ML20040C335
| ML20040C335 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 01/08/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| References | |
| TAC-07199, TAC-7199, NUDOCS 8201270543 | |
| Download: ML20040C335 (6) | |
Text
_ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _
,;i JAN 8
~
DISTRIBUTI0fL 4
~
flSIC D
s TERA g
ORB #3 Rdg RECEIVFD Docket :;o. 50-344 DElsenhut OELD
- t JAN1319@
11 ;
I&E-3 n ica,,,,,
ACRS-10 muua. swaws as fir. Bart D. Uithers JHeltemes Vice President ::uclear Pt< Kreutzer-3 Portland General Electric Company RAClark 121 S. '.l. Saloon Street CTrammell Portland, Oregon 97204 Gray File ADeAgazio
Dear !:
- r..'ithers:
SDiab i.
'!e are currently reviewing the Trojan t:uclear Plant's overpressure mitiga-tion system (0::S) and your associated proposed Technical Specification changes (LCA 52 dated May 1, 1979). Our review has resulted in the need for additional infarr,:ation as identified in the enclosure.
In order for us to maintain our current review schedule, your response is requested by February 15, 1982. OMG clearance for this request is not required since the information is being sought from fewer than ten addressees.
Please contact us if you have any questions concerning this request.
Sincerely, Oddnal s.una oy; W kr, IChol'le ll w E
Robert A. Clark, Chief Operating Reactors Branch 93 Division of Licensing
Enclosure:
Request for Additional Infornation 1
cc w/ enclosure:
l Se next page i
i l
l 8201270543 820108 f
PDR ADOCK 05000344 O
l P
(
~
l
.I cd-
.,Rh1.h.L...
. k,Bk;f),L,,
0.$.B d 3,;,D L.,.P,fdtzer R
l ornce>
1/ (, a,mme.ll/,pn R,,, l a r.k.,
suome >
3/82 1/
/82 1/ ~ /.8 2..
DATE )
mc resu ass 00-8c3 nacu em OFFIClAL RECORD COPY usc>ra im _33,u
+
Portland General Electric Company cc: Multnomah County Library Social Science and Science Department 801 S.W.10th Avenue Portland, Oregon 97205 Michael Malmros, Resident Inspector U. S. Nuclear Regulatory Commission l
Trojan Nuclear Plant P. O. Box 0 Rainier, Oregon 97048 Robert M. Hunt, Chairman Board of County Commissioners Columbia County St. Helens, Oregon 97501 i
Donald W. Godard, Supervisor Siting and Regulation Oregon Department of Energy Labor and Industries Building Room 111 Salem, Oegon 97310 Regional Administrator Nuclear Regulatory Commission, Region V Office of Inspection and Enforcement 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 l :
l l
.i l
l
?
i t
t l
REQUEST FOR ADDITIONAL INFORMATION 1.
Branch Technical Position RSB 5-2 requires the Overpressurization Mitigation Systea OMS to meet single active failure analysis when the initiating cause of the event is not considered as the single active failure.
In addition to your analysis submitted in your July 21, 1977 letter, consider as the initiating event the failure of a DC power bus which results in the isolation of letdown flow and also fails closed one of the pressurizer PORVs. A postulated single failure (failing closed) of the other PORV would fail mitigating systems for i
this event. Discuss your plant's provisicns to mitigate such a transient.
2.
The branch position requires an alarm to alert the operator that a pressure transient is occuring. You state that a high pressure alarm is received in the control room on the plant 250 computer.
a.
How is the alarm annuciated?
b.
Must the alarm be acknowledge to silence the annuciation?
c.
What visual indication associated with the alarm condition is available?
d.
When is the alarm enabled when you are cooling the plant down from hot stand-by to cold shutdown?
e.
How often are the setpoints checked and alarm action tested?
f.
Is there a backup alarm available during high vulnerability periods (low temperature and water-solid RCS) when the plant 250 computer is removed from service for maintenance (you stated that maintenance is normally performed during low temperature operation)?
3.
The branch position requires an alarm to alert the operator to enable the OMS at the correct plant condition during cooldown. You rely on a pressure actuated l
alarm to perform this function. How do you ensure that the Reactor Coolant i
j.
i i
~
2-System temperature does not fall below the allowable temperature corresponding i
to the above alarm pressure setpoint, thus violating Appendix G limits?
4.
Deleted.
l 5.
The Branch Technical Position requires the OMS to be functional through an Operating Basis Earthquake. You stated that the air accumulators met Seismic Category I requirements but failed to mention the rest of the system.
Identify all system components that are not designed to function during an a.
Operating Basis Earthquake, and give the basis for these components not meeting this requirement.
b.
Analyze the situation if the components that you identify in "a" above do not function.
c.
Are the PORV operators qua. fied to operate through an OBE?
6.
Additional information is regaested on the following items concerning RCS and RHR relief valves and safety valves.
i a.
What is the basis for the backpressure assumed for the PORVs in your tran-sient analysis?
j b.
What is the relief capacity sensitivity to the PORV backpressure?
Is the relief capacity of RHR safety valve PSV-8708 sufficient to mitigate c.
l the overpressure transients that were analyzed for the OMS?
d.
Does the valve position indication of the PORVs and the PORV block valves m.
,_._,,_,_y.__,-
p,
! I f
indicate a control circuit condition or the actual position of th'e valves?
i e.
Do the PORVs and RHR safety valves have control room temperature indication on the piping downstream of the valves?
7.
Provide the following additional information concerning Trojan operating proce-dures:
a.
Have appropriate caution or warning notes been included in all applicable procedures to make operators aware of the situations that could possibly lead to pressure transients?
b.
Provide some examples of these caution notes in Trojan procedures.
8.
In your April 8,1977 letter (Appendix B), you provided some information on the l
training that you conducted on the overpressurization incidents; provide the following additional training information:
a.
What overpressure training have you performed since mid-1977?
b.
How do you ensure that a continued emphasis is placed on possible over-pressurization situations in your licensing and retraining programs?
c.
How is this training and LER review documented?
9.
What is the present status of the Trojan OMS?
a.
Have all permanent OMS installations and modifications been completed?
b.
Have the proposed temperature detectors been installed on the secondary side of the steam generator to provide primary to secondary differential temperature indication?
c.
Where does this AT indication read out?
?.
,c
l C
f '
t I
d.
What alarms are associated with this AT system?
I f
l 4
1 h
6 i
i k
_ - _ _