRC (1974); Serial No C7404NE50;   Isotopes: 8 |
| mCi Cs-137; 50 mCi Am-241/Be                                                 |
|                                                                              |
| Charles Adams, FL Bureau of Radiation Control, notified NRC Region 2 (FL     |
| Radiological Incident No. FL99-07).                                          |
|                                                                              |
| ******************** UPDATE AT 0745 ON 03/24/99 FROM CHARLES ADAMS TO        |
| TROCINE ********************                                                 |
|                                                                              |
| The State of Florida Bureau of Radiation Control called to correct the FL    |
| Radiological Incident No.  The number should have been FL99-037.             |
|                                                                              |
| The NRC operations officer notified the R2DO (Lesser) and NMSS EO (Cool).    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35503       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD                REGION:  4  |NOTIFICATION DATE: 03/24/1999|
|    UNIT:  [3] [] []                 STATE:  LA |NOTIFICATION TIME: 10:50[EST]|
|   RXTYPE: [3] CE                               |EVENT DATE:        03/24/1999|
+------------------------------------------------+EVENT TIME:        00:00[CST]|
| NRC NOTIFIED BY:  GREGORY SCOTT                |LAST UPDATE DATE:  03/24/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES CAIN         R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Discovery of false information provided by a contract employee granted       |
| access to the site.                                                          |
| Immediate compensatory measures taken upon discovery.                        |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| Call HOO for more information.                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35504       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 03/24/1999|
|    UNIT:  [1] [2] [3]               STATE:  SC |NOTIFICATION TIME: 17:37[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        03/24/1999|
+------------------------------------------------+EVENT TIME:        13:00[EST]|
| NRC NOTIFIED BY:  THERESA MELTER               |LAST UPDATE DATE:  03/24/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK LESSER          R2      |
|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       99       Power Operation  |99       Power Operation  |
|2     N          Y       99       Power Operation  |99       Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT SECURITY REPORT -                                                      |
|                                                                              |
| PLANT SECURITY COMPUTER SYSTEM DEGRADATION.  COMPENSATORY MEASURES           |
| IMMEDIATELY TAKEN UPON DISCOVERY.  REFER TO THE HOO LOG FOR ADDITIONAL       |
| DETAILS.                                                                     |
|                                                                              |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35505       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 03/24/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 22:12[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/24/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        13:26[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/24/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |PATRICK HILAND       R3      |
|  DOCKET:  0707001                              |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEVIN BEASLEY                |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - Power to C-746-Q Building Criticality Accident Alarm System lost when a    |
| bird contacted an overhead electrical line -                                 |
|                                                                              |
| At 1326 CST on 03/24/99, air circuit breaker #23B5B tripped due to a bird    |
| contacting an energized portion of the overhead electrical line.  As a       |
| result of this breaker tripping, power was lost to the C-746-Q Building      |
| Criticality Accident Alarm (CAA) System beacons.  CAA System audibility for  |
| the C-746-Q Building was lost,.  However, the breaker tripping did not       |
| affect the detectability of the CAA System.   Power to the C-746-Q Building  |
| was restored and the  CAA System was declared operable at 1337 CST.          |
|                                                                              |
| The inaudibility of the CAA Systems is reportable as a 24-hour event report  |
| per 10CFR76.120(c)(2).  (Paducah Problem Report No ATR-99-1691; Paducah      |
| Event Report No PAD-1999-022).                                               |
|                                                                              |
| The NRC Resident Inspector has been notified of this event.                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35506       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 03/25/1999|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 00:18[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        03/24/1999|
+------------------------------------------------+EVENT TIME:        21:00[CST]|
| NRC NOTIFIED BY:  DAVID H. HANKS               |LAST UPDATE DATE:  03/25/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES CAIN         R4      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| High Pressure Core Spray (HPCS) Division 3 Diesel Generator declared         |
| inoperable.                                                                  |
|                                                                              |
|                                                                              |
| HPCS (Division 3) EDG oil level was discovered to be out of specification    |
| low during normal rounds.  The Division 3 EDG was conservatively declared    |
| inoperable until further evaluations can be performed to determine final     |
| disposition of oil leakage from its inspection cover.  The licensee entered  |
| Technical Specification 3.8.1 (72 hour limiting conditioning of operation).  |
| All Emergency Core Cooling systems including HPCS are fully operable.        |
| Earlier in the day an undervoltage spike on the electrical grid caused the   |
| Division 3 EDG to start. The diesel was properly secured.                    |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35507       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 03/25/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 01:36[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/24/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        19:00[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/25/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |PATRICK HILAND       R3      |
|  DOCKET:  0707002                              |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|OCBC 76.120(c)(2)(iii)   REDUNDANT EQUIP INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TSR allowed one of two smoke detectors to be inoperable during withdrawal    |
| operations when both smoke detectors have to be operable during withdrawal   |
| operations.                                                                  |
|                                                                              |
| On March 10, 1999, Operations personnel identified a deficiency in a TSR     |
| requirement for the Pigtail line Isolation System at ERP (extended range     |
| product), LAW (low assay withdrawal), and TAILS, (TSR 2.5.3.4). The TSR      |
| required action allowed continued withdrawal operations if one (1) smoke     |
| detector was inoperable.  The Pigtail Line Isolation System requires two (2) |
| Pyrotronics Smoke Detectors to actuate for the isolation valve to close.     |
| Operation personnel initiated a Compensatory Action (CA-99-009) for this     |
| anomaly to isolate the withdrawal cylinder and manifold per TSR 2.5.3.4b if  |
| one smoke detector is declared inoperable.                                   |
|                                                                              |
| Initially there was no evidence that the Pigtail Line Isolation System had   |
| been allowed to operate any applicable mode (modes II or III) with one or    |
| more inoperable smoke head.  As a follow up investigation to this            |
| deficiency, a search of the BPS system (problem report database) was         |
| conducted.  This search identified that on July 8, 1998, a Pyrotronic smoke  |
| head at the Law IA withdrawal position had been declared inoperable and      |
| cylinder filling operations had been allowed to continue.                    |
|                                                                              |
| This event is reportable due to a Safety System required by the TSR not      |
| being available or operable and no redundant equipment was available to      |
| perform the required safety function.                                        |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the certificate     |
| holder.                                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35508       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 03/25/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 02:34[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/25/1999|
+------------------------------------------------+EVENT TIME:        01:30[EST]|
| NRC NOTIFIED BY:  GRANT FERNSLER               |LAST UPDATE DATE:  03/25/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        R1      |
|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        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOCAL LEAK RATE TEST PERFORMED ON THE "A" LOOP FEEDWATER CONTAINMENT         |
| PENETRATION FAILED.                                                          |
|                                                                              |
|                                                                              |
| An Appendix  "J" Local Leak Rate Test was performed on the "A" Loop          |
| Feedwater containment penetration.  The penetration piping was unable to be  |
| pressurized and therefore the leakrate exceeded Tech Spec limits.  The       |
| penetration is isolated and the condition does not represent an immediate    |
| threat to the public health or safety.                                       |
|                                                                              |
| The NRC Resident Inspector will notified of this event by the licensee.      |
+------------------------------------------------------------------------------+