ML19225B825
| ML19225B825 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/22/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19225B813 | List: |
| References | |
| NUDOCS 7907260088 | |
| Download: ML19225B825 (11) | |
Text
f$pa aregk UNITED STATES NUCLEAR REGULATORY COMMISSION y
WA5m NGTON, D. C. 20555 ap s.g
/
PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER & LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING '.ICENSE Amendment No. 41 License No. NPF-i 1.
The Nuclear Regulatory Commission '. the Commission) has found that.
A.
The application for amendment b Portland General Electric Company, the City of Eugene, L Mon, and Pacific Power and Light Company (the licensee) daud June 6,1979, as supplemented June 20, 1979 complies with the standcrds and requirements of the Atomic nergy Act of 1954, as amended e
(the Act), and the Conmissir:,'s rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the amendment, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requi ements have been satisfied.
436 Jgg 70.0726 90 g g
. 2.
According~y, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph C.C.(2) of Facility License No. NPF-1 is hereby amended to read as follows:
"(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.41, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications except as noted in paragraph 2.C.(10) below."
3.
This license amendment is effective as of its date of issuance.
FOR TiiE NUCLEAR REGULATORY COMMISSION Mh A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: June 22,1979 436 7,
s u ;,
=
ATTACHMENT TO LICENSE AMENDMENT N0.41 FACILITY OPERATING LICENSE N0. NPF-1 DOCKET NO. 50-344
^
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document comoleteness.
Pages 3/4 3-15 3/4 3-21 3/4 3-22 3/4 3-26 3/4 3-29 m
5 41 m
en +
v
.x l
~
'.- ^h e-436 3,0
TABLE 3.3-3 d
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Li
?
G.
ii f d
MINIMUM TOTAL N0.
CHANNELS C'1ANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1.
SAFETY INJECTION AND FEEDWATER ISOLATION a.
'%nual Iritiation 2
1 2
1,2,3,4 18 b.
Automat Actuation 2
1 2
1,2,3,4 13 Logic c.
Containment 3
2 2
1,2,3 14 Pressure-High 0
d.
Pressuri er 3
2 2
1, 2, 3#
14 z
os Pressure - Low 5;
e.
Differential 1, 2, 3##
L, Pressure Between Steam Lines - High
._ll?}
HW N
Four Loops 3/ steam line 2/ steam line 2/ steam line 14 Operating any steam line B"
Three Loops 3/ operating 1
/ steam 2/ operating 15 i
Operating steam line line, any steam line P
operating 1-steam line
]
i.
- hi!!
2 h
a
!!L, i
,(
hih h,
l f!f f N ff I h ll f';h
!. If ;
l
]
l
]
I l
))
i TABLE 3.3-3 (Continued)
ENGINEERED SAFELY FEATURE ACTUATION SYSTEM INSTRUMENTATION a:o
!!h Y
MINIMUM E
TOTAL N0.
CHANNELS CHANNELS APPLICABLE Z
FUNCTIONAL UNIT OF C. ANNELS TO TRIP
_0PERABLE MODES ACTION
- 1 f.
Steam Flow in Two 1, 2, 3 Steam Lines-High w
Four Loops 2/ steam line 1/ steam line 1/ steam line 14 Operating any 2 steam lines
- U Three Loops 2/ operating l
/any 1/ operating 15 Operating steam line operating steam line steam line M
COINCIDENT WITH
.;q
[
EITHER N
h T
--Low-L w 1, 2, 3 avg Four Loops 1Tavg/l p
2T any 1T any 14 avg avg Operating
- Y loops 3 loops g
Three Loops 1 T,yg/
1 T
in 1T in any 15 avg avg uperating O
operating any operating two operating loop loop loops g
N h-
.ji p.
W 0
! lNEIII@lll@l!Il!l!!ll!ilil]Illif![llillllliiiIi3lli!!D]!!!!I5!ll!!W!!!!llHl!Ulllllult"lM"hlli!!l!!!}llM!lllH!!9 ?ll?""U""!lfil!!lH!!!lli!!!Wl!Wi
==
-M 2
Td.==
TABLE 3.3-3 (Continued) aY
- b. Above P-ll or P-12. demonstrate that the Minimum Channels OPERABLE requirement is met within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; operation may M
continue with the inoperable channel bypassed and one r
additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for L
surveillance testing per Specification 4.3.2.1.
M M
ACTION 17 - With less than the Minimum Channels OPERABLE, operation may s ::
= m~
continue provided the containment ventilation valves R
are maintained closed.
- x ACTION 18 - With the number of OPERABLE Channels one less than the Total s
E Number of Channels, restore the inoperable channel to OPERABI E status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following g$
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
==~
=
a; ENGINEERED SAFETY FEATURES INTERLOCKS a
5_=
DESIGNATION CONDITION AND SETPOINT FUNCTION P-ll With 2 of 3 pressurizer Prevents or defeats k
pressure channels > 1925 manual block of safety Es E
psig.
injection actuation on low pressurizer pressure.
h P-12 With 3 of 4 T channels Prevents or defeats manual block of safety
[
> 553 F.
injection actuation high g
steam line flow and low gi steam line pressure.
g 55 With 2 of 4 T channels Allows manual block of 53 safety injection actua-EE
< 553 F*
tion on high steam line t
flow and Icw steam line J
pressure.
Causes steam
=r line isolation on high 3
steam flow.
Affects
.E steam dump blocks.
Q Ast E=-
.C
'IE5 EE r~
E E5 NE Amendment No. 4hjf blJ
'E TROJAN-UNIT 1 3/
(
7 1-
-p a
.e.
IIbi NI!
- i$
E!.!:
g TABLE 3.3-4 e
m ui;[
g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION YRIP SETPOINTS E
i E
Z r;.1CTIONAl UNIT TRIP SETPOINT ALLOWASLE VALUES 40!
1.
SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION in i m
a..
Manual Initiation Not Applicable Not Applicable T ll "i
b.
Automatic Actuation Logic Not Applicable Not Applicable c.
Containment Pressure--High 1 5 psig 1 5.5 psig
- o jiiiii
> 1755 psig d.
Pressurizer Pressure--Low
> 1765 psia q;
' ]ih e.
Differential Pressure
< 100 psi
< 112 psi m
ii
)
BetwJen Steam Lines--High
- q!!!
[
f.
Steam Flow in Two Steam Lines--
1 A function defined as 1 A function defined as High Coincident with T
--Low-Low follows:
40% of full steam follows: 44% of full N
orSteamLinePressurey@ow flow between 0% and 20% load steam low between 07,and a
ih and then increasing linearly 20% loa 6 and then increasing i!;
to 110% of full stcam flow 1incarly to 111.5% of full jg at full load full steam flow at full load n
T
> 553 F T
> 551 F jqjj y
g avg avg
- l g
> 600 psig steam line
> 580 psig steam line
.f M-pressure pressure
[h u
i:
N e
oun h!i'
]
inin
.I!!
ll! g we ominnp,wnnenpnenpun,r -:w:*nu mon.mn:,ninn c: r r -os'n nor~n on""'nenonumu Hh "r
TABLE 3.3-5 1~ _
. _ =
M ENGINEERED SAFET( FEATURES RESPONSE TIllES M
w INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS eS 1.
Mar.ual g.
a.
Safety Injection (ECCS)
Not Applicable
[
Feedwater Isolation Not Applicable 3
Not ',pplicable Eg Containment Isolation Not Applicable Containment Ventilation Isolation Not Applicable j
5 Auxiliary Feedwater System Not Ap.nlicable 2
Service Water System Not Applicaole n~ -
M Emergency Fan Coolers Not Applic.ible i
T b.
Containment Spray Not Applicable
- G Si' c.
Containment Isolation Not Applicable EEn F5is d.
Steam Line Isolation Not Applicable
=+
=%
2.
Containment Pressure-High
&M a.
Safety Injection (ECCS) 1 27.0*
.= 5 b.
Reactor Trip (from SI)
~
3.0 M
55 c.
Feedwater_ Isolation 1
8.0 g
555 d.
Containment Isolation i 18.0#/28.0##
-g MS c.
Containment Ventilation Isolation Not Applicatie
.=_
f.
Aux!liary Feedwater Pumps not applicable gh
$f g.
Service Water System i 13.0#/48.0##
g=g
"==
h.
Emergency Fan Coolers
< 10.0#/49.0##
EEE$
E-b
==
TROJAN-UNIT 1 3/4 3-25
=
436 315 P
'LZ
' ~ ~ ~
- dC" 5. '..... 2".
.~ S
?-~~-'~~"
~ ~ '
~_
L
' ~--..:.
- 35'.T.bE" $[_U
~".._[
dC: %- -
~
..._. ; _D;f
_=:
TABLE 3.3-5 (Continued) s-T ENGINEERED SAFETY FEATURES RESPONSE TIMES
~i~
=.
INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS 3.
Pressurizer Pressure-Low
_z a.
Safety Injection (ECCS) 1 27.0*/13.0#
.?
b.
Reactor Trip (from SI) 1 3.0 k
c.
Feedwater Isolation 1 8.0 d.
Containment Isolation
< 18.0#
e.
Containment Ventilation Isolation "ot Applicable h-f.
Auxiliary Feedwater Pumps Not Applicable 6
c.
Service Water System
< 48.0*/13.03 r-h.
Emergency Fan Coolers 1 10.0#/49.G##
5 EE:
4.
Differential Pressure Between Steam Lines-High y
a.
Safety Injection (ECCS) 1 13.0#/23.0##
g b.
Reactor Trip (from SI) 1 3.0
= =.
c.
Feedwater Isolation 1 8.0 34 d.
Containment Isolation 1 18.0#/26.0##
F e.
Containment Ventilation Isolation Not Applicable
{=f f.
Auxiliary Feadwater Pumps Not Applicable g
g.
Service Water Systems 1 13.0#/48.0f#
g h.
Emergency Fan Coolers 1 10.0#/49.0##
5#
}E 5.
Steam Flow in Two Steam Lines - High Coh :ident
[h with T
--' W-'U" avg a.
Safety Injection (ECCS) 1 15.0#/25.0!#
=-
b.
Reactor Trip (from SI) 1 5.0
=
c.
Feedwater Isolation
-< 10.0
.e
~
te=-
d.
vontainment Isolation 1 20.0#/30.0##
s]=:,
e.
Containment Ventilation Isolation
!!ot Applicable g
f.
Auxiliary Feedwater Pumps Mot Applicable 9
Service Water System i 15.0#/50.0##
gy h.
Steam Line Isolation i 10.0 i.
Emergency Fan Coolers
-< 12.0#/5?.0##
5
=
et
=
TROJAN-UNIT 1 3/4 3-26 Amendment f'o. 41
'~
436 316 s.e-...
.. ~...
.;..~.
......i.
'... ~... ~... ~.
^*-
y - --- -
TABLE 4.3-2 yxy ENGINEERED SAFETY FFATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS z
iih E
C CHANNEL MODES IN WHICH j;ii
,]
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 1.
SAFETY INJECTION AND H
FEEDWATER ISOLATION a.
Manual Initiation N.A.
f!. A.
ft(1) 1, 2, 3, 4 L
b.
Automatic Actuation Logic f!. A.
ff. A.
M(2) 1, 2, 3, 4 c.
Containment Pressure-High S
R M(3) 1, 2. 3 d.
Pressurizer Pressure--Low S
R M
1,2,3 y
e.
Differential Pressure S
R M
1,2,3
.; 3 g
Between Steam Lines--High u
cd f.
Steam Flow in Two Steam S
R fi 1,2,3 ll !
Lines--High Coinc.aent with T
--Low or Steam Line h!U P9Esure--Law g
2.
fianual Initiation f!. A.
N.A.
M(1) 1, 2, 3, 4 g
5 b.
Automatic Actuation Logi'-
N.A.
f!. A.
fi(2) 1, 2, 3, 4
=
c.
Containment Premore -;11gh-S R
M(3) 1, 2, 3 l.
High e
N!!i ;
o h@lpi]ljl!Ji !I!!!J!N!Uf y[glll{}lllggll@lQ]Ql[llllg[gjgl]lyql]llg l} Q ]j]llll]lplyj]jp j;gl g l{ll{llllpi$l:illll g hll1Jg
a g TABLE 4.3-2 (Continued) o ENGINEERED SAFETY FEATURE ACTUATION SYSTEM ti@TRUMENTATION lip. SURVEILLANCE REQUIRE' TENTS U CH."NNEL MODES IN WHICH j;ji. CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE i" ~ iJ , FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 3. CONTAINMENT ISOLATION a. Containment Isolation
- 1) Manual N.A.
N.A. M(1) 1, 2, 3, 4 2) From Safety Injection N.A. N.A. M(2) 1, 2, 3, 4 Automatic Actuation Logic j b. Containment Ventilation Isolatien {
- 1) Manual N.A.
N.A M(1) 1, 2, 3, 4 O
- 2) Containment Radio-S R
1, 2, 3, 4 activity-High ni ?! A D4 O ii U ~ CO h h0*r"n"ogglggqigggggjglglglglpgpnysinnennen> r >m 'm " ' aninsu!!Luw:-
- i e -
m
- p. -
ol: I + vont i,uin r .}}