ML20012C877
| ML20012C877 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/15/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012C878 | List: |
| References | |
| NUDOCS 9003260038 | |
| Download: ML20012C877 (43) | |
Text
m i
L,,:
$OOO
> If.
o,,
UNITED $TATES
[
g NUCLEAR REGULATORY COMMISSION
. - 5
- j WASHINGTON, D. C. 20565
%,...+/
CUKE POWER COMPANY DOCKET NO. 50-369 l
McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.105 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Commission) has found that:
The app (lication for amendnent to the McGuire Nuclear Station,the facility) 1 A.-
thit 1 by the Duke Power Conpany (the licensee) dated January 17, as supplemented January 29, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations as set forth in 10 CFP, i
Chapter I; D.
The facility will cperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amt:ndment can be conducted without endangering the health and 1
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; 1
D.
The issuance of this amendment will not be inimical to the comnon I?
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Convaission's regulations and all applicable requirements-have L
been satisfied.
1' 9003260038'900315
(
PDR ADOCK 05000369 l
P PDC h
i
i 6.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of facility Operating License No. NPF-9 is hereby amended to read as follows:
Technical Specifications
-The Technical Specifications contained in Appendix A, as revised through Amendment No.105, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
?Y st 2' David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: March 15, 1990 t
o
{'
l l
l l
c
- --t.
- +*
'o,,.
UNITED STATES
'[
p, NUCLEAR REGULATORY COMMISSION
- ,- 5
- j WASHINGTON, D. C. 20555
\\...../
DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Comission) has found that:
The app (lication for amendnent to the McGuire Nuclear Station,the facility)
A.
Uni t 1 by the Duke Power Company (the licensee) dated January 17, as j
supplemented January 29, 1990, complies with the standards and 1
. requirements of the Atomic Energy Act of 1954, as amended (the Act),
i and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the Consnission; j
C.
There is reasonable assurance (1) 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 fo th in 10 CFR Chapter I; i
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this anendment is in accordance with 10 CFR Part 51 of 1
the Commission's regulations and all applicable requirements have been-
-l satisfied.
4
2
-2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.87 are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the-Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W
0.5 q
P RTP F (Z) I q
K(Z) for P 10.5 Where FRW = the F limit at RATED THERMAL POWER (RTP) specified 9
9 in the CORE OPERATING LIMITS REPORT (COLR),
p, THERMAL POWER
, and RATED THERMAL POWER K(Z) = the normalized F (Z) for a given core height 9
specified in the COLR.
APPLICABILITY:
MODE 1.
ACTION:
With F (Z) exceeding its limit:
q 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 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 c.apping to be within its limit.
q t
McGUIRE - UNITS 1 and 2 3/4 2-6 Amendme t No,105(Unit 1)
Amendment No. 87(Unit 2)
o 1
s POWER DISTRIBUTION LIMITS i
i SURVEILLANCE REQUIREMENTS 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:
9 9
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 (2) 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.
l Verify the requirements of Specification 3.2.2 are satisfied.
c.
Satisfying the following relationship:
RTP M
F Fq (7) i Q x K(z) for P > 0.5 P x W(z)
RTP N
F Fq (z) 5 Q x K(z) for P < 0.5 W(z) x 0.5 where F (z) is the measured F (z) increased by the allowances for 9
manufacturing tolerances and measurement uncertainty, FhTPis the F limit, K(z) is the normalized F (z) as a function of core height, q
9 P is the relative THERMAL POWER, and W(z) is the cycle dependent function that accounts for power distribution transients encountered TP during normal operation.
F
, K(z), and W(z) are specified in the CORE OPERATING LIMITS REPORT per Specification 6.9.1.9.
N 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 9
2.
At least once per 31 Effective Full Power Days, whichever occurs first.
- 0uring 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.
l McGUIRE - UNITS 1 and 2 3/4 2-7 Amendment No.10!(Unit 1)
Amendment No. 8XUnit 2)
i I'
f 4
[
l POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) i i
e.
With measurements indicating maximum
[FM (,)
( K(z) )
over z N
has increased since the previous determination of F9 (2) either of the following actions shall be taken:
M 1)
F9 (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
[F (z)\\isnotincreasing, maximum over 2
( K(2))
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:
9 fmaximum M
} -14 j
F
) x W(z) n x 100 for P > 0.5 oy,7 7 x K(z).
s
([ maximum m
M 3
1 Fg (z) x W(z)
-1 r x 100 for P < 0.5 over z RTP
- K(*) J)
L
.5 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 reducing the AFD limits of Specification 3.2.1 by 1% AFD for each percent F (z) exceeds l
9 its limits 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 limits, or b)
Comply with the requirements of Specification 3.2.2 for F (z) 9 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 No10S(Unit 1)
Amendment No. 87(Unit 2)
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (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.
4.2.2.3 Base load operation is ptrmitted at powers above APLND* 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 2a hours. Maintain base load operation surveillance (AFD within the target band about the target flux difference of Specification 3.2.1) during this time period.
Base load operation is then permitted providing THERMAL POWER is ND OL ND maintained between APL and APL or between APL and 100%
(whichever is most limiting) and FQ surveillance is maintained pursuant BL to Specification 4.2.2.4.
APL is defined as:
x K(Z) ] x 100%
APL over Z F (2) x W(Z)BL where:
F (z) is the measured F (z) increased by the allowances for q
manufacturing tolerances and measurement uncertainty, FfTPis the Fq limit.
K(z) is the normalized F (z) as a function of core height.
q W(z)BL is the cycle dependent function that accounts for limited power distribution transients encountered during base load operation.
F
, K(z), and W(z)gg are specified in the CORE OPERATING LIMITS l
REPORT per Specification 6.9.1.9.
b.
During base load operation, if the THERMAL POWER is decreased below l
APL then the conditions of 4.2.2.3.a shall be satisfied before ND l
re-entering base load operation.
l 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 incore detectors to obtain a power distribution HD l
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 l
increasing the value by 5% to account for measurement uncertainties.
l l
Verify the requirements of Specification 3.2.2 are satisfied.
l ND
- APL is the minimum allowable (nuclear design) power level for base load operation in Specification 3.2.1.
McGUIRE - UNITS 1 and 2 3/4 2-9 Amendment No.105 Unit 1)
Amendment No.87 (Unit 2)
i POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) i c.
Satisfying the following relationship:
RTP p
0 x
ND F (Z) < p for P > APL Fh(Z)isthemeasuredF(Z).FhTP where:
is the F limit.
9 9
K(2) is the normalized F (Z) as a function of core height.
P is the n
relative THERMAL POWER.
W(Z)BL is the cycle dependent function that accounts for limited power distribution transients encountered during base load operation.
FhTP, K(Z), and W(Z)BL are specified in the CORE OPERATING LIMITS REPORT per Specification 6.9.1.9, i
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 satisfyinn 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 maximum [
]
over Z 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 specified in q
4.2.2.4.c, or 2.
F (Z) shall be measured at least onca per 7 EFPD until 2 l
successive maps indicate that l
F (Z) p maximum [ K Z) ] is n t 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 No105(Unit 1)
Amendment No. 87(Unit 2)
i i
POWER DISTRIBUTION LIMITS i
+
SURVEILLANCE REQUIREMENTS (Continued) 2.
Comply with the requirements of Specification 3.2.2 for F (2) 9 exceeding its-limit by the percent calculated with the following expression:
F (Z) x W(Z)BL ND
[(max. over z of [
J ) -1 ) x 100 for P > APL RTP 0
x K(Z)-
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.
t 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 l
g of specification 4.2.2.2 an overall measured F (z) shall be obtained from a power t
9 distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
l f
l McGUIRE - UNITS 1 and 2 3/4 2-9b Amendment No105(Unit 1)
Amendment No.87(Unit 2)
4.
4 l
- 4 1
i l
-i b
b THIS PAGE INTENTIONALLY DELETED.
i t
McGuire - UNITS 1 and 2 3/4 2-12 Amendment No.105 (Unit 1)
Amendment No. 87 (Unit 2)
4 POWER DISTR'BUTION LIMITS I
3/4.2.? RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDIT. TON FOR OPERATION 9
3.'2. 3 The combination of indicated Reactor Coolant System (RCS) total flow rate and R shall be maintained within the region of allowable operation specified in the CORE OPERATING LIMITS REPORT (COLR) for four loop operation:
Where:
N ON a
R=
[1.0 + MFAH (1.0 - P)] '
FAH THERMAL POWER b.
P RATED THERMAL POWER N
c.
F g = Measured values of F obtained by using the movable incore detectors to obtain a power distribution esp.
The measured values of F shall be used to calculate R since the figure H
specified in the COLR includes penalties for undetected feedwater venturi fouling of 0.1% and for measurement uncertainties of 1.7% for flow and 4% for incore measurement l
- ofFfg, FfH=TheFfg limit at RATED THERMAL POWER (RTP) specified in the P
l d.
COLR, and e.
MF3g= The power factor multiplier specified in the COLR.
APPLICABILITY:
MODE 1.
l ACTION:
With the combination of RCS total flow rate and R outside the region of acceptable operation specified in the COLR:
l a.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:
1.
Restore the combinati3n of RCS total flow rate and R l-to within the above limits, or 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint l
to less than or equal to 55% of RATED THERMAL POWER within the next 4 hcurs.
l l
14
' McGUIRE.- UNITS 1 and 2 3/4 2-14 Amendment No.105(Unit 1) l' Amendment No. 87(Unit 2) h 4
, sy.
L f&OWERDISTRIBUTIONLIMITS LIMITING CONDITION FOR OPERATION
' ACTION:
(Continued) b, Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially being outside Je above limits, verify through incore flux mapping and RCS total flow rate comparison that the combination of R and RCS total flow rate are restored to within the above limits, or reduce THERMAL POWER to less than'5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, c.
Identify and correct the cause of the out-of-lisiit condition prior to increasing THERMAL' POWER above the reduced THERMAL POWER limit required by ACTION a.2. and/or b. above; subsequent POWER OPERATION-may proceed provided that the combination of R and indicated RCS total flow rate are demonstrated, through incore flux mapping ard RCS total flow rate comparison, to be within the region of acceptable operation specified in the COLR prior to exceeding the following l.
THERMAL POWER levels:
1.
A nominal 50% of RATED THERMAL POWER, 2.
A nominal 75% of RATED THERMAL POWER, and 3.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater thia or equal to 95% of RATED THERMAL POWER.
SURVEILLANCE REQUIREMENTS 4.2.3.1-The provisions of Speelffcation 4.0.4 are not applicable.
4.2.3.2.The combination of indicated RCS total flow rate determined by process computer readirrgs or digital voltmeter measurement and R shall be within the region'of acceptable operation specified in the COLR:
l a.
Prior to operation above 75% of RATED TiiERMAL POWER after each f uel loading, and b.
At least once per 31 Efisctive Full Power Days.
4.2 3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation specified in the COLR at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l
'when the most-recently obtained value of R obtained per Specification 4.2.3.2,
'is assumed to exist.
4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at' least once per 18 months.
4.2.3.5 The RCS total flow rate shall be determined by pre:ision heat balance measurement at least once per 18 months.
McGUIRE - UNITS 1 and 2 1/4 2-15 Amendment No.109' Unit 1)
Amendment No. 8XUnit 2) e
.s
~
m;....~
l a
[
?
L t
a
(
H THIS PAGE INTENTIONALLY DELETED.
t 4
' '.McGUIRE'- UNITS 1 and 2 3/4 2-17 Amendment No.10% Unit 1)
Amendment No.87 (Unit 2) 1,n 3t
,1 W.
- o,
o-f INSTRUMENTATION' MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:
a.
At least 75% of the detector thimbles, l
b.
A minimum of two detector thimbles per core quadrant, and l
c.
Sufficient movable detectors, drive, and readout equipment to map these thimbles.
APPLICABILITY:
When the Movable Incore Detection System is used for:
a.
Recalibration of the Excore Neutron Fluy Detection System, b.
Monitoring the QUADRANT POWER TILT RATIO, or N
c.
Measurement of FA and F (Z) 9 ACTION:
With the Movable Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.2 The Movable incore Detection System shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by normalizing each detector output when required for:
a.
Recalibration of the Excore Neutron Flux Detection System, or b.
Monitoring the QUADRANT POWER TILT RATIO, or c.
Measurement of F and F (Z)
H q
McGUIRE - UNITS 2 and 2 3/4 3-45 Amendment No.105 (Unit 1)
Amendment No.87 (Unit 2)
- - o ; w 3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that
(1) the reactor can be made subcritical from all operating conditions, (2) the reactivity transients-associated with postulated accident conditions are controllable within acceptable limits, and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,yg..The most restrictive-condition occurs at EOL, with T,yg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncon-trolled RCS cooldown.
In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.3% delta k/k is required to control the reactivity transient.
Accordingly,.the SHUTDOWN MARGIN requirement is based upon this limiting con-dition and is consistent with FSAR safety analysis assumptions.
With T,yg
-less thhn 200*F, the reactivity transients resulting from a postulated steam line break cooldown are minimal and a 1% delta k/k SHUTDOWN MARGIN provides adequate protection.
-3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting condition assumed.in the FSAR accident and transient analyses.
The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of MTC values ut conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.
The most negative hTC value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions.
These corrections 0 -involved' subtracting the incremental change in the-MDC associated with a core condition of all rods inserted (most positive MDC) to an all rods withdrawn condition and, a conversion for the rate of change of moderator density with temperature at RATED THERMAL POWER conditions. This value of the MDC was then transformed into the limiting End Of Cycle Life (E0L) MTC value. The 300 ppm surveillance limit MTC value represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppm equilibrium boron concentration and is obtained by making these corrections to the limiting EOL MTC value.
McGUIRE - UNITS 1 and 2 B 3/4 1-1 Amendment No.105(Unit 1)
Amendment No.87 (Unit 2)
- _ ---- -- - --- - - - --- - -- ----~"
..--_____ _ _~ -. _ _ _
- 4 REACTIVITY CONTROL SYSTEMS BASES
[0RATIONSYSTEMS(Continued)
The boron capability required below 200'F is sufficient to provide a SHUTDOWN MARGIN of 1% delta k/k after xenon decay and cooldown from 200'F to 140*F. This condition requires either 2000 gallons of 7000 ppm borated water from the boric acid storage tanks or 10,000 gallons of 2000 ppm borated water from the refueling water storage tank.
The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 10.5 for the solution recirculated within containment after a LOCA.
This pH band minim 1zes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
The OPERABILITY of one Boron Injection System during REFUELING ensures that this system is available for reactivity control while in MODE 6.
'3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that:
(1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of rod misalignment on associated accident analyses are-limited.
OPERABILITY of the control rod position-indicators is: required to determine control rod positions and thereby ensure compliance. with the control rod alignment and insertion limits.
The control rod insertion limit and shutdown rod ~ insertion limits are specified in the CORE OPERATING LIMITS REPORT per specification 6.9.1.9.
The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met.
Misalignment of a rod requires measurement of peaking' factors and a restriction-in THERMAL POWER.
These restrictions provide assurance of fuel rod integrity during continued operation.
In addition, those safety analyses affected by a misaligned rod are reevaluated to_ confirm that the results remain valid during future operation.
-The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses.
Measurement with T greater than or equalto551*FandwithallreactorcoolantpumpsoperatinfEnsuresthatthe measured drop times will be representative of insertion times experienced during a' Reactor trip at operating conditions.
Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.
These verification frequencies are adequate for assuring that the applicable _LCO's are satisfied.
McGUIRE - UNITS 1 and 2 B 3/4 1-3 Amendment No.105 (Unit 1) i Amendment No. 87 (Unit 2) l
e-3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance cf fue1~ 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 assumed design criteria.
In addition, limiting the peak linear power density during Condition I events provides assurance that the ir.itial 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.
3/4.2.1 AXIAL FLUX DIFFERENCE The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the F (Z) upper 9
boundenvelopeoftheFhTP limit specified in the CORE OPERATING LIMITS REPORT (COLR) times the normalized axial peaking factor is not exceeded during either normal operation or in the event of xenon redistribution following power changes.
L Target flux difference is determined at equilibrium xenon conditions.
The full-length rods may be positioned 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 L
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 %re burnup conditions. Target flux differences for other l
THERMAL POWER leveh 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.
I-McGUIRE - U!iITS 1 ana 2 8 3/4 2-1 Amendment No.105(Unit 1)
Amendment No. 87 (Unit 2)
L
,. g
l
, e.
I
{
POWER DISTRIBUTION LIMITS BASES AXIAL FLUX DIFFERENCE (Continued)
E At power levels below APL
, the limits on AFD are defined in the COLR, l
1.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 factor 5D I
would change _sufficiently to prevent operation in the vicinity of the APL power level.
E At power levels greater than APL
, two modes of operation are permissible;
The RAV operating procedure above APL is the same as-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) less_than its limiting value.
To allow operation at-the maximum q
permissible value, the base load operating procedure restricts the indicated AFD to relatively small target band and power swings (AFD target band as specified BL in the COLR, APL
< power < APL or 100% Rated Thermal Power, whichever is lower).
~
l For base load operation, it is expected that the plant will operate within the l
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 I
of peaking factors would change sufficiently to prohibit continued operation in the power region defined above.
To assure there is no residual xenon redistri-bution 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 E
period at a power level above APL and allowed by RAOC is necessary.
During this time period load changes and rod motion are restricted to that allowed by the base l
load procedure.
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 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) APL* (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.
1 McGUIRE - UNITS 1 and 2 8 3/4 2-2 Amendment No.105(Unit 1)
Amendment No. 87(Unit 2)
I
y,+,
'{
POWER DISTRIBUTION LIMITS BASES i
j
-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 l
The limits on heat flux hot channel factor, RCS flow rate, and nuclear enthalpy rise hot 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.
These limits are specified in the CORE OPERATING LIMITS REPORT per Specification 6.9.1.9.
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 sufficient to insure that the limits are maintained provided:
a.
Control rods in a single group move together with no individual rod insertion differing by more than + 13 steps from the group demand position; b.
Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.6; c.
The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained; and d.
The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.
N F
will be maintained within its limits provided Conditions a. through d.
g above are maintained.
As noted on the figure specified in the CORE OPERATING LIMITS REPORT (COLR), RCS flow rate and power may be " traded o.'f" against one another (i.e., a low measured RCS flow rate is acceptable if the power level is l
decreased) to ensure that the calculated DNBR will not be below the design DNBR L
value.
The relaxation of F as a function of THERMAL POWER allows changes in g
l' the radial power shape for all permissible rod insertion limits.
R as calculated in Specification 3.2.3 and used in the figure specified in the COLR, accounts for F lessthanorequaltotheFhP limit specified in g
ThisvalueisusedinthevariousaccidentanalyseswhereFfH the COLR.
influences parameters other than DNBR, e.g., peak clad temperature, and thus is the maximum "as measured" value allowed.
Margin between the safety analysis limit DNBRs and the design limit DNBRs j
is maintained.
A fraction of this margin is utilized to accommodate the transi-tion core DNBR penalty (2%) and the appropriate fuel rod bow DNBR penalty (WCAP - 8691, Rev. 1).
When an F measurement is taken, an allowance for both experimental error q
and manufacturing tolerance must be made.
An allowance of 5% is appropriate McGUIRE - UNITS 1 and 2 B 3/4 2-2a Amendment No.105(Unit 1)
Amendment No. 87(Unit 2)
- , 6.
P0hERDISTRIBUTION_I_IMITS BASES JW +
HEAT FLUX H0T CHAMEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTON (Continued) for'a full-core map taken with the Incore Detectcr Flux Mapping System, and a
-3% allowance is appropriate for manufacturing tolerance.
WhenRCSflowrateandFfgare measured, no additional allowances are necessary prior to comparison with the limits of the figure specified in the E
COLR.
Measurement errors of 1.7% for RCS total flow rate and 4% for F have N
AN been allowed for in determination of the design DNBR value.
The measurement error for RCS total flow rate is based upon performing a j
precision heat balance and using the result to calibrate tha RCS flow rate indicators.
Potential fouling of the feedwater venturi which might not be detected could bias the result from the precision heat balance in a non-k conservative manner.
Therefore, a penalty of 0.1% for undetected fouling of g
the feedwater venturi.is included in the figure specified in the COLR.
Any l
fouling which might bias the RCS_ flow rate measurement greater than 0.1% caa be detected by monitoring and trending various plant _ performance parameters, i
If detected, action shall be taken before' performing sutsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quantified g
and compensated for in the RCS flow rate maasurement or the venturi shall be cleaned to eliminate the fouling.
The 12-hour periodic surveillance of indicated RCS flow is sufficient to de'cect only flow degradation which could lead to operation outside the accept-able region of operation specified on the figure specified in the COLR.
l The hot-channel factor F (z) is measured periodically and increased by a cycle and height dependent power factor appropriate to either RA0C 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 restrictive operating limits allowed by base load operation which result in less severe transient values.
The W(z) function for normal operation T
and the W(z)BL function for base load operation are specified in the CORE OPERATING LIMITS REPORT per Specification 6.9.1.9.
=
?
McGUIRE - UNITS 1 and 2 B 3/4 2-4 Amendment No.105(Unit 1) j Amendment No. 87 (Unit 2) l 1
1 4 : <'. =
4 ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT 6.9.1.9 Core operating. limits shall be established and documented in the CORE OPERATING LIMITS REPCRT before each reload cycle or any remaining part of a reload cycle for the following:
1.
Moderator Temperature Coefficient BOL and E0L limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, 2.
Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 3.
Control Bank Insertion Limits for Specification 3/4.1.3.6, ND 4.
Axial Flux Difference limits, target band, and APL for
-Specification 3/4.2.1, TP ND 5.
Heat Flux Hot Channel Factor, F
,K(Z),W(Z),APL and W(Z)BL II Specification 3/4.2.2, and RTP 6.
Nuclear Enthalpy Rise Hot Channel Factor, F
, and Power Factor Multiplier, MFAH, limits for Specification 3/4.2.3.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC in:
1.
WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"
July 1985 (W Proprieta m.
(Methodology for Specifications 3.1.1.3 - Moderator Tempcrature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
2.
WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION", June 1983 (W Proprietary).
(Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for F Methodology.)
q 3.
WCAP-10266-P-A Rev. 2 "THE 1981 VERSION OF WESTINGHOUSE EVALUATION' MODEL USING BASH CODE", March 1987, (l! Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto,'shall be pr.wided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report.
l McGUIRE - UNITS 1 and 2
' 21 Amendme'it No.105 (Unit 1)
Amendm< + No. 87 (Unit 2)
-