bluuebunny/crossref_metadata_2025_split huggingface dataset:
Evaluating AOV and MOV Performance
Authors: Walker Tom , Camilli Nick 
Published: December 2017

Calculating margin for valve operation under design basis conditions requires evaluation of the stem loads required to operate the valve and the load capability of the actuator. These evaluations require justified and validated methodologies with verified inputs to implement the methodologies. The lack of validated methodologies in the past led to plant events and issues that prompted three NRC generic letters for MOVs and numerous generic correspondence documents from the NRC on AOV and MOV performance. Over the past 25 years, EPRI has performed extensive research to better understand the performance of valves and power operators. This research has been used to develop predictive methods for the evaluation of valve required operating loads and actuator output capability.
This paper summarizes EPRI’s research related to the development of predictive methodologies for valves and power operators and methods that are available, specifically methods for:
• Predicting required operating loads under design basis conditions,
• Predicting actuator output capability,
• Addressing thermal binding of gate valves, and
• Addressing the rate-of-loading phenomenon for MOVs.
This paper also describes a recent project to develop and validate a method for predicting the required thrust to overcome friction between the valve disk and body due to disk side-loading in cage-guided balanced disk globe valves.
Paper published with permission.
Design Basis Verification and Preservice Testing Considerations for OM Code Mandatory Appendix III
Authors: Estep Neal E. 
Published: December 2017

ASME OM Code Mandatory Appendix III (Appendix III) [1] for inservice testing of motor-operated valves (MOVs) contains prerequisites for a design basis verification test (DBVT) and preservice test prior to initiating inservice testing. The DBVT has specific requirements that depend on valve type and operational experience and the preservice test must adequately bridge the DBVT and inservice test. In addition, certain replacement, repair, or maintenance activities require an evaluation to determine what aspects (if any) of the DBVT or preservice test require repeat testing and/or engineering analysis to either confirm existing reference values or establish new reference values. Finally, existing testing performed under legacy NRC Generic Letter (GL) 89-10/96-05 MOV Programs or ASME QME-1 functional qualification standard may be credited to satisfy all or a portion of the DBVT and preservice test.
The purpose of this paper is to describe, by valve type:
• the specific requirements for the DBVT and preservice test,
• the use of previous qualification testing (e.g. GL 89-10/96-05 and ASME QME-1) to satisfy the DBVT and preservice test requirements,
• what activities may require analysis and/or repeating portions of the DBVT and preservice testing, and
• applicability to legacy MOV programs.
Paper published with permission.
Condition Monitoring of Rotating Equipment in Nuclear Power Plants
Authors: Jacks Ronny 
Published: December 2017

This presentation provides an overview of condition monitoring for rotating equipment in nuclear power plants. Specific condition monitoring technologies addressed include vibration analysis, lube oil analysis, thermography, and motor current signature analysis. Plant and equipment parameters, such as motor electrical and plant process parameters, useful for evaluating equipment condition, are also identified. The technologies are examined based on availability, cost effectiveness, and importance to a condition monitoring program. Although vibration analysis and oil analysis are the primary emphasis for performing condition monitoring, the inter-relationships between the technologies, techniques and other readily available plant data explored here demonstrate how a more complete and accurate diagnosis of the condition of a machine set can be determined. A discussion of each technology will include the various machine set faults which the technology will identify, as well as, how the overlapping technologies improve the effectiveness of a condition monitoring program.
Paper published with permission.
ISTB Pump Implementation Issues
Authors: McGaha Melvin L. , Rogers Tony Wayne 
Published: December 2017

Members of ISTB and ISTA have developed a list of issues regarding ISTB Pump Implementation that have been identified during IST Program Reviews, Day to Day operation of IST Programs, and site assessments of IST Programs (including issues found during updates). Implementation of the ISTB requirements for pumps in commercial US plants has presented challenges over the last few years with all the changes in ISTB since the issuance of the 1995 Edition of the ASME OM Code through the 2006 Addenda. This paper will discuss issues related to IST implementation. Good practices will be discussed to help IST engineers improve their programs. Some projected issues with implementation of 2012 Edition Appendix V will also be discussed.
Paper published with permission.
Gauging the Force Effects of Valve Stem Packing on Valve Stem Actuation
Authors: Drago James , Evans Wayne 
Published: December 2017

Stem friction in an operating valve is a function of the dynamic interaction of a number of variables — packing material of construction, number of packing rings, compressive load, lubrication, stem surface finish, temperature, cycling, etc. Forces due to friction can be reduced by modifying these factors. Attaining low actuation force and good sealing requires a balanced approach. Packing manufacturers have their own procedures for determining the frictional properties of different packing materials. This paper will show one such procedure and how varying materials and packing set configurations affect actuation force. The focus will be on linear reciprocating valve stems.
The equation F = π × d × H × GS × μ × Y can be used to calculate the force of the packing on the valve stem: Where F - Force needed to overcome packing friction; d - Stem diameter; H - Packing set height; GS - Compressive stress on the packing; μ - Packing coefficient of friction; Y - Ratio of radial to axial load transference, commonly equal to 0.50. Knowing the force, F, by test allows the calculation of the packing set’s frictional characteristics. . This knowledge can guide valve designers and builders to properly size actuating units for consistent and reliable valve performance.
Paper published with permission.
Snubber Program Transition From ISI Code to IST Code, ISTD
Authors: Palmer Glen R. 
Published: December 2017

The ASME OM Code, Subsection ISTD, is the required code for conducting preservice and inservice examination and testing of dynamic restraints (Snubbers). The latest approved edition of this OM Code is now, or soon to be the 2012 Edition. With the publication of the 2006 addenda to Section XI of the ASME Boiler & Pressure Vessel Code, the snubber requirements, which were previously located in Article IWF-5000, were deleted. When the requirements of IWF-5000 were deleted, the requirements for examination and testing of snubbers as required by 10CFR50.55a were required to be in accordance with the ASME OM Code, Subsection ISTD.
When Owners prepare their ten-year ISI program updates that incorporate the 2006 Addenda and later of the Section XI Inspection Code, the snubber requirements will be required to be in accordance with the ASME OM Code, Subsection ISTD, 2004 Edition with Addenda through 2006 or later approved editions. This edition of the ASME OM Code has been referenced in the NRC Regulations dated June 21, 2011. Since that time, Owners are required to meet the requirements of the latest approved edition of the ASME OM Code, for snubber examination and testing requirements when snubber programs are updated.
With the transition of the snubber program from the ISI program and ASME Section XI Code requirements to the IST program and the ASME OM Code, there is sometimes confusion and implementation gaps where regulatory program requirements could be missed.
This paper will address the transition and identify potential pitfalls and how to mitigate them.
Paper published with permission.
Curtiss-Wright Electro-Hydraulic Actuators for Main Steam and Main Feedwater Isolation Valves
Authors: Mkrtchyan Haykaz , Torosyan Ararat , Peng Hua 
Published: December 2017

This paper is about Curtiss Wright’s electro-hydraulic actuator environmental and seismic qualification for Main Steam Isolation Valve (MSIV) and Main Feedwater Isolation Valve (MFIV) applications. The qualification was performed in compliance with IEEE-382 and RCC-E requirements qualifying the actuator for US, Chinese and European power plant designs. The qualification entailed several challenges and application of analytical and test methodologies. The weight of the actuator/yoke assembly made seismic qualification one of the most challenging steps in the program. The seismic qualification was performed jointly with the Areva US Technical Center in Lynchburg, VA. The qualification program was designed to envelope the requirements power plant designs in US, China and Europe.
Paper published with permission.
Effective Diaphragm Area Test Program for Air Operated Valve Actuators
Authors: Leutwyler Zachary , Kalsi Manmohan , Thidavanh Lisa , Luckhardt Laurie , Cunningham Thomas 
Published: December 2017

GE contracted Kalsi Engineering, Inc. (KEI) to perform actuator testing to determine the effective diaphragm area for the Model 37/38 actuator line and to develop a bounding effective diaphragm area tolerance to account for measurement uncertainties and manufacturing tolerances.
The GE sponsored test matrix includes Model 37/38 Sizes 9, 11, 13, 15, 18, and 24 actuators. The test matrix was primary defined to provide EDA data for actuators used in US nuclear power plants. The test matrix was primarily designed to facilitate the evaluation of the effects of stroke position, pressure, diaphragm materials, and measurement uncertainty. The test matrix also included with and without spring test configurations, two spring options for the same actuator size and model, and two diaphragm materials: Nitrile Elastomer and Silicone.
The test program provides reliable data for AOV design basis evaluations as required by the NRC RIS 2000-03. This paper presents the results for the Masoneilan Model 38 Size 11 diaphragm actuator, which show that EDA is strongly position dependent and weakly pressure-dependent.
As part of the project, a method for determining the required EDA tolerance to account for manufacturing variations was developed, which allows EDA determined by testing to be used across the product line.
Paper published with permission.
Estimating Safety Valve Stochastic Failure-to-Close Probabilities for the Purpose of Nuclear Reactor Severe Accident Analysis
Authors: Ghosh S. Tina , Hathaway Alfred , Esmaili Hossein , Ross Kyle W. , Osborn Douglas M. , Wagner Kenneth C. 
Published: December 2017

Recent consequences analyses of potential station blackout (SBO) accidents at nuclear power plants have shown that an important uncertainty in accident progression and radionuclide release is the probability that a safety valve (SV) will fail-to-close after it has opened to relieve pressure [1]. The U.S. Nuclear Regulatory Commission’s (NRC’s) State-of-the-Art Reactor Consequence Analyses (SOARCA) and associated uncertainty analyses for SBOs at a pressurized-water reactor (PWR) indicated that SV behavior is an important determinant of whether an induced steam-generator tube rupture (an undesirable bypass event) may develop [2], and an important determinant of whether a PWR with an ice condenser containment may experience an early containment failure [3]. Given the importance of SV failure-to-close probabilities in these accidents, available information was reviewed to help develop better estimates of the probability for a SV’s failure-to-close on demand. The SVs of interest in the SOARCA PWR analyses are the PWR code SVs, designated SVVs in a study of SVs published in 2007 (NUREG/CR-7037) [4]. There are two sets of failure probabilities reported in NUREG/CR-7037: failure probabilities based on behavior after reactor scrams i.e., after actual operating events, and failure probabilities based on tests. Information is included for both the secondary-side, main steam system (MSS) valves, as well as reactor coolant system (RCS) valves.
The NUREG/CR-7037 failure probabilities based on actual operating events differ markedly from the failure probabilities based on tests. Further inquiries on valve testing and review of testing requirements show that the focus of testing is to demonstrate that the valves will open to relieve pressure during design-basis accidents to prevent overpressure events. The reseating or closing capability is not tested under severe accident conditions, in other words, the valve’s repeated full-stroking and passing steam. As such, the testing data was not considered applicable for severe accident modeling purposes. Furthermore, the assumption was made that MSS data was representative of RCS valve failures too during severe accident scenarios, as it is judged that they are similar enough in weighing the difference between the valves against the lack of operational data on the RCS SVs (only four data points, and one of two failures having a cause of failure now-defunct in the majority of operating PWRs in the U.S.). Lastly, recovered valve function, e.g., a previously stuck-open valve closing when pressure reduces, was not considered as a successful valve operation based on a review of licensee event reports.
Paper published with permission.
Predictive Monitoring of Main Steam Safety Valves
Authors: Patrone Jessica , Twaddle Phillip 
Published: December 2017

This report describes the tools employed by the Braidwood Generating Station Main Steam System Engineer to identify Main Steam Safety Valves (MSSVs) which may require refurbishment. These methods include in-service Trevitesting results, visual identification of steam leaks past the valve disc, external temperatures readings on the body and tailpipe flange of the valve, thermography, and risk rank charts. Utilizing these methods, Braidwood Generation Station will begin the transition from preventative maintenance of the MSSVs to a more cost effective predictive maintenance, in which the valves are rebuilt or refurbished on an as-needed basis.
Paper published with permission.
ASME OM Code Subsection ISTE: A Discussion of the Upcoming Subsection
Authors: Sellers Craig D. 
Published: December 2017

Subsection ISTE provides mandatory requirements for owners’ who voluntarily elect to implement a risk-informed inservice testing (IST) Program. The Subsection was originally prepared by combining the component categorization requirements and methodology from Code Case OMN-3 with component specific testing requirements developed, or under development, by the component-specific subgroups. Many of these requirements were based on the existing risk-informed Code Cases.
The original publication of ISTE was not endorsed by the NRC. The OM Subcommittee on Risk-Informed Activities has revised the subsection over the last four years and it is now expected to satisfy NRC concerns. This paper presents the upcoming proposed requirements for categorizing plant pumps and valves as either High Safety Significant Components or Low Safety Significant Components in accordance with ISTE and presents examples.
Paper published with permission.
Obesity prevalence among healthcare professionals in England: a cross-sectional study using the Health Survey for England
Authors: Kyle Richard G , Wills Jane , Mahoney Catherine , Hoyle Louise , Kelly Muireann , Atherton Iain M 
Published: December 2017

ObjectiveTo estimate obesity prevalence among healthcare professionals in England and compare prevalence with those working outside of the health services.DesignCross-sectional study based on data from 5 years (2008–2012) of the nationally representative Health Survey for England.SettingEngland.Participants20 103 adults aged 17–65 years indicating they were economically active at the time of survey classified into four occupational groups: nurses (n=422), other healthcare professionals (n=412), unregistered care workers (n=736) and individuals employed in non-health-related occupations (n=18 533).Outcome measurePrevalence of obesity defined as body mass index ≥30.0 with 95% CIs and weighted to reflect the population.ResultsObesity prevalence was high across all occupational groups including: among nurses (25.1%, 95% CI 20.9% to 29.4%); other healthcare professionals (14.4%, 95% CI 11.0% to 17.8%); non-health-related occupations (23.5%, 95% CI 22.9% to 24.1%); and unregistered care workers who had the highest prevalence of obesity (31.9%, 95% CI 28.4% to 35.3%). A logistic regression model adjusted for sociodemographic composition and survey year indicated that, compared with nurses, the odds of being obese were significantly lower for other healthcare professionals (adjusted OR (aOR) 0.52, 95% CI 0.37 to 0.75) and higher for unregistered care workers (aOR 1.46, 95% CI 1.11 to 1.93). There was no significant difference in obesity prevalence between nurses and people working in non-health-related occupations (aOR 0.94, 95% CI 0.74 to 1.18).ConclusionsHigh obesity prevalence among nurses and unregistered care workers is concerning as it increases the risks of musculoskeletal conditions and mental health conditions that are the main causes of sickness absence in health services. Further research is required to better understand the reasons for high obesity prevalence among healthcare professionals in England to inform interventions to support individuals to achieve and maintain a healthy weight.
Encouraging translation and assessing impact of the Centre for Research Excellence in Integrated Quality Improvement: rationale and protocol for a research impact assessment
Authors: Ramanathan Shanthi , Reeves Penny , Deeming Simon , Bailie Ross Stewart , Bailie Jodie , Bainbridge Roxanne , Cunningham Frances , Doran Christopher , McPhail Bell Karen , Searles Andrew 
Published: December 2017

IntroductionThere is growing recognition among health researchers and funders that the wider benefits of research such as economic, social and health impacts ought to be assessed and valued alongside academic outputs such as peer-reviewed papers. Research translation needs to increase and the pathways to impact ought to be more transparent. These processes are particularly pertinent to the Indigenous health sector given continued concerns that Indigenous communities are over-researched with little corresponding improvement in health outcomes. This paper describes the research protocol of a mixed methods study to apply FAIT (Framework to Assess the Impact from Translational health research) to the Centre for Research Excellence in Integrated Quality Improvement (CRE-IQI). FAIT will be applied to five selected CRE-IQI Flagship projects to encourage research translation and assess the wider impact of that research.Methods and analysisPhase I will develop a modified programme logic model for each Flagship project including identifying process, output and impact metrics so progress can be monitored. A scoping review will inform potential benefits. In phase II, programme logic models will be updated to account for changes in the research pathways over time. Audit and feedback will be used to encourage research translation and collect evidence of achievement of any process, output and interim impacts. In phase III, three proven methodologies for measuring research impact—Payback, economic assessment and narratives—will be applied. Data on the application of FAIT will be collected and analysed to inform and improve FAIT’s performance.Ethics and disseminationThis study is funded by a nationally competitive grant (ID 1078927) from the Australian National Health and Medical Research Council. Ethics approval was obtained from the University of Newcastle’s Human Research Ethics Committee (ID: H-2017–0026). The results from the study will be presented in several peer-reviewed publications, through conference presentations and via social media.
Linking management practices with range health in northern temperate pastures
Authors: Pyle Lysandra , Hall Linda M. , Bork Edward W. 
Published: December 2017

Little information exists on the management and range health (RH) of northern temperate pastures, where health is defined as the ability to sustain ecosystem function. We surveyed 102 pastures for RH and their associated managers during 2012–2013 across central Alberta, Canada. Pastures were generally diverse mixes of introduced grasses and contained few legumes, despite most (55%) being seeded to legumes. The majority of pastures were healthy (mean RH score = 78.8% ± 1.3%), with 2.9% having scores <50%. Criteria reducing scores were noxious weeds, bare soil, and evidence of erosion. Most pastures had a reported history of cultivation (75.5%), with those previously cultivated and seeded to introduced forage having greater stocking rates [6.18 ± 0.91 animal-unit-months (AUM) ha−1] compared with those lacking cultivation (2.14 ± 2.91 AUM ha−1). Farms with horses or mixed livestock tended to practice year-round continuous grazing and supplemental hay feeding. Stocking rates on continuous and rotationally grazed pastures were similar regardless of grazing season, with the highest stocking on pastures used year-round (19.54 ± 2.03 AUM ha−1) or throughout the dormant season (20.29 ± 3.10 AUM ha−1). Use of management inputs was variable, with manuring and harrowing common and fertilizing, over-seeding, and aerating infrequent. Herbicide use was reported on 15.7% of pastures, despite 83.3% containing noxious weeds. Use of prescribed fire was rare, although 36.3% of pastures had evidence of fire. Industrial disturbances were reported on 48.3% of pastures. Overall, these results indicate that these pastures experience complex management and the limited decline in RH is due to high stocking under year-long grazing.
Thermal inertia variations from gully and mass-wasting activity in Gasa crater, Mars
Authors: Harrison Tanya N. , Tornabene Livio L. , Osinski Gordon R. , Conway Susan J. 
Published: December 2017

Abstract

Gasa crater has been the most active site observed on Mars to date, making it of particular interest for studying the process(es) behind gully formation and activity. In this study, we investigate whether differences in thermal inertia across different segments of gully systems, combined with morphological and colour observations with High-Resolution Imaging Science Experiment (HiRISE), can provide some constraints on the physical characteristics associated with recent activity within gullies in Gasa. We also investigate thermophysical differences between slopes in Gasa dominated by gully activity compared to those predominantly modified by dry mass-wasting processes. We find that Gasa crater exhibits clear variations in thermal inertia across its walls, controlled by the material properties and the types of dominant mass movement processes occurring on each wall. The youthful gully-fan lobes display thermal inertia values
c.
20–40 J m
−2
K
−1
s
−1/2
higher than adjacent older eroded and dust-covered lobes. The talus aprons from mass wasting in Gasa have thermal inertia values
c.
60–80 J m
−2
K
−1
s
−1/2
higher than gully aprons. The results of this study thus suggest that thermal imaging can inform us on surface change detection on Mars.