Event Notification Report for August 26, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/25/1999 - 08/26/1999 ** EVENT NUMBERS ** 35970 35984 36068 36069 36070 36072 36073 +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 35970 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: JL SHEPHERD & ASSOCIATES |NOTIFICATION DATE: 07/28/1999| |LICENSEE: JL SHEPHERD & ASSOCIATES |NOTIFICATION TIME: 19:17[EDT]| | CITY: SAN FERNANDO REGION: 4 |EVENT DATE: 07/26/1999| | COUNTY: STATE: CA |EVENT TIME: 00:00[PDT]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 08/25/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |BILL JONES R4 | | |VERN HODGES, FAX NRR | +------------------------------------------------+ | | NRC NOTIFIED BY: J.L. SHEPHARD | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PACKAGE APPEARED NOT TO BE CONSTRUCTED IN ACCORDANCE WITH DESIGN | | CERTIFICATE. | | | | J.L. SHEPHERD AND ASSOCIATES HAS A USNRC APPROVED QUALITY ASSURANCE PROGRAM | | FOR RADIOACTIVE MATERIAL PACKAGES, NUMBER 0122, REVISION 5, EXPIRATION DATE | | 01/31/2001. J. L. SHEPHERD & ASSOCIATES RECEIVED NOTIFICATION OF | | NONCOMPLIANCE OF ONE OF THEIR PACKAGES FROM THE ATOMIC ENERGY CONTROL BOARD | | (AECB), OTTAWA, ONTARIO, CANADA BY LETTER ON JULY 26, 1999. | | | | J. L. SHEPHERD & ASSOCIATES IMMEDIATELY REMOVED ALL THESE TYPES OF PACKAGES | | FROM SERVICE ON JULY 27, 1999 AND WILL NOT USE THEM FOR TRANSPORTATION OF | | RADIOACTIVE MATERIAL UNTIL THE QUESTION OF NONCOMPLIANCE HAS BEEN RESOLVED. | | | | A WRITTEN REPORT ON THE NONCOMPLIANCE WILL BE FORWARDED TO THE USNRC WITHIN | | 30 DAYS OF THIS NOTIFICATION. | | | | * * * UPDATE AT 2300 EDT ON 8/25/99 BY MARY SHEPHERD TO FANGIE JONES * * * | | | | A faxed update with additional information was received by the Operations | | Center which includes copies of certificates for the packages described. | | These packages are still removed from service, until the non-compliance | | issues are resolved. | | | | The HOO notified the R4DO (Phil Harrell) and NMSS (Kevin Ramsey). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35984 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 08/02/1999| | UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 17:21[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/02/1999| +------------------------------------------------+EVENT TIME: 15:53[CDT]| | NRC NOTIFIED BY: SEWEEL |LAST UPDATE DATE: 08/25/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |TOM STETKA R4 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLATFORM GRATING CLAMPS(FASTENERS) APPEAR NOT TO BE SEISMICALLY QUALIFIED. | | | | THE LICENSEE HAS DETERMINED THAT THE PLATFORM GRATING CLAMPS DO NOT APPEAR | | TO HAVE BEEN QUALIFIED FOR THE REQUIREMENTS OF A SEISMIC CATEGORY 1 | | COMPONENT WHEN LOADED. WITH THE GRATINGS UNLOADED, HOWEVER, THIS CONDITION | | DOES NOT AFFECT THE ABILITY OF SAFETY RELATED SYSTEMS TO PERFORM THERE | | INTENDED FUNCTIONS DURING A DESIGN BASIS EARTHQUAKE. ENGINEERING IS | | CONTINUING TO EVALUATE THIS CONDITION. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED | | | | * * * RETRACTED AT 2221 EDT ON 8/25/99 BY TIM CLOUSER TO FANGIE JONES * * * | | | | "After further review of the condition (event # 35984) reported on August | | 2,1999, TXU did not identify any deviation from the design basis | | requirements of the plant as defined in 10CFR50.2. Although the basic | | premise of the conservative reporting of this issue was that a "test | | failed", it was later noted that the newly tested configuration was not the | | as built configuration. Specifically, the new test configuration used an | | EPI clamp versus | | the friction clamps actually installed in the field. In addition, plant | | drawings and procedures already prohibited live loads in the areas that were | | deemed susceptible to the conditions identified in the initial corrective | | action document. Therefore, the platforms still maintained their ability to | | perform their specified safety functions, are not a condition outside of the | | design basis, and not reportable under 10CFR50.72/73. Accordingly, this | | report is hereby retracted." | | | | The licensee notified the NRC Resident Inspector and the R4DO (Phil Harrell) | | was informed by the HOO. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36068 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 08/25/1999| | UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 04:29[EDT]| | RXTYPE: [1] GE-4 |EVENT DATE: 08/25/1999| +------------------------------------------------+EVENT TIME: 01:48[EDT]| | NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 08/25/1999| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |KATHLEEN MODES R1 | |10 CFR SECTION: | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNEXPECTED HIGH PRESSURE COOLANT INJECTION SYSTEM SUCTION SWAPOVER DURING | | ROUTINE EMERGENCY DIESEL GENERATOR TESTING | | | | While using the "Diesel Generator Undervoltage Test Auto Start Switch" to | | start the 'B' emergency diesel generator as part of a routine surveillance | | test, an unexpected high pressure coolant injection system suction swapover | | occurred, and three valves actuated to swap the suction from the condensate | | storage tank (normal) to the torus. Apparently, a low spike was received on | | both the DC1 system and condensate storage tank level when the "Diesel | | Generator Undervoltage Test Auto Start Switch" was operated. After the | | condensate storage tank and torus levels were verified to be normal, the | | licensee swapped the high pressure coolant injection suction back to its | | normal lineup. The licensee is currently investigating the cause of this | | transient. | | | | The 'B' emergency diesel generator started as expected. | | | | The licensee plans to notify the NRC resident inspector and the State of | | Vermont. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 36069 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: AUGUSTANA COLLEGE |NOTIFICATION DATE: 08/25/1999| |LICENSEE: AUGUSTANA COLLEGE |NOTIFICATION TIME: 10:27[EDT]| | CITY: Sioux Falls REGION: 4 |EVENT DATE: 08/24/1999| | COUNTY: Minnehaha STATE: SD |EVENT TIME: 17:00[MDT]| |LICENSE#: 40-06921-03 AGREEMENT: N |LAST UPDATE DATE: 08/25/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |PHIL HARRELL R4 | | |FRANK CONGEL IRO | +------------------------------------------------+JOHN HICKEY NMSS | | NRC NOTIFIED BY: MIKE WANOUS |AARON DANIS, NMSS IAT | | HQ OPS OFFICER: LEIGH TROCINE |D. CHAMBERLAN, REG4 IAT | +------------------------------------------------+R. WARREN, NMSS IAT | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |PAAB 74.11(a) LOST/STOLEN SNM | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF A SMALL DISC CONTAINING 0.023 �Ci OF PLUTONIUM - 238 AND 239 | | | | After completing an inventory at 1700 MDT on 08/24/99, the licensee | | discovered the loss of a disc containing 0.023 �Ci of plutonium-238 and 239 | | in a one-to-one ratio (electroplated on hastelloy-B planchet). The missing | | disc was one of twelve that was used for physics classroom demonstrations. | | It was about the size of a quarter, and it was stored inside a plastic case | | about the size of a �-inch thick credit card. | | | | The loss of the disc was discovered during the first inventory conducted by | | a new radiation safety officer, and it is not known when the last accurate | | inventory was conducted. The licensee searched for the missing disc and | | talked with appropriate individuals. At this time, the licensee believes | | that the disc was lost and not stolen. | | | | The licensee plans to generate a written 30-day report. | | | | (Call the NRC operations officer for a site contact telephone number.) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36070 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 08/25/1999| | UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 13:20[EDT]| | RXTYPE: [1] GE-4 |EVENT DATE: 08/25/1999| +------------------------------------------------+EVENT TIME: 07:30[EDT]| | NRC NOTIFIED BY: MARK SCHAFFER |LAST UPDATE DATE: 08/25/1999| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |KATHLEEN MODES R1 | |10 CFR SECTION: | | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FITNESS-FOR-DUTY REPORT | | | | A LICENSEE SUPERVISOR WAS DETERMINED TO BE UNDER THE INFLUENCE DURING A | | FOR-CAUSE FITNESS-FOR-DUTY TEST. THE INDIVIDUAL'S PLANT ACCESS | | AUTHORIZATION WAS TERMINATED. THE INDIVIDUAL HAS BEEN REFERRED TO THE | | LICENSEE FITNESS-FOR-DUTY PROGRAM. CONTACT THE NRC OPERATIONS OFFICER FOR | | ADDITIONAL DETAILS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 36072 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: US ARMY (ACALA) |NOTIFICATION DATE: 08/25/1999| |LICENSEE: US ARMY (ACALA) |NOTIFICATION TIME: 17:22[EDT]| | CITY: ROCK ISLAND REGION: 3 |EVENT DATE: 08/20/1999| | COUNTY: STATE: IL |EVENT TIME: [CDT]| |LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 08/25/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MELVYN LEACH R3 | | |PHIL HARRELL R4 | +------------------------------------------------+JOSEPHINE PICCONE NMSS | | NRC NOTIFIED BY: JEFF HAVENNER | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CHEMICAL AGENT DETECTOR CELL MODULE DISCOVERED MISSING DURING INVENTORY | | | | AN M43A1 CHEMICAL AGENT DETECTOR CELL MODULE CONTAINING 250 MICROCURIES OF | | AMERICIUM-241 WAS DISCOVERED MISSING DURING AN INVENTORY CHECK COMPLETED IN | | AUGUST 1999 BY THE 63RD REGIONAL SUPPORT COMMAND LOCATED AT LOS ALAMITOS, | | CALIFORNIA. THE LAST ACTIVITY RECORDED FOR THIS PARTICULAR UNIT WAS AT FT. | | McCOY, WISCONSIN IN 1989. NO SEARCH FOR THE MISSING SOURCE IS PLANNED AT | | THIS TIME SINCE THIS PARTICULAR UNIT MAY HAVE BEEN TRANSPORTED AND USED IN | | DESERT STORM. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 36073 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: CD TECHNOLOGIES |NOTIFICATION DATE: 08/25/1999| |LICENSEE: CD TECHNOLOGIES |NOTIFICATION TIME: 18:00[EDT]| | CITY: CONSHOHOCKEN REGION: 1 |EVENT DATE: 08/25/1999| | COUNTY: STATE: PA |EVENT TIME: [EDT]| |LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 08/25/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |KATHLEEN MODES R1 | | |PHIL HARRELL R4 | +------------------------------------------------+RICHARD WESSMAN NRR | | NRC NOTIFIED BY: TERRY KINDEN |VERN HODGE (FAX) NRR | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10CFR PART 21 REPORT DUE TO SAFETY RELATED LEAD ACID BATTERY CELL | | NONCONFORMANCE | | | | A nonconformance within LCR-25 safety related lead acid battery cells | | manufactured by C&D for Nebraska Public Power District's (NPPD's) Cooper | | Nuclear facility has been discovered. The cells were purchased by NPPD and | | they reported to C&D that they have seen growth in the positive plates | | within some cells and at least one cell was removed when a short developed. | | Analysis of the cells has been completed by C&D, in conjunction with NPPD | | personnel, showing nonconforming levels of calcium within the positive grid | | alloy. | | | | To the best of C&D's knowledge, no other utility has been effected by this | | nonconformance besides NPPD. | | | | A final evaluation will be delivered to the NRC and to effected utilities | | within 30 days. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021