ML20151N344

Forwards Request for Addl Info Re Chapter 9, Auxiliary Sys, & Chapter 5, RCS, CESSAR-DC,Sys 80+ in Order to Continue Review of Amend B

ML20151N344
Person / Time
Site:	05000470
Issue date:	08/03/1988
From:	Vissing G Office of Nuclear Reactor Regulation
To:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
References
PROJECT-675A NUDOCS 8808080184
Download: ML20151N344 (5)

Text

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, August 3, 1988

. Project No. G75 Mr. A. E. Scherer, Director Nuclear Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTER 9 AUXILIARY SYSTEMS AND CHAPTER 5, REACTOR COOLANT SYSTEM, CESSAR-DC, SYSTEM 80+, PLANT SYSTEM BRANCH Our Plant Systems Branch has reviewed Amendment B of Chapters 5 and 9 of l

CESSAR-DC, System 80+ transmitted by your letter dated April 11, 1988, and has identified the need for additional information. 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, DrTginal Signed By:

Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects i Office of Nuclear Reactor Regulation i

Enclosure:

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%,*...+/" August 3, 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

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTER 9, AUXILIARY SYSTEMS AND CHAPTER 5, REACTOR COOLANT SYSTEM, CESSAR-DC, SYSTEM 80+, PLANT SYSTEM BRANCH Our Plant Systems Branch has reviewed Amendment B of Chapters 5 and 9 of CESSAR-DC, System 80+ transmitted by your letter dated April 11, 1988, and has identified the need for additional information. 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,

,:A A Guy S. Vissing, oject Manager Standardization and Non-Power Reactor Project Directorate '

Division of Reactor Projects III, IV, Y and Special Projects Office of Nu: lear Reactor Regulation

Enclosure:

As stated cc: See next page l

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t Combustion Engineering, Inc. Project No. 675 Advanced CESSAR cc: Mr. C. B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.

7910 Woodmont Avenue, Suite 1310 ,

Bethesda, Maryland 2081?

Dr. Michael Green Manager of Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 l

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• REQUEST FOR ADDITIONAL INFORMATION PLANT SYSTEMS BRANCH COMBUSTION ENGINEERING STANDARD SAFETY ANALYSIS REPORT DESIGN CERTIFICATION (CESSAR-DC), CE SYSTEM 80+

PROJECT NO. 675 281.50 With respect to the design requirements of the process sampling (9.3.2) system, address the provision of passive flow restrictions to limit reactor coolant loss from a rupture of the sample line, in accordance with the requirements of 10 CFR Parts 20 and 20.1(c) to keep radiation exposures ALARA, and the requirements of GDC 60 to control the release of radioactive materials to the environment.

Discuss conformance with the guidelines of Regulator Guide 8.8, position 2.1.(6).

281.51 With respect to the post-accident sampling system, address the (9.3.2) requirement that, if on-line gas chromatography is used for reactor coolant analyses, special provisions should be available to prevent high-pressure carrier gas from entering the reacte. coo 16nt.

281.52 According to CESSAR, the Chemical and Volume Control System (CVCS)

(9.3.4) provides means to purify the contents, add makeup, and adjust the chemistry of the inside containment refueling water storage tank (IRWST). Provide the P&ID showing the connecting lines of the CVCS to the IRWST, and discuss containment isolation provisions for these lines, if they penetrate containment.

281.53 Provide the CVCS process flow data, and excess reactor coolant (9.3.4) generated during typical plant operations (Tables 9.3.4-3, 9.3.4-6).

281.54 Section 9.3.4 states that all portions of the CVCW outside containment, l (9.3.4) with the exception of the containment isolation valves and '

penetrations, are designated as non-nuclear safety or Safety Class 4. l Section 3.2.2, however, states that components whose failure would result in release to the environment of radioactive gases normally required to be held for decay are designated Safety Class 3, and all Safety Class 3 components are Seismic Category I. Justify your safety and seismic classification of the CVCS components in view of the classification methodology given in Section 3.2.2.

281.55 Discuss the conformance of the leakage detection and control program (9.3.4) for the CVCS makeup and letdown lines, to the requirements of NUREG-0718 Item III.D.l.l.

281.56 Provide a list of all venting and draining points of the CVCS system (9.3.4) and discuss the destination of potential discharges from these points.

410.12 Identify technical changes between the CESSAR-DC Amendment B (5.2.5) subnittal and CESSAR 80 for reactor coolant pressure boundary leakage detection systems.

410.13 The demineralized water makeup system provides high quality makeup (9.2.3) water to a number of systems for which the functional description, to be provided in other sections of Chapter 9, is now designated as "later". Demonstrate that none of these systems require a seismic Category I makeup source.

. . .- l i I 410.14 Provide as functional requirements, provisions for directing (9.2.3) regeneration wastes from the demineralized water makeup system to a suitable point in the radwaste system or other specified area for processing prior to discharge to the environment, and instrumentation and isolation capabilities including the ability to detect corrosive ,

solutions and valving necessary to isolate the system. '

410.15 Provide a list of all miscellaneous systems drains and safety-related (9.2.6) systems which are connected to the condensate storage system.

Provide the requirements or demonstrate that a) a failure of a system compnent connected to a safety-related system will not affect tht safety function of the safety-related system, b) a system leakage or storage tank failure will not result in adverse environmental effects, and c) a storage tank overflow is handled in a safe manner.

410.16 Provide the following information (now shown as "later") in order (5.1.4, to permit the staff to perform an integrated review of the systems:

5.4.11, 9.2.1, 1) 5.1.4.G - Nuclear Steam Supply System - Balance of Plant 9.2.2, Interface Requirements 9.2.4, 9.2.5, 2) Section 5.4.11 - Pressurizer Relief Tank 9.3.1, 9.3.3) 3) Section 9.2.1 - Station Service Water System

4) Section 9.2.2 - Cooling System for Reactor Aux 111eries

5) Section 9.2.4 - Potable and Sanitary Water Systems

6) Section 9.2.5 - Ultimate Heat Sink  !

7) Section 9.3.1 - Compressed Air Systems 1

8) Section 9.3.3 - Eauipment and Ficor Drainage System  !

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