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{{#Wiki_filter:Final Submittal | |||
(Blue Paper) | |||
FINAL RO/SRO WRITTEN | |||
EXAMINATION REFERENCES | |||
NORTH ANNA JUNE 2008 EXAM | |||
05000338/2008301 & 05000339/2008301 | |||
GENERIC FUNDAMENTALS EXAMINATION | |||
EOUATIONS AND CONVERSIONS HANDOUT SHEET | |||
EOUATIONS | |||
p = Po 10SUR(I) | |||
P = Poe(l/t) | |||
Q = rh~h | |||
Q = UA~T | |||
. * 3 | |||
Q oc mNal Cire | |||
~T oc rh~al Cire 11M = CR/CRx | |||
K"ff = 1/(1 - p) | |||
P = (K"ff - 1)/Kcff F=PA | |||
SUR = 26.06/'t ril = pAY | |||
~Cff - P WPump = ~Pu | |||
t =~-- | |||
A.cff P | |||
E=IR | |||
~. ~eff | |||
p=-+--- | |||
t + A.cff 't: Thermal Efficiency = Net Work OutlEnergy In | |||
g(Z2-Z\) + (V/_V\2) +U(P 2 -P 1)+(U2 -u\)+(q-w)=0 | |||
&: 2&: | |||
A.eff = 0.1 sec* 1 (for small positive p) | |||
&: = 32.2 1bm-ftllbf-sec2 | |||
2 2 | |||
DRW oc <Pti/<Pavg | |||
CONVERSIONS | |||
I Mw = 3.41 X 106 Btu/hr 1 Curie = 3.7 x 10\0 dps | |||
1 hp = 2.54 x 103 Btu/hr 1 kg = 2.21 Ibm | |||
1 Btu = 778 ft-Ibf 1 gal walcr = 8.35 Ibm | |||
°C = (5/9)CF - 32) 1 Wwater = 7.48 gal | |||
of = (9/5)CC) + 32 | |||
-3- | |||
._-- NUCLEAR DESIGN INFORMATION PornAL ._.. | |||
RTS Instrumentation | |||
3.3.1 | |||
3.3 INSTRUMENTATION | |||
3.3.1 Reactor Trip System (RTS) Instrumentation | |||
LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 | |||
shall be OPERABLE. | |||
APPLICABILITY: According to Table 3.3.1-1. | |||
ACTIONS | |||
- - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - | |||
Separate Condition entry is allowed for each Function. | |||
CONDITION REQUIRED ACTION COMPLETION TIME | |||
A. One or more Functions A.1 Enter the Condition Immediately | |||
with one or more referenced in | |||
required channels or Table 3.3.1-1 for the | |||
trains inoperable. channel(s) or | |||
train(s). | |||
B. One Manual Reactor B.1 Restore channel to 48 hours | |||
Trip channel OPERABLE status. | |||
inoperable. | |||
OR | |||
B.2 Be in MODE 3. 54 hours | |||
C. One channel or train C.1 Restore channel or 48 hours | |||
inoperable. train to OPERABLE | |||
status. | |||
-OR | |||
C.2.1 Initiate action to 48 hours | |||
fully insert all rods. | |||
AND (continued) | |||
North Anna Units 1 and 2 3.3.1-1 Amendment 231/212 | |||
- NUCLEI~R DESIGN INFORMA nON POR rAL-- | |||
RTS Instrumentation | |||
3.3.1 | |||
ACTIONS | |||
CONDITION REQUIRED ACTION COMPLETION TIME | |||
C. (continued) | |||
}} | }} |
Latest revision as of 14:38, 14 November 2019
ML082390023 | |
Person / Time | |
---|---|
Site: | North Anna |
Issue date: | 08/22/2008 |
From: | NRC/RGN-II |
To: | |
References | |
50-338/08-301, 50-339/08-301 | |
Download: ML082390023 (25) | |
See also: IR 05000338/2008301
Text
Final Submittal
(Blue Paper)
FINAL RO/SRO WRITTEN
EXAMINATION REFERENCES
NORTH ANNA JUNE 2008 EXAM
05000338/2008301 & 05000339/2008301
GENERIC FUNDAMENTALS EXAMINATION
EOUATIONS AND CONVERSIONS HANDOUT SHEET
EOUATIONS
p = Po 10SUR(I)
P = Poe(l/t)
Q = rh~h
Q = UA~T
. * 3
Q oc mNal Cire
~T oc rh~al Cire 11M = CR/CRx
K"ff = 1/(1 - p)
P = (K"ff - 1)/Kcff F=PA
SUR = 26.06/'t ril = pAY
~Cff - P WPump = ~Pu
t =~--
A.cff P
E=IR
~. ~eff
p=-+---
t + A.cff 't: Thermal Efficiency = Net Work OutlEnergy In
g(Z2-Z\) + (V/_V\2) +U(P 2 -P 1)+(U2 -u\)+(q-w)=0
&: 2&:
A.eff = 0.1 sec* 1 (for small positive p)
&: = 32.2 1bm-ftllbf-sec2
2 2
DRW oc <Pti/<Pavg
CONVERSIONS
I Mw = 3.41 X 106 Btu/hr 1 Curie = 3.7 x 10\0 dps
1 hp = 2.54 x 103 Btu/hr 1 kg = 2.21 Ibm
1 Btu = 778 ft-Ibf 1 gal walcr = 8.35 Ibm
°C = (5/9)CF - 32) 1 Wwater = 7.48 gal
of = (9/5)CC) + 32
-3-
._-- NUCLEAR DESIGN INFORMATION PornAL ._..
RTS Instrumentation
3.3.1
3.3 INSTRUMENTATION
3.3.1 Reactor Trip System (RTS) Instrumentation
LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1
shall be OPERABLE.
APPLICABILITY: According to Table 3.3.1-1.
ACTIONS
- - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - -
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME
A. One or more Functions A.1 Enter the Condition Immediately
with one or more referenced in
required channels or Table 3.3.1-1 for the
trains inoperable. channel(s) or
train(s).
B. One Manual Reactor B.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
Trip channel OPERABLE status.
B.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />
C. One channel or train C.1 Restore channel or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
inoperable. train to OPERABLE
status.
-OR
C.2.1 Initiate action to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
fully insert all rods.
AND (continued)
North Anna Units 1 and 2 3.3.1-1 Amendment 231/212
- NUCLEI~R DESIGN INFORMA nON POR rAL--
RTS Instrumentation
3.3.1
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
C. (continued) C.2.2 Place the Rod Control 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />
System in a condition
incapable of rod
withdrawal.
D. One Power Range ------------NOTE-------------
Neutron Flux-High The inoperable channel may be
channel inoperable. bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
for surveillance testing and
setpoint adjustment of other
channels.
0.1.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
AND
0.1.2 Reduce THERMAL POWER 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />
to :::; 75% RTP.
0.2.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
AND
NOTE-----------
Only required to be performed
when the Power Range Neutron
Flux input to QPTR is
0.2.2 Perform SR 3.2.4.2. Once per
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
0.3 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />
North Anna Units 1 and 2 3.3.1-2 Amendment 231/212
- NUCLEAR DESIGN INFORMATION PORTAL-
RTS Instrumentation
3.3.1
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
E. One channel ------------NOTE-------------
inoperable. The inoperable channel may be
bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
for surveillance testing of
other channels.
E.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
E.2 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />
F. One Intermediate Range F.1 Reduce THERMAL POWER 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
Neutron Flux channel to < P-6.
F.2 Increase THERMAL POWER 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
to > P-10.
G. Two Intermediate Range ------------NOTE-------------
Neutron Flux channels Limited plant cool down or
inoperable. boron dilution is allowed
provided the change is
accounted for in the
calculated SDM.
G.1 Suspend operations Inmediately
involving positive
reactivity additions.
AND
G.2 Reduce THERMAL POWER 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
to < P-6.
North Anna Units 1 and 2 3.3.1-3 Amendment 231/212
-- NUCLEAR DESIGN INFORMATION PORTAL ---
RTS Instrumentation
3.3.1
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
H. One Source Range ------------NOTE-------------
Neutron Flux channel Limited plant cool down or
inoperable. boron dilution is allowed
provided the change is
accounted for in the
calculated SDM.
H.l Suspend operations Inmediately
involving positive
reactivity additions.
1. Two Source Range 1.1 Open Reactor Trip Immediately
Neutron Flux channels Breakers (RTBs).
J. One Source Range J.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
Neutron Flux channel OPERABLE status.
-OR
J.2.1 Initiate action to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
fully insert all rods.
AND
J.2.2 Place the Rod Control 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />
System in a condition
incapable of rod
withdrawal.
North Anna Units 1 and 2 3.3.1-4 Amendment 231/212
--- NUCLEAR DESIGN INFORMATION PORTAL--
RTS Instrumentation
3.3.1
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
K. Required Source Range ------------NOTE-------------
Neutron Flux channel Plant temperature changes are
inoperable. allowed provided the
temperature change is
accounted for in the
calculated SDM.
K.1 Suspend operations Irrrnediately
involving positive
reactivity additions.
AND
K.2 Perform SR 3.1.1.1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
AND
Once per
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
thereafter
L. One channel ------------NOTE-------------
inoperable. The inoperable channel may be
bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
for surveillance testing of
other channels.
L.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
L.2 Reduce THERMAL POWER 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />
to < P-7.
North Anna Units 1 and 2 3.3.1-5 Amendment 231/212
- NUCLEAR DESIGN INFORMATION PORTAL--
RTS Instrumentation
3.3.1
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
M. One Reactor Coolant ------------NOTE-------------
Pump Breaker Position The inoperable channel may be
channel inoperable. bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
for surveillance testing of
other channels.
M.1 Restore channel to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
OPERABLE status.
-OR
M.2 Reduce THERMAL POWER 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />
to < P-7.
N. One Turbine Trip ------------NOTE-------------
channel inoperable. The inoperable channel may be
bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
for surveillance testing of
other channels.
N.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
N.2 Reduce THERMAL POWER 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br />
to < P-8.
O. One train inoperable. ------------NOTE-------------
One train may be bypassed for
up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for
surveillance testing provided
the other train is OPERABLE.
0.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
OPERABLE status.
0.2 Be in MODE 3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />
North Anna Units 1 and 2 3.3.1-6 Amendment 231/212
_._- NUCLEAR DESIGN INFORMATION PORTAL-
RTS Instrumentation
3.3.1
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
P. One RTB train ------------NOTES------------
inoperable. 1. One train 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
surveillance testing,
provided the other train
is OPERABLE.
2. One RTB 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
maintenance on
undervo1tage or shunt trip
mechanisms, provided the
other train is OPERABLE.
3. One RTB train may be
bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
for concurrent
surveillance testing of
the RTB and automatic trip
logic, provided the other
train is OPERABLE.
P.1 Restore train to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
OPERABLE status.
P.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />
Q. One or more channels Q.l Verify interlock is in 1 hour
inoperable. required state for
existing unit
conditions.
Q.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />
North Anna Units 1 and 2 3.3.1-7 Amendment 231/212
--- NUCLEAR DESIGN INFORMATION PORTAL-
RTS Instrumentation
3.3.1
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
R. One or more channels R.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
inoperable. required state for
existing unit
conditions.
R.2 Be in MODE 2. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />
S. One trip mechanism S.l Restore inoperable 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
inoperable for one trip mechanism to
RTB. OPERABLE status.
-OR
S.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />
SURVEILLANCE REQUIREMENTS
- - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - -
Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.
SURVEILLANCE FREQUENCY
SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
SR 3.3.1.2 -------------------NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
after THERMAL POWER is ~ 15% RTP.
Compare results of calorimetric heat 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
balance calculation to power range channel
output. Adjust power range output if
calorimetric heat balance calculation
result exceeds power range channel output
by more than +2% RTP.
North Anna Units 1 and 2 3.3.1-8 Amendment 231/212
--- NUCLEAR DESIGN INFORMAnON PORTAL--
RTS Instrumentation
3.3.1
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
SR 3.3.1. 3 -------------------NOTE--------------------
Not required to be performed until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
after THERMAL POWER is ~ 15% RTP.
Compare results of the incore detector 31 effective
measurements to Nuclear Instrumentation full power days
System (NIS) AFD. Adjust NIS channel if (EFPD)
absolute difference is ~ 3%.
SR 3.3.1.4 -------------------NOTE--------------------
This Surveillance must be performed on the
reactor trip bypass breaker immediately
after placing the bypass breaker in
service.
Perform TADOT. 31 days on a
STAGGERED TEST
BASIS
SR 3.3.1. 5 Perform ACTUATION LOGIC TEST. 31 days on a
STAGGERED TEST
BASIS
SR 3.3.1.6 -------------------NOTE--------------------
Verification of setpoint is not required.
Perform TADOT. 92 days
SR 3.3.1. 7 -------------------NOTE-------------------
Not required to be performed for source
range instrumentation prior to entering
MODE 3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after
entry into MODE 3.
Perform COT. 92 days
North Anna Units 1 and 2 3.3.1-9 Amendment 231/212
- NUCLEAR DESIGN INFORMATION PORTAL-
RTS Instrumentation
3.3.1
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
SR 3.3.1.8 -------------------NOTE-------------------- -----NOTE-----
This Surveillance shall include Only required
verification that interlocks P-6 and P-10 when not
are in their required state for existing performed wi thi n
unit conditions. previous 92 days
Perform COT. Pri or to reactor
startup
AND
Four hours after
reducing power
below P-6 for
source range
instrumentation
AND
Twelve hours
after reducing
power below P-10
for power and
intermediate
range
instrumentation
AND
Once per 92 days
thereafter
SR 3.3.1. 9 -------------------NOTES-------------------
1. Adjust NIS channel if absolute
difference ~ 3%.
2. Not required to be performed until
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after THERMAL POWER is
~ 50% RTP.
Compare results of the excore channels to 92 EFPD
incore detector measurements.
North Anna Units 1 and 2 3.3.1-10 Amendment 231/212
._- NUCLEAR DESIGN INFORMATION PORTAL--
RTS Instrumentation
3.3.1
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
SR 3.3.1.10 -------------------NOTE--------------------
This Surveillance shall include
verification that the time constants are
adjusted to the prescribed values.
Perform CHANNEL CALIBRATION. 18 months
SR 3.3.1.11 -------------------NOTE--------------------
Neutron detectors are excluded from CHANNEL
CALIBRATION.
Perform CHANNEL CALIBRATION. 18 months
SR 3.3.1.12 Perform CHANNEL CALIBRATION. 18 months
SR 3.3.1.13 Perform COT. 18 months
SR 3.3.1.14 -------------------NOTE--------------------
Verification of setpoint is not required.
Perform TADOT. 18 months
SR 3.3.1.15 -------------------NOTE--------------------
Verification of setpoint is not required.
Perform TADOT. Prior to
exceeding the
P-8 interlock
whenever the
unit has been in
MODE 3. if not
performed wi thi n
the previous
31 days
North Anna Units 1 and 2 3.3.1-11 Amendment 231/212
.- NUCLEAR DESIGN INFORMATION PORTAL--
RTS Instrumentation
3.3.1
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
SR 3.3.1.16 -------------------NOTE--------------------
Neutron detectors are excluded from
response time testing.
Verify RTS RESPONSE TIME is within limits. 18 months on a
STAGGERED TEST
BASIS
North Anna Units 1 and 2 3.3.1-12 Amendment 231/212
-- NUCLEAR DESIGN INFORMATION PORTAL-
RTS Instrumentation
3.3.1
Table 3.3.1-1 (page 1 of 5)
Reactor Trip System Instrumentation
APPLICABLE MODES
OR OTHER
SPECIFIED REQUIRED SURVEILLANCE
FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE
1. Manual Reactor Trip I, 2 2 B SR 3.3.1.14 NA
3(a), 4(a), 5(a) 2 C SR 3.3.1.14 NA
2. Power Range Neutron Flux
a. High I, 2 4 D SR 3.3.1.1 S 110% RTP
SR 3.3.1. 7
SR 3.3.1.11
SR 3.3.1.16
b. Low 4 E SR 3.3.1.1 S 26% RTP
SR 3.3.1.11
SR 3.3.1.16
3. Power Range Neutron Flux Rate
a. High Positive Rate I, 2 4 E SR 3.3.1.7 S 5.5% RTP
SR 3.3.1.11 with time
constant
~ 2 sec
b. High Negative Rate I, 2 4 E SR 3.3.1. 7 S 5.5% RTP
SR 3.3.1.11 with time
SR 3.3.1.16 constant
~ 2 sec
4. Intermediate Range Neutron Flux 1(b), 2(c) 2 F, G SR 3.3.1.1 S 40% RTP
SR 3.3.1.11
5. Source Range Neutron Flux 2(d) 2 H, I SR 3.3.1.1 S 1. 3 E5 cps
SR 3.3.1.11
SR 3.3.1.16
2 I, J SR 3.3.1.1 S 1.3 E5 cps
SR 3.3.1. 7
SR 3.3.1.11
SR 3.3.1.16
K SR 3.3.1.1 NA
SR 3.3.1.11
(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.
(b) Below the P-I0 (Power Range Neutron Flux) interlocks.
(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks.
(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.
(e) With the Rod Control System incapable of rod withdrawal. In this condition, source range Function does
not provide reactor trip but does provide indication.
North Anna Units 1 and 2 3.3.1-13 Amendment 231/212
...- NUCLEAR DESIGN INFORMATION PORTAL -
RTS Instrumentation
3.3.1
Table 3.3.1-1 (page 2 of 5)
Reactor Trip System Instrumentation
APPLICABLE MODES
OR OTHER
SPECIFIED REQUIRED SURVEILLANCE
FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE
6. Overtemperature ~T I, 2 3 E SR 3.3.1.1 Refer to
SR 3.3.1.3 Note 1 (Page
SR 3.3.1. 7 3.3.1-16)
SR 3.3.1. 9
SR 3.3.1.12
SR 3.3.1.16
7. Overpower ~T I, 2 3 E SR 3.3.1.1 Refer to
SR 3.3.1. 7 Note 2 (Page
SR 3.3.1.12 3.3.1-17)
8. Pressurizer Pressure
a. Low 3 L SR 3.3.1.1 ~ 1860 psig
SR 3.3.1. 7
SR 3.3.1.10
SR 3.3.1.16
b. High I, 2 3 E SR 3.3.1.1 ~ 2370 psig
SR 3.3.1.10
SR 3.3.1.16
9. Pressurizer Water Level-High 3 L SR 3.3.1.1 ~ 93%
SR 3.3.1. 7
SR 3.3.1.10
SR 3.3.1.16
10. Reactor Coolant Flow-Low 3 per L SR 3.3.1.1 ~ 89%
loop SR 3.3.1. 7
SR 3.3.1.10
SR 3.3.1.16
11. Reactor Coolant Pump (RCP) 1 per M SR 3.3.1.14 NA
Breaker Position RCP
12. Undervoltage RCPs 1 per L SR 3.3.1.6 ~ 2870 V
bus SR 3.3.1.10
SR 3.3.1.16
13. Underfrequency RCPs 1 per L SR 3.3. 1. 6 (g) ~ 56 Hz
bus SR 3.3.1.10
SR 3.3.1.16
14. Steam Generator (SG) Water I, 2 3 per SG E SR 3.3.1.1 ~ 17%
Level-Low Low SR 3.3.1. 7
SR 3.3.1.10
SR 3.3.1.16
(f) Above the P-7 (Low Power Reactor Trips Block) interlock.
(g) Required to be performed for Unit 2 only.
North Anna Units 1 and 2 3.3.1-14 Amendment 231/212
-- NUCLEAR DESIGN INFORMA nON PORTAL-
RTS Instrumentation
3.3.1
Table 3.3.1-1 (page 3 of 5)
Reactor Trip System Instrumentation
APPLICABLE MODES
OR OTHER
SPECIFIED REQUIRED SURVEILLANCE
FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE
15. S6 Water Level-Low I, 2 2 per S6 E SR 3.3.1.1 ~ 24%
SR 3.3.1.10
Coincident with Steam I, 2 2 per S6 E SR 3.3.1.1 $ 42.5% full
Flow/Feedwater Flow Mismatch SR 3.3.1.7 steam flow at
16. Turbine Trip
a. Low Auto Stop Oil Pressure 1(h) 3 N SR 3.3.1.10 ~ 40 psig
SR 3.3.1.15
b. Turbine Stop Valve Closure 1(h) 4 N SR 3.3.1.10 ~ 0% open
SR 3.3.1.15
17. Safety Injection (SI) Input I, 2 2 trains 0 SR 3.3.1.14 NA
from Engineered Safety Feature
Actuation System (ESFAS)
18. Reactor Trip System Interlocks
a. Intermediate Range Neutron 2(d) 2 Q SR 3.3.1.11 ~ 3E-11 amp
Flux, P-6 SR 3.3.1.13
b. Low Power Reactor Trips 1 per R SR 3.3.1.5 NA
Block, P-7 train
c. Power Range Neutron Flux, 4 R SR 3.3.1.11 $ 31% RTP
P-8 SR 3.3.1.13
d. Power Range Neutron Flux, I, 2 4 Q SR 3.3.1.11 ~ 7% RTP
e. Turbine Impulse Pressure, 2 R SR 3.3.1.10 $ 11% turbi ne
P-13 SR 3.3.1.13 power
19. Reactor Trip Breakers(i) I, 2 2 trains P SR 3.3.1.4 NA
3(a), 4(a), 5(a) 2 trains C SR 3.3.1.4 NA
20. Reactor Trip Breaker I, 2 1 each S SR 3.3.1.4 NA
Undervoltage and Shunt Trip per RTB
Mechanisms
3(a) * 4(a) , 5(a) 1 each C SR 3.3.1.4 NA
per RTB
21. Automatic Trip Logic I, 2 2 trains 0 SR 3.3.1.5 NA
3(a), 4(a) , 5(a) 2 trains C SR 3.3.1.5 NA
(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.
(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.
(h) Above the P-8 (Power Range Neutron Flux) interlock.
(i) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.
North Anna Units 1 and 2 3.3.1-15 Amendment 231/212
-- NUCLEAR DESIGN INFORMATION PORTAL-
RTS Instrumentation
3.3.1
Table 3.3.1-1 (page 4 of 5)
Reactor Trip System Instrumentation
Note 1: Overtemperature ~T
The Overtemperature ~T Function Allowable Value shall not exceed the
following nominal trip setpoint by more than 2.0% of ~T span.
Where: ~T is measured RCS ~T, OF.
~To is the indicated ~T at RTP, OF.
s is the Laplace transform operator, sec-I.
T is the measured RCS average temperature, OF.
T is the nominal Tavg at RTP, S [*]OF.
I
P is the measured pressurizer pressure, psig
pi is the nominal RCS operating pressure, ~ [*] psig
KI S [*] K2 ~ [*];oF K3 ~ [*]/psig
'ti ~ [*] sec 't2 S [*] sec
f 1 (~I) = [*] {[*] - (qt - qb)} when qt - qb < [*] % RTP
0 when [*]% RTP S qt - qb S [*] % RTP
[*] {(qt - qb) - [*]} when qt - qb > [*]% RTP
Where qt and qb are percent RTP in the upper and lower halves
of the core, respectively, and qt + qb is the total THERMAL
POWER in percent RTP.
The values denoted with [*] are specified in the COLR.
North Anna Units 1 and 2 3.3.1-16 Amendment 245/226
._- NUCLEAR DESIGN INFORMATION PORTAL ---
RTS Instrumentation
3.3.1
Table 3.3.1-1 (page 5 of 5)
Reactor Trip System Instrumentation
Note 2: Overpower .1T
The Overpower .1T Function Allowable Value shall not exceed the following
nominal trip setpoint by more than 2% of .1T span.
Where: .1T is measured Res .1T, of .
.1To is the indicated .1T at RTP, OF.
s is the Laplace transform operator, sec-i.
T is the measured RCS average temperature, OF.
T is the nominal Tavg at RTP, S [*]OF.
I
K4 S [*]
Ks ~ [*] rF for i ncreas i ng Tavg K6 ~ [*]/oF when T > TI
[*] rF for decreas i ng Tavg [*]/oF when T S T I
The values denoted with [*] are specified in the COLR.
North Anna Units 1 and 2 3.3.1-17 Amendment 231/212
-. NUCLEAR DESIGN INFORMATION PORTAL -
Spent Fuel Pool Storage
3.7.18
45000
40000 ,/
35000 /
30000 / J
s
i
~
!. 25000 V /
V
1//
Q.
.== I
/
c: Acceptable Conditionally
aI Acceptable
- SE 20000
J /
Gi
~
=
15000 /I /
/
I Unacceptable I
10000 I /
V
5000
/ V
/
o
1.4
/ 1.8
/ 2.2 2.6 3 3.4 3.8 4.2 4.6
Initial U-235 Enrichment (nominal w/o)
Acceptable: Acceptable for storage in non-matrix location or low reactivity location in matrix
configuration. May also be placed in high reactivity locations in matrix configuration.
Conditionally Acceptable: Acceptable for storage in non-matrix location, but must be placed
in high reactivity location if stored in matrix configuration.
Unacceptable: Must be stored in high reactivity location in matrix configuration. Surry spent
fuel must be stored in high reactivity locations in a matrix.
Figure 3.7.18-1 (page 1 of 1)
Burnup Credit Requirements
North Anna Units 1 and 2 3.7.18-3 Amendments 231/212
- NUCLEAR DESIGN INFORMATION PORTAL-
Inverters-Operating
3.8.7
3.8 ELECTRICAL POWER SYSTEMS
3.8.7 Inverters-Operating
LCO 3.8.7 The Train H and Train J inverters shall be OPERABLE.
- - - - - - - - - - - - NOTE - - - - - - - - - - - -
One inverter may be disconnected from its associated DC bus
for ~ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform an equalizing charge on its
associated battery. provided:
a. The associated AC vital bus is energized from its constant
voltage source transformer; and
b. All other AC vital buses are energized from their
associated OPERABLE inverters.
APPLICABILITY: MODES 1. 2. 3. and 4.
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
A. One inverter A.1 ---------NOTE--------
inoperable. Enter applicable
Conditions and
Required Actions of
"Distribution
Systems-operating"
with any vital bus
de-energized.
Restore inverter to 7 days
OPERABLE status.
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
associated Completion
Time not met. -AND
B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
North Anna Units 1 and 2 3.8.7-1 Amendments 235/217
-- NUCLEAR DESIGN INfORMATION PORTAL-
Inverters-Operating
3.8.7
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
SR 3.8.7.1 Verify correct inverter voltage and 7 days
alignment to required AC vital buses.
North Anna Units 1 and 2 3.8.7-2 Amendments 231/212
_. NUCLEAR DESIGN INFORMAnON POR fAL --
Distribution Systems-Operating
3.8.9
3.8 ELECTRICAL POWER SYSTEMS*
3.8.9 Distribution Systems-Operating
LCO 3.8.9 The following distribution subsystems shall be OPERABLE:
a. The Train H and Train J AC, DC, and AC vital buses; and
b. One AC and DC bus on the other unit for each required
shared component.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
A. One or more A.l ---------NOTE--------
LCO 3.8.9.a AC Enter applicable
electrical power Conditions and
distribution Required Actions of
inoperable. Sources-Operating, II
for DC train(s) made
inoperable by
distribution
subsystem(s).
Restore AC electrical 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
power distribution
subsystem(s) to AND
OPERABLE status.
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from
discovery of
fail ure to meet
LCO
North Anna Units 1 and 2 3.8.9-1 Amendments 231/212
- NUCLEAR DESIGN INFOHMATION PORTAL-
Distribution Systems-Operating
3.8.9
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
B. One or more B.1 Restore AC vital bus 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
LCO 3.8.9.a AC vital subsystem(s} to
bus(es} inoperable. OPERABLE status. AND
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from
discovery of
fail ure to meet
LCO
C. One or more C.1 Restore DC electrical 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
LCO 3.8.9.a DC power distribution
electrical power subsystem(s} to AND
distribution OPERABLE status.
subsystem(s} 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from
inoperable. discovery of
fail ure to meet
LCO
D. --------NOTE---------- D.1 Declare associated Immediately
Separate Condition shared component(s}
entry is allowed for inoperable.
each AC subsystem.
One or more required
electrical power
distribution
subsystem(s}
E. --------NOTE---------- E.1 Declare associated Immediately
Separate Condition shared component(s}
entry is allowed for inoperable.
each DC subsystem.
One or more required
electrical power
distribution
subsystem(s}
North Anna Units 1 and 2 3.8.9-2 Amendments 231/212
-- NUCLEAR DESIGN INFORMA nON PORTAL -
Distribution Systems-Operating
3.8.9
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
associated Completion
Time for Condition A, AND
B, or C not met.
F.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
G. Two or more G.1 Enter LCO 3.0.3. Immediately
LCO 3.8.9.a electrical
power distribution
subsystems inoperable
that result in a loss
of safety function.
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
SR 3.8.9.1 Verify correct breaker alignments and 7 days
voltage to required AC, DC, and AC vital
bus electrical power distribution
.subsystems.
North Anna Units 1 and 2 3.8.9-3 Amendments 231/212