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PROS 2015 Summer Meeting

2015 PROS Meeting will be in Texas.

A NASA tour is planned. You will love the Gulf Coast. Plan your meeting now, and have some fun too.

Read page two. News continues, don't stop on page one.

NRC Takes State of Georgia Agreement State Program Off Probation

Chairman of the NRC, Allison M. Macfarlane informed the Governor of Georgia that the Commission is ending the Probation period by the state of Gergia for the NRC Agreement State Program.

The NRC’s most recent review of the Georgia Program found that the actions taken to implement your “Program Improvement Plan” to address previously identified weaknesses have resulted in significant performance improvements. Additionally, our review found significant improvement in staff and management communications due to the appointment of a new program manager and weekly staff and management meetings. The NRC staff will continue to hold bimonthly calls with the Georgia Program to monitor the progress of the actions committed to in the Program Improvement Plan and will schedule a review of the Georgia Program in approximately 2 years.

Argonne, KAERI developing prototype sodium-cooled fast nuclear reactor

PgsfrThe US Department of Energy’s Argonne National Laboratory is working with the Korea Atomic Energy Research Institute (KAERI) to develop a Prototype Generation-IV Sodium-cooled Fast Reactor (PGSFR). KAERI’s Sodium-cooled Fast Reactor Development Agency has provided $6.78 million funding to date for Argonne’s contributions through a Work-for-Others contract.

A sodium-cooled fast reactor uses liquid sodium to transfer heat to a working fluid for power generation. The SFR is designed for management of high-level wastes and, in particular, management of plutonium and other actinides (the radioactive elements that lie between actinium and lawrencium on the periodic table, with atomic numbers 89 - 103). (Earlier post.)

The PGSFR is a 400 MWth, 150 MWe advanced sodium-cooled fast reactor that incorporates many innovative design features—in particular, metal fuel, which enables inherent safety characteristics.

NRC Facts

NRC FY 2014 Budget - $1.056 billion

Total Staff: 3,815

Projected recovered budget: $930.7 million

NRC Research program support: $50 million

 

U.S. Commercial Nuclear Power Reactors

• Generate about 20 percent of the Nation’s electricity

• 31 States with operating reactors

• 100 nuclear power plants licensed to operate in the United States: 65 pressurized-water reactors and 35 boiling-water reactors

• 4 reactor fuel vendors

• 23 parent operating companies

• About 80 different designs

• 62 commercial reactor sites

• 17 power reactors undergoing decommissioning

• About 6,600 total inspection hours at operating reactors in calendar year (CY) 2013

• Approximately 3,000 inspection documents concerning events reviewed

 

Reactor License Renewal

Commercial power reactor operating licenses are valid for 40 years and may be renewed for up to an additional 20 years.

• 28 units with original license

• 43 sites comprised of 72 units issued renewal licenses

• 12 sites with license renewal applications in review

• 6 sites with letters of intent to submit renewal license applications

 

New Reactor License Process

Early Site Permit (ESP)

• 4 ESPs issued and 1 application in review

SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 - NRC COMPONENT DESIGN BASES INSPECTION REPORT

by Bob Meyer

The inspection report issued on August 27, 2014 found one violation of NRC requriements. How timely is your corrective actions on key components? Do you have work request tags on equipment for extended amount of time?

Violation: PSEG did not promptly identify and correct degraded conditions associated with the Unit 1 and Unit 2 auxiliary feedwater storage tank (AFWST) and refueling water storage tank (RWST) instrumentation panels. PSEG's short-term corrective actions included installing bolts/plugs on the Unit 1 RWST panel 378-1 and unplugging the failed fan in Unit 1 AFWST panel 802-1.

The NRC determined that if this condition went uncorrected the conditions coupld potentially result in a loss of level indication, non-conservative level indication, and/or loss of low level alarm functions. 

The finding has a cross-cutting aspect in the area of Problem Identification and Resolution, Corrective Action Program, because PSEG did not identify issues completely, accurately, and in a timely manner in accordance with the corrective action program. Specifically, PSEG did not identify degraded conditions associated with the Unit 1 and Unit 2 AFWST and RWST panels and take timely and appropriate corrective actions [P.1].

V.C. Summer 10 CFR Part 21 Report Due to Deviations Regarding Rebar Embedment

by Bob Meyer

On August 14, 2014, Chicago Bridge and Ironworks (CBI) reported to the NRC that a Part 21 deviation was discuvered at V.C. Summer Unit 2 AP1000 nuclear project. The NRC just released this information on September 2, 2014. 

Quality control inspections revealed some rebar was found with the incorrect length and some embedment anchors were found with weld and bending deviations. CBI is expected to submit an evaluation of the deviations by mid-October. 

CBI did not meet the 60 day required evaluation of data discovered in December of 2013. The unreported condition was discovered during reviews conducted due to discovery of other similar conditions.

 © Copyright protected.

Nine Mile Point Unit 2 LER: Emergency Diesel Generator Actuation Due to Loss of Offsite Power Source Line 5

by Bob Meyer

The timeline is included. This can be used for OE or training on a loss of a single source.

Here is the LER:

On February 16, 2014 at 1216, Nine Mile Point Unit 2 (NMP2) was operating at 100 percent power when an automatic actuation of the Division I and III Emergency Diesel Generators (EDG) occurred due to a loss of a 345 kV bus owned by National Grid. The bus outage resulted in the loss of off-site power source (Line 5) owned by Exelon. Automatic actuation of the EDGs is reportable under 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.73(a)(2)(iv)(A). The cause of the loss of Line 5 is due to a faulted current transformer associated with 345kV Breaker R210 owned by National Grid, the transmission owner. The faulted transformer caused a voltage transient for both station service and offsite power loads. This resulted in the loss of: 1) the service water radiation monitor and radwaste/reactor building vent gaseous effluent monitoring systems 2) the 'C' and 'D' Reactor Water Cleanup (WCS) filter strings, and 3) spent fuel pool cooling. The voltage transient also caused Feed Water level control valve actuator controls to lock up and go to manual operation. The causal analysis identified the failure mechanism of the CT as an insulation breakdown internal to the CT. The corrective actions include purchasing spare CTs and performing follow up tests and repairs on damaged equipment. NMP1 LER 2008-001 and NMP2 LER 2012-004 are similar LERs submitted previously which involve the actuation of the EDGs due to a loss of Power Line 5.

SURRY: NOTIFICATION TO STATE OF VIRGINIA REQUIRED BY SITE DISCHARGE PERMIT

On 08/29/2014 at 1457 hours [EDT], Surry Power Station notified the State of Virginia Department of Environmental Quality (DEQ) that two of the three turbine building sumps, required to be sampled by the discharge permit VA00004090, indicated an out of specification condition for oil and grease parameters. The laboratory supervisor reviewed the analysis and found no discrepancies. Sample methods and sample locations were reviewed and were unchanged from previous samples. A review of the operation of the sump oil skimmers indicated that they have been operating properly. In addition, there have been no oil spills or maintenance that would cause elevated readings in the sumps.

Backup samples of both sumps were obtained on 08/27/14 and 08/28/14. The results of the backup samples were received on 08/29/2014 and all samples indicated a less than the detectable levels.

Based upon an initial review of the issue, the results of the backup samples, and at least 5-year history of less than detectable oil and grease levels in the sump, the original samples for the sumps are considered anomalous. The results, however, are being reported in accordance with the permit requirements. This report is being issued in accordance with 10 CFR 50.72(b)(2)(xi), any event or situation related to the protection of the environment for which notification to other government agencies has been made.

NRC Notified By: SCOTT BRAY

10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION

RX Type: [1] W-3-LP,[2] W-3-LP

Anti-nukers, congressmen fret over Entergy finances, requested subsidies

The Recorder - Greenfield, Mass

The Nuclear Regulatory Commission recently reopened a year-old petition from anti-nuclear groups concerned about Entergy Corp.’s financial ability to safely operate its nuclear plants, including Vermont Yankee.

The original petition, filed before Entergy announced plans to shut the 620-megawatt Vernon, Vt., reactor at the end of 2014 for economic reasons, had called for NRC staff to seek detailed financial information from Entergy Corp., but after the company balked, arguing such scrutiny was beyond... 

Palisades owner Entergy bet on future of nuclear power -- and it has proven a gamble

MLIVE - Michigan

TOWNSHIP, MI -- The biggest threat to the Palisades Nuclear Plant may be the volatile U.S. energy market.

When Entergy Corp. bought the plant from Consumers Energy in 2007, it appeared the Lousiana-based utility was acquiring a cash cow, an investment that would... 

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