ML20029A701
| ML20029A701 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/27/1991 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20029A702 | List: |
| References | |
| NUDOCS 9103040077 | |
| Download: ML20029A701 (11) | |
Text
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UNITED 8T Af ts I
NUCLE AR REGULATORY COMMISSION e
5 wAsHiwoTow. o, c. po666 DUKE POWER C0ttPANY DOCKET _NO. 50 369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPFRAT!NG LICENSC Anendment No. 117 License No. NPF-9 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the f uility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated December 19, 1990, as sepplemented February 16, 1991 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 CFR Chapter li B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission:
C.
Thereisreasonableassurance(i)thatth?activitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activitica will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter li D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
l
Mr. H.S. Tuckman Duke Power Con,pany McGuire Nuclear Station CCI Hr. A.V. Carr, Esq.
Dr. John M. Barry Duke Power Company Department of Environmental Health 422 South Church $treet Hecklenburg County Charlotte, North Carolina 20242 0001 1200 Blythe Boulevard Charlotte, North Carolina 28203 County Manager of Mecklenburg County 720 East Fourth Street Mr. Dayne H. Brown, Director Charlotte, North Carolina 28202 Department of Environmental, Health and Natural Resources Mr. Paul Guill Division of Radiation Protection Duke Power Company P.O. Box 27687 Nuclear Production Departn. tnt Raleigh, North Carolina 27611-7687 P.O. Box 1007 Charlotte, North Carolina 28201-1007 Mr. Alan R. Herdt, Chief Project Branch f3 U.S. Nuclear Regulatory Commission J. Michael McGarry, 111 Esq.
10] Marietta Street, NW, Suite 2900 Winston and Strawn Atlanta, Georgia 30323 1400 L Street, N.W.
Washington, DC 20005 Ms. Karen E. Long Assistant Attorney General N. C. Department of Justice Senior Resident Inspector P.O. Box 629 c/o U.S. Nuclear Regulatory Connission Raleigh, North Carolina 27602 12700 Hagers Ferry Road Huntersv111e, North Carolina 28078 Mr. R.L. Gill, Jr.
Nuclear Production Department Regional Administrator, Region !!
Duke Power Company U.S. Nuclear Regulatory Commission P.O. Box 1007 101 Marietta Street, N.W., Suite 2900 Charlotte, North Carolina 28201-1007 Atlanta, Georgia 30323 Mr. Frank Modrak Project Man &ger, Mid South Arce Eba0 Projects Westinghouse Electric Corporation MNC West Tower - Bay 241 P. O. Box 35b Pittsburgh, Pennsylvania 15230
4
- 2-2.
Accordingly, the license is hereby amended by page changes to the Techrical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating Licerise No. NPT-9 is hereby aneended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.117, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specificatio, and the Environtrental Protection Plan.
3.
This license amendment is ef fective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION j"hul,,f'
- p h'
N <L ic s
David B. Matthews, Director Project Directorate !! 3 Division of Reactor Projects-l/ll Office of Nuclear Reactor Regelation
Attachment:
Technical Specification Changes Date of Issuance: February 27, 1991
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UNITED 8TATES 8
I' NUCLEAR REGULATORY COMMIS$lON WASHINGTON, O C. P%%
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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No NPF-17 1.
The Nuclear Regulatory Comission (the Comission) has found that:
4 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 (the licensee) dated Occember 19, 1990, as supplemented February 15, 1991 complies with the standards and requirements of the Atomic Eneroy Act of 1954, as amended (the Act),
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 provisions of the Act, and the rules and regulatichs of the Comissions 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 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 amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been r,ati sf ied. -
2 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, l
and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
1 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 99, 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 c' its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
)
st David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-l/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
February 27, 1991
ATTACHMENT TO LICENSE AMENDMENT NO.117 QCIL11YOPERATlhGLICENSENO.NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 99 FAClllTY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the f ollowing pages of the Appendix "A" Technical Specifications with the enclosed pa9es. The revised pages are identified by Amendment number and cont 6in vertical lines indicating the areas of change.
Remove Pages Insert Pages 3/4 2-7 3/4 2-7 3/4 2-9 3/4 2-9 3/4 2-9b 3/4 2-9b 3/4 2-14 3/4 2-14 3/4 3-45 3/4 3-45 1
t 1
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2 For RA00 operation, F (2) 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 map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.
b.
Increasing the measured F (z) component of the power distribution 9
map by 3% to account for manufacturing tolerances and further l
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:
RTP N
F Fg (z) i g x g(*) for P > 0.5 P x W(z)
RTP N
F Fg (z) 1 0 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, FhTP is the F limit, K(2) is the normalized F (z) as a function of core height, g
9 P is the relative THERMAL POWER, and W(z) is the cycle dependent function that accounts for power distribution transients encountered i
during normal operation.
FhTP, K(z), and W(z) are specified in the CORE OPERATING LIMITS REPORT _per Specification 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 9
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.
- For_ Unit 1, Cycle 7, when the number of available moveable detector thimbles is greater than or equal to 50% and less than 75% of the total, the 5% mea-i surement uncertainty shall be increased to (5% + (3-T/14.5)(2%)] where T is the number o" available thimbles.
1 i
McGUIRE
-UNITS 1 and 2 3/4 2-7 Amendment No.117(Unit 1)
L Amendment No. 99(Unit 2) l
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Cortinued) 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:
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 sur-veillance (AFD within the target band about the target flux difference of Specification 3.2.1) during this time period.
Baseloadoperatig is then andAPL{ermittedprovidingTHERMALPOWERismaintainedbetweenAPL g
or between ND APL and 100% (whichever is most limiting) and FQ grveillance is maintained pursuant to Specification 4.2.2.4.
APL is defined as:
x K(Z) ] x 100%
APL over Z F (2) x W(Z)gt where:
F (z) is the measured F (Z) increased by the allowances for g
TP manufacturing tolerances and measurement uncertainty.
F is the F 9
limit.
K(2) is the normalized F (z) as a function of core height.
9 W(z)gt is the cycle dependent function that accounts for limited power distribution transients encountered during base load operation.
Ff,K(z),andW(z)BL are specified in the CORE OPERATING LIMITS REPORT 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 9
F (Z) is within its limit by:
9 a.
Using the movable incore detectors to obtain a power distribution ND map at any THERMAL POWER above APL b.
Increasing the measured F (Z) component of the power distribution 9
map by 5% to account for manufacturing tolerances and further increasing the value by 5%** to account for measurement uncertainties.
I Verify the requirements of Specification 3.2.2 are satisfied.
ND
- APL is the minimum allowable (nuclear design) power level for base load operation in Specification 3.2.1.
- For Unit 1, Cycle 7, when the number of available moveable detector thimbiss is greater than or equal to 50% and less than 75% of the total, the 5% mea-surement uncertainty shall be increased to (5% + (3-T/14.5)(2%)] where T is the number of available thimbles.
McGUIRE - UNITS 1 and 2 3/4 2-9 Amendment No.11XUnit 1)
Amendment No. 9RUnit 2)
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 2.
Comply with the reqairements of Specification 3.2.2 for F (Z) 9 exceeding its in it by the percent calculated with the following expression:
F (Z) x W(2)BL ND
[(max, over of[
J ) 1 ) x 100 for P y, AH RTP p
f x K(2) g.
The limits specified in 4.2.2.4.e, 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 it 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 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, i
i i
"For Unit 1, Cycle 7, when the number of available moveable detector thimbles is greater than or equal to 50% and less than 75% of the total, the 5% mea-surement uncertainty shall be increased to [5% + (3-T/14.5)(2%)] where T is the number of available thimbles.
McCUIRE - UNITS 1 and 2 3/4 2-9b Amendment No.11XUnit 1)
Amendment No. 95(Unit 2)
f POWER DISTRIBUTION LIMITS 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System (RCS) total flow L
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:
q SH a.
R=
[1.0 + MFAH (1.0 - P)]
p AH THERMAL POWER b.
P
= RATED THERMAL POWER s
FfH=MeasuredvaluesofFfg ebtained by using the movable incore c.
-detectors to obtain a power distribution map.
The measured values of F shall be used to calculate R since the figure q
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
ofFfH' FhP= The Fh limit at RATED THERMAL POWER (RTP) specified in the d.
COLR, and e.
MF3g= The power factor multiplier specified in the COLR.
1 APPLICABILITY:
MODE 1.
ACTION:
With the combination of RCS total flow rate and R outside the region of acceptable operation specified in the COLR:
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 combination of RCS total flow rate and R 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 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 />.
- For Unit 1, Cycle 7, when the number of available moveable detector thimbles
-is greater than or equal to 50% and less than 75% of the total, thg% mea-surement uncertainty shall be increased by changing the value of f in theRequationto[(0.0149/14.5)T+1.4453)whereTisthenumberBYavailable thimbles.
McGUIRE - UNITS I and 2 3/4 2-14 Amendment No.117(Unit 1)
Amendment No. 99(Unit 2)
. -. -. ~.. -.
-. - ~. -
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, I
b.
A minimum of two** detector thimbles per core quadrant, and I
c.
Sufficient niovable 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 Flux Detection System, b.
Monitoring the QUADRANT POWER TILT RATIO, or 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 N
c.
Measurement of F and F (Z) g q
- For Unit 1, Cycle 7, the minimum percentage of detector thimbles may be reduced to 50% provided the applicable provisions for >50% and <75% of the total detec-tor thimbles of specifications 4.2.2.2.b, 4.2.4.b, 4.2.2.5, 3.2.3.c 'and 3.3.3.2.b are followed.
- For Unit 1, cycle 7, when the number of available moveable detector thimbles
.is > 50% and <75% of the total, a minimum of four detector thimbles per qua3 rant is required (where quadrant includes both horizontal-vertical quad-rants and diagonally bounded quadrants).
McGUIRE - UNITS 1 and 2 3/4 3-45 Amendment No.117(Unit 1)
Amendment No.
99(Unit 2) l
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