ML19341B200

Amend 30 to License DPR-70,revising Tech Spec Limiting Axial Flux Difference Target Band

ML19341B200
Person / Time
Site:	Salem
Issue date:	12/22/1980
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML19341B201	List: ML19341B200 ML19341B203 ML19341B205
References
NUDOCS 8101300433
Download: ML19341B200 (11)

Text

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UNITED STATES y

g NUCLEAR REGULATORY COMMISSION g

• E WASHINGTON, D. C. 20555 t

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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPEP,ATING LICENSE Amendment No.30 License No. DPR-70 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated Octoher 20, 1980, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regul:tions 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 (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 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.

8101300

s.

ATTACHMENT TO LICENSE AMENDMENT N0. 30 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 2-1 3/4 2-1 3/4 2-6 3/4 2-6 B3/4 2-2 83/4 2-2 83/4.2-3 B3/4 2-3 f

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+m INDICATED AXIAL FLUX DIFFERENCE Fipre 5 3/4 21 TYPICAL INDICATED AXIAL PLUX OlFFERENCE VERSUS THERMAL PCWER SALEM - UNIT 1 B 3/4 2-3 Amendment No. 30

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M WER DISTRIBUTION LIMITS ~

BASES 3/4.2.2 and.3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL AND RADIAL PEAKING FACTORS-and Fyy(Z)

F II):

H O

The limits on heat flux and nuclear enthalpy hot channel factors 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 acceptance criteria limit.

Each of these hot channel factors are measurable but will nonna11y only be determined periodienlly as specified in Specifications 4.2.2 and 4.2.3.

This periodic surveillance is sufficient to insure that the hot channel factor limits are maintained provided:

Control rod in a single group move together with no individual a.

rod insertion differing by more than + 12 steps from the group demand posillon.

'b.

Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.5.

The control rod insertion limits of Specifications 3.1.3.4 and l

c.

3.1.3.5 are maint'ained, d.

The axial power distribution, expressed ih tenns of AXIAL FLUX DIFFERENCE, is maintained within the limits.

l N

The relaxation in F as a function of TliERMAL POWER allous changes the radial power shap8Nfor all permissible rod insertion li' nits.

i a$$ve,ll be maintained within its limits provided conditions a t wi are maintained.

When an Fn measurement is taken, both experimental error and man-ufacturing to1Mrance must be allowed for. 5% is the appropriate allowance for a full core map taken with the incore detector flux mapping system and 3% is the appropriate allowance for manufacturing tolerance.

N When F is measured, experimental error must be allowed for and 4%

is the apprbhriate allowance for a full core map taken with the incore detection system. The specified limit for also contains an 8%

ance for uncertainties which mean that Asnnal operation will result all in The 8% allowance is based on the following considera-tionN < 1.55/1.08.

SALEM - UNIT 1 B 3/4 2-4 Amendment No. M,

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3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance of fuel integ-rity during Condition I (Nomal Operation) and II (Incidents of Moderate Frequency) events by:

(a) maintaining the minimum DNBR in the core >

1.30 during normal operation and in short term transients, and (b) 1Tmiting the fission gas release, fuel pellet temperature and cladding mechanical properties to within assumed design criteria.

In addition. limiting the peak linear power density during Cnndition 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 hot channel fac' tors as used in these specifi-cations are as follows:

F(Z)

Heat Flux Hot Channel Factor, is defined as the maximum local 0

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.

F"3g 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.

Radial Peaking Factor is defined as the ratio of peak power xy(Z)

F density to average power density in the horizontal plane at core elevation Z.

3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)

The limits on AXIAL FLUX DIFFERENCE assure that the Fn(Z) upper i

bound envelope of 2.32 times the normalized axial peaking Yactor is not exceeded during either normal operation or in the event of xenon redts-tribution following power changes.

Target flux difference is detemined 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 target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL p0WER for the associated core burnup l

conditions. Target flux differences for other THERMAL POWER levels are i

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.

l SALEM - UNIT 1 B 3/4 2-1 Amendment No. N.20 l

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POWER DISTRIBUTION LIMITS BASES 4

Although it is intended that the plant will be operated with the AXIAL FLUX DIFFERENCE within the +6, -9% target band about the target flux l

difference, during rapid plant THERMAL POWER reductions, control rod motion will cause the AFD to deviate outside of the target band at re-duced THERMAL POWER levels. This deviation will not affect the xenon redistribution sufficiently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duration of the devi-I ation is limited.

Accordingly, a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation limit cumu-lative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is provided for operation outside of the target band but within the limits of Figure 3.2-1 while at THERMAL i

POWER levels between 50% and 90% of RATED THERMAL POWER.

For THERMAL 1

POWER levels between 15% and 50% of rated THERMAL POWER, deviations of the AFD outside of the target band are less significant. The penalty of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> actual time reflects this reduced significance.

Provisions for monitoring the AFD are derived from the plant nuclear instrumentation system through the AFD Monitor Alarm. A control room recorder continuously displays the auctioneered high flux difference and the target band limits as a function of power level. A first alarm is received any time the auctioneered high flux difference exceeds the target band limits. A second alarm is received if the AFD exceeds its allowable limits for a cumulative time of one hour during any 24 hm. -

time period starting with the occurrence of the first alarm. Time 'out-side the target band is graphically presented on the strip chart.

Figure B 3/4 2-1 shows a typical monthly target band.

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r SALEM - UNIT 1 B 3/4 2-2 Amendment No. 30

-. -, ~.

POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR-FK LIMITING CONDITION FOR OPERATION 3.2.2 F (Z) shall be limited by the following relationships:

g F (Z) < [2.32] [K(Z)] for P > 0.5 0

P F (Z) < [(4.64)] [K(Z)] for P < 0.5 n

THERMAL POWER where P = RATED THERMAL POWER and K(Z) is the function obtained from Figure 3.2-2 for a given core height-location.

APPLICABILITY: MODE 1 ACTION:

With F (Z) exceeding its limit:

n Reduce THERMAL *, POWER at least 1% for each 1% Fn(Z) excete '3e a.

limit within 15 minutes and similarly reduce the Power. 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 AT Trip Setpoints have been reduced at'least 1% for each 1% F (Z).

n exceeds the limit.

The Overpower AT Trip Setpoint re5uction shall be performed with 'the reactor in at least HOT STAND 8Y.

b.

Identify'and correct the cause of the out of limit condition prior to' increasing THERMAL POWER above the reduced limit

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required by a. above; THERMAL. POWER may then be increased provided F (Z) is. demonstrated through incore mapping to be n

within its limit.

SALEM -. UNIT.1"

.'3/4! 2-5

-Amendment No'. 30

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 F

shall be evaluated to determine if F (Z) is within its "Y

0 limit by:

Using the movable incore detectors to obtain a power distribu-a.

tion map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

b.

Increasing the measured F component of the power distribution map by 3% to account for EITnufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.

c.

Comparing the F computed (F ) obtained in b, above to:

xy 1.

The F limits for RATED THERMAL POWER (F P) for the xy appropriate measured core planes give.: in e and f below, and 2.

The relationship:

F,

=F

[l+0.3(1-P)]

l wher,e F ' is the limit for fractional THERMAL POWER P

operatio expressed as a function of F and P is the fraction of RATED THERMAL POWER at which F was measured.

d.

Remeasuring F according to the following schedule:

xy P

1.

When F is greater than the F limit for the appropriate measured core plane but less than the F,y relationship, additional power distribution maps shall be taken and P

F,C compared to F and F y

a)~ Either within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding by 205 cf RATED THERMAL POWER or greater, the THERMAL ~ POWER at which F was last determined, or SALEM - UNIT 1 3/4 2-6 Amendment No. 30

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3/4. 2 POWER DISTRIBUTION LIMITS AXI AL FLUX DIFFERENCE (AFD)

LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within a +6, -9% target band (flux difference units) about the target flux 2

difference.

APPLICABILITY: MODE 1 AB0VE 50% RATED THERMAL POWER

• ACTION:

a.

With the indicated AXIAL FLUX DIFFERENCE outside of the above limits and with THERMAL POWER:

1.

Above 90% of RATED DiERMAL POWER, within 15 minutes:

a) Either restore the indicated AFD to within the target band limits, or

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b)

Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.

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2.

Between 50% an~d 90% of RATED THERF%L POWER:

a)

POWER OPERATION may continue provided:

1) The indicated AFD has not been outside of the above limits for more than-1 hour penalty deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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 />.

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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 /> operation may be accumulated with the AFD ~

outside of the target band during this testing i'

without penalty deviation.

l

• See Special Test Exception 3.10.2 i

SALEM - UNIT-1

.3/4 2-1

' Amendment-No. E,19,30 -

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POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) b.

THERMAL POWER shall not be increased above 90% of RATED THERMAL POWER unless the indicated AFD is within the above limits and ACTION 2.a) 1), above has been satisfied.

THERMAL POWER shall not be increased above 50% of RATED THERMAL c.

POWER unless the indicated AFD has not been outside of the above limits for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.1.1 The ind'eated AXIAL FLUX DIFFERENCE shall be determined to be within its lim'ts during POWER OPERATION above 15% of RATED THERMAL POWER by:

Monitoring the indicated AFD for each OPERABLE excore channel:

a.

1.

At least once per 7 days when the AFD Monitor Alar is i

OPERABLE, and 2.

At least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter restoring the AFD Monitor Alarm to OPERABLE status.

I b.

Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AXIAL FLUX DIFFERENCE Monitor Alam is inoperable.

The logged values of the indicated AXIAL FLUX DIFFERENCE shall be assumed to exist during the interval preceding each logging.

4.2.1.2 The indicated AFD shall be considered outside of its limits when at least 2 of 4 or 2 of 3 OPERABLE excore channels are indicating the AFD to be outside the limits of Specification 3.2.1.

Penalty deviation outside of the limits shall be accumulated on a time basis' of:

One minute penaity deviation for each one minute of POWER a.

OPERATION cutside of the limits at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and b.

One-half minute. penalty deviation for each one minute of POWER OPERATION outside of the limits at THERMAL POWER levels below 50% of RATED THERMAL POWER.

SALEM - UNIT 1 '

3/4 2-2 Amendment No. 29, 30

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