ML19353A094
| ML19353A094 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/10/1980 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19353A093 | List: |
| References | |
| NUDOCS 8101070134 | |
| Download: ML19353A094 (17) | |
Text
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/* "*4 UNITED STATES
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, i' t NUCLEAR REGULATORY COMMISSION j
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WASHING TON, D. C. 20555 i
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s; -o VIRGINIA ELECTRIC AND POWER CCMPANY DOCKET NO. 50- D NORTH ANNA POWER STATION. UNIi NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. NPF-4 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Cormany (the licensee) dated NovemDer 10, 1980, coglies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's niles and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the pr.ovisions of the Act, and the rules and regulations of the Coanission; 1
C.
There is reasonable assurance (i) tnat the activities authorized by this amendment can be conducted withcut endcngering the health and safety of the public, and (ii) *. hat such activities will be conducted in cogliance with the Comission's regulations; l
D.
The issuance of this amendment will not be inimical to the connon l
defense and security or to the health and safety of the public; and l
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.
Y%WY
i
.l,
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.0. (2) of Facility Operating License No. NPF-4 is hereby amended to rcad as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and 3, as revised through Amendment No.
22, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION S'
y Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical l
Specifications i
Date of Issuance: December 10, 1980 I
1 ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 22 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendnent number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document conpleteness.
Paces 3/42-1 3/4 2-2 3/4 2-4 3/4 2-7 3/4 2-16 3/4 2-17 3/4 2-18 B 3/4 2-2 B 3/4 Z-6 l
l l
l l
l
.c-
F 3/4.2 POWER DISTRIBUTION LIMITS AXIAL FLUX DIFFERENCE (AFD)
LIMITING CONDITION FOR OPERATION
- 3. 2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within a +5% target band (flux difference units) about the target flux difference.
APPLICABILITY: MODE 1 ABOVE 50% RATED THERMAL POWER
- ACTION:
With the indicated AXIAL FLUX DIFFERENCE outside of the + 5%
a.
target band about the target flux difference and with THERMAL POWER:
1.
Above 82% of RATED THERMAL POWER, within 15 minutes:
a)
Eit:ier restore the indicated AFD to within the target band limits, or b)
Reduce THERMAL POWER to less than 82% of RATED THERMAL POWER.
1 2.
Between 50% and 82% of RATED THERMAL POWER:
a)
POWER OPERATION may continue provided:
1)
The indicated AFD has not been outside of the t 5% target band for more than I hour penalty deviation cumulative during the previous 2a hours, and 2)
The indicated AFD is within the limits shown on Figure 3.2-1.
Otherwise, 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 < 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)
Surveillance testing of the Power Range Neutron Flux Channels may be performed pursuant to Specification 4.3.1.1.1 provided the indicated AFD is maintained within the limits of Figure 3.2-1.
A total of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of operation may be accumulated with the AFD outside of the target band during this testing without penalty deviation.
"See Special Test Exception 3.10.2.
NORTH ANNA-UNIT 1 3/4 2-1 Amendment No. 3, B,22
POWER DISTRIBUTION LIMITS SURVEILLANCE REOUIREMENTS (Continued) 4.2.1.3 The target 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 applicable.
4.2.1.4 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 interpolation between the most recently measured.value and 0 percent at the end.of the cycle life.
The provisions of Specification 4.0.4 are not applicable.
i 1
6 2
NORTH ANNA - UNIT 1 3/4 2-3 Amendment No.16 i
!p0WERDISTRIBUTIONLIMITS i
SURVEILLANCE REOUIREMENTS (Continued) b)
At least once per 31 EFPD, whichever occurs first.
RTP 2.
When the F is less than or equal to the F limit for the x
appropriate measured core plane, additional power distribution maps shall be taken and F*C compared to F*TP and F ' at least R
I Y
Y XY once per 31 EFPD.
e.
The F limits for RATED THERMAL POWER within specific core xy planes shall be:
P lj 1.
F 1 1.71 for all core planes containing bank "D" control
- rods, 2.
F 1 1.60 for all unrodded core planes from 0 to 28%
l jj of core height, R
1 57 for all unrodded core planes from 28% to 65%
1 3.
F y of core height, and f
RU 4
F 1 1.62 for all unrodded core planes above 65% of l
y ll core height.
ii
((
f.
The F limits of e, above, are not applicable in the following xy II core plane regions as measurec in percent of core height from the bottom of the fuel:
i
!,l 1.
Lower core region from 0 to 15%, inclusive.
Ii'I 2.
Upper core region from 85 to 100%, inclusive.
60.6 + 2% and 74.9 + 2%, inclusive (17'~x 17 fuel elements).
3.
Grid plane regions at 17.8 + 2%, 32.1 + 2%, 46.4 + 2%,
i 4.
Core plane regions within + 2% of core height (+ 2.88 inches) ljl about the bank demand position of the bank "D" control rods.
f g.
With F exceeding F the effects of F on F (Z) shall be x
g ll evaluated to determine if F (Z) is within its limit.
9 l'.2.2.3 When F (Z) is measured for other than F determination, an 4
9 xy overall measured F (Z) shall be obtained from a power distribution map and g
- increased by 3% to account for manufacturing tolerances and further increased
- : by 5% to account for measurement uncertainty.
ll NORTH ANNA-UNIT 1 3/4 2-7 AmendmentNo.)f,22
i IABLE 3.2-1 I
5 DNB PARAMETERS E5 LIMITS _
b 2 Loops In Operation **
2 Loops In Operation **
3 Loops In
& Loop Stop
& Isolated Loop
-i PARAMETER Operation Valves Open Stop Valves Closed Reactor Coolant System T,yg 1 585V Pressurizer Pressure 1 2205 psig*
Reactor Coolant System 1 278,400 gpm Total Flow Rate M,
n
'?
G
- Limit not applicable during either a TilERMAL POWER ramp increase in excess of 5% RATED TilERMAL POWER per minute or a TilERHAL POWER step increase in excess of 10% RATED TilERMAL POWER.
- Values dependent on NRC approval of ECCS evaluation for these conditions
POWER DISTRIBUTION LIMITS LIMIT..iG CONDITION FOR OPERATION (Continued) is the stardard deviation associated with thimble j, expressed ej as a fraction or percentage of R, and i3 derived from n flux maps j
from the relationship below, or 0.02, (2%) whichever is greater.
n ej = [n1i1 j-R$3)2]I/2 Rj The factor 1.07 is comprised of 1.02 and 1.05 to account for the axial power distribution instrumentation accuracy and the measure-ment uncertainty associated with F using the movable detector g
system, respectively.
The factor 1.03 is the engineering uncertainty factor.
APPLICABILITY: MODE I above 92% OF RATED THERMAL POWER.
ACTION:
With a F (Z) factor exceeding [F (Z)]3 by <_ 4 percent, reduce a.
j j
THERMAL POWER one percent for every percent by which the F (Z) j factor exceeds its limit within 15 minutes and within the next two hours either reduce the F (Z) factor to within its limit j
or reduce THERMAL POWER to 92% or less of RATED THERMAL POWER.
b.
With a F (Z) factor exceeding [F (Z)]3 by > 4 percent, reduce j
j THERMAL POWER to 92% or less of RATED THERMAL POWER within 15 minutes.
1 The APDMS may be out of service when surveillance for determining power distribution maps is being performed.
NORTH ANNA - UNIT l 3/4 2-17 Amendment No. 3, 5,22 c -.
i 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:
(a) maintaining the minimum DNBR in the core > 1.30 during nomal operation and in short term transients, and (b) 1Tmiting the fission gas release, fuel pellet temperature & cladding In addition, mechanical properties to within assumed design criteria.
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 O
heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for man-ufacturing tolerances on fuel pellets and rods.
Ff Nuclear Enthalpy Rise Hot Channel Factor, is defined as the "H
ratio of the integral of linear power along the rod with the highest integrated power to the average rod power.
Radial Peaking Factor, is defined as the ratio of peak power xy(Z) density to average power density in the horizontal plane at F
core elevation I.
3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)
The limits on AXIAL FLUX DIFFERENCE assure that the F (Z) upper n
bound envelope of 2.10 times the normalized axial peaking factor is not exceeded during either normal operation or in the event of xenon redis-tribution following power changes.
Target flux difference is deternined 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 nomal 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 condi-tions. 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.
NORTH ANNA - UNIT 1 B 3/4 2-1 Amendment No. 3, 5, 16
POWER DISTRIBUTION LIMITS BASES rodmisalignment,effectF{gheradialpowershape,suchasfrom abnormal perturbations in a.
Tore directly than F,
q although rod movement has a direct influence upon limiting F b.
to withjn its limit, such control is not readily available tb limitFbH,and errors in prediction for control power shape detected during c.
startup physics tests can be compensated for in Fg by regtri-cting axial flux distributions.
This c.cmpensation for Fig is less readily available.
3/4.2.4 OUADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the radial power distribution satisfies the design values used in the power capability analysis.
Radial power distribution measurements are made during start-up testing and periodically during power operation.
The limit of 1.02 at which corrective action is required provides DNB and linear heat generation rate protection with x-y plane power til ts.
The two hour time allcwance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned rod.
In the event such action is rein-does not correct the tilt, the margin for uncertainty on Fg i
i stated by reducing the power by 3 percent for each percent of tilt in excess of 1.0.
NORTH ANNA - UNIT 1 B 3/4 2-5
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