ML20093E069
| ML20093E069 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/13/1984 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20093E071 | List: |
| References | |
| TAC-55177, TAC-55178, NUDOCS 8410110528 | |
| Download: ML20093E069 (17) | |
Text
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UNITED STATES y hyg,g NUCLEAR REGULATORY COMMISSION
- ,[&.p.ff 4
p WASHINGTON, D. C. 20555 Q
~ DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY.0PERATING LICENSE' Amendment No. 34 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 June 14, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulaticns 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 Comission'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:
8410110528 840913 PDR ADOCK 05000369 P.
i
-2 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 34 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 was effective June 21, 1984.
FOR THE NUCLEAR REGULATORY COMMISSION Aa M L-Elinor G. Adensam, Chief l
Licensing Branch No. 4 l
Division of Licensing
Attachment:
Technical Specification Changes Date nf issuance: September 13, 1984 i
t f
a
7 l
t s.
[p r8c og To UNITED STATES g
- y gg NUCLEAR REGULATORY COMMISSION 4
4 WASWNGTON D. C. 20555
...../
gv DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.15 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Comission) 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 June 14, 1984, 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; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Cor mission; 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 Comission'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 anA 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-17 is hereby amended to read as follows:
M
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.15, 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 was effective June 21, 1984.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of 1ssuance: September 13, 1984 4
D 3
r-ATTAteENT TO LICENSE AMENDMENT 110. 34 FACILITY OPERATING LICENSE NO NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO.15 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET N0. 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 a vertical line indicating the area of change.
Amended Page 3/4 2-1 3/4 2-la(newpage) 3/4 2-7 3/4 2-8 3/4 2-9 3/4 2-9a(newpage) 3/4 2-9b (new page)
B3/4 2-1 B3/4 2-2 83/4 2-2a(newpage)
B3/4 2-6 6-21
/
W u
m m
o 3/4.2 POWER DISTR'BUTICN LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (UNIT 1)
LIMITING CONDITION FOR OPERATION l
3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within:
a.
the allowed operational space defined by Figure 3.2-1 for RAOC operation, or b.
within a i 3 percent target band about the target flux difference during base load operation.
APPLICABILITY: MODE I above 50% of RATED THERMAL POWER *.
ACTION:
a.
For RAOC operation with the indicated AFD outside of the Figure 3.2-1
- 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 l
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 />, b.
For Base Load operation above APLND" with the indicated AXIAL FLUX DIFFERENCE outside of the applicable target band about the target flux differenca:
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, THERMAL POWER shall not be increased above 50h; of RATED THERMAL c.
POWER unless the indicated AFD is within the Figure 3.2-1 limits.
i
- See Special Test Exception 3.10.2.
ND
- APL 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. 34(Unit 1)
Amendment No.15(Unit 2)
SURVEILLANCE RE00!REMENTS 4.2.1.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 50% of RATED THERMAL POWER by:
a.
Monitoring the indicated AFD for each OPERABLE excore channel:
1.
At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2.
At least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the AFD Monitoring Alarm to OPERABLE status.
b.
Monitoring and logging the indicated AFD for each OPERABLE excore channel at least'once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AFD Monitor Alarm is inoperable. The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.
4.2.1.2 The indicated AFD shall be considered outside of its limits when at least two OPERABLE excore channels are indicating the AFD to be outside the Ifmits.
4.2.1.3 When in Base load operation, the target axial flux difference of each OPERABLE excore channel shall be determined by measurement at least once per 92 Effective Full Power Days. The provisions of Specification 4.0.4 are not appifcable.
4.2.1.4 When in Base load operation, the target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining the target flux difference pursuant to 4.2.1.3 above or by linear interpola-tion between the most recently measured value and 0 percent at the end of cycle life. The provisions of Specification 4.0.4 are not applicable, 4
McGUIRE - UNITS 1 and 2 3/4 2-la Amendment No.34 (Unit 1)
Amendment No.15 (Unit 2)
SURVEILLANCE REQUIREMENTS (UNIT 1) 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2 For RAOC operation, F (z) shall be evaluated to determine if F (z) is within its limit by:
q g
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 g
map by 3% to account for manufacturing tolerances and further increasirg the value b/ M to account for measurement uncertainties.
c.
Satisfying the following relationship:
Fg (z) 1 x K(z) for P > 0.5 M
2.15 N
2 Fg (z) <
z) x 0 for P 5,0.5 where F (z) is the measured F (z) increased by the allowances for g
manufacturing tolerances and measurement uncertainty, 2.15 is the F q
.. limit, K(z) is given in Figure 3.2-2, P is the relative THERMAL 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 Specification 6.9.1.9.
N d.
Measuring Fq (z) a: cording to the following schedule:
1.
Upon achieving equilibrium conditions af ter exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which F (z) was last detennined," or q
2.
At least once per 31 Effective Full Powe'[0ays, 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 I and 2 3/4 2-7 Amendment No.34(Unit 1)
Amendment No.15(Unit 2)
SURVEILLANCE REC..AEMEtiTL (UNIT 1) (Continued) t e.
With measurements indicating maximum FM (z) over z
(
z M
has increased since the previous determination of Fq (z) either of the fo11 ewing actions shall be taken:
1)
Fq (2) shall be increased by 2% over that specified in Specifi-cation 4.2.2.2c. or 2)
F "(z) shall be measured at least once per 7 Effective Full q
Power Days until two successive maps indicate that maximum fFM(z) is not increasing.
(
z/
over 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
)4 x 100
[ maximum M
F0 (3)
- WIZ) j -1 for P > 0.5 L,y,7,
.2 15 xX(z) s q(,
Imaximum F0 (*)
- WII)*-13 M
, x 100 for P < 0.5 l\\
L h x X(z)/ s 2)
One of the following actions shall be taken:
a)
Within 15 minutes, control the AFD'to within new AFD limits which are determined by reducin 3.2 1 by 1% AFD for each percent F (z)g the AFD limits of exceeds its limits q
as determined 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 Ilmits, or b)
Comply with the requirements of Specification 3.2.2 for F (z) exceeding its limit by the percent calculated q
atove, 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 NoJ4 (Unit 1)
Amendment No.15 (Unit 2)
SURVEILLANCE REC :REMENTC (UNIT 1) (Continued) 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.
ND 4.2.2.3 Base Load operation is permitted.at powers above APL if the following conditions are satisfied:
a.
Prior to entering Base Load operation, maintain THERMAL POWER above 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 s'urveillance (AFD within i 3% of target flux difference) during this 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 F surveillance is maintained q
BL pursuant to Specification 4.2.2.4.
APL is defined a;:
APLBL = minimum g (2.15 x K(Z) ) x 100%
over Z F (Z) x W(Z)BL M
-where:
F (z) is the measured F (z) increased by the allowances for q
q manufacturing tolerances and measurement uncertainty. The F limit q
is 2.15.
K(z) is given in-Figure 3.2-2.
W(z)BL is the cycle dependent function that accounts for limited power distribution transients encountered 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 ND APL then the conditions of 4.2.2.3.a shall be satisfied before 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:
q 9
a.
Using the movable incoro detectois to obtain a power distribution ND map at any THERMAL POWER above APL 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.
McGUIRE - UNITS 1 and 2 3/4 2-9 Amendment No.34 (Unit 1)
Amendment No.15 (Unit 2) 7 T
SURVEILLANCE RE0' REMENTS (UNIT 1) (Continued) c.
Satisfying the following relationship:
F (Z) < 2.15 x
) for P > APLND where: F (Z) is the measured F (Z). The F limit is 2.15.
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 (I) 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 [
]
over Z has increased since the previous determination F (Z) either of the following actions shall be taken:
1.
F (Z) shall be increased by 2 percent over that specified in
- 4. 2. 2. 4. c, or M
2.
F (Z) shall be measured at least once per 7 EFPD until 2
-successive maps indicate that F (Z) maximum [ q7) - ] 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. 3t(Unit 1)
Amendment No.1% Unit 2)
SUP.VEILLANCE REQUIREMEfC5 (UNIT 1) (Continued) 2.
Comply with the requirements of Specification 3.2.2 for F (Z) 9 exceeding its limit by the percent calculated with one of the following expressions:
F (Z) x W(Z)BL ND
[(max. over z of [ 2.15
) ) -1 ] x 100 for P > APL x K(Z) p F (Z) x W(Z)
ND
[(max. over z of [ 2.15
) ) -1 ] x 100 for 0.5,P < APL 5
x K(Z) p g.
T,he 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, inc1psive.
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 q
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.
~
l McGUIRE - UNITS I and 2 3/4 2-9b Amendment No.34 (Unit 1)
Amendment No.15 (Unit 2)
3/4.2 POWER DISTEIEUTION 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-ertics to within assumed 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 9
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; and N
E Fxy(Z)
Radial Peaking Factor, is defined as the ratio of peak power density y
to average power density in the horizontal plane at core elevation Z.
e-3/4.2.1 AXIAL FLUX DIFFERENCE The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the FQ(Z) upper bound envelope of 2.32 (Unit 2), 2.15 (Unit 1) 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 determined at equilibrium ~ xenon conditions.
The full-length rods may be positioned within the enre 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 1 and 2 B 3/4 2-1 Amendment No.34 (Unit 1)
Amendment No.15 (Unit 2) 4
)
i
~
POWER DISTRIBUTION LIMITS 1
BASES AXIAL FLUX DIFFERENCE (Continued)
~
Although it is intended that the plant will be operated with the AFD within the target band required by Specification 3.2.1 about the target flux difference, during rapid plant THERMAL POWER reductions, control rod motion.
will cause the AFD to deviate outside of the target band at reduced THERMAL POWER levels. This deviation will not affect the xenon redistribution suffi-ciently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duration of the deviation is limited. Accordingly, a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation limit cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is provided for n
operation outside of the target band but within the limits of Figure 3.2-1 e
while at THERMAL POWER levels between 50% and 90% of RATED THERMAL POWER.
For THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER, devia-u T
tions of the AFD outside of the target band are less significant. The penalty of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> actual time reflects this reduced significa'nce.
Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm.
The computer deter-mines the 1 minute averag'e of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for two or more OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than 90%-of RATED THERMAL POWER. During operation at THERMAL POWER levels between 50% and 90% and between 15% and 50% RATED THERMAL POWER, the computer outputs an alarm message when the penalty deviation accumulates beyond the limits of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, respectively.
Figure B 3/4 2-1 shows a typical monthly target band.
ND For Unit 1, 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 significant xenon redistribution such that the envelope of peaking factors would change sufficiently to prevent operation in the vicinity of the APL"U power level.
ND At power levels greater than APL, two modes of operation are permissible; E
- 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 13% band u
ND 5
about a target value. The RAOC operating procedure above APL is the same as ND that defined for operation below APL Howe"er, 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 operationwith.}(z)lessthanitslimitingvalue.
To allow operation at the maximum permissible value, the Base Load operating procedure restricts the McGUIRE - UNITS 1 and 2 B 3/4 2-2 Amendment No.34 (Unit 1)
Amendment No.15 (Unit 2) f
POWER DISTRIBUTIC LIMITS BASES AXIAL FLUX DIFFERENCE (Continued) indicated AFD to relatively small target band and power swings (AFD target band of 13%, APLND < power < APLBL 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 significant 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 ND 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 and allowed by RAOC is necessary. During this time period load changes and rod motion are g
restricted to that allowed by the Base Load procedure. After the waiting g
period extended Base Load operation is permissible.
j For Unit 1, the computer determines the one minute average of each of the OPERAB'.E excore detector outputs and prov~ ides an alarm message immediately if o
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 RA0C 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.
3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR, and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR The limits on heat flux hot channel factor, RCS flow rate, and neclear enthalpy rise het channel factor ensure that:
(1) the design limits on peak local' power density and minimum DNBR are not exceeded, and (2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200 F ECCS accep-tance criteria limit.
Each of these is measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3.
This periodic surveillance is i
sufficient to insure that the limits are maintained provided:
I McGUIRE - UNITS 1 and 2 B3/4 2-2a Amendment No.34 (Unit 1)
Amendment No.15.(Unit 2) l l'
r
PC'.lER DISTRIBUTIC4 LIMIT 3 BASES HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)
The hot channel factor F (z) is measured periodically and increased by a cycle and height dependent power factor appropriate to either RAOC or Base Load operation, W(z) or W(z)BL, to provide assurance that the limit on the hot channel factor, F (z), is met. W(z) accounts for the effects of normal 9
operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. W(z)BL accounts for,
the more re.strictive operating limits allowed by Base Load operation which-result in less severe transient values. The W(z) function for normal operation is provided in the Peaking Factor Limit Report per Specification 6.9.1.9.
3/4.2.4 QUADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power distri-bution satisfies the design values used in the power capability analysis.
Radial power distribution measurements are made during STARTUP testing and periodically during power operation.
The 2-hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correc-tion of a dropped or misaligned rod.
In the event such action does not cor-rect the tilt, the margin for uncertainty on F is reinst.ated by reducing q
the power by 3% from RATED THERMAL POWER for each percent of tilt in excess of 1.0.
For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the moveable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incore detector monitoring is do,ne with a full incore flux map or two sets of four symmetric thimbles. The two sets of four symmetric thimbles is a unique set of eight detector locations.
These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, N-8.
3/4.2.5 DNB PARAMETERS The limits on the DNB-related parameters assure that each of the para-meters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a design limit DNBR throughout each analyzed transient.
The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limity following load changes and other expected transient operation.
e e
McGUIR4 - UNITS I and 2 B3/4 2-6 Amendment No.34 (Unit 1)
Amendment No.15 (Unit 2) 4
~
AD'AINISTRATIVE C'::TROLS
-RADIAL PEAKING FACTOR LIMIT REPORT
~.9.1.9 The F limit for RATED THERMAL POWER (FRTP) shall be provided to 6
xy x
the Regional Administrator of the NRC Regional Office, with a copy to the Director, Nuclear Reactor Regulation, Attention: Chief, Core Performance Branch, U. S. Nuclear Regulatory Commission, Washington, D.C.
20555 for all N
g core planes containing Bank "0" control rods and all unrodded core planes at z.
least 60 days prior to cycle initial criticality.
In the event that the limit would be submitted at some other time during core life, it shall bd submitted u-g 60 days prior to the date the limit would become effective unless otherwise exempted by the Commission.
RTP Any infornation needed to support F will be by request from the NRC and x
need not be included in this report.
ND The W(z) functions for RAOC and Base Load operation and the value for APL (as required) shall be provided to the Director, Nuclear Reactor Regulations, Attention: Chief, Core Performance Branch, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 at least 60 days prior to cycle initial criticality.
y In the event that these values would be submitted at some other time during g '. core life, it will be submitted 60 days prior to the date the values would become effective unless otherwise exempted by the Commission.
o ND 5
Any information needed to support W(z), W(z)BL and APL will be by request
,from the NRC and need not be included in this report.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the 2
NRC Regional Office within the time period specified for each report.
,e McGUIRE - UNITS 1 and 2 6 Amendment No. 34(Unit 1)
Amendment No.15(Unit 2)
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