LD-91-006, Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes

Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes

ML20072S448
Person / Time
Site:	05000470
Issue date:	01/30/1991
From:	Erin Kennedy ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Wambach T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
PROJECT-675A LD-91-006, LD-91-6, NUDOCS 9104160004
Download: ML20072S448 (6)

Text

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ABB ASEA DROWN BOVEFH '

v January 30, 1991 LD-91-006 Project No. 675 ,

Mr. Thomas V. Wambach, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 n

Subject:

Combustion Engineering Standard Safety

( Analysis Report - Design Certification, Amendment I

Reference:

Letter LD-89-035, A. E.'Scherer (C-E) to' T. E. Murley (NRC), dated March 30, 1989-

Dear Mr. Wambach:

This letter transmits an advance copy of Amendmant I to the I

Combustion Engineering Standard. Safety Analysis Report..-

Design Certification (CESSAR-DC). Our application for design certification was submitted via the reference l letter. <

a For your convenience, we have summarized the contents of-Amendment I in Enclosure I. This copy of-Amendment I (Enclosure II) is provided for your information and planning purposes. The formal: amendment :is currently in the printing process and,-together with the affidavit required by - 10 CFR 50.4 (b) and 10l CFR 50.30(b) , will be submitted in approximately four' weeks.

I i

l t Nr; ABB Combustion Engineering Nuclear Power- -

.JJo 3 ^1, Cauwan Engmeerg tre .1000 Prowect HW Road Post Othce Box 500

. Telephone (203) 68819M

' Fax (203) 285 9012

.f I 9104160004 910130 '

wedsa, connecocus com oeco 7.iennm couets wson w PDR ADOCK 05000470 l

A PDR

_. , . - - . , , , , .  :. - , a. -

, Mr. Thonac-V. Wambach ID-91-006 January 30, 1991 Pago 2 t ,

O V If you have any. questions, please feel free to call me or 3 Mr. S. E. Ritterbusch of my staff at (203) 285-5206.  ;

Sincerely yours, COMBUSTION ENGINEERING, INC.

fl f/

E. H. Kennedy-Manager Nuclear Systems Licensing EHK:lw

Enclosures:

As Stated cc: C. L. Miller'(NRC) w/o' encl.

T. E. Murley (NRC) w/o encl.

F. W. Ross (DOE - Germantown) w/o encl.

G. L. Vine (EPRI) w/o encl.

O L

I

l Enclosure I to

.. LD-91-006 O ,

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SUMMARY

OF CESSAR-DC, AMENDMENT I O

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SUMMARY

OF CESSAR-DC. AMENDMENT I General Comments:

This amendment 'includa many minor changes to close out _ "open items" from previous amendments and to respond to NRC questions.--

.L Interface requirements for site-specific. structures and systems are  !

4 included in the text of CESSAR-DC. These interface requirements ir will be summarized -in Chapter ~ 1, Section 1.9, in .a ifuture amendment, i

Chanter 2 (Site Characteristigg.)...-

, Ss ation 2.5 now includes the site seismic . envelope, supporting.

analysis, and-the criteria to determine-whether'any specific site

is covered by.the envelope.-

! Chanter 3 (Desian of Structures. Systems, and Comoonents) 1 -

Section 3.2 has been expanded to include safety classifications for; the " balance-of-plant" structures, systems,'and components.

section 3.6 includcs tables identifying high energy lines outside the containment.

i Section 3.7 summarizes the wismic analysis methods and results for major structures and systems.

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.< Section 3.8 summarizes the design of Category Ilstructures.

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L Section 3.11 now provides the test profiles for environmental

! qualification of equipment located in various zones throughout tho

! plant. Listings of equipment in those! zones is albo_provided.- >

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1 Chanter 5 (Reactor Coolant and Connected Systemgi Section 5.2 includes a more detail'ec' lescription.of:the leakage detection . system and Appendix 5A now's .:ludes the- ASME -Code se fety valve sizing analysis.

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Chapter 6 (Encineered Safety Features)'

Section 6.2 has been revised to include the containment Annulus

Ventilation System --description,' a listing =of containment isolation

. valves, and a description of the Combus_tible-Gas Control._ System. -

LO Section- 6.7 includes a revised Depressurization System design.

description of the Safety.

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fM Section 6.0 is a new section describing the -In-containment

\ Refueling Water Storage Tank and the Cavity Flooding System.

Chapter 7 (Instrumentation and Controls)

There are minor revisions to existing material in Chapter 7 (e.g., ,

nomenclature changes, minor technical revisions, etc.).

Chapter 8 (Electrical Power Systems)  !

Chapter 8 now contains tables identifying' diesel generator load sequences and the loads for 1E power systems.

Chanter 9 (Auxiliary Systems)

There are a number of miscellaneous e'ditorial and minor technical-revisions. to the fuel handling, ' storage, and cooling systems; ultimate heat sink; chilled water systems; chemical volume and control system; lighting systems; and diesel generator sy. items.

Sections 9.2.1 and 9.2.2 provide more detailed descriptions af the Station Service Water and Component Cooling Water Systems.

More detailed descriptions of the : heating, ventilation and air conditioning systems are provided in Section-9.4.

A more detailed description of the Fire Protection System is provided in Section 9.5.1. "

Chaoter 10 (Power Conversion Systemsi There are minor i ahnical changes to Chapter 10 . - They do not

\ change any of the asign_ bases or features.

Chaoter 11 (Radioactive Waste Manacement)

Source term activities are provided and a description of the Radiological Monit.oring and Sampling Systems is . included in Section.

11.5.

Chapter 12 (Radiation Prot'ection)

This chapter has been re-written, including new information ' on-.-

radiation-zones and radiation' source activity levels.

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l Chanter 16 (Technical Specifications)

I

_,) l This chapter provides a set of proposed technical specifications, l (It is recognized that Technical Specifications for a specific plant are issued by the NRC as part of the Operating License or Combined Operating License.) The format of the proposed technical specifications follows the " segregated" format which is currently under development by the NRC staff in conjunction with the !

Combustion Engineering Owners Group.

Chanter 18 (Human Factors Encineerina)

There are a number of changes to this chapter to reflect design progress and minor technical revisions.

Annendix A (USIs/GSlgl Writeups are provided for an additional twenty-seven USIs and GSIs applicable to the System 80+ design.

Apnendix B (PRA)

A summary and conclusions section was added to this appendix. The

/} technical results remain unchanged.

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