ML20116F371

Proposed Tech Specs 6.9.1.6b Including TR, SBLOCA Analysis Methodology, in List of NRC-approved Methodologies & Rev of Unit 1 Rx Trip Setpoints

ML20116F371
Person / Time
Site:	Comanche Peak
Issue date:	07/31/1996
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20116F358	List: ML20116F356 ML20116F371
References
NUDOCS 9608060328
Download: ML20116F371 (7)

Text

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2G 40 80 80 100 120 PERCENTOF RATED THERMAL POWER FIGURE 2.1 la UNIT 1 REACTOR CORE SAFETY LIMITS COMANCHE PEAK - UNITS 1 AND 2 22 Unit 1 Amendment No. H,21 Unit 2 Amendment No. 7 b

. _ -.. to TXX 96433 Page 2 of 6 670 Unacceptable gg Operation 650 P = 2385 psig 640 P = 2235 psig E 630 s

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20 40 60 80 100 120 Pweent et meses w Power FIGURE 2.1-la UNIT 1 REACTOR CORE SAFETY LIMITS

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COMANCHE PEAK - UNITS 1 AND 2 22 Unit 1 Amendment No. H.21 Unit 2 Amendment No. 7 1

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- to TXX-96433 Page 3 of 6 TABLE 2.2-1 (Continued)

TABLE NOTATIONS NOTE 1:

Overtemperature N-16 N

=K

- K, [1r_Ii1 T, - T,*] + K (P-P1) -f (Aq) i 3

t 1+ T S 2

Where:

N

= Measured N-16 Power by ion chambers.

T,

= Cold leg temperature.

'F, T,'

= 560.5*F for Unit 1. - 560.8*F for Unit 2 - Reference T, at RATED THERMAL POWER, K

= 1.150.

i K,

0.0134/"I 0'.'0173/*F for Unit 1 0.0138/*F for Unit 2 1 _i 1

The function generated by the lead-lag controller for T.

1+ t,S dynamic compensation, t,

r, Time constants utilized in the lead-lag controller for

=

i T,t 2 10s, and r, s 3s, i

K

= 0.000710/ psi;; 0;_000890/psig for Unit 1 3

0.000720/psig for Unit 2 COMANCHE PEAK - UNIT 1 AND 2 2-9 Unit 1 - Amendment No. 44de, 49 Unit 2 - Amendment No. 7, 35

! to TXX-96433 l

Page 4 of 6 TABLE 2.2-1 (Continued)

TABLE NOTATIONS (Continued)

NOTE 1:

(Continued) k Pressurizer pressure, psig, P

=

P >_ 2235 psig (Nominal RCS operating pressure),

d Laplace transform operator, s2, S

=

b and f (A q) is a function of the indicated difference between top and bottom halves of t

detectors of the power-range neutron ion chambers; with gains to be selected based on measured m

instrument response during plant STARTUP tests such that:

For Unit 1 m

(I) for qt - q, between -65% and +44416%. f ( A q) = 0, where qt and q, are percent RATED t

g THERMAL POWER in the top and bottom halves of the core respectively, and qt + q,is total THERMAL POWER in percent of RATED THERMAL POWER.

(ii) for each percent that the magnitude of qt - q, exceeds -65%. the N-16 Trip Setpoint shall be automatically reduced by 414010X* of its value at RATED THERMAL POWER, and (111) for each percent that the magnitude of qt - q, exceeds +444;6%. the N-16 Trip Setpoint gg shall be automatically reduced by e-26tr3.04% of its value at RATED THERMAL POWER.

3#

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• fNois.etpointJreduction21s3equiredifoNthelspan:ofCthe" I;findication]

m-II 3a "t

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_ - - _. _ _ to TXX-96433 Page 5 of 6 TABLE 2.2-1 (Continued)

TABLE NOTATIONS (Continued)

NOTE 1:

(Continued)

For Unit 2 (I) for q, - q, between -65% and +2.5%. f (A q) = 0, where q, and q, are percent RATED t

THERMAL POWER in the top and bottom halves of the core respectively, and qt + g,is total THERMAL POWER in percent of RATED THERMAL POWER.

1 (ii) for each percent that the magnitude of qt - q, exceeds -65% the N-16 Trip Setpoint shall be automatically reduced by 1.86% of its valva at RATED THERMAL POWER, and l

(iii) for each percent that the magnitude of q, - q, exceeds +2.5%. the N-16 Trip Setpoint shall be automatically reduced by 1.65% of its value at RATED THERMAL POWER.

NOTE 2: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than f

3-61+3;64% of span for Unit 1 or 1.864 of span for Unit 2.

L CONANCHE PEAK - UNIT 1 AND 2 2-11 Unit 1 - Amendnent No. 14, 21, 41, 49 Unit 2 - Amendment No. h-M. 35

._ to TXX-96433 Page 6 of 6 glINISTRATIVE CONTROLS f4RE OPERATING LIMITS REPORT (Continued) i Reference 18) is for Unit 2 only:

18). WCAP 9220 P-A, Rev. 1, " WESTINGHOUSE ECCS EVALUATION MODEL 1981 Version". February 1982 (M Proprietary).

j 19). RXE-94 001-A, " Safety Analysis of Postulated Inadvertent Boron Dilution Event in Modes 3, 4, and 5," February 1994.

(Methodology for Specifications 3/4.1.1.1, 3/4.1.1.2, 3/4.1.2.2, 3/4.1.2.4, and 3/4.1.2.6 - Shutdown Margin.)

20) J' ~ Methodology," December.2 995.RXE 95;001-P;lSmall Break' Loss or Coola 1

' ~ ~

6.9.1.6c The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.6d The CORE OPERATING LIMITS REPORT, including any mid cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS i

6.9.2 In addition to the applicable reporting requirements of Title 10 Code of Federal Regulations, special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

6. *t 0 NOT USED 6.11 NOT USED 6.12 HIGH RADIATION AREA 6.12.1 Pursuant to paragraph 10CFR20.1601(c), in lieu of the " control device" or " alarm signal" required by paragraph 10CFR20.1601(a), each high radiation area, as defined in 10CFR20, in which the intensity of radiation is equal to or less than 1000 mrem /h at 30cm (12 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).

Individuals qualified in radiation protection procedures (e.g.,

Radiation Protection Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with dose rates equal to or less than 1000 mrem /h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

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COMANCHE PEAK UNITS 1 AND 2 6 11 Unit 1 Amendment No. 21.42.44.50

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Unit 2 - Amendment No. 7.2C,20,36 1

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