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NUREG-1513 Integrated Safety Analysis Guidance

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NUREG-1513 Integrated Safety Analysis Guidance

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NUREG-1513 Integrated Safety Analysis Guidance

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Course Code: NUREG1513
University: The Pennsylvania State University

MyAssignmentHelp.com is not sponsored or endorsed by this college or university

Country: United States

Questions:

1. What information is required in the environmental report required as part of a 10 CFR 50 license application? What is the driver for the NRC to conduct an environmental review (i.e., what responsibility is the NRC fulfilling by requiring applicants to submit an Environmental Report) How long is the review process expected to take?  
2. What is the DNFSB? What do they do? Why was the DNFSB conceived? Pick a DOE site and investigate and summarize a recent event currently discussed in one of the monthly reports. In your opinion, is the existence of an independent organization like the DNFSB needed and why or why not?3. What is the NWTRB? What key issues do they and current events are they tasked with investigating?      4. Describe the accident analysis techniques referenced in NUREG-1513?5. How do the consequence threshold limits and qualitative likelihood classification guidelines that govern the DOE facility basis analysis (Table 1 and Table 2 of DOE-STD-3009) compare with the NRC guidance for risk determination?  6. What are the required steps for performing an Integrated Safety Analysis?

Answer:
1. Environmental Reports
The essential information required in developing the environmental report for the license application entails the reactor operators’ data.  Moreover, the information on the nuclear reactors, SNM, process facilities as well as waste and medical isotopes can also be incorporated in the process. Some of  the information which one  need  to  incorporate  in the  environmental  report  include controls for the effluent, construction  issuance  permits, technical specifications and environmental conditions,  application for the public inspection, technical and general information.
NRC Drivers
Furthermore, the critical driver to the environmental reviews mainly aims at depicting the imminent impacts and effects which the proposed project may cause on the environment. In fact, the vital aspects appraised in the environmental assessment include reviewing the technical elements, safety as well as the overall situation (Hamilton, 2018).
The process is essential in developing the mitigation plan for curbing all the related effects which the project and the operations might cause on the environment. Additionally, the appraisal and assessment helps in attaining the relevant criteria and plan activities and regulation which must be adhered to ensure that the processes adequately managed. The reviewing process does not have the set time for the overall process. However, it is expected that upon the completion of submission of all the relevant and required documents, a review and appraisal is carried out. Once, the process is completed, and all the set criteria are satisfactory, the license will be issued for the commencement of the activities and project process (“Defense Nuclear Facilities Safety Board”, 2018). 
2. According to Defense Nuclear Facilities Safety Board (2018) DNFSB refers to the Defense Nuclear Facilities Safety Board and, essentially mandated to coordinate all the related activities at the plant with the aim of ensuring that there proper and adequate safety in the site. The DNFFSB was mainly conceived to deal with all the issues related to human healthcare and report all the viable and safety risks to the state. In essence, the mandate on the protection mainly considered and taken into account with the aim of ensuring that both the workers and the overall people living within the site proximity are protected decisively.  Thus, the organ functions to ensure that the overall health care of the people living within the proximity is protected from the hazardous risks which might come from the nuclear materials.
Monthly summary Report
The recent monthly report by the board reported is on the impacts of the active nuclear materials on the human healthcare and safety. This report indicated that there are significant impacts and side effects which the active atomic elements have on the people living within the proximity. Thus, it is reported from the survey that an evacuation mechanism should be put into consideration on how the active nuclear handling and failures should be handled without affecting human health. The report also incorporate the safety performance, fuel cycle facilities as well as the overall nuclear reactors and this assessment was conducted on 230 security entities in 2017 (“NRC Publishes Annual Report to Congress on Nuclear Security Inspections”, 2018).
In my option, the existence of the DNFSB is a fundamental requirement for the better of the process and related activities. In fact, the recommendations and the evaluations which they carry out and report both the president and energy forms part and parcel of the improvements which can be put in place. In essence, some of the recommendation and reviews may be adopted into law and thus, ensure that healthcare and safety of the people within the proximity is considered at all times.  When the companies associated with human risks like the nuclear plants are set without proper installation and incorporation of the independent organs to carry out the oversight and assessment reviews, then the human safety and healthcare are imminently exposed to enormous risks. 
3. NWTRB is a known independent state agency as far as the United States of America Federal Government is concerned. NWTRB means Nuclear Waste Technical Review Board which deals with all the issues regarding the nation in line with the nuclear waste management as well as the disposal processes in the country as a whole.  The board is mandated to perform both the technique unbiased as well as the scientific evaluation on the ongoing nuclear processes and report all the findings on the waste and hazardous effects which they have to both the environment and people living in the immediate surrounding.  Thus, the board represents their findings to various key stakeholders such as the administrators, the government, congress, the DOE as well as the non-governmental organizations.
The key and vital role of this organization is to undertake an in-depth study and review of all the related technical issues. The issues which the board is currently working on and reviewing include radioactive waste, transportation, storage and packaging of the nuclear elements, geological disposal as well as the related international experience in line with the process. The aging management is a vital issue which the NWTRB takes into consideration.  In essence, the analysis mainly carried out on the DOE SNF as well as the storage facility.  The current event which the board is dealing with is the management of the nuclear fuel disposal. The key and emerging issues in the examination are on the SNF degradation for both the storage facilities as well as the containers used in the process. According to U.S. Nuclear Waste Technical Review Board (2018), the effects on the mitigation and the standardized containers and the non-naval package often forms part and parcel of the NWTRB examination. 
4. There analysis used in describing the accidents involve in the nuclear process is another key and important aspect which is incorporated in the SAR.  The four key approaches used in the process include release mechanism, engineering evaluation, sequence analysis as well as consequence appraisal. In analyzing the accidents involve in the nuclear process, the key technique involve in the process is the evaluation of the accident in details since it is not easy to evaluate both the probability and the consequences of the accident occurrence. In essence, the first step in the accident evaluation is to appraise and examine the major sequences such as the external events, equipment failures as well as the human error. Once, the identification has been conducted, and then the second stage is to evaluate and examine the selected accident in a more detailed manner. Here, the accident is imminent appraised in terms of its design basis and the worst-credible level. Moreover, the risks involve with the happenings like equipment failure and resealing of the overall radioactive materials are also appraised at this stage. The probability mainly entails the evaluation of the accident using different scientific approaches such as the meteorological site history and the plant experience analysis. On the other hand, the analysis on the consequences mainly examined with referenced the likelihood events aftermath (Anderson, 2016). 
5. First and foremost, I will like to state that the consequences of both the qualitative and threshold limits are essential ingredients which one needs to consider when classifying the DOE facility. The governing guidelines which I came across in the evaluation of the DOE facility are the three-dimension analogy. This procedure is based on the three aspects and parameters as per my understanding. Thus, I established that the three aspects incorporate low, medium as well as the high techniques and focuses on ensuring that both safety as well as the health of the public and workers at all times is considered.  Although, the approach is good and gives some in-depth evaluation and context on the qualitative and threshold limits, the approach does not spell out the technique and individual measures which can be used to handle risks at individual stages.  While table one tends to give analysis on the hazard identification approach, the second table gives an in-depth analysis on the hazard summary. The critical analogy used in the process is the low, medium and high technique (Fyffe, 2016). On the other hand, risk determination using the NRC guidance primarily grounded on the identification, analysis and safety control measures on the risks and is grounded on the performance based approach.  Thus, the NRC guidance gives more in-depth analyses as compared to the first ones which mainly entail the classification of the associated risks (Peterson et al., 2018).  On the other hand, the second table gives analysis on the unmitigated release approach on the hazards whereas the first table gives only the bound risks relations. Moreover, a standard denotes the first table analysis but the second one does not have any amicable relation. Thus, in my option, the first table gives precise and detailed analysis as compared to the second. Thus, I would recommend the adoption of the first table seems it have less limitations as compared to the second table. 
6. There are various steps in performing the integrated safety assessment and these steps include

Obtaining of the authentication and approval for evaluating the hazards involve at the DOE nuclear premises by the contractor.
Describing the facility in terms of the physical amenities and the related components.

Developing systematic approached to be used for the identification of both the human made and the natural hazards and risks.

Evaluating the hazards in terms of both the normal as well as abnormal risks associated with the accident conditions.
Developing and deriving the hazard controls.
Finally, developing the define characteristics such the overall maintenance required, human personnel and the quality assurance.  

References
Anderson, R. L. (2016). US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 SUBJECT: Request for Additional Information License Amendment Request for Adoption of TSTF-545,”TS Inservice Testing.
Defense Nuclear Facilities Safety Board. (2018). Retrieved from https://www.dnfsb.gov/
Fyffe, L. M. (2016). An Evaluation of Safety and Health Data, with an Emphasis on Developing Performance Measures for Nuclear Chemical Facilities, Using Quantitative and Semi- quantitative Methods. Vanderbilt University. pp.67-89
Hamilton, T. M. (2018). Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50- 400/Renewed Facility Operating License No. NPF-63 Subject: Application to Adopt 10 CFR 50.69,” Risk-Informed Categorization and Treatment of Structures, Systems, and Components (SSCs) for Nuclear Power Reactors.
Lynch, S., Balazik, M. F., Tran, L. N., & Adams, A. (2016). US Nuclear Regulatory Commission Licensing and Oversight Activities Related to Domestic Molybdenum-99 Production.
NRC Publishes Annual Report to Congress on Nuclear Security Inspections. (2018). Retrieved from https://www.nrc.gov/reading-rm/doc-collections/news/2018/18-029.pdf
Peterson, R. A., Buck, E. C., Chun, J., Daniel, R. C., Herting, D. L., Ilton, E. S., … & Clark, S. B. (2018). Review of the Scientific Understanding of Radioactive Waste at the US DOE Hanford Site. Environmental science & technology, 52(2), 381-396.
U.S. Nuclear Waste Technical Review Board | NWTRB. (2018). Retrieved from https://www.nwtrb.gov/

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