ML19323G431
| ML19323G431 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/16/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19323G432 | List: |
| References | |
| NUDOCS 8006020440 | |
| Download: ML19323G431 (18) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION e
n WASHINGTON, D. C. 20$55 h
.t VIRGINIA ELECTRIC AND POWER COMPANY C9CKET N0. 50 281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated May 31, 1979, as supplemented October 16 and 25,1979, and January 11 and February 20, 1980, complies with the standards and requirements of the Atomic Energy. Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 regulations of the Commission; 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; 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.
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. 7 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment, and paragraph 3.8 of Facility Operating License No. DPR-37 is amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 58, 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 NWW" A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 15, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 58 FACILITY OPERATING LICENSE NO. DPR-37_
DOCKET NO. 50-281 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and certain vertical lines indicating the area of change.
Remove Insert 3.12-4 3.12-4 3.12-4a 3.12-4a 3.12-4b 3.12-4b 3.12-5 3.12-5 3.12-6 3.12-6 3.12-14 3.12-14 3.12-17 3.12-17 3.12-18 3.12-18 J
3.12-19 3.12-19 3.12-20 3.12-20 3.12-21 3.1 2-21 TS Table 3.12-1B TS Table 3.12-1B TS Figure 3.12-8 TS Figure 3.12-8a TS Figure 3.12-8b i
TS Figure 3.12-10 TS Figure 3.12-10 l
i 3
TS 3.12-4 Unit 1 Unit 2 Fq(Z) 1 2.05/P x K(Z) for P > 0.5 Fq(Z) 1 2.19/P x K(Z) for P > 0.5 F (Z) 14.10 x K(Z) for P 1 5
F (Z) < 4.38 x K(2) for P < 0.5 d
9 q
F", 1 1.55 a + o.2 u-m x T(BU)
F"g 1 1.55 a.o.2 a-m x T(Bo A
Assm.
l.476/P A
F Assm.
l.38/P F
AH AH AH Rod
-< l.55/P F"AH Rod< 1.45/P F
where P is the f raction of rated power at which the core is operating, K(Z) is the function given in TS Figure 3.12-8a for Unit 1 and Figure 3.12-8b for Unit 2, Z is the core height location of Fq, and T(BU) is theinterimthimblecellrodbowpenaltyonF{H E
'8"#*
3.12-9.
2.
Prior to exceeding 75% power following each core loading, and during each effective full power mo: th of operation thereaf ter, power distribu-tion maps using the movable detector system, shall be made to confirm that the hot channel factor limits of this specification are satisfied.
For the purpose of this confirmation:
Themeasurementoftotalpeakingfactor,Fqeas,shallbeincreased a.
by eight percent to account for manufacturing tolerances, measure-ment error, and theJeffects of rod bow. The measurement of enthalpy rise hot channel factor, the hot assembly enthalpy rise factor, l3 3H R d, shall be FfH and the hot rod enthalpy rise factor, F increased by four percent to account for measurement error.
If any measured hot channel factor exceeds its limit specified under 3.12.B.1, the rasctor power and high neutron flux trip setpoint
. shall be reduced until the limits under 3.12.B.1 are met.
If the hot ' channel factors cannot be brought to within the limits listed below within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the Overpower AT and Overtemperature AT trip setpoints shall be similarly reduced.
Amendment No. 58, Unit 2
T5 3.12-4a Unit 1 Unit 2-q _ 2.19 x K(Z)
F.a _< 4. 0 5 y.
K(Z)
F N
AH 1.55 T.'.. < 1. 5 5 F
22 -
Assa.
l.476 4
)
- 1 Assa.
l.38 AH
_5 iLOCA < 1*45 F
LOCA < l.55 N
4
~1Ej2od AH Rod l
4 L
4 DELETED 1
1 s
t i
1 4
t 5
1 4
1 a
w-Amendment No. 58,2tinit~2 m
g y
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DELETED I
Amendment flo. 58, linit 2
TS 3.12-5 3.
The reference equilibrium indicated axial flux difference (called the target flux difference) at a given power level Po, is that indicated axial flux difference with the core in equilibrium xenon conditions (small or no oscillation) and the control rods more than 190 steps w;thdrawn. The target flux difference at any other power level, P, is equal to the target value at Po =ultiplied by the ratio,
?/P. The target flux difference shall be measured at least once per o
equivalent full pcwer quarter. The carget flux difference cust be upda:ei duri:; each effective full power month of operation either by actual =easurement, or by linear interpolation using the most recent value a:d the value predicts; for the end of the cycle life.-
4.
Except as nodified by 3.12.B.4.a, b, c, or d beIow, the indicated axial flux difference shall be maintainad within a tS" band about the target flux difference (defines the target band on axial flux difference).
At a power level greater than 90 percent of rated power, if a.
the indicated axial flux dif ference deviates from its target band, within 15 minutes either restore the indicated axial flux difference to within the target bard, or reduce the reactor power to less than 90 percent of rated power.
b.- At a power level no greater thau 90 percent of rated power, i
(1) The indicated oxial flux difference may deviate from its target band for a maxfmum of one hour
-(cumulative) in any 24-hour period providad the flux dif ference 'is within the limits - shown.on Figure 3.12-10.
Amendment ~ No. 58, linit. 2 c_
TS 3.12-6 One minute penalty is accumulated for each one minute of operation outside of the target band at power levels equal to or above 50% of rated power.
(2)
If 3.12.3.4.b(1) is violated, then the reactor power shall be reduced to less than 50% power within 30 minutes and the high neutron flux setpoint shall be reduced to no greater than 55% power within the next four hours.
(3) A power increase to a level greater than 90 percent of rated power is contingent upon the indicated axial flux difference being within its target band.
(4) ScrreM'asce testing of the Power Range Neutron Flux G*--# = may be performed pursuant to Table 4.1-1 provided the indicated C is maintained within the limits of Figure 3.12-10.
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 vi:h the AFD outside of the target band during this testing without penalty deviation.
i At a power level no greater than 50 percent of rated power, (1) The indicated axial flux difference may deviate from its target band.
(2) A power increase to a level greater than 50 percent of rated power 1:e contingent upon the indicacea axial flux difference not being outside its target band for core than one hour accumulcted penalty during the preceding-24-hour period. One half minute penalty is accumuisted for each one minute of operation outside of the target band at power levels between 15% and 50% of rated power'.
d.
The axial flux difference limits of Specifications 3.12.B.4.a,
'b, and c may be suspended during.the-performance of physics tests provided:
~(1) The power level is maintained at or below 85% of rated power, and (2) The limits of Specification 3.12.B.1 are maintained.
The power level-shall be determined to be < 85% of rated power at least once per hour during physics tests. Verifi-cation that the limits of Specification 3.12.B.1 are being cet shall be dem;>nstrated through in-core flux mapping at
{
l' east once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
' Amendment No. 'iH. Ifn i t 7 W
TS 3.12-14 F (Z), hight Dependent lleat Flux Hot Channel Factor, is de f f swd as tlm maximum q
local heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods.
F, Engineering Heat Flux Hot Channel Factor, is defined as the allowance on heat flux required for manufacturing tolerances. The engineering factor allows for local variations in enrichment, pellet density and diameter, surface area of the fuel rod and eccentricity of the gap between pellet and clad. Combined statistically the net effect is a factor of 1.03 to be applied to fuel rod surface heat flux.
F g Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power for both LOCA and non-LOCA considerations.
sm., Hot Assembly Nuclear Enthalpy Rise Factor, is defined as the ratio F H of the integral of linear power along the assembly with the highest integrated power to the average assembly power.
It should be noted that the enthalpy rise factors are based on integrals and are used as such in the DNB and LOCA calculations. Local heat fluxes are obtained by using hot channel and adjacent channel explicit power shapes which take into account variations in radial (x-y) power shapes throughout the core.
Thus, the radial power shape at the point of maximum heat flux is not necessarily directly related to the enthalpy rise factors. The results of the loss of coolant accident analyses are conservative with respect to the ECCS acceptance criteria as specified in 10 CFR 50.46 using an upper bound envelope of 2.05 (Uni' 1) or 1.19 (Unit 2) times the hot channel factor normalized operating envelope given by TS Figures 3.12-8a and 3.12-8b.
Amendment No. 58, Unit 2
l' 6.
TS 3.12-L7 1
DELETED Amendment No. SR, Unit ?
A
TS 3.12-18 DELETED i
i Amendment No. SR, finit 2
~ ~
' ^ ~ ~ ~
~ ~ TS 3.12-19 '
~~
DELETED 1
The procedures for axial power distribution control are designed co mini-cize the ef fects of xenon redistribution on the axial power distribution during load-follow maneuvers. Basically, control of flux dif ference is required to limit the difference between the current value of flux dif-ference (AI) and a' reference value which corresponds to the ful1~ power equilibrium value of axial offset (axial offset = AI/ fractional power).
The referenec value'of flux difference varies with power level and burnup, but expressed as axial of fset it varies only with burnup.-
4 Amendment tio.-58,-Ilnit 2
TS 3.12-20 The technical specifications on power distribution control given in 3.12.B.4 together with,'he surveillance requirements given in 3.12.B.2 t
assure that the Limiting condition for Operation for the heat flux hot channel factor is net.
The target (or reference) value of flux difference is determined as felicws. At any ti=e that equilibrium xenon conditions have been estab-lished, the indicated flux difference is noted with the full length rod cc tzt1 bani zare than 190 steps withdrawn (i.e. normal full power opera-ti ; ; sitics appr:priate for the ti=e in life, usually withdrawn farther as burnup preceeds). This value, divided by the fraction of full power at -thich the core was operating is the full power value of the target flux difference. Values for all other core power levels are obtained by cultiplying the full power value by the fractional. power.
Since the indi-cated equilibric= value was noted, no allowances for.excore detector err.cr are necessary and indicated deviation of +5% AI are permitted from the inditated reference value. During periods where extensive load folicwing is required, it may be impractical to establish the required core conditions for measuring the target flux difference every month.
For this reason, the specification provides two methods for -updating the target flux difference.
Strict control of the flux' difference (and rod position) 'is not as neces-sary during part power operation. This is because xenon distribution control at part power is not as significant as the control at full
-Amendment flo. 58,tinit 2 i
TS 3.12-21 power and allowance has been made in predicting the heat flux peaking factors fort less strict control at part power.
Strict control of the flux difference is not always possible during certain physics tests or during excore detector calibrations.
Therefore, the specifications on pcvar distribution control are less restrictive during physics tests and er:are detector calibrations; this is acceptable due to the low probabili-ty f a significant accident occurring during these operations.
11 s--= 4 stances of rapid, unit power reduction automatic rod =ocion will cruaa :he flux diffarance to deviate from the target band when the reduced pc-ar level is reached. This does not necessarily affect the xenon dis-tributica sufficiently to change the envelope of peaking factors which can be reached on a subsequent return to full power within the target barf; however, to sinplify the specification, a limitation of one hour in any period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is placed on operation outside the band.
This ensures,that the resulting xenon distributions are not significantly different from those resulting from operation within the target band.
The instantaneous consequences of being outside the band, provided rod insertion li=its are observed, is not worse than a 10 percent increment in peaking factor for the allowable flux difference at 907. power, in the ranga + 13.8 percent- (+10.3 percent indicated) where for every 2 percent below rated power, the permissible flux difference boundary is extended by 1 percent.
As discussed above, the essence of the procedure is to maintain the xenon.
-distribution in the core asiclose to the equilibrium full power condition Amendment No. 58,ifnit 2-
TS Tc.bla 3.12-18 i
THIS TABLE HAS SEEN DELE' ZED.
I i
I I
Amendment flo. SP,, finit ?
L
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l Amendment No. 58, Unit 2
TS FIGURE 3.12-8b HOT CHANNEL FACTOR NOPJfALIZED OPERATING ENVELOPE SURRY FOWER STATION UNIT NO. 2
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T3 FIGURE 1.12-10 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED POWER SURRY POWER STATION 1D l
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Amendment No. 58,tinit 7
.