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OPERATOR LICENSING IMPLEMENTATION TEAM (OLIT) FINAL ACTION PLAN

By Bob Meyer
The Operator Licensing Implementation Team (OLIT) Final Action Plan submitted the final recommendations to NRC Headquarters. The LLRT was convened after the March 18, 2014, Atomic Safety and Licensing Board decision to overturn the NRC staff’s denial of a Senior Operator License for an applicant at the Vogtle Electric Generating Plant. 
Overall, 19 of the 23 recommendations are being implemented as originally intended by the LLRT. The OLIT determined that four LLRT recommendations would be implemented in a different manner as detailed in its initial OLIT Action Plan.  
Recommendations are in the following areas:
- NUREG-1021 Grading Standards for Simulator Operating Tests and Regional Consistency
- NUREG-1021 Grading Standards for Simulator Operating Tests and Regional Consistency
- The Waiver process for Previously Passed Portions of the Examination
- The Administrative Review process for Contested simulator Operating Testing Results
- Examination Team Composition
- Review of Interim Guidance to the Conduct of Initial Operator Licensing Examinations 
- Review of 2011 independent Review Team Report
Members can got to the FORUM topic under "Members Forum" to see all the recommendations and the NUREG-1021 Rev. 11 publishing date.  This is a members only section.

Millstone Power Station Unit 2: Historical Oil Leakage from "C" RBCCW Pump Bearings Challenged Meeting Mission Time

by Bob Meyer

Brief your crews on this, if you do not have this case in your Ops Determination procedure. SRO MUST READ.

On April 17, 2015, with Millstone Power Station Unit 2 (MPS2) at 100% power and in operating MODE 1, the Nuclear Regulatory Commission questioned the historic operability of Millstone Power Station Unit 2's (MPS2) "C" Reactor Building Closed Cooling Water (RBCCW) pump because several condition reports had reported the need to frequently add oil to the pump's outboard bearing bubbler between November 2014 and early April 2015. Upon further review,

Dominion concluded that operability could not be assured since there may not have been sufficient oil to meet mission time requirements at all times with no compensatory measures in place. Plant Technical Specification 3.7.3.1 "Reactor Building Closed Cooling Water System" requires two reactor building closed cooling water loops shall be operable.

Since there were periods of time that plant operators were crediting the "C" RBCCW pump for one of the two required reactor building closed cooling water loops, and operability could not be assured at all times, Dominion is reporting this event pursuant to 10 CFR 50.73(a)(2)(i)(B), as a condition that was prohibited by the plant's Technical Specifications.

Crystal River Unit 3 - Notification of Schedule Changes for the Post-Shutdown Decommissioning Activities Report

by Bob Meyer

Duke Energy Florida, Inc. (DEF) submitted a notification to the NRC that DEF is planning to perform certain activities that constitute a schedule change as previously submitted to the NRC.

The Crystal River Unit 3 (CR-3) Post-Shutdown Decommissioning Activities Report (PSDAR) and associated Site-Specific Decommissioning Cost Estimate (DCE) and certain construction activities with associated costs were not planned by the PSDAR and DCE.

The disposal of legacy waste (i.e., retired steam generators, reactor vessel closure head and hot leg piping) from the site is behind schedule. DEF's new schedule is lagging four years compared to the original plan for these activities. DEF claims the changes will not add to the cost or to occupational dose.

Duke Energy Florida significantly underestimated the cost of cost of the demolition of the Ready Warehouse, CR-3 SAFSTOR decommissioning cost estimate with dry fuel storage, and Security cost with an increased security footprint associated with dry fuel storage. The schedule has been extended past the original 2074 for the completion of the dry fuel storage. 

DEF has concluded there is no significant impact to the overall cost or schedule that would jeopardize the ability of CR3 to continue to demonstrate financial assurance.

SAINT LUCIE: INVALID AUXILIARY FEEDWATER ACTUATION SYSTEM PARTIAL ACTUATION

On May 4, 2015 with Unit 1 in Mode 1 at 100 percent power, during performance of the 'A' channel Auxiliary Feedwater Actuation System (AFAS) monthly functional test, an invalid 'A' channel AFAS actuation occurred. The monthly functional test resulted with AFAS-1 in a half trip condition. Due to a poor contact on a manual actuation switch, a pathway was dropped out causing the partial AFAS actuation to occur. The faulty mechanical switch was replaced and the post maintenance testing was satisfactory. 

The partial AFAS actuation resulted in the successful start of 'A' AFW electric driven pump and the opening of its motor control valve, feeding the 'A' steam generator. The system responded to the invalid actuation as designed. 

PART 21 - POSSIBLE SAFETY DEFECT IN NON-INSTALLED POWER RANGE DETECTOR AT PALISADES (NOT YET INSTALLED)

Thermo Gamma-Metrics LLC, a part of Thermo Fisher Scientific, regarding potential noncompliance of their d ual uncompensated ion chamber power range detector. 

Based upon Fisher's evaluation, Thermo Gamma-Metrics has determined that a Reportable Condition under 10 CFR Part 21 exists for plant listed herein.

Taiwan seals Lungmen No.1 nuclear reactor

Taiwan seals Lungmen No.1 nuclear reactor

The No. 1 reactor at Lungmen Nuclear Power Plant in New Taipei City’s Gongliao District is mothballed July 1 for an initial phase of three years. (Courtesy of Taiwan Power Co.)

 

The No. 1 reactor at Lungmen Nuclear Power Plant in New Taipei City’s Gongliao District was sealed for three years starting July 1, according to facility operator Taiwan Power Co.

Small modular reactor bill passes state Senate

A bill to support the manufacturing of small modular reactors in Washington state passed the state Senate 31-12 on Tuesday as the Legislature wrapped up its work.

As of 8 p.m. Tuesday, however, the House had yet to consider it.

Sen. Sharon Brown, R-Kennewick, said that if it did not pass, she would be back with the bill next year.

It had bipartisan support in the Senate, plus the support of the governor, she said.

POINT BEACH: OFFSITE NOTIFICATION DUE TO AN INJURED EMPLOYEE TRANSPORTED TO HOSPITAL

This notification is being made in accordance with NUREG-1022, Event Report Guidelines 10 CFR 50.72 and 50.73 Section 3.2.12, News Release or Notification of Other Government Agency. 

On June 30, 2015 at 1256 [CDT] an employee was injured while conducting a work activity and a non-contaminated hospital transport was completed. 

29 CFR 1904.39(a) requires a report to the Occupational Safety

NRC Publishes Annual Report to Congress on Nuclear Security Inspections

The Nuclear Regulatory Commission has made available to the public an unclassified version of its annual report to Congress detailing the previous year’s security inspection program. The report is required under the Energy Policy Act of 2005. 

The report covers the NRC’s security inspection program, including force-on-force exercises, for commercial nuclear power reactors and Category I fuel cycle facilities for calendar year 2014. 

“The NRC files this report to inform Congress on our efforts to oversee the protection of the nation’s civilian nuclear power infrastructure,” NRC Chairman Stephen G. Burns said. “The NRC is committed to ensuring licensees maintain robust and rigorous physical and cybersecurity programs to protect the facilities we regulate and the materials managed within them.” 

In 2014, the NRC updated its force-on-force inspection procedure and continued efforts to review and enhance security inspections at nuclear power plants entering the decommissioning process. 

Overall, the NRC conducted 233 security inspections, including 23 force-on-force inspections, during 2014. The security program and publicly available results of the inspections are discussed in the report. 

Whenever a finding is identified during a security inspection, the NRC ensures the issue is corrected immediately or compensatory measures are put in place, if necessary. Details of security findings are considered sensitive and not released to the public.

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