ML20024G852

Proposed Tech Specs,Including Page 2.1/2.3 & App 7

ML20024G852
Person / Time
Site:	Monticello
Issue date:	07/10/1975
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20024G851	List: ML20024G850 ML20024G852
References
NUDOCS 9105010214
Download: ML20024G852 (10)

Text

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O OO O.PJ n-lKJb 09 l VG LIMITI!!f. SAFETY SYSTE?! SETTI!;GS

@ 2.') SADTi LWITS ff 23L FffEL CIADDING I!TTEc"ITY 2.3 MXL CIADDII!G IIITEGRIlT Applicability- g rficability:

l Applies to the interrelated variables Applies to trip settings of the instruments . d devicr ; which are provided to prevent the 3 isociatad with fuel thernal behsvior. reactar nystem safety limits frem being exceeded.

Oblective:_  ! icc t ive :

To de fine the level of the process variables To establish limits belw which the nt which automatic protective action is integrity of the fuel cla:'!!rg is preserved. initiated to prevent the safety limits from being exceeded.

Specifiention: jpec i fication:

A. Core Therm 1 Pwer Limit (Reactor 'Ih e limiting safety system settings shall be as Pressure > 800 Psia and Gore Flow is rpecified below:

> 107. of Rated)

A. Neutren Flux Scram When the reactor pressure is > 800 Psia and core flow is > 107 of rated, the 1. APRM -- The APFli flux scram trip setting existence of a mini::mri critical power shall be as shown in Figure 2.3.1 and shall bc:

ratio (MCPR) less than 1.06 shall con- S$ 0.58 W + 62 7.

stitute violation of the fuel cla3 ding integrity safety limit, where:

S = Scram setting in percent of rated themal power W= rercent of desis;n recirces-lation driving flew 6

2.1/2.3 REV l - _ _ _ _ _ _ _

l .

2.0 SAFETY L1? TITS LIMITII:G SAFETf SYSTD1 SETTINGS In the event of operation with a total peakin :

B. Core Therma l Power Linit (Reactor Pres- factor (PF) greater than the design peaking factor sure 6 804 rsia or Coro Flow 5 107. (DPF), the setting shall be podified as " IIcvn:

of Rated)

Khen the rea ctor pressure is 5 800 S 2 (0.58 W & 62 7.) DFF pg Psia or Core Flow is $i 7 1 of rated, the core thermal power shall not ex- where:

cced 257 of rated therna! pcwe r. Drr = 3.08 for 7 x 7 fuct  !

= 3.04 for 8 x 8 fuel C. Power Transients '. IR?t--Flux Scram retting shall be $ 207. of rated To insure that the safety ILmit estab- i lished in Specification 2.1. A is not \ Pat Red Block--lhe APRM red block setting shall be B.

exceeded, enf~ required scram shall be slu nm in Figure 2.3.1 and shall be:

initiated by i ts primary source signal as indicated by the plant proccas com- RB 5 0.58 W + 50%

puter.

there.

RB = Red Block setting in percent of rated thermal power W = Percent of design recirculation driving flow In the event of operation with a total peaking factor (PF)  !

nreater than the design peaking factor (DFF), the setting Shall be modified as follows:

UPF RB 5 (0.58 W + 50 %)

I j pp taere: ,

t I

DPF = 3.08 for 7 x 7 fuct I

= 3.0% for 8 x 8 fuel C. Reactor Low Water Level Scram setting shall be h 10'6 obove the top of the active fuel.

7 2.1/2.3

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APPENDIX C 1

TYPIC *dt Eh*R GETAB APPLIC\ TION P_lant Infomation Reouest

1. QUESTION:

%j Identify the scrm reactivity curve used to calculate the cystem responce folicving a turtir.c trip at the end of the equilibriten cycle. Ic it the desi,r. basic c eve ("D" cur.:c) ?

RESPONSE

The scram reactivity curve applied is the Manticello End-of-Cycle 4 "C" curve (EOC-C), nultiplied by the Design Conservative Factor (0.8) . The EOC4-C curve reflects the expected Cycle 4 End of Cycle scram reactivity function, l

2. QUESTION-Provide the n ~inal valucc of the fcliccing par =cters used in the derivatior, of M:Fie2.CC ani 2. 3C: h fa:tcv, arici p xcr chapa, crial c:d local pc 1'in; fac n re, radia2 pcahin; fa: tor, nc':fuc2 p xcr fraction, aucr pc p".% r der.sity, bundle pc:xr, bw:dic fice, and inlet cr.thalpy. Justify the par cters cclected.

RESRT:SE :

The following list su:miarizes the requested infomation.

1. R-factor = 1.102. This value is !he highest expected R-factor during the operating cycle.

2. Axial Power Shape:

APF N3DE APF NODE 0.3F 1 (Bottom) 1.44 13 0.45 2 1.51 14 0.50 3 1.55 15 0.53 4 1,57 10 0.60 5 1.55 17 0.65 6 1.50 IE 0.70 7 1.42 le 0.75 8 1.28 20 0.85 9 1.10 21 1.00 10 0.90 22 1.16 11 0.69 23 1.34 12 0.51 24 (Top) 1

l APPENDIX C

2. RLSPONSE:

2. Axial Powr Shape: (Continued)

The above design axial power shape yields a conservative representation of the conditions which might exist during an operating cycle as discussed further in NEIO-10958 Appendix 1.

)

l

3. Axial Peaking Factor = 1,57 at node 16 as shown above. l

4. Local Peaking Factor = 1.22 (design value, but not used directly in GETAB analyses.)

5. Radial Peaking Factor = 1.47. This design value is larger than the l

highest expected bundle radial peaking factor; therefore, it establishes '

a conservative upper limit.

6. Nonfuel Power Fraction = 0.035 (Design value, but not critical to GETAB evaluations.

7. Average Power Density = 40.6 DUL (Design value, but not used direct?y in GETAB analyses.

8. Bundle Power = 4.962 (Based on the design core power and the r h radial peaking factor discussed in item 5.)

5

9. Bundle Flow = 1.065 x 10 lbs/hr (This value is the steady-state flow in the fuel bundle operating at the highest bundle power,

10. Inlet Enthalpy = 523.0 Btu /Lb (Design value determined from a reactor heat balance operating with rated core flow,100% power and maximtn feedwater temperature.)

APPEND 1X C 1

3. QUliFi!ON :

Identify the relative bundic to biesdic power distribution (by histogr.r r:cthod) that is e-ployed in the application of the GET .d statistical analysis to Monticello.

RESTO SE:

"Ihe histogram of relative bundic power used in GETAB statistical analysis for hbnticello is shown in Figure 3-1. This histogram was generated by arranging the control rod pattern such that the maximum number of fuel assemblics were placed at positions of minimum FEPR as described further in NED0-10958 Appendix IV.

4.a QUESTION:

Vnat is the rciative b:c:i:c power dictribution of the Monticello plant at ,

the vorst tir:a of the fucl cycle? Io it the sa";c ca the one used in ihr ^

etatictical r.,= L iliny t r:n<:iticm analycic. If not, justify L'hy it ie not ucci in the derivaticn cf MTR valucc.

RESPONE:

Because the power distribution described in the answer to Question 3 is selected and forced to be conservative (NEDJ-10958 Appendix IV-4), the worst distribution for hbnticello during its fuel cycle is not expected to _

be as severe as the distribution used in the analysis.

To illustrate the conservatism inherent in the selected power distribution, comparative analyses were performed using an actual operating power C istribution fram a typical BWR/4, The analysis showed that the 99.9% limit is met with an MCPR 0.05 lower than the value krived with the conservative power distribution. Hence, the selected pwer distribution is indeed very conservative.

APPL % DIX C I

4.b QlESilGN:

Provide a Monticello hwndle poucr histogram (calculated result) in order to see that the predicted Monticelto caec io not aa severe as that used in GETAB analyaca and reportcd in the response to 4.a, above.

PISTONSE :

The requested histogram is shown in Figure 4-1. The case chosen is an end-of-cycle condition which typically exhibits highest radial peaking.

Comparison with that used for ETAB analysis (question 3) will show that the Histogram used in ETAB analyses is skewed more to the right than the calculated histogram. Therefore, in the response to question 4a above, it can be concluded that the Histogram used for ETAB analyses is indeed conservative for Monticello.

5. QUESTION:

The TII' uncertainty cf 6. 7% io prcote ably based on a epctric, reload core, a*t3 LPfa' catrz cla:rd T:i' data (based cn the information chcun in NEDO-20340).

Jtsstify the accu ~'ption cf poucr cy~t":ctly for the N:nticello reload corc.

l RESPONSI::

The 8.M uncertainty accounts for no identified physical assymmetry in the Mon +.icello core. If some assymetry exists, it has not been detected and is therefore not taken into account. The 8.M relates only to TIP assymmetry.

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