ML20052D670
| ML20052D670 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/21/1982 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052D667 | List: |
| References | |
| NUDOCS 8205070073 | |
| Download: ML20052D670 (3) | |
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,A UNITED STATES
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1 NUCt.E AR RiGUL ATORY COMMISSION a
w e e.io v o e so m
.1 SAFETY EVALUATION BY THE OFFICE OF NUCLEA3_ REACTOR FEGULATi.
,RELATED TO AMEN! MENT NO.71 TO FACILITY OPERATING LICENSE _ NC. 'i i.
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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY p
TROJAli MUCLEAR PLANJ F.
D0CKET NO. 50-344 L
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Introduction:==
,g ty letter dated March 3, 1982, Portland General Electric Company, et ai.
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4 Pc the licensee, requested an amendment to Facility Operating License No.
WPF-1 for operation of the Trojan Nuclear Plant, a pressurized water s
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reactor located in Columbia County, Oregon.
The licensee seeks to aterc the Technical Specifications appended to the operating license by dele *.1, gJ the maximum allowable strokt- (operating) time requirement for six speci< _
ase-automatic motor-operated valves.
The valves are located in the r m 1-
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F mal heat removal and containment spray systems in lines that connect tho s.
9, containment recirculation susp to the suction of the containment spray (i S
and residual heat removal (RHR) pumps. The valves are identified as fel t e-:
V:
Valve N0.
Function Isolatic.1 time p.y j MD 8811A,5 recirculation to RHR 17 pumps-outside containment MO 2052A,B recirculption to CS pumps-10
+
outside containment h
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MD 2069 A,8 containment sump 17 isolation-inside containment 3
Mscussion and Evaluation J
I?
The licensee's attention was focused on these time limits as a result of a detailed mytew of environmental qualification of safety-related L
I, electrical equipment as required by IE Bulletin 79-01E and an NRC Order it of October.24,1980 which Wquires that all safety-related electrical i
epipment be fully. qualified by not later than June 30, 1982.
['
'As reported by PGE in Licensee Event Report 80-22 dated Octobe-31. IE.
...- the brakes en some Limitorque motor operators were deterw.ined tc 140 5.-
full environmental qualification bechse radiation qualification testin -
s I'
had not been performed. Although similar brakes are qualif ted, in',ut' icier t information exists to apply the existing test results to scoe of tre Tr sr
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valve operators.
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PGE proposrs to rerove the brakes to correct the environtwntal ga.=': *,.e, p.9blem. However, in removing the brakes from such valves, their o r es. -
must be slowed down in order to operate properly without bra 6es.
pr;, c e that the valve stroke time most be increased to about 30 seconds.
Tb s w.
be contrary to the Technical Specifications for MO 2069 A and B whia o
shown above, have maximum allowable stroke times of 17 seconds.
T h e : : r.s four valves are not affected by the environmental qualification brab n
and their stroke time would c)t be changed.
The licensee's revie c' t % - c.
however, has resulted in its eetermination that the time limit shoule t.. +:<
for all six valves.
Seth the NRC and PGE have attespted to determine the basis for the tima i m i:-
for these valves. No time limits exist for any of the other containmer.1 isolation valves of this type (non-automatic, power-operated valves.
P.e e r. b i
was found and therefore we have concluded that these time limits were ar. a r r-made when the original Technical Specifications were issued.
Specific valu stroke times for this category of valves are not required today, and base '.ct been required previously. The reasons for this are discussed below.
The valves are in fluid lines that must remain in service for long-terr: ccre cooling following a loss-of-coolant accident (LOCA).
They do not receive.
automatic signals to operate; they are manually moved by the reactor operator after the contents of the refueling water storage tank have been pumped into the reactor coolant system and containment.
Thus, the valves are sequential!,
4 aligned manually for recirculationr by the operator following this. injec*
- n phase-at least 25 minutes after a LOCA.
In addition, valves MO 8811 MB anc Z052 A&S are normally closed with power removed.
Under these circumstances, a specific valve stroke time is inconsequential, since the time when the vaive moves is governed or dominated entirely by the time that the operator takes att*
to move the valve. On the basis of the foregoing, we find the licensee's pro-posal acceptable.
The existing requirements for valve operability and periodic testing are not altered by this change.
4 kavironmentalConsideration ide have determined that the amendment does not authorize a change to effluent t;ypes or total amounts nor an increase in power level and will not result in arty significant environmental imoact.
Having made tMs deterwination, we have further concluded that the amendment involves an action which is insignificant from the sts.ndpoint-of environmental impact and, pursuant to 10 CFR $51.5(d)(4), that an environmenta l impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection witn the issuance of this amendment.
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Conclusion Ve have concluded, based on the considerations discun ed n.~,
(il because the amendment does not involin.s signifi; ant i.
in the probability or consequences of.widents previously c:ns,.
and does not involve a significant decrease in a
,3f. ty ra p,-
amendment does not involve a significant hazards consider i-icn.
there is reasonable assurance that the health.and safety of in,=
will not be endangered by operation in the pro;osed rianc.e,
.3 n c.
i such activities will be conducted in compliance with the Cc-n s,s.
regulations and the issuance of' this amendment will riot. e inim to the cosenon defense and security or to the health and sitc'f f
the public.
i Date: April 21, 1982 Principal Contributor:
Charles Trenne11 e
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