ML20093K218
| ML20093K218 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/11/1984 |
| From: | Jens W DETROIT EDISON CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| EF2-71991, NUDOCS 8410170225 | |
| Download: ML20093K218 (12) | |
Text
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- w4 -
.e Waym H. Jern
' Vic) Presider:t Nuclear Operations Ferml-2 6400 North Dixie Highway ISOn Newport.wch,gan stce October 11, 1984 (313) sasais EF2-71991 Director of Nuclear Reactor Regulation
' Attention:
Mr.
B. J.
Youngblood, Chief Licensing Branch No. 1 U. S. Nuclear Regulatory Commission Washington, D.
C. 20555
Reference:
Fermi 2 NRC Docket No. 50-341
Subject:
Corrections to the FSAR
Dear Mr. Youngblood:
The a"tachment includes corrections to several sections of the Fi. 21 Safety Analysis Report.
The need for correction was identified during the resolution of staff comments on the Fermi 2 technical specifications.
These corrections will be incorporated in a subsequent amendment but are being provided by letter to support an NRC contractor comparison of the technical specifications with the FSAR.
In addition to these changes, Edison will be making corrections to certain figures in the FSAR which use vendor drawings as the source document.
Drawings used as source documents for FSAR figures are under frequent revision.
To account for this, it is Edison's policy to periodically update the FSAR figures with the latest revision of the design drawings.
This update is consistent with this policy.
However, since it is not entirely within Edison's ability to control the schedule of vendor drawing changes, they will be made as quickly as possible, but may not be completed prior to the review by NRC's contractor.
If you have any questions on this matter, please contact Mr.
O.K. Earle at (313) 586-4211.
Y Sincerely, hokkDO O 00 g
A
'i cc:
(All with attachments)
Mr.
P.
M.
Byron j
Mr.
D.
Hoffman J
Mr. M.
D.
Lynch Mr. M. Virgilio USNRC,_ Document Control Desk Washington,.D.C.
20555 g
y
. n.b,:
- v...-
s J.=
Mr. _ B. - J. ' Youngblood
. October 11,.1984 EF2-71991.
.Page 2 J
C bcc:
F.-E. Agosti
- L.-P.
Bregni W.
F. Colbert *
-O.
K.'Earle W.
R. Holland R.
S. Lenart
- E.
Lusis P.
A. Marquardt T.
D.
Phillips *
~
G. M. Trahey R. A. Vance A.~E. Wegele Approval-Control
- O.-K..Earle (Bethesda Office)
M.
S. Rager
- Secretary's Of fice 2 412 WCB NRR Chron File *
- With attachment A
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1 EF-2-FSAR 15 4 TABLE 6.2-1 CONTAINMENT DESIGN PARAMETERS (a) (Cont'd)
VIII., Temperature Distributions and Effects
,I (Not Applicable)
IX.
Assumptions Used in Pressure Transient Analysis A.
Feedwater valve closure time Instantaneous B.
MSIV closure time, s 3.5 C.
Scram time, s 1
D.
Liquid carryover, %
100 X.
Additional Information XI.
General Information'for the Pressure Suppression Type Containment A.
Drywell 1.
Maximum code allowable pressure, psig 62 2.
Internel design pressure, psig 56 3.
External design pressure, psig 2
54 4.
Design temperature,
'F 340 B.
Suppression pool 1.
Maxieum code allowable pressure, psig 62 2.
Internal design pressure, psig 56 3.
External design pressure, psig 2
4.
Design temperature,
- F 281 C.
Drywell free volume, including vent system 163,730 (minimum), ft3 54 D.
Suppression pool free volume, ft3 (wiav) 130,900 E.
Suppression pool water volume, ft3(,w;n) 121,080
)
54 Note:
Footnotes are listed on last page of this table.
6.2-76 Amendment 54 - March 1984
=
EF-2-FSAR TABLE 7.2-3 CHANNELS REQUIRED FOR FUNCTIONAL PERFORMANCE I
OF REACTOR PROTECTION SYSTEM:
RUN MODE
.h This table shows the normal and minimum number of channels required for the functional performance of the RPS in the RUN MODE.
The " Normal" column lists the normal number of channels per trip system.
The " Minimum" column lists the minimum number of channels per untripped trip system required to maintain functional performance.
Minimum (a,b )' l 56 Channel Description Normal Neutron Monitoring System (APRM) 2 2
Nuclear System High. Pressure 2
2 Primary Containment High Pressure
)
2
'2 RPV Low Water Level 2
2 Scram Discharge Voluae High Water Level 2
2 4
l Manual Scram 1
1 Each Main Steam Line Isolation f
f i
Valve Position
-2 :0170 2/v:1^ e 9
(~.
V Each Turbine Stop Valve Position l [ lve
-2+fvalve 2..
f i
Turbine Control Valve Fast Closure 2
2 Turbine First Stage Pressure (Bypass Channel)
(
2 2
/
tieparing testing af
- he ehemel ch:uld M tripped ahea
==a=nen.
th initi:1.i.L.
v: the== nan" i= a^t err;..ti.1 Lv t he - test:.
l (b) Nominal values given for information.
See Technical Specifi-cations for operational requirements.
56
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- tap
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7.2-27 Amendment 56 - April 1984 Iu
i EF-2-FSAR shown in Figure 7.3-2.
The controla position valvan to that during normal operation, steam line drainage is routed to the main condenser.
Upon receipt of.an HPCI initiation signal, the J
drainage path is isolated.
The water level in the steam line drain condensate pot is controlled by a level switch and a pilot i
air-operated solenoid valve which energizes to allow condensate to flow out of the pot.
During test operation, the HPCI pump disch&rge is routed to the condensate storage tank.
Two de motor-operated valves are installed in the pump discharge to the condensate storage tank pipeline.
The piping arrangement is shown in Figure 7.3-1.
The control scheme for the two valves is shown in Figure 7.3-2.
Upon receipt of an HPCI system initiation signal, the two valves close and remain closed.
The valves are interlocked to close if either i
of the suppression chamber suction valves are fully open.
Numerous indications pertinent to the operation and condition of the HPCI system are available to the main control room operator.
I Figures 7.3-1 and 7.3-2 show the various indications provided.
7.3.1.2.1.4 Redundancy and Diversity The HPCI system is actuated either by RPV low water level or by primary containment high pressure.
Both of these conditions could result from a LOCA.
The redundancy of the HPCI system initiating circuits is consistent with the design of the HPCI system.
A single failure does not prevent' activation.
4 7.3.1.2.1.5 Actuated Devices
/
All automatic valves in the HPCI system are equipped with remote manual test capability so that the entire system can be operated from the main control room.
Motor-operated valves are provided with appropriate limit switches to turn off the motors when the i
fully open or fully closed positions are reached.
Valves that are automatically closed upon either isolation or turbine trip signals are equipped with manual reset devices so that they cannot be reopened without operator action.
All essential components of the HPCI system controls operate independently of offsite ac power.
} d =To ensure hat the HPCI system can be brought to the design flow-rate within seconds from the receipt of the initiation signal, j
the following maximum operating times for essential HPCI system valves are provided by the valve operation mechanisms:
a.
HPCI turbine steam supply. valve
.20 seconds b.
HPCI pump discharge valves - 20 seconds HPCI pump minimum flow bypass valve \\- 10 seconds c.
The operating time is the time required for the valve to travel from the fully closed to the fully open position, or vice versa.
j The HPCI steam supply line inboard isolation valve and the bypass 5 81 valve around the HPCI outboard isolation valve are provided, 57 7.3-6 Amendment 58 - July 1984
/
EF-2-FSAR orrangId to scal into tha control circuitry.
Those signals must be manually reset to clear.
A timer is used in each ADS logic.
The time delay setting before actuation of the ADS is long enough that the HPCI system has time to operate, yet not so long that.the LPCI and core spray systems are unable to adequately cool the fuel if the HPCI system cannot.
56 An alarm in the main control room is activated when eithgr of the timers is timing.
Resetting the ADS initiating signals recycles the timer.
A display of the time remaining before the ADS actu-atos is available to the operator in the main control room.
7.3.1.2.2.2 Logic and Sequencing The three initiation signals used for the ADS are RPV low water level, primary containment (drywell) high pressure, and RHR and/or core spray pumps running.
All signals must be present to cause the safety / relief valves to open, as shown in Figure 7.3-3.
An RPV low water level indicates that the fuel is in danger of becoming uncovered.
The second (lower) low water level initiates the ADS.
The instrument trip settings are given in Table 7.3-2.
Primary containment high pressure indicates a breach in the nuclear system process barrier inside the drywell.
For each logic train, a permissive signal indicating LPCI or core spray pump dis-
-56 charge pressure is also required.'
Discharge pressure on either of the two LPCI pumps or two of the core spray pumps /In the sam 4'----
division is sufficient to give the permissive signal. 'This signal prevents initiation of the ADS until the low pressure ECCS's are f) operating.
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After receipt of the initi'ation signals and after a delay provided by timers, each of the solenoid pilot air valves is energized.
This allows pneumatic pressure.from the accumulator i
to act on the air cylinder operator.
The air cylinder operator holds the relief valve open.
Lights in the main control room 47 indicate when the safety / relief valve is opened.
Manual reset circuits are provided for the ADS initiation signal and primary containment high pressure signals.
By resetting these signals manually, the delay times are recycled.
The operator can use the reset pushbuttons to delay or prevent automatic opening of the relief valves if such delay or i
prevention is prudent.
l l
Control switches are available in the main control room for each safety / relief valve associated with the ADS.
The OPEN position I
is for manual safety / relief valve operation.
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7.3-12 Amendment 56 - April 1984 J
O 9
O, TABLE 7.3-5 HIGH PRESSURE COOLANT INJECTION SYSTEM:
MINIMUM NUMBERS OF TRIP CHANNELS REQUIRED FOR FUNCTIONAL PERFORMANCE, Minimum Number of Trip Channels Number of Required to Component Trip Instrument Trip Channels Maintain Punctional Affected Channel Type Provided Performance (a)
MFCI System RPV low water Level transmitter 4 pr rig 2,per untripped Initiation level
. system trip system i
WCI System Primary containment Pressure transsitter 4 r- *-9 2 per untripped Initiation high pressure
.syeeen trip system-MFCIS Turbine WCI system pump Plow indicator 1
1 discharge flow controller-WCIS Turbine RPV high water Level transmitter
\\M 1
q 1evel
^"
[%
90 f
MPCIS Turbine Turbine exhaust Preheure transmitter 2
1(b) h co diaphrage high CO W
pressurs MPCIS Turbine WCI systes pump low Pressure switch 1
1(b)
~
47 suction pressure j
Minimum Flow WCI system pump Flow switch 1
1 Bypese Valve flow a.
4 I
]
WCIS Steam Supply WCI system steam Pressure transmitter
.? r-trip k per untripped y
Valve and Suppres-supply low pressure systas trip system et sian Chamber Suction valve i
a 4
Suppression Chamber Condensate storage Level transmitter 4(c) 2 i
Suction valve tank low level and
- g suppression pool IF>
high level r1 0
D*
(a) Nominal values are given for information. See hchnical Specifications for operational requirements.
g (b) An inoperable trip channel should be placed in the untripped state.
e co (c)Two each condensate storage low, suppression pool high.
4 W
m ---
TABLE 7.3-6 AUTOMATIC DEPRESSURIZATION SYSTEM:
MINIMUM NUMBERS OF. TRIP CHANNELS REQUIRED FOR FUNCTIONAL PERFORMANCE Minimum Number of Trip Channels Number of Required to Initiating Instrument Trip Channels Maintain Functional Function Type Provided Performance (a,b)
RPV Low Water Level Level transmitter 2 per trip system 2 per untripped trip system l
Primary Containment High Pressure Pressure transmitter 2 per trip system 2 per untripped 47 trip system Time Delay Timer 1 par trip system 1 per untripped m
trip system
?
u I A*L P # '/'
/
ac Interlock (RHR or Core Spray
, Pressure transmitter
_t ; : -- ^ i, _, _ i_
-2 ;:p py p-i,; sr-ey a
M r _ - _ _ _
Pump Running)
^l 71 y
co (O
l (alone trip logic of each trip system mist be fully operable. Both an RPV law water level trip channel and a primary containment high pressure trip channel should not be inoperable in any l
one trip logic.
,E, (b) Nominal values are given for information. See 'Itchnical Specifications for operational requirements.
l47 Q.
I B
t t)
D tt I
b l
4 i
3
.l u
rs
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CD l
l e
O e
a TABLE 7.3-7 CORE SPRAY SYSTEM:
MINIMUM NUMBERS OF TRIP CH ANNELS REQUIRED FOR FUNCTIONAL PERFORMANCE Minimum Number.of Trip Channels Number of Required to Component Trip Instrumenti Trip Channels Maintain Functional Affected Channel Type Provided Performance (a)
Core Spray System RPV low water Level transmitter 4 ;__ tip 2 per untripped level 7,_'
trip system 47 Core Spray System Primary containment Pressure transmitter 4._-- ' rip 2 per untripped high pressure eye *--
trip mystem Core Spray Dis-RPV low pres-Pressure transmitter 4 s. C.g 2 per untripped charge Valves sure
^-
trip system A
_,_1
-a T
e Core Spray Sparger Core pressure Differential 1 per sparger 1 per sparger f0 Leak Detection differential pressure switch (alarm only)
(alarm only) k 00 CO>
(*) Nominal values are given for information. See Technical Specifications, for operational requirements. l47 E
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TABLE 7.3-8 LOW PRESSURE COOLANT INJECTION:
MINIMUM NUMBERS OF TRIP CHANNELS REQUIRED FOR FUNCTIONAL PERFORMANCE
~
. Minimum Number of Trip Channels i
m Number of Required to
, Component
- Triit -
,. Instrument Trip Channels
- Maintain Punctional 4
~ _, - Affect %_'~
~
ChannQl f-Typo LPCI i$itiation Provided _
' Performance (a)
, RPV low watG:,
Level transmitter _
level
, 4 ;__ ' 2 p..
2 per,untripped
'.,.--tg__.-
/ '-
.tyip pystem
(
,7 LPCI Initiatic.',,"
, Primary containment Pressure traps 8 titter 4,__
2'per untripped
// high pressure Jr a'--
rrip system
~
u t
Co"ntainment SprayI RPV low water Level transmitter 1
')IDI
~~~~
a Valves level inside
"/
/
,TT1 y
shroud
~.I s,
y-
- j '
Y Minimum Flow Bypass' LPCI pumps discharge Plow switch 10 1,32ICI'
[(
1,2(c) y Valves Iow flow
/
f (one per pumis)
LPol: In%ctica Recirculation loop Differential 4
2 4
Va % s aind break pressure transmitter g
Recirculation Loop I
a valves i
1 3
a,
.s 3
LPCI Injection RPV low pres-Pressure transmitter 4
2 Valves
~f sure n
3 Reactor Recirculation RPV low water Level transmitter 4
2 Pumps level I
~
c Com.alnment Cooling Primary containment
- s Pressure. transmitter 4
2 Valves (drywell) high Q.
pressure i
wy (a) Nominal values are given for information.
(b) An inoperable sensor should be placed in the untripped state.See Technical Specifications for operational requirements w
(c)One channel to open, 2 channels to close.
l
t F
F k
(Cont 'd )
NUCLEAR PLANTS PRINCIPAL PLANT DESIGN FEATURES COMPARISON i
TABLE 1.3-1 i
th,in 1. Hatch Reuclear Plant Brunswick Brown's Ferry Fermi 2 Unita 1 & 2 Unita 1 & 2 Cooper Unit 1 1.
Primary Containment (Cont'd)
(2) Pressure Sappression trus/ steel Torus / reinforced true/ steel trus/ steel trus/ steel weasel concrete with vessel woesel vessel Chamber steel liner
+56
+62
+56
+56
+56 (c) Pressure happression Chamber-Internal Design Pressure, poig (d) Pressure anppression
+2
+2
+1
+2
+2 Chamber-suternal Design Pressure, poig (e) Drywell-Internal Design
+56
+62
+56
+56 '
+56 ITIp Pres.ure,,ei f
(f) Drywell-External Design
+2
+2
+1
+2
+2 T@
Pressure, poig l58 w
I 3
163,730 164,100 159,000 145,430 146,240 y
W
.(g)
Drywell Free volume, it (Meh) 124,000 119,000-109,810 110,950 W
(h) Pressure suppression 3
Chamber Free Volume, it 12.1,0$0 (m'n)
- -' C ld -)
87,600 85,000 87,660 87,660 (1) Pressure suppression p
Pool tanter Volume, f t g
3 (3) submergence of Vent Pipe 4-0 4-0 4-0 4-0 3-s fD G
selow Pressure Pool l
h surface, ft-in.
F (k) Design h aperature of 281 300 281 281 281 o
Drywell
- r (1) Design haperature of 281 220 281 281 CD 1
Pressure suppression Cha h r, *r (m) Downcomer Vent Pressure 6.21 6.21 6.21 6.21 6.21 q
C H
N Loes Factor
{
(n) Break Area / Gross Vent Ares 0.019' O.02 0.019 0.019 0.019
.s.
(o) Drywell Free Volume /
1.25 1.32 1.33 1.4 1.3 i
CD Pressure Suppreeston Chamber Free Volume
?
- EF-2-FSAR e.
Indicator lights in the main control room show whether or not the explosive. valve firing circuitry
'has; continuity f.
Indicator-lights in the main _ control room show if service valve'F008 is open or closed, as shown in Figure 7.4-3
~
.g.
Indicator lights in the main control room show if the testable check P006 and F007 disk and actuator are open or closed h.
Indicator lights on the local panel show if-the manually controlled high power storage tank heater is on or off i.
Indicator lights on the local panel show if the thermostatically controlled low power storage tank heater is on or off.
The SLCS main control room annunciators annunciate whens a.
There is a loss of continuity of either explosive valve primers 4
b.
The standby liquid storage temperature becomes too hot or too cold T
+
c.
The standby liquid tank level is too high or too J
low.
7.4.1.2.5.3 Setpoints i
The SLCS has setpoints for the various instruments as follows:
a.
The loss of continuity meter is set to activate the annunciator just below trickle current that is observed when the primers of the explosive valves are new b.
The high and low standby liquid temperature switch is set to activate the annunciator at temperatures of 56l approximately 110*F and 70*F, re tively c.
The high and low standby li d storage tank level allons net.andp5344[f 4617 he annunciator when the switch is set to activat 56l volume is approximately gallons net of the storag ank capacity, respectively d.
The thermostatic controller is set to turn on the 56l heater when the standby liquid drops to approximately 75*F and to turn off the heater at 85'F.
i L
i l
7.4-10 Amendment 56 - April 1984 i
..