Morning Report for May 29, 2001
Headquarters Daily Report MAY 29, 2001 *************************************************************************** REPORT NEGATIVE NO INPUT ATTACHED INPUT RECEIVED RECEIVED HEADQUARTERS X REGION I X REGION II X REGION III X REGION IV X PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS MAY 29, 2001 Licensee/Facility: Notification: Part 21 Database MR Number: H-01-0036 Abb Automation Date: 05/29/01 Subject: Part 21 - Broken base for two telephone relays in Class 1E type CV-7 relay Discussion: VENDOR: ABB Automation PT21 FILE NO: m1-16-0 DATE OF DOCUMENT: 04/10/01 ACCESSION NUMBER: ML011130015 SOURCE DOCUMENT: LETTER REVIEWER: REXB, R. Telson The vendor ABB Automation reported a potential defect in its Class 1E type CV-7 relay. In November of 1999 Duke Energy Corporation returned four such relays that had cracked or broken bases for the plastic pedestal used to mount a plate retaining two telephone relays. The vendor concluded the cause of failure was "shipping damage." The vendor redesigned the telephone relay mounting plate. The affected styles are 1454C77A02, A08, and A11. The vendor states that it will notify and instruct all its affected customers to visually inspect the product and return it to the vendor for repair if required. The NRC will post ensuing reports on this subject on its Web site at http://www.nrc.gov/NRC/PUBLIC/PART21/2001. Contact: R. Telson, NRR 301-415-1175 E-mail: rdt@nrc.gov _ HEADQUARTERS MORNING REPORT PAGE 2 MAY 29, 2001 Licensee/Facility: Notification: Part 21 Database MR Number: H-01-0037 Framatome Anp Date: 05/29/01 Subject: Part 21 - Calculation of time to criticality for a boron dilution event Discussion: VENDOR: Framatome ANP PT21 FILE NO: m1-17-0 DATE OF DOCUMENT: 04/27/01 ACCESSION NUMBER: ML011200457 SOURCE DOCUMENT: LETTER REVIEWER: REXB, E. Goodwin The vendor Framatome ANP reported that for reactor coolant flow rates near the lower end of the flow range of the shutdown cooling system, use of the instantaneous mixing model, which assumes a completely mixed coolant volume, may lead to a non-conservative prediction of the time to criticality for a boron dilution event. If a completely mixed coolant volume cannot be assumed, then the dilution front model is used to evaluate the adequacy of margin to criticality. For high flow rates, the calculated times to criticality from the initiation of a boron dilution event are about the same for both models but for low flow rates, they may be significantly different. A quantitative flow criterion has not been established for choosing between these models. In the instantaneous mixing model, unborated water injected into the reactor coolant system is assumed to mix instantaneously with an effective system volume. The change in core boron concentration with time is continuous and homogeneous, corresponding to the increasing amount of dilution water entering the reactor coolant system. In the dilution front model, unborated water injected into the reactor coolant system is assumed to mix with a slug of borated water at the injection point. The diluted slug is assumed to move through the reactor core and around the reactor coolant system. The change In core boron concentration with time depends on the location of the diluted slug. The vendor states that it notified customers potentially affected by this issue, drafted a flow criterion that supports the use of the instantaneous mixing model in those current analyses where it has been used, and continues to evaluate the criterion. The NRC will post ensuing reports on this subject on its Web site at http://www.nrc.gov/NRC/PUBLIC/PART21/2001. Contact: E. Goodwin, NRR 301-415-1154 E-mail: efg@nrc.gov HEADQUARTERS MORNING REPORT PAGE 3 MAY 29, 2001 MR Number: H-01-0037 (cont.) _ HEADQUARTERS MORNING REPORT PAGE 3 MAY 29, 2001 Licensee/Facility: Notification: Part 21 Database MR Number: H-01-0038 Abb Power Date: 05/29/01 Subject: Part 21 - Failure of K-Line circuit breaker to close because of a malfunctioning hairpin retainer Discussion: VENDOR: ABB Power PT21 FILE NO: m1-18-0 DATE OF DOCUMENT: 05/02/01 ACCESSION NUMBER: SOURCE DOCUMENT: EN 37961 REVIEWER: REXB, V. Hodge The vendor ABB Power Distribution reported a failure to close of a K-Line circuit breaker during service testing due to a malfunctioning replacement control device. The retainer on the close coil armature pivot pin becomes dislodged from its slot, allowing the pin to "wander" from the proper position inside the armature. The vendor states that this part was subject of a design change in November 1998. To facilitate assembly, hairpin retainer part number 53152C00 was changed to 53152D00 in K-Line 708392T## series control device assemblies. This issue only affects K-Line circuit breakers with a mechanical "black box" control device containing an internal close coil and purchased between November 1998 and February 15, 2001. The vendor states this design change was reversed on February 16, 2001, and that affected assembly personnel have been trained. The vendor recommends repairing or replacing these control devices as soon as feasible and states that it will notify all customers who purchased this product. The NRC will post ensuing reports on this subject on its Web site at http://www.nrc.gov/NRC/PUBLIC/PART21/2001. Contact: V. Hodge, NRR 301-415-1861 E-mail: cvh@nrc.gov _ HEADQUARTERS MORNING REPORT PAGE 4 MAY 29, 2001 Licensee/Facility: Notification: Part 21 Database MR Number: H-01-0039 Inovision Date: 05/29/01 Subject: Part 21 - Spiking R-11 radiation monitor output Discussion: VENDOR: Inovision PT21 FILE NO: m1-19-0 DATE OF DOCUMENT: 05/11/01 ACCESSION NUMBER: SOURCE DOCUMENT: EN 37985 REVIEWER: REXB, C. Petrone The vendor Inovision (formerly Victoreen and Keithley Radiation Measurements) reports a potential defect in its R-11 radiation monitor. The problem, a rapid increase (spiking) in displayed concentration and analog output values for activity in the upper range that may render the instrument inoperable, is believed due to microprocessor inability to read and clear a register in the allotted time. The vendor believes this problem only affects Model 960 firmware modules upgraded or purchased since 1992 and expects to complete its evaluation by July 10, 2001. The NRC will post ensuing reports on this subject on its Web site at http://www.nrc.gov/NRC/PUBLIC/PART21/2001. Contact: C. Petrone, NRR 301-415-1027 E-mail: cdp@nrc.gov _ REGION I MORNING REPORT PAGE 5 MAY 29, 2001 Licensee/Facility: Notification: Niagara Mohawk Power Corp. MR Number: 1-01-0014 Nine Mile Point 2 Date: 05/25/01 Lycoming,New York Dockets: 50-410 BWR/GE-5 Subject: MAY 24, 2001 REACTIVITY TRANSIENT Reportable Event Number: 38033 Discussion: Licensee investigation identified that the cause of the May 24, 2001, 'B' recirculation flow control valve (FCV) malfunction and subsequent reactivity transient was a failed radial variable differential transformer (RVDT) in the valve position indication/feedback control circuit (located inside the drywell). Upon confirmation of the RVDT failure, the recently installed alternate position indicating/feedback circuit for both recirculation FCVs was placed in-service. Following a station operations review committee examination of the post-transient analysis and critique, the unit was returned to full power operations on May 28. The licensee plans to continue operations with the alternate circuit as the primary FCV position indication and feedback control circuit. Licensee analysis, as well as, independent review by the Global Nuclear Fuels, confirmed that all safety systems functioned as designed and that no thermal or mechanical design limits were exceeded. Review of the installed transient analysis recording system data identified that indicated neutron flux ranged between 117 and 61 percent, until the operators were able to lock- up the FCV and stabilize recirculation flow. Maximum simulated thermal power during the transient was determined to be approximately 102 percent (reference Event No. 38033). Detailed review of the reactor protection system response, including back-up calculations of flow biased rod block and trip setpoints, confirmed that no protective limits were exceeded during the transient. The resident inspectors were assisted by a region based inspector in reviewing the operators' response to the transient and the licensee's detailed analysis of the event prior to resumption of full power operations. Contact: William Cook (610)337-5074 Michelle Evans (610)337-5224 _
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Page Last Reviewed/Updated Wednesday, March 24, 2021