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Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23291A4242023-10-24024 October 2023 1 to Updated Final Safety Analysis Report, Chapter 7, Section 7.6, All Other Instrumentation Systems Required for Safety ML23292A2052023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions 021.01 Through 021.88 PLA-8081, 1 to Updated Final Safety Analysis Report, Questions and Responses 121.1 Through 121.212023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 121.1 Through 121.21 ML23292A2242023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 032.1 Through 032.103 ML23292A2232023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 331.1 Through 331.19 ML23292A2212023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Response 260.1 ML23292A2202023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 441.1 Through 441.15 ML23292A2172023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 410.1 Through 410.13 ML23292A2162023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 040.1 Through 40.99 ML23292A2142023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 005.1 Through 005.6 ML23292A2132023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 362.1 Through 362.25 ML23292A2092023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 421.1 Through 421.42 ML23292A2082023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 422.1 Through 422.4 ML23292A2062023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 372.1 Through 372.28 ML23292A1692023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 15, Section 15.3, Decrease in Reactor Coolant System Flow Rate ML23292A2022023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Response 112.1 Through 112.10 ML23292A2012023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 16, Section 16.2, Proposed Final Technical Specifications ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23292A1982023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 17, Section 17.2, Quality Assurance During the Operations Phase ML23292A1922023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 232.1 Through 232.4 ML23292A1912023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 110.1 Through 110.57 ML23292A1892023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 18, Section 18.2, Response to Requirements in NUREG 0694 ML23292A1872023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 16, Section 16.3, Technical Requirements Manuals ML23292A1752023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 15, Appendix 15B, Accident Dose Model Descriptions ML23292A1742023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 10, Section 10.3, Main Steam Supply System ML23292A1722023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 11, Section 11.7, Independent Dry Fuel Storage ML23292A1712023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 11, Section 11.2, Liquid Waste Management Systems ML23292A1672023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 9, Section 9.5, Other Auxiliary Systems ML23292A2072023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions 230.1 Through 230.8 ML23292A1732023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 9, Appendix 9A, Analysis for Non-Seismic Spent Fuel Pool Cooling Systems ML23292A2002023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 18, Responses to TMI Related Requirements ML23292A2102023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions 313.1 Through 313.9 ML23292A1652023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 11, Section 11.4, Solid Waste Management System ML23292A1682023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 9, Section 9.3, Process Auxiliaries ML23292A2192023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 231.1 Through 231.5 ML23292A2282023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Question and Response 440.1 ML23292A2042023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 130.1 Through 130.28 ML23292A2182023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 1, Questions 010.1 Through 010.26 ML23292A1862023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 18, Section 18.1, Response to Requirements in NUREG-0737 ML23292A1962023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions 123.1 Through 123.9 ML23292A1702023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 15, Appendix 15D, Susquehanna Steam Electric Station Unit 2 Final Safety Analysis Report Cycle Specific Data ML23292A1852023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 442.1 Through 442.3 ML23292A2152023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 423.1 Through 423.58 ML23292A2272023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Figures Referenced in the FSAR Are Withheld Under 10 CFR 2.390 ML23292A2262023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Chapter 16, Section 16.1, Preliminary Technical Specifications ML23292A2032023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 211.1 Through 211.296 ML23292A1942023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Response 361.1 Through 361.5-1 ML23292A2122023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 222.1 Through 222.2 ML23292A2112023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions and Responses 400.1 ML23292A2222023-10-12012 October 2023 1 to Updated Final Safety Analysis Report, Questions 321.1 Through 321.7 2023-10-24
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SSES-FSAR
QUESTION 422.1 operation of the Susquehanna Station, provide the following In regard to the technical groups providing support for the Plant Engineering, Figure 13.1-3 (Power Plant Additions, Power information for the three groups reporting to the Manager-Power Plant Engineering Development, and Project Engineering Manager Susquehanna} and the three groups reporting to the Manager Nuclear Support, Figure 13.1-4 (Simulator Supervisor Susquehanna, Senior Nuclear Support Engineers, and Staff Health Physicists):
( 1} The number of professional persons assigned or expected to be assigned at the time of plant startup for the group.
(2) The expected proportion of time that they can be assigned to support the operation of Susquehanna if they have assignment for other activities.
RESPONSE
Power Plant Additions
- 1) This group will include approximately 100 professional technical personnel at the time of plant start-up
(1981).
- 2) This group's primar~ responsibilities are the engineering required in support of the company's existing fossil power plants and company buildings and will not have regular assignments in support of Susquehanna SES. They may, on occasion, be cal led upon for some specific assignment in a specialty area such as an architectural project to expand the
- off ice facilities at the plant. Less than 5% of this group's time is anticipated to be spent on support of Susquehanna SES operation. Under emergency conditions engineers from this group could be called upon for support as needed.
Power Plant Engineering Development
- 1) This group will include approximately 40 professional technical personnel at the time of plant start-up.
- 2) This group will provide operational support for Susquehanna SES in the area of engineering standards, guidelines and procedures, economic and feasibility studies, and technical consulting. Approximately 20\\ of this group's time is expected to be directed to
Rev. 46, 06/93 422.1-1 SSES-FSAR
Susquehanna SES support activities. Under emergency conditions, additional support could be provided as needed.
Project Engineering Manager-Susguehanna This title has been revised to Manager-Nuclear Plant Engineering and the Group name is Nuclear Plant Engineering.
- 1) This group will include approximately 75 professional technical personnel at the time of plant start-up.
- 2) This group is dedicated to Susquehanna SES and will spend 100% of its time on operational support.
Simulator Supervisor-Susgµehanna
- 1) This group will include 5 professional technical personnel at the time of plant start-up.
- 2) This group is dedicated to Susquehanna SES and will spend 100% of its time on operational support.
Senior Nuclear Support Engineers
- 1) This group will include 6 professional technical personnel at the time of plant start~up.
- 2) This group is dedicated to Susquehanna SES and will spend 100\\ of its time on operational support.
Staff Health Physicists
- 1) This group will include 3 professional technical personnel at the time of plant start-up.
- 2) This group is dedicated to Susquehanna SES and will spend 100% of its time on operational support.
Rev. 46, 06/93 422.1-2 SSES-FSAR
QUESTION 422.2 Describe the qualification requirements for the positions of Senior Results Engineer and Chemistry Analyst either by reference to ANSI N18.1 or by describing the specific requirements for the positions.
RESPONSE
The Senior Results Engineer will have, prior to fuel load or appointment to the position (whichever is later), a bachelor's degree in Engineering or the Physical Sciences and three years of power plant experience.
The position of Chemistry Analyst requires a high school diploma or equivalent, successful completion of a high school level chemistry course, and the demonstrated ability to complete Chemistry Analyst training as evidenced by successful completion of a selection examination. After appointment to the position, the employee will complete a training program consistent with training and experience previously received.
Prior to becoming fully qualified upon completion of this training, the Analyst may perform work for which proficiency has been demonstrated in accordance with the training program.
Rev. 46, 06/93 422.2-1 SSES-FSAR
QUESTION 422.3 Please provide the qualifications of the person filling the position of Quality Supervisor.
RESPONSE
As described in Subsection 17.2.1.1.1.4.1.1, the Quality Supervis9r meets the requirements set forth in Section 4.4.5 of ANSI/ANS 3.1-1978.
Rev. 46, 06/93 422.3-1 SSES-FSAR
QUESTION 422.4 Provide the position titles of members to be assigned to the Nuclear Review Board or describe the qualification requirements for members of the Board.
RESPONSE
See Subsection 13.4.2.2 for this information.
Rev. 46, 06/93 422.4-1