ML20195D225
| ML20195D225 | |
| Person / Time | |
|---|---|
| Site: | 05000470 |
| Issue date: | 11/01/1988 |
| From: | Vissing G Office of Nuclear Reactor Regulation |
| To: | Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| References | |
| NUDOCS 8811040272 | |
| Download: ML20195D225 (4) | |
Text
p.
November 1, 1988 Project No. 675 Mr. A. E. Scherer Director Nuclear Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Bo': 500 Windsor, Connecticut 06095-0500
Dear Mr. Scherer:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTERS 5, 6 AND 10, ANENDMENT C, CESSAR-DC, SYSTEM 80+, CHEMICAL ENGINEERING BRANCH
~
Our Chemical Engineering Branch has reviewed Amendment C of Chapters 5, 6 and 10 of CESSAR-DC, System 80+ transmitted by ycur letter dated June 30, 1988 and has identified the need for additional information. The enclosed Request for Additional information describes the needed information. Our schedule a
calls for the information to be received within 90 days from receipt of this letter.
Sincerely,
/s/
Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects - III, IV, Y and Snecial Projects Office of Nuclear Reactor Regulation i
Enclosure:
As stated cc: See next page
,DISTRIBUT'ON:
_ 504R0% FT ft o
NRC PDR
-Q d PDSNP R/F i
o,81 EHylton
-o GVissing
$8 EJordan i
RGrimes Nd OGC-Rockville
$8 FWitt g4 CMcCracken ACRS(10)
L Ne MM t
PM:PD 4
- PD 4
E lton GVis fcw (ACHiller k\\
5/fs/88
/</ / /u
's li/;/e8 1
4 r
UNITE] STATES NUCLEAR RECULATORY COMMISSION
{*
wAsumorow, o. c. mses
\\**..*,!
November 1, 1988 Project No. 6/5 Mr. A. E. Scherer, Director Nuclear Licensing Combustien Engineering 1000 Prospect N111 Road Post Office Box 500 Windsor, Connecticut 06095-0500
Dear Mr. Scherer:
SUBJECT:
REQUEST FOR AD0!TIONAL INFORMAT.'ON CONCERNING CHAPTERS 5, 6 AND 10, AMENDMENT C, CESSAR-DC, SYSitM 80+, CHEMICAL ENGINEERING BRAhCH Our Chemical Engineering Branch has reviwed Amendment C of Chapters 5, 6 and 10 of CESSAR-DC, System 80+ transmitted by y';ur letter dated June 30, 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 receipt of this letter.
Sincerely.
Guy S. Vissing, Pro t Manager Standardization and Non-Power F.eactor Project Directorate Division of Reactor Projects - III, IV, Y and fpecial Projects l
Office of Nuclear Reactor Regulation
Enclosure:
t As stated cc: See next page i
r
Combustion Engineering, Inc.
Project No. 675 d
Advanced CESSAR cc: Mr. C. B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.
7910 Weodmont Avenue, Suite 1310 Bet'nesda, Maryland 70814 Mr. Ernest Kennedy Manager of Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 4
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION CONCERNING 7MINltAT.7NBlhTIl0NG BRANCH REVIEW OF CHAPTERS 5. 6 AND 10 (5UBMITTAL GROUP CD COMBUSTION ENGINEERlhG SYSTEM 80 + DESIGN - CESSAR-DC Post accident sampling capability is indicated in this section.
281-25 pg. 5.4-24 However, the attached P&ID0 of the Shutdown Cooling System do Section X.5 not indicate post accident sampling lines.
281-26 Again, post accident sampling capability is indicated for the pg. 6.3-6 Safety Injection System. The P&lDs do not show the post accident Section X.3 sampling lines for the Safety Injection System.
In addition, it I
should be indicated that the post accident sampling system meets the requirements of Item II.B.3, Post Accident Sampling Capability of NUREG 0737, November 1980.
I 281-27 This paragraph should state that the steen generator blowdown system design meets the primary boundary material integrity pg. 10.4-22 requirements of General Design Criteria 14 as it relates to Section I maintaining acceptable secondary water chemistry (SR? 10.4.8).
The steam generator chemistry program for blowdown samples l
l i
should meet the requirements of SRP 5.4.2.1, BTP MTE8 'J-3 (Monitoring of Secondary Side Water Chemistry Water Chemistry j
I in PWR Steam Generators).
i l
This paragraph should indicate that the steam generator blowdown 2Al-28 system from the steam generator up to and including the first pg. 10.4-23 isolation valve outside containment is constructed according to i
Section J Quality Group B and seismic category I requirements in accordance with Regulatory Guide 1.25 and 1.29. This part of the steam l
generator blowdown system should meet the quality standards requirements in General Design Criteria 1 and the seismir, require-ments of General Design Criteria 2.
(SRP10.4.8) 281-29 There should be a paragraph added to indicate that the steam generator blowdown system downstream of the outer containment pg. 10.4-24 isolation valves is not seismic Category I and meets the quality standards of Position C.1.1 of Regulatory Guide 1.143 since it is not safety related (SRP 10.4.8)
I
_ _ _ _ _ _