ML20235E873
| ML20235E873 | |
| Person / Time | |
|---|---|
| Site: | 05000000, 05000531 |
| Issue date: | 02/19/1975 |
| From: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| To: | Stuart I GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20234E460 | List:
|
| References | |
| FOIA-87-40 NUDOCS 8707130121 | |
| Download: ML20235E873 (7) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMisslON WASHINGTON, D. C. 20555
' C A T B G O R W a ne;C u m ELINFQMB8r Docket No. STN 50-531 FEB 191975 General Electric Company arac [0RSEGk U.S.
E.C.
ATTN: Mr. Ivan Stuart, Manager Safety and Licensing Section FEB 211975 Nuclear Energy Division 175 Curtner Avenue AM W
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' San Jose, California 95114 7 DIM 11 Mal 2g3di5i6 l
l Gentlemen:
We have completed our review of your retendered GESSAR-251 application I
consisting of a Preliminary Safety Analysis Report (PSAR). We have concluded that it is acceptable for docketing. The application was docketed under Docket No. STN 50-531 on February 14, 1975. You will be advised of key milestones of the GESSAR-251 review as soon as the schedule is developed and approved. We will prepare the schedule based on the assumption that your responses to all of the review questions x
contained in Enclosure 1 are received by March 21, 1975.
If this mile-stone cannot be met it will be necessary for us to revise our schedule.
The information requested in Enclosure 1 is based on our understanding of the information which the General Electric Company has agreed to provide the staff in the first quarter of 1975. This is based on the minutes of the meeting for October 29-31,1974 for GESSAR-238 and Supplement No.1 to the GESSAR-238 Safety Evaluation Report.
Our review of GESSAR-251 will include an evaluation of the NSSS'and optional systems including the interfaces of the NSSS and optional systems with each other and with the balance of plant. With respect g
to Chapter 7 of the GESSAR-251 PSAR, the majority of information contained therein is identical to that contained in the GESSAR-238, Hartsville and Skagit PSAR's. Accordingly, we plan to conduct a single review of this information for these four applications. However, '
interfaces will be handled on a case-by-case basis.
If during the course of the review you believe there is a need to appeal
'a staff position, this proposed action should be brought to the assigned Licensing Project Manager's attention as early as possible. This will pennit him to arrange an appropriate meeting on a timely basis. Although Eflf s
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a written request is not necessary, all such requests should be directed to the assigned Licensing Project Manager. This procedure is an informal one, designed to allow opportunity for applicants to discuss with Nuclear Regulatory Commission management areas of disagreement in individual case reviews.
i Sincerely.
l N
. Giam usso, Director -
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Division of Reactor Licensing i
Office of Nuclear Reactor Regulation f
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Enclosure:
l Request for Additional Information ccw/ enc 1:
Mr. W. Gilbert, Manager Safety and Standards
. General Electric Company i
175 Curtner Avenue San Jose, California 95114 i
Mr. L. Gifford, Manager 1.
Regulatory Operations Unit-l General Electric Company j
4720 Montgomery Lane j
Bethesda, Maryland 20014 9
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i ENCIOSJRE 1 I
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LIST T DEFICIENCIES AND
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REQUEST FOR ADDITIONAL INEOMATION GENERAL EIAITRIC 00t@ANY GESSAR 251 EOR NSSS PIOJECT.NO. STN 538 e
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220.0 EEECTRICAL, INSTRIMNTATION AND CONTROL SYSTINS i
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220.3 Attachment A is a list of the infomation which the staff has (7.0) concluded it will require in order to complete its review of GESSAR-251. This information shall be provided by 3/21/75.
With respect to each item in Attachent A provide the following infonnation:
j Classify each entry with one of the following designations as 1
appropriate; GESSAR-251 NSSS, GESSAR-251 option, or not applicable to GESSAR-251.
Where any of the information requested cannot be provided by l
3/21/75 a schedule for its subnittal shall be provided. In l
such cases justification shall be provided to include why the requested information is not available and -4 it is not
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required at the PDA stage of review.
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I 1.
Seismic Design I
a) A list of equipment
.b) A qualification procedure 2.
Environmental Design a)
A. list of equipment I
b) A qualification procedure 3.
Electrical Penetrations a)
Preliminary de51gn
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b)
The procedures and methods used to qualify them 4~, Separation a) Qualification of Isolation devices 5.
ReactorTripSystem(RTS)
' a') Further information on the Turbine Trip event and the I
relation to the RTS i
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Further information on re-j classification of the RTS
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buses and power s'upplies c)
Further information on the I
i bypassing of reactor. trip' from closure of the main -
steamline isolation valve d).Further information on the
' pulse testing scheme l
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Engineered Safety Features a)
Information, on testing scheme l
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7.
Automatic Depressurization System
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a)~ Information on inadvertent.
actuation of valves b)
Information on improved test method for pilot solenoid valves
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Low Pressure Core Spray and Low Y. * * -
8.
Pressure Coolant Injection (PRR) 1 a)
Information on the isolati.dn of the low pressure system
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from the high pressure
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system - diverse interlocks
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on valves
- 9. Flammability Control System a)
Design Criteria b)
Preliminary design
- 10. Suppression Pool Make-up System a)
Information on inadvertent dump b) Preliminary design
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- 11. Containment spray Sy' stem a)
Preliminary design p
12., Safety Related Display Instrumentation
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a). Control Board arrangements 4
, 13. Preliminary design information
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.for the following systems
'a) Refueling Interlocks b)
Reactor Vessel Instrumentation and Control.
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c) Process radiation monitoring h
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i d) Area radiation monitoring e)
Reactor ilater Clean-up f
Process computer g
Contain:nent Atmosphere monitoring f-
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.h Neutron monitoring
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Intermediate range (2) Traversing In-core Probes 14.
Reactor Pressure Pelief Instrumentation a) Preliminary design i'
- 15. Reactor flanual Control System (including Rod Pattern Control and i
Ganged rod motion) a) Preliminary des'ign t
16.
Preliminary design information for the i
follouing a) Recirculation Flow Control l
Systems b) Gascous P.aduaste i
c) Liquid Radwaste 4
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