ML20153B186
| ML20153B186 | |
| Person / Time | |
|---|---|
| Issue date: | 03/15/1988 |
| From: | Vissing G Office of Nuclear Reactor Regulation |
| To: | Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| References | |
| PROJECT-675A NUDOCS 8803210450 | |
| Download: ML20153B186 (5) | |
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March 15,1988 Project No. 675 Mr. A. E. Scherer, Director Nuclear Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500
Dear Mr. Scherer:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTER 10, CESSAR.DC, PLANT SYSTEMS BRANCH Our Plant Systems Branch has reviewed the Amendment 12, Chapter 10 of the System 80+ CESSAR-DC, transnitted by your letter dated November 30, 1987, and has identified the need for additional information in order to continue the review. The enclosed Request For Additional Information describes the ncaded information. Our schedule calls for the information to be received within 90 days from the date of this letter.
Sincerely, Origina1 Signed P7:
Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV.
Y and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
As stated Distribution:
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March 15,1988 Project No. 675 Mr. A. E. Scherer, Director Nuclear Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500
Dear Mr. Scherer:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTER 10 CESSAR-DC, PLANT SYSTEMS BRANCH Our Plant Systems Branch has reviewed the Amendment 12, Chapter 10 of the System 80+ CESSAR-DC, transmitted by your letter dated November 30, 1987, and has identified the need for additional information in order to continue the review. The enclosed Request For Additional Information describes the needed information. Our schedule calls for the information to be received within 90 days from the date of this letter.
Sincerely, Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV>
Y and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
As stated j
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Cembustion Engineering, Inc.
Project No. 675 l
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cc: Mr. C. B. Brinkman, Manager Washington Nuclear Operations l
Combustion Engineering, Inc.
7910 Woodmont Avenue, Suite 1310 Bethesda, Maryland 20814 1
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Enclosure REQUEST FOR ADDITIONAL INFORMATION PLANT SYSTEMS BRANCH COMBUSTION ENGINEERING STANDARD SAFETY ANALYSIS REPORT DESIGNCERTIFICATION[CESSAR-DC),CESYSTEM80+
PROJECT NO. 675 110.1 A.
Provide a legible large size copy of 1) Figure 10.1-1, Steam
- G03, and Power Conversion System Flow Diagram, 2) Figure 10.1-3, 10.3, Main Steam System Piping and Instrumentation Diagram, and 10.4, 2,
- 3) Figure 10.4.8-1. Steam Generator Blowdown System Flow Diagram.
10.4.4, Also provide large legible copies of flow diagrams and piping and main condenser (MC) grams for the main steam supply system (MSSS),
10.4.7, instrumentation dia and main vacuum system (MVS), turbine and 10.4.8) bypass system (TBS), condensate and feedwater system (CFS), and piping and instrument diagram for steam generator blowdown system (SGBS). The above drawings should include interfaces showing safety design classifications, plant-specific scope information, piping sizes and tabulated process system parameters including flows, pressures and temperatures for the various operational modes.
B.
Provide rated capacity, design conditions including number required, pressure, temperature, flow, codes, and other related data in a tebulated form for safety-related system equipment and major piping for the steam and power conversion systems in the CE scope including interface requirements for the plant-specific scope of supply.
C.
Provide the following information (now shown as "later") in order to pe"mit the staff to perform an integrated review of the steam and power conversion systems:
- 1) Table 10.1 Stean and Power Conversion System Design Performance Characteristics
- 2) Figure 10.1 Heat Balance for Steam and Power Conversion System
- 3) Section 10.2 - Turbine Generator Section 10.4.3 - Turbine Gland Sealing System Section 10.4.5 - Circulating Water System 1
- 4) Steam generator mass decrease data from zero percent to 100 percent load based on steady state conditions
- 5) Steam generator blowdown nozzles (hot leg and economizer) data for thermodynamic conditions m-
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410.2 Verify that the design of the MSSS includes the capability (10.3) to operate the atmospheric dump ialves locally or remotely following a station blackout so that a safe shutdown can be achieved independent of preferred and onsite emergency ac power in accordance with 10 CFR 50.63. Also, confirm that safety related electrical, instrumentation and control systems are provided for the atmospheric dump valves in order to comply with the BTP RSB 5-1 sosition regarding the capability to achieve a safe cold slutdown using only safety related equipment.
410.3 Verify that the design of the secondary systems including MSSS, (10.3, TBS, CFS, and SGBS are designed in accordance with BTP ASB 3-1 10.4.4, and MEB 3-1 as related to cracks and breaks in high-and 10.4.7, moderate-energy piping outside of containment.
10.4.8) 410.4 Demonstrate that the r'ain steam isolation valve (MSIV) and (10.3, main feedwater isolation valve (MFIV) closure times are in 10.4.7) accordance with SRP Section 15.0 accident analysis assumptions.
410.5 Confirm that the MSSS design includes the capability to detect (10.3) and control MSSS system leakage and isolate portions of the system in case of excessive Icakage or component malfunctions.
410.6 Verify that measures have been provided to detect radioactive (10.4.1) leakage into and out of the main condenser system and to preclude unacceptable releases of radioactive materials to the environment from the system.
410.7 Verify that the design includes protection of safety related (10.4.1) equipment from flooding resulting from a complete failure of the main condenser circulating water system.
410.8 Verify that the main condenser evacuation system (MCES) desion (10.4.2) conforms to the requirements of General Design Criteria (GDC) 50 ar.d 64 with regard to control and monitoring of releases of radioactivity to the environment.
410.9 Verify that the steam bypass capacity of the TBS is consistant (10.4.3) with reactor transient analysis in accordance with the criteria of SRP Section 4.4.
410.10 Verify that the CFS is designed in accordance with the guidance (10.4.7) contained in BTP ASB 10-2 to eliminate or reduce possible fluid flow instabilities (e.g., water hammers).
410.11 Identify these features of the CFS which are provided to I
(10.4.7) improve its reliability and thereby reduce the number of l
challenges to safety related systems, i
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