ML20128M056
| ML20128M056 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 05/15/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128M060 | List: |
| References | |
| TAC-56746, TAC-56747, NUDOCS 8505310562 | |
| Download: ML20128M056 (28) | |
Text
-
%g UNITED STATES j
g NUCLEAR REGULATORY COMMISSION
)
- .y
.j WASHINGTON. D. C. 20555
%,+j DUKE POWER COMPANY DOCKET NO. 50-369 d
W McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPF-9 1.
The Nuclear. Regulatory Comission (the Comission) has found that:
A.-
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No..NPF-9 filed by the Duke Power Company (licensee) dated January 11, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; 4
B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 43, are hereby incorporated into this license.
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2-The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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$W
.+g Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical. Specification Changes Date of Issuance:
May 15, 1985 e
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E' e ]4 UNITED STATES NUCLEAR REGULATORY COMMISSION g -
E WASHINGTON, D. C. 20555
\\..w...f DUKE POWER COMPANY DOCKET N0. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated January 11, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amer.ded by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 24, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.
3.
This license. amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h.N Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance:
May 15, 1985
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.Aj ATTACHMENT TO LICENSE AMENDMENT NO. 43 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 24 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 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.
Amended Page 2-2 2-2a 2-5 2-6 2-8 2-9 2-10 3/4 2-1 3/4 2-6 3/4 2-7 3/4 8 3/4 2-9 3/4 2-9a 3/4 2-9b 3/4 2-12 3/4 2-13 3/4 2-16 3/4 2-17 3/4 3-9 3/4 3-10 3/4 3-28 B3/4 2-1 83/4 2-2 i
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-THIS PAGE DELETED McGUIRE - UNITS 1 and 2.
2-2 Amendment No.43 (Unit 1)
Amendment No.24 (Unit 2)
e 660!
FLOW PER LOOP = 97220 gpm I 655j UNACdEPTABLE{
6W Jg #*/aj OPERATION 645-2p 640 g"*ia.
g, 630' Ci 625 2%
=i
{g20l a:
19,"*iaj 3
615!
610 ACCEPTABLE 60 @
OPERATION 6001 595i 590 I
l'
- 585, 0'
O.1' O.2' O.3:
0.4' O.51 0.6i 0.7! 0.8i 0.9I 1.0! 1.1i 1.21 POWER (fraction of nominal)i r
FIGURE 2.1-1 UNITS 1 AND 2 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION McGUIRE - UNITS 1 and 2 2-2a Amendment No.43(Unit 1)
Amendment No.24 (Unit 2)
TABLE 2.2-1 n
E REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 5
E FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- 1. Manual Reactor Trip N.A.
N.A.
d
- 2. Power Range, Neutron Flux Low Setpoint 5 25% of RATED
. Low Setpoint 126% of RATED THERMAL POWER THERMAL POWER e
n.
E High Setpoint - < 109% of RATED m
THERMAL POWER
~
High Setpoint - < 110% of RATED-THERMAL POWER- ~
- 3. Power Range, Neutron Flux,
< 5% of RATED THERMAL POWER with
< 5.5% of RATED THERMAL POWERk High Positive Rate a time constant 2 2 seconds Uith a time constant 2,2 seconds-
- 4. Power Range, Neutron Flux, 5 5% of RATED THERMAL POWER with
< 5.5% of RATED THERMAL POWER High Negative Rate a time. constant 1 2 seconds with a time constant 1 2 seconds
'?
- 5. Intermediate Range, Neutron
< 25% of RATED THERMAL POWER 1 30% of RATED THERMAL POWER Flux
- 6. Source Range, Neutron Flux i 105 counts per second i 1.3 x 105 counts per second
- 7. Overtemperature AT See Note 1 See Note 3
- 8. Overpower AT See Note 2 See Note 3 FF
- 9. Pressurizer Pressure--Low 1 1945 psig 2 1935 psig
&y
- 10. Pressurizer Pressure--High 5 2385 psig i 2395 psig
- 11. Pressurizer Water Level--High
~< 92% of instrument span
~< 93% of instrument span
?E y3
- 12. Low Reactor Coolant Flow 1 90% of design flow per loop *
> 89% of design flow per loop
- EE oo M
g
- Design flow is 97,220 gpa per loop.
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 5
A FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- 13. Steam Generator Water 1 12% of span from 0 to 30% of 111% of span from 0 to 30% of
-j Level--Low-Low RATED THERMAL POWER, increasing RATED THERMAL POWER, increasing linearly to 2 40% of span at to 39.0% of span at 100% of r,
100% of RATED THERMAL POWER RATED THERMAL POWER.
E
- 14. Undervoltage-Reactor 1 5082 volts-each bus 1 $016 volts-each bus s,
Coolant Pumps
- 15. Underfrequency-Reactor 1 56.4 Hz - each bus 1 55.9 Hz each bus Coolant Pumps
- 16. Turbine Trip 7
a.
Low Trip System Pressure 1 45 psig 1 42 psig b.
Turbine Stop Valve Closure 1 1% open 1 1% open
- 17. Safety Injection Input N.A.
N.A.
from ESF 18.
Reactor Trip System Interlocks 3g a.
Intermediate Range Neutron Flux, P-6, 1 1 x 10 88 amps 1 6 x 10 11 amps gg Enable Block Source Range Reactor Trip EE gg b.
Low Power Reactor Trips Block, P-7 ee gg 1)
P-10 Input 10% of RATED 2 9%, 1 11% of RATED THERMAL POWER THERMAL POWER
-w jfjf 2)
P-13 Input 5 10% RTP Turbine 1 11% RTP Turbine Impulse Pressure Impulse Pressure s,,,
Equivalent Equivalent vv
TABLE 2.2-1 (Continued) x E
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 5
N NOTATION NOTE 1:
OVERTEMPERATURE AT w
1+tS 1
l g
AT (f
) (y ga3) 1 AT,{Ky 3)-T'] + K (P-P') - f (AI)}
-Kg (y.
g)[T(1 3
y a
Measured AT by RTD Manifold Instrumentation, Where:
AT
=
1 t,S lead-lag compensator on measured AT,
=
3 T1 T2
= Time constants utilized in the lead-lag controller for AT, ti 1 8 sec., T2 5 3 sec.,
i m
1 a
Lag compensator on measured AT,
=
1 Time constants utilized in the lag compensator for AT, 135 l
=
Ts 6 sec.
j AT, Indicated AT at RATED THERMAL POWER,
=
K 5 1.200, 4
y
,. ?>g>
K 0.0222
=
l E"
?, k 1+I5 l
4 55
=. The function generated by the lead-lag controller for T,yg dynamic compensation, y
,,3 i
EE y&
14 ts Time constants utilized in the lead-lag controller for T,yg,
=
T4 1 28 sec, Ts 5 4 sec.,
gg oa Average temperature, "F, T
=
ms 1
Lag compensator on measured T,yg, l
y.
3
=
\\
TABLE 2.2-1 (Continued)
E
\\
i REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 5
R NOTATION (Continued)
NOTE 1:
(Continued) e 3
d Ts Time constant utilized in the measured T,yg lag compensator, Tc 5 l
=
6 sec g
T' 5 588.2*F Reference T,yg at RATED THERMAL POWER,
=
K 0.001095,
=
3 P
=
Pressurizer pressure, psig, P'
2235 psig (Nominal RCS operating pressure),
=
S
=
Laolace transform operator, sec 1, m
E and f (AI) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(i) for q 9 between -29% and +9.0%; f (AI) = 0, where q and g are percent RATED l
t b
y t
b THERMAL POWER in the top and bottom halves of the core respectively, and q
+q b is total THERMAL POWER in percent of RATED THERMAL POWER; gR (ii) for each percent that the magnitude of q 9 exceeds -29%, the AT Trip Setpoint l
ua t
b yg shall be automatically reduced by 3.151% of its value at RATED THERMAL POWER; and c+ r yy (iii) for each percent that the magnitude of q 9 exceeds +9.0%, the AT Trip Setpoint t
b yO shall be automatically reduced by 1.50% of its value at RATED THERMAL POWER.
CC t+
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i TABLE 2.2-1 (Continued) g REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS S
NOTATION (Continued) iE NOTE 2:
OVERPOWER AT E
17 S 1
1 h
AT(7 T3}(1+TS}5
{K
-K Il + 1 5) (1 + T y
- 5) T -K [T(y Tsg)- T"] - f (AI)}
1+TS2 3
0 4
5 6
p 7
8 e
Where:
AT
=
As defined in Note 1, f
Ij b
= As defined in Note 1
= As defined in Note 1 It. T2 As defined in Note 1,
=
1+TS3 AT, As defined in Note 1,
=
s K
5 1.0900, 4
5 0.02/*F for increasing average temperature and 0 for decreasing average K
=
temperature, T5 7
1 + tyS The function generated by the rate-lag controller for T,yg dynamic
=
compensation, 5N g@
T7 Time constant utilized in the rate-lag controller for T,,
, 1
=
7 > 5 sec,
@E 1
gg As defined in Note 1,
=
yT3 G
ee zz
{ P, Ts
=
As defined in Note 1, cw gg K
=
0.00169/*F for T > T" and K6 = 0 for T 5 T",
6 hk SC
3/4.2 POWER DISTRIBUTION LIMITS
~
3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)
LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within:
the allowed operational space defined by Figure 3.2-1 for RACC operation, a.
or b.
within a 15 percent target band about the target flux difference during base load operation.
APPLICABILITY:
MODE 1 above 50% of RATED THERMAL POWER *.
ACTION:
For RAOC operation with the indicated AFD outside of the Figure 3.2-1 a.
- limits, 1.
Either restore the indicated AFD to within the Figure 3.2-1 limits within 15 minutes, or 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux -
High Trip setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, ND" b.
For Base Load operation above APL with the indicated AXIAL FLUX DIFFERENCE outside of the applicable target band about the target flux difference:
1.
Either restore the indicated AFD to within the target band limits within 15 minutes, or ND 2.
Reduce THERMAL POWER to less than APL of RATED THERMAL POWER and discontinue Base Load operation within 30 minutes.
THERMALPOWERshallnotbeincreasedabove50%ofRAThDTHERMAL c.
POWER unless the indicated AFD is within the Figure 3.2-1 limits.
- See Special Test Exception 3.10.2.
- APL"O is the minimum allowable power level for base load operation and will be provided in the Peaking Factor Limit Report per Specification 6.9.1.9.
McGUIRE - UNITS 1 and 2 3/4 2-1 Amendment No.43(Unit 1)
Amendment No.24(Unit 2)
POWER DISTRIBUTION LIMITS
~
3/4.2.2 HEATFLUXHOTCHANNELFACTOR-Fg LIMITING CONDITION FOR OPERATION 3.2.2 F (Z) shall be limited by the following relationship:
q F (Z) 5 [2.26] [K(Z)] for P > 0.5 q
F (Z) 1 [2
] [K(Z)] for P 1 0.5 9
Where: P _ THERMAL POWER RATED THERMAL POWER '
and K(Z) is the function obtained from Figure 3.2-2 for a given core height location.
APPLICABILITY: MODE 1.
ACTION:
With F (Z) exceeding its limit:
9 a.
Reduce THERMAL POWER at least 1% for each 1% Fn(Z) exceeds the limit within 15 minutes and similarly reduce the PowVr Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provided the Overpower Delta T Trip Setpoints (value of K ) have been reduced at least 1% (in AT span) for each 4
1% F (Z) exceeds the limit; and 9
b.
Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit required by ACTION a., above; THERMAL POWER may then be increased.provided F (Z) is demonstrated through incore mapping to be within its limit.
q McGUIRE - UNITS 1 and 2 3/4 2-6 Amendment No.43(Unit 1)
Amendment No.24(Unit 2)
POWER DISTRIBUTION LIMITS
/
1 SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2 For RA0C operation, F (z) shall be evaluated to determine if F (z) q q
is within its limit by:
a.
Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.
b.
Increasing the measured F (z) component of the power distribution q
map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.
Verify the requirements of Specification 3.2.2 are satisfied, c.
Satisfying the following relationship:
Fq (z) 1 x K(z) for P > 0.5 M
2.26 P x W(z)
Fq (z) 1 x K(z) for P 5 0.5 N
2.26 W(z) x 0.5 M
where F (z) is the measured F (z) increased by the allowances for g
q manufacturing tolerances and measurement uncertainty, 2.26 is the F limit, K(z) is given in Figure 3.2-2, P is the relative THERMAL q
POWER, and W(z) is the cycle dependent function that accounts for power distribution transients encountered during normal operation.
This function is given in the Peaking Factor Limit Report as per Speci-fication 6.9.1.9.
M d.
Measuring Fq (z) according to the following schedule:
1.
Upon achieving equilibrium conditions after exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which F (z) was last determined,* or q
2.
At least once per 31 Effective Full Power Days, whichever occurs first.
- During power escalation at the beginning of each cycle, power level may be increased until a power level for extended operation has been achieved and a power distribution map obtained.
McGUIRE - UNITS 1 and 2 3/4 2-7 Amendment No.43(Unit 1)
Amendment No.24(Unit 2)
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS-(Cont.inued) e.
With measurements indicating
[F maximum (z) over z
( K(z)/
M has increased since the previous determination of Fq (z) either of the following actions shall be taken:
M 1)
Fq (z) shall be increased by 2% over that specified in Specifi-cation 4.2.2.2c. or N
2)
Fq (z) shall be measured at least once per 7 Effective Full Power Days until two successive maps indicate that
[Fg (7)I is not increasing.
M maximum over z
\\ K(z)/
^
f.
With the relationships specified in Specification 4.2.2.2c. above not being satisfied:
1)
Calculate the percent F (z) exceeds its limit by the following expression:
q
[loverz
[ maximum M
I
- U 0
-lif x 100 for P > 0.5 j
(
2 26 p
x K(z)j
/
I
I maximum
~ M(Z)
- WCZ)
]
0
-1 dx100 for P < 0.5 over z 2
x K(z)
- 2) s One of the following actions shall be taken:
a)
Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the AFD limits of 3.2-1 by 1% AFD for each percent F (z) exceeds its limits as deter-q mined in Specification 4.2.2.2f.1).
Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reset the AFD alarm setpoints to these modified limits, or b)
Comply with the requirements of Specification 3.2.2 for F (z) q exceeding its limit by the percent calculated above, or c)
Verify that the requirements of Specification 4.2.2.3 for Base Load operation are satisfied and enter Base Load
~
operation.
McGUIRE - UNITS 1 and 2 3/4 2-8 Amendment No.43(Unit 1)
Amendment No.24(Unit 2)
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 9 g.
The limits specified in Specifications 4.2.2.2c, 4.2.2.2e., and 4.2.2.2f.
above are not applicable in the following core plane regions:
1.
Lower core region from 0 to 15%, inclusive.
2.
Upper core region from 85 to 100%, inclusive.
4.2.2.3 Base Load operation is permitted at powers above APLND if the following conditions are satisfied:
Prior to entering Base Load operation, maintain THERMAL POWER above a.
ND APL and less than or equal to that allowed by Specification 4.2.2.2 for at least the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Maintain Base Load operation surveillance (AFD within iS% of target flux difference) during this l
time period.
Base Load operation is then permitted providing THERMAL ND BL ND POWER is maintained between APL and APL or between APL and 100% (whichever is most limiting) and FQ surveillance is maintained BL pursuant to Specification 4.2.2.4.
APL is defined as:
O APL ' = "ove"r"ZI i U" [ (2.26 x K(Z) ] x 100%
M p (Z) x W(Z)BL q
where:
F (z) is the measured F (z) increased by the allowances for 9
manufacturing tolerances and measurement uncertainty.
The F limit q
is 2.26.
K(z) is given in Figure 3.2-2.
W(z)BL is the cycle dependent function that accounts for limited power distribution transients en-countered during base load operation.
The function is given in the Peaking Factor Limit Report as^ per Specification 6.9.1.9.
b.
During Base Load operation, if the THERMAL POWER is decreased below APL"Ethentheconditionsof4.2.2.3.ashallbesatisfiedbefore re-entering Base Load operation.
4.2.2.4 During Base Load Operation F (Z) shall be evaluated to determine if F (Z) is within its limit by:
9 q
Using the movable incore detectors to obtain a power distribution a.
ND map at any THERMAL POWER above APL
' b.
Increasing the measured F (Z) component of the power distribution 9
map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.
Verify the requirements of Specification 3.2.2 are satisfied.
b McGUIRE - UNITS 1 and 2 3/4 2-9 Amendment No.43 (Unit 1)
Amendment No.24 (Unit 2)
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) c.
Satisfying the following relationship:
F"(Z) <
6
) for P > APLND where:
F"(Z) is the measured F (Z).
The F limit is 2.26.
q q
q K(Z) is given in Figure 3.2-2.
P is the relative THERMAL POWER.
W(Z)BL is the cycle dependent function that accounts for limited power distribution transients encountered during normal operation.
This function is given in the Peaking Factor Limit Report as per Specification 6.9.1.9.
d.
Measuring F (Z) in conjunction with target flux difference deter-mination according to the following schedule:
1.
Prior to entering BASE LOAD operation after satisfying Section 4.2.2.3 unless a full core flux map has been taken in the previous 31 EFPD with the relative thermal power having been ND maintained above APL for the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to mapping, and 2.
At least once per 31 effective full power days.
e.
With measurements indicating F"(Z) maximum [ K(Z) 3 over Z M
has increased since the previous determination F (Z) either of the following actions shall be taken:
M 1.
F (Z) shall be increased by 2 percent over that.pecified in 4.2.2.4.c, or F"(Z) shall be measured at least once per 7 EFPD,until 2 2.
successive maps indicate that F"(Z) g maximum [ g(7) ] is not increasing.
over z f.
With the relationship specified in 4.2.2.4.c above not being satisfied, either of the following actions shall be taken:
1.
Place the core in an equilbrium condition where the limit in 4.2.2.2.c is satisfied, and remeasure F"(Z), or McGUIRE - UNITS 1 and 2 3/4 2-9a Amendment No.43 (Unit 1) t Amendment No.24 (Unit 2) i
~
POWER DISTRIBUTION LIMITS i
~
SURVEILLANCE REQUIREMENTS (Continued) 2.
Comply with the requirements of Specification 3.2.2 for F (Z) q
. exceeding its limit by the percent calculated with the following expression:
[(max. over z of [ 2.26F (Z) x W(Z)BL ) ) -1 ] x 10 ND x K(Z) p
. g.
The limits specified in 4.2.2.4.c, 4.2.2.4.e, and 4.2.2.4.f above are not applicable in the following core plan regions:
1.
Lower core region 0 to 15 percent,. inclusive.
2.
Upper core region 85 to 100 percent, inclusive.
4.2.2.5 When F (Z) is measured for reasons other than meeting the requirements
~
9 of specification 4.2.2.2 an overall measured F (z) shall be obtained from a power q
distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
s McGUIRE - UNITS 1 and 2 3/4 2-9b Amendment No.43(Unit 1)
Amendment No.24(Unit 2) i
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c-s McGUIRE. UNITS 1 and 2 3/4 2-13 Amendment No.43(Unit 1)
Amendment No.24(Unit 2)
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~ McGUIRE - UNITS 1-and'2 3/4 2-16 Amendment No.43 (Unit 1)
Amendment No.24 (Unit 2)
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53 TABLE 3.3-2
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N?
REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES i
E
- g b!
FUNCTIONAL UNIT RESPONSE TIME 1.
Manual Reactor Trip N.A.
ct m
2.
Power Range, Neutron Flux
< 0.5 second*
3.
Power Range, Neutron Flux, liigh Positive Rate N, A.
4.
Power Range, Neutron Flux, High Negative Rate
< 0.5 second*,
u, 5.
Intermediate Range, Neutron Flux N.A.
}
30 l
um 6.
Source Range, Neutron Flux N.A.
E 7.
Overtemperature AT i 8.0' seconds
- 8.
Overpower AT
< 8.'0 seconds
- 9.
Pressurizer Pressure--Low
$P $I
~< 2.0 seconds c
E@
10.
Pressurizer Pressure--High
-< 2.0 seconds g.g.
11.
Pressurizer Water Level--High N.A.
c+ c+
N5 Ub Neutron detectors are exempt from response time testing.
Response time of the neutron flux signal portion c272 of the channel shall be measured from detector output or input of first electronic component in channel.
- 3. 3.
c+ c+
4 i
a
.m
- a:
TABLE 3.3-2 (Continued)
E E3 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES E
c:
FUNCTIONAL UNIT RESPONSE TIME z
>a d
12.
Low Reactor Coolant Flow w
a.
Single Loop (Above P-8)
< l.0 second b.
-Two Loops (Above P-7 and below P-8) 7 1.0 second m
,, #.S '
13.
Steam Generator Water Level--Low-Low
< 3.5 seconds
/ 'q; p f 14.
Undervoltage-Reactor Coolant Pumps
< 1.5 seconds 4
15.
Underfrequency-Reactor Coolant Pumps
< 0.6 second d
16.
Turbine Trip Ri a.
Low Fluid Oil Pressure N.A.
4' b.
Turbine Stop. Valve Closure N.A.
4 1
c$
17.
Safety Injection Input from ESF N.A.
18.
Reactor Trip System Ireterlocks N.A.
19.
Reactor Trip Breakers N.A.
l 20.
Automatic Trip and Interlock Logic N.A.
i i
's a en
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TABLE 3.3-4 (Continued)
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ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E
m FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES E
01, 7.
4 6'
a.
Manual Initiation N.A.
N.A.
E" b.
Automatic Actuation Logic N.A.
N.A.
N and Actuation Relays c.
Steam Generator Water Level--Low-Low i
1)
Start Motor-Driven Pumps 2 12% of span from 0 to 2 11% of span from 0 to 30% of RATED THERMAL POWER, 30% of RATED, THERMAL POWER, increasing linearly to increasing linearly to t'
1 40.0% of span at 100%
2 39.0% of span at 100%
l-of RATED THERMAL POWER.
of RATED THERMAL POWER.
w 4
2)
Start Turbine-Driven Pumps 2 12% of span from 0 to 1 11% of span from 0 to 1
30% of RATED THERMAL POWER, 30% of RATED THERMAL POWER, increasing linearly to increasing linearly to 1 40.0% of span at 100%
1 39.0% of span at 100%
l of RATED THERMAL POWER.
of RATED THERMAL POWER.
i d.
Auxiliary Feedwater 1 2 psig 1 1 psig g, g, Suction Pressure - Low ElEl (Suction Supply Automatic 52 Realignment) iLiL 2z e.
Safety Injection -
See Item 1. above for all Safety Injection Trip Setpoints
{P Start Motor-Driven Pumps and Allowable Values cw 22 72 f.
Station Blackout - Start 3464 i 173 volts with a
-> 3200 volts EL EL Motor-Driven Pumps and 8.5 1 0.5 second time r* r*
Turbine-Driven Pump delay BC g.
Trip of Main Feedwater Pumps -
N.A.
N.A.
Start Motor-Driven Pumps
3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by:
(1) maintaining the calculated DNBR in the core at or above the design limit'during normal operation and in short-term transients, and (2) limiting the fission gas release, fuel pellet temperature, and cladding mechanical prop-erties to within assund design criteria.
In addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200*F is not exceeded.
The definitions of certain hot channel and peaking factors as used in these specifications are as follows:
F (Z)
Heat Flux hot Channel. Factor, is defined as the maximum local 0
heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing toler-ances on fuel pellets and rods; F
Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of H
the integral of linear power along the rod with the highest integrated power to the average rod power.
3/4.2.1 AXIAL FLUX DIFFERENCE The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the F (Z) upper q
bound envelope of 2.26 times the normalized axial peaking factor is not exceeded during either normal operation or in the event of xenon redistribution following power changes.
Target flux difference is
.termined at equilibrium xenon conditions.
The full-length rods may be pot.tioned within the core in accordance with their respective insertion limits and should be inserted near their normal position for steady-state operation at high power levels.
The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup conditions. Target flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level.
The periodic updating of the target flux difference value is necessary to reflect core burnup considerations.
McGUIRE - UNITS I and 2 B 3/4 2-1 Amendment No. 43 (Unit 1)
Amendment No. 24 (Unit 2)
POWER DISTRIBUTION LIMITS BASES AXIAL FLUX DIFFERENCE (Continued)
ND At power levels below APL
, the limits on AFD are defined by Figures 3.2-1, i.e. that defined by the RAOC operating procedure and limits.
These limits were calculated in a manner such that expected operational transients, e.g. load follow operations, would not result in the AFD deviating outside of those limits.
However, in the event such a deviation occurs, the short period of time allowed outside of the limits at reduced power levels will not result in significantxenonredistributionsuchthattheenvelopeofpeakingfactor50 would cnange sufficiently to prevent operation in the vicinity of the APL power level.
ND At power levels greater than APL
, two modes of operation are permissible;
- 1) RAOC, the AFD limit of which are defined by Figure 3.2-1, and 2) Base Load operation, which is defined as the maintenance of the AFD within a i 5% band ND about a target value.
The RAOC operating procedure above APL is the same as ND that defined for operation below APL However, it is possible when following extended load following maneuvers that the AFD limits may result in restrictions in the maximum allowed power or AFD in order to guarantee operation with F (z) q less than its limiting value.
To allow operation at the maximum permissible value, the Base Load operating procedure restricts the indicated AFD to relatively small ND BL target band and power swings (AF,D target band of 15%, APL 1 power 5 APL or 100% Rated Thermal Power, whichever is lower).
For Base Load operation, it is expected that the plant will operate within the target band.
Operation outside of the target band for the short time period allowed will not result in signi-ficant xenon redistribution such that the envelope of peaking factors would change sufficiently to prohibit continued operation in the power region defined above.
To assure there is no residual xenon redistribution impact from past operation on the Base Load operation, a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> waiting period at a power level above APL"O and allowed by RAOC is necessary.
During this time period load changes and rod motion are restricted to that allowed by the Base Load pro-ceoure.
After the waiting period extended Base Load operation is permissible.
The computer determines the one minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for at least 2 of 4 or 2 of 3 OPERABLE excore channels are:
- 1) outside the allowed AI power operating space (for RAOC operation), or 2) outside the allowed AI target band (for Base Load operation).
These alarms are active when power is greater than:
- 1) 50% of RATED THERMAL POWER (for RAOC operation),
or 2) APLND (for Base Load operation).
Penalty deviation minutes for Base Load operation are not accumulated based on the short period of time during which operation outside of the target band is allowed.
McGUIRE - UNITS 1 and 2 B 3/4 2-2 Amendment No. 43(Unit 1)
Amendment No. 24(Unit 2)