ML20072L208
| ML20072L208 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/28/1983 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072L211 | List: |
| References | |
| NUDOCS 8307130112 | |
| Download: ML20072L208 (15) | |
Text
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l DUKE P0"ER C0"PAMY DOCKET N0. 50-369 I?CGUIPE HUCLEAR STATION, Ul!IT 1 ADE!lDMEllT TO FACILITY OPERATING LICE!!SE Anendnent No. 22 License No. I;PF-9 1.
The Huclear Regulatory Coenission (the Comission) has found that:
A.
The application for acendnent to the McGuire fluclear Station, Unit 1 (the facility) Facility Operating License !!o. HPF-9 filed by the Duke Power Conpany ~(licensee) dated Noveeber 23, 1983, and supple-nented March 14, March 28, April 26, and April 27, 1983, complies with the standards and requirements of the Atonic Energy Act of 1954, as anended (the Act) and the Concission's regulations as set forth in 10 CFR Chapter I; U.
The facility will operate in confornity with the application, as auended, the provisions of the Act, and the regulations of the Con-nission; C.
There is reasonable assurance: (i) that the activities authorized by this anendmnt can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in empliance with the Connission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendnent will not be inimical to the comn defense and security or to the health and safety of the public; E.
The issuance of this anendnent is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirenents have been satisfied.
2.
Accordingly, the license is hereby anended by page changes to the Technical Specifications as indicated in the attachnents to this license amendment and paragraph 2.C.(2) of Facility Operating License No. HPF-9 is hereby amended to road as follows:
8307130112 830628 PDR ADOCK 05000369 P
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SURNAME) ys DATE)
RM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY usaro:ini-sw m
r (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Anendment No. 22, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license anendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C0!'illSSION
/
E inor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance: June 28, 1983 W
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DUKE POWER COMPANY DOCKET HQ. 50-370 MCCUIRE NUCLEAR STATIGH, UNIT 2 A!OlDRENT TO FACILITY OPERATING LICEHSL Anendnent No. 3 License No. 4PF-17 1.
The Huclear Regulatory Commission (the Connission) has found that:
A.
The application for anendment to the UcGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. HPF-17 filed by the Duke Power Corpany (licensee) dated Hovenber 23, 1982, anG supple-mented March 14, " arch 28, April 26, and April 27, 1983, conplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confornity with the application, as anended, the provisions of the Act, and the regulations of the Con-mission; C.
There is reasonable assurance: (1) that the activities authorized by this amendrent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in conpliance with the Connission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license anendnent will not be ininical to the connon defense and security or to the health and safety of the public; E.
The issuance of this anendnent is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirenents have been satisfied.
2.
Accordingly, the license is hereby anended by page changes to the Technical Specifications as indicated in the attachnents to this license amendnent and paragranh 2.C.(2) of Facility Operating License Ho. HPF-17 is hereby anended to read as follows:
- mL
. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment flo. 3, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license arendnent is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COPl!ISSIOU El nor G. Adensac, Chief Licensing Branch tio. 4 Division of Licensing Attachrent:
Technical Specification Changes Date of Issuance:
June 28, 1983 1)
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OFF1CiAL RECORD COF'Y usom mie NRC FORM 318 (10-80) NHCM 024o
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ATTACWiENT TO LICENSE A!!END!!EllT NO. 22 FACILITY OPERATIt!G LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AliEhDMENT NO. 3 FACILITY OPERATING LICENSE M0. IlPF-17 DOCKET !!0. 50-370 e
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Anendaent number and contain a vertical if ne indicating the area of change. The corresponding overicaf pages are also provided to maintain docunent completeness.
Amended Overleaf Pace Pace 3/4 2-8 3/4 2-7 3/4 2-9 3/4 2-10 3/4 2-11 3/4 2-12 B 3/4 2-4 8 3/4 2-3 8 3/4 2-5 8 3/4 2-6
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POWER DISTRIBUTION LIMITS r
SURVEILLANCE REQUIREMENTS (Continued)
RTP 2)
When the F is less than or equal to the F lidt for the x
appropriate measured core plane, additional power distribution RTP l
maps shall be taken and F compared to F and F at least x
xy once per 31 EFPD.
e.
The F limits for RATED THERMAL POWER (FRTP) shall be provided for xy x
all core planes containing Bank "D" control rods and all unrodded core planes in a Radial Peaking Factor Limit Report per Specifica-tion 6.9.1.12, f.
The F limits of Specification 4.2.2.2e., above, are not applicable xy in the following core planes regions as measured in percent of core height from the bottom of the fuel:
1)
Lower core region from 0 to 15%, inclusive, 2)
Upper core region from 85 to 100%, inclusive, 3)
Grid plane regions at 17.8 t 2%, 32.1 12%, 46.412%, 60.6 2%
and 74.9 2%, inclusive, and 4)
Core plane regions within 2% of core height (
2.88 inches) about the bank demand position of the Bank "D" control rods.
g.
With F exceeding F
, the effects of F on F (Z) shall be q
evaluated to determine if F (Z) is within its limits.
9 4.2.2.3 When F (Z) is measured for other than F determinations, an overall 9
measured F (Z) shall be obtained from a power distribution map and increased q
by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
\\.
McGUIRE - UNITS 1 and 2 3/4 2-7
.js W
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 rate and R, R shall be maintained within the region of allowable operation 3
7 shown on F1gure 3.2-3 for four loop operation:
Where:
N FAH a*
R 1 = 1.49 [1.0 + 0.2 (1.0 - P)]
R) b.
R 2 * [1-RBP(BU)]
THERMAL POWER c*
P
=
RATED THERMAL POWER d.
F g = Measured values of F g obtained by using the movable incore detectors to obtain a power distribution map.
The measured values of F shall be used to calculate R since Figure 3.2-3 H
includes penalties for undetected feedwater venturi fouling of 0.1% and for measurement uncertainties of 1.7% for flow and 4%
for incore measurement of F H, and RBP (BU) = Rod Bow Penalty as a function of region average burnup as e.
shown in Figure 3.2-4, where a region is defined as those assemblies with the same loading date (reloads) or enrichment (first core).
APPLICABILITY:
MODE 1.
ACTION:
With the combination of RCS total flow rate and R), R2 utside the region of acceptable operation shown on Figure 3.2-3:
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,j R to within the above limits, or 2
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 />.
Amendment No. 22(Unit 1)
McGUIRE - UNITS 1 and 2 3/4 2-8 Amendment No. 3 (Unit 2)
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I y
PENALTIES OF 0.1% FOR UNDETECTED ~~
ACCEPTABLE: !
c3 FEEDWATER VENTURI FOULING AND j
OPERATION
--t 2--
5 MEASUREMENT UNCERTAINTIES OF i
i M
46 1.7% FOR FLOW AND 4% FOR INCORE i- -~~
REGION FOR
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R ONLY MEASUREMENT OF F$g ARE INCLUDED V
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IN THIS FIGURE.
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R = R /11 - RBP(Bu)l
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FIGURE 3.2-3 RCS TOTAL FLOWRATE VERSUS R AND R - FOUR LOOPS IN OPERATION i
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PbWERDISTRIBUTIONLIMITS ACTION: (Continued) b. Within 24 hours of initially being outside the above limits, verify through incore flux mapping and RCS total flow rate comparison that the combination of R, R and RCS total flow rate are restored to 3 within the above limits,2or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours. c. Identify and correct the cause of the out-of-limit 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, R and indicated 3 7 RCS total flow rate are demonstrated, through incore flux mapping and RCS total flow rate comparison, to be within the region of acceptable operation shown on Figure 3.2-3 prior to exceeding the following THERMAL POWER levels: 1. A nominal 50% of RATED THERMAL POWER. 2. A nominal 75% of RATED THERMAL POWER, and 3. Within 24 hours of attaining greater than or equal to 95% of RATED THERMAL POWER. SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable. 4.2.3.2 The combination of indicated RCS total flow rate determined by process computer readings or digital voltmeter measurement and R and R y 2 shall be within the region of acceptable operation of Figure 3.2-3: a. Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and b. At least once per 31 Effective Full Power Days. 4.2.3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation of Figure 3.2-3 at least once per 12 hours when the most recently obtained values of R and R, btained per Specification y 2 4.2.3.2, are 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 precision heat balance measurement at least once per 18 months. Amendment No.22 (Unit 1) McGUIRE - UNITS 1 and 2 3/4 2-11 Amendment No. 3 (Unit 2)
i POWER DISTRIBUTION LIMITS 3/4.2.4 QUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION 3.2.4 The QUADRANT POWER TILT RATIO shall not exceed 1.02. APPLICABILITY: MODE 1 above 50% of RATED THERMAL POWER *. ACTION: a. With the QUADRANT POWER TILT RATIO determined to exceed 1.02 but less than or equal to 1.09: 1. Calculate the QUADRANT POWER TILT RATIO at least once per hour until either: a) The QUADRANT POWER TILT RATIO is reduced to within its limit, or b) THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER. 2. Within 2 hours either: a) Reduce the QUADRANT POWER TILT RATIO to within its limit, or b) Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1.0 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours. 3. Verify that the QUADRANT POWER TILT RATIO is within its limit within 24 hours after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours 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 hours; and 4. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL power may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours or until verified acceptable at 95% or greater RATED THERMAL POWER. ^See Special Test Exception 3.10.2. McGUIRE - UNITS 1 and 2 3/4 2-12
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I .1 - t i.: i. i i -i I: i 2 0.20 Q- - - l.. r-' ~l ' 1 .I .e e. l. --l : l ru r !:IM r i:I 'l ' I i- =. I 'a f f. li 0.10 .l..- l -l l: T -~ ..g. "g:- 1". O ~ -30% -20% -10% 0 +10% +20% +30% INDICATED AXIAL FLUX DIFFERENCE FIGURE B 3/4 2-1. l l TYPICAL INDICATED AXIAL FLUX DIFFERENCE VERSUS THERMAL POWER l N - McGUIRE - UNITS 1 and 2 B 3/4 2-3 f 1
W POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR, and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued) 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. EhwillbemaintainedwithinitslimitsprovidedConditionsa.through
- d. above are maintained.
As noted on Figures 3.2-3 and 3.2-4, RCS flow rate and F may be " traded off" against one another (i.e., a low measured RCS flow H rate is acceptable if the measured F is also low) to ensure that the calcu-H lated DNBR will not be below the design DNBR value. The relaxation of F as H a function of THERMAL POWER allows changes in the radial power shape for all permissible rod insertion limits. R as calculated in Specification 3.2.3 and used in Figure 3.2-3, accounts 1 for F less than or equal to 1.49. This value is used in the various accident H analyses where F influences parameters other than DNBR, e.g., peak clad tem-H perature, and thus is the maximum "as measured" value allowed. R, as defined, 2 allows for the inclusion of a penalty for Rod Bow on DNBR only. Thus, knowing the"asmeasured"valuesofFhandRCSflowallowsfor" tradeoffs"inexcess of R equal to 1.0 for the purpose of offsetting the Rod Bow DNBR penalty. Fuel rod bowing reduces the value of DNB ratio. Credit is available tc partially offset this reduction. This credit comes from a generic design margin which total 9.1% when the analysis is performed with the approved interim methods. The penalties applied to F to account for rod bow (Figure H 3.2-4) as a function of burnup are consistent with those described in Mr. John F. Stolz's (NRC) letter to T. M. Anderson (Westinghouse) dated ) April 5,1979, and W 8691, Rev.1 (partial rod bow test data). 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 for a full-core map taken with the Incore Detector Flux Mapping System, and a 3% allowance is appropriate for manufacturing tolerance. Amendment No.22 (Unit 1) McGUIRE - UNITS 1 and 2 B 3/4 2-4 Amentment No. 3 (Unit 2)
.n POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued) WhenRCSflowrateandFharemeasured,noadditionalallowancesare necessary prior to comparison with the limits of Figures 3.2-3 and 3.2-4. Measurement errors of 1.7% for RCS total flow rate and 4% for F" have been allowed for in determination of the design DNBR value. The measurement error for RCS total flow rate is based upon performing a precision heat balance and using the result to calibrate the 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-conservative manner. Therefore, a penalty of 0.1% for undetected fouling of the feedwater venturi is included in Figure 3.2-3. Any fouling which might bias the RCS flow rate measurement greater than 0.1% can be detected by monitoring and trending various plant performance parameters. If detected, action shall be taken before performing subsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cle'ned to eliminate the fouling. The 12-hour periodic surveillance of indicated RCS flow is sufficient to detect only flow degradation which could lead to operation outside the accept-able region of operation shown on Figure 3.2-3. 3/4.2.4 QUADRANT 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 STARTUP 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 tilts.. A limiting tilt of 1.025 can be tolerated before the margin for uncertainty in F is depleted. A limit of 1.02 was selected to provide an allowance for the q uncertainty associated with the indicated power tilt. 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 control rod. In the event such action does not correct the tilt, the margin for uncertainty on F is reinstated by reducing q the maximum allowed power by 3% for each percent of tilt in excess of 1.0. Amendment No. 22 (Unit 1) McGUIRE'- UNITS 1 and 2 B 3/4 2-5. Amendment No. 3 (Unit 2)
}- s P0WER DISTRIBUTION LIMITS 1 l BASES QUADRANT POWER TILT RATIO (Continued) 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 l POWER TILT RATIO. The incore detector monitoring is done 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 parameters 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 minimum DNBR of 1.30 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 limits following load changes and other expected transient operation. r Amendment No.22 (Unit 1) LMcGUIRE - UNITS 1 and 2 8 3/4 2-6 Amendment No. 3 (Unit 2) ..._.. _. _ _ - -.. _ _... -,.}}