ML20080R427

Amends 34 & 20 to Licenses NPF-87 & NPF-89,respectively, Changing TS 3/4.2.2, Heat Flux Hot Channel Factor-FQ(Z) & 6.9.1.6.a, COLR to Implement Revised Methodology for Calculating Penalty to Fq(Z)

ML20080R427
Person / Time
Site:	Comanche Peak
Issue date:	03/01/1995
From:	Polich T NRC (Affiliation Not Assigned)
To:
Shared Package
ML20080R429	List: ML20080R427 ML20080R436
References
NFP-87-A-034, NFP-87-A-34, NUDOCS 9503090299
Download: ML20080R427 (11)

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UNITED STATES fs:

NUCLEAR REGULATORY COMMISSION

. WASHINGTON, D.C. 3000640M 4....

_ l TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION.' UNIT 1 5

-DOCKET NO. 50-445' AMEN 0 MENT TO FACILITY OPERATING LICENSE J

Amendment No. 34 License No. NPF-87 1.

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

A.

The application for amendment.by Texas Utilities Electric Company '

l (TU Electric, the licensee) dated November 18, 1994, complies with the' standards and requirements of-the' Atomic Energy.Act of 1954, as amended (the. Act), and the Commission's rules and reg 11ations set i

forth in:10 CFR Chapter I; B.

The facility will operate in conformity with-the application, as E

amended, the provisions of the Act, and the rules and regulations of

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-the: Commission; C.. There is reasonable assurance:

(1) that the activities authorized j

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 license amendment will not be inimical' to the ~

j common defense and security or to the health and safety of the i

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.

2.

Accordingly, the license is amended by changes to the Technical i

Specifications as indicated in the attachment to this license. amendment

- and Paragraph 2.C.(2) of Facility Operating License No.- NPF-87 is hereby.

amended to read as follows:

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2. - Technical Soecifications and Environmental Protection Plan The Technical Specificati$ns contained in Appendix A, as revised.

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through ' Amendment No. 34,. and. the Environmental. Protection Plan contained.in Appendix.B,-both of which are attached hereto, are-

' hereby incorporated-in the license. The -licensee shall operate-the

facility in.accordance with the Technical

Specifications and the

. Environmental Protect 1on P1an.

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The license amendment'is effective as~of.its date'of issuance to be-implemented within 30 days of issuance.'

I FOR THE NUCLEAR REGULATORY COP 911SSION' M

Timothy J. Polich,' Project Manager Project Directorate IV-1; Division of Reactor Projects III/IV Office of Nuclear Reactor _ Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 1,'1995

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UNITED STATE 8

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' NUCLEAR REGULATORY COMMISSION -

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WASHINGTON, D.C. 30006 4001

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' TEXAS UTILITIES ELECTRIC COMPANY' COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2-li 1

DOCKET NO. 50-446:

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AMENDMENT TO FACILITY OPERATING LICENSE 1

-Amendment.No'. 20z License No.;NPF-89 b

-1.-

The Nuclear Regulatory Commission-(the Commission) has'found that:-

A.

The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated November 18, 1994,. 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

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forth in 10 CFR Chapter I;-

B.

The. facility will operate in conformity with the application, as amended, 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 license 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.

2.

Accordingly, the license is' amended by changes to. the Technical Specifications' as indicated in the attachment to this license amendment

.j and Paragraph 2.C.(2) of Facility Operating License No. NPF-89 is hereby amended to read as follows:

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-:2 (2) Technical Snecifications and Environmental Protection Plan m

The~ Technical Specifications contained in: Appendix A, as revised through' Amendment No.~ 20, and the Environmental Protection Plan ?

- contained'in Appendix B, are hereby incorporated-into this license.

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- TU Electric. shall operate the' facility in.accordance with the Technical-Specifications _and the Environmental Protection: Plan.

3.

This. license amendment is. effective as'of its date of issuance'to be "T

' implemented within 30. days of issuance.

FOR THE NUCLEAR REGULATORY COPWISSION' Timothy-J..Polich, Project Manager Project Directorate IV-I Division of Reactor' Projects:III/IV.

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Office of Nuclear Reactor Regulation.

Attachment:

Changes to the Technical. Specifications I

Date of Issuance: March 1, 1995 r

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p-n..c ATTACHMENT TO LICENSE AMENDMENT NOS. 34 AND 20 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 DOCKET-NOS. 50-445 AND 50-446 Replace the following pages of the Appendix A. Technical Specificat' ions with

.the attached.pages. The revised pages'are identified by Amendment number and i

contains marginal lines indicating the areas of change..The corresponding overleaf pages are also provided.to maintain document completeness.

REMOVE INSERT-3/4 2-6.

3/4 2-6 3/4 6-20 3/4 6-20 3/4 6-21 3/4 6-21 P

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

4.2.2.2.

F,(Z) shall be evaluated to determine if it is within its limit by:

a. Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

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b. Determining the computed heat flux hot channel factor, F,*. (Z), as follows:.

Increase the measured F (Z) obtained from the power distribution map by 3% to account for ma,nufacturing tolerances and further increase the value by 5% to account for measurement uncertainties.

c. Verifying that F * (Z), obtained in Specification 4.2.2.2b. above, satisfiestherelationshipin. Specification 3.2.2.

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d. The F * (Z) obtained in 4.2.2.2b above shall satisfy the following relationship at the time of the target flux determination:

i F,*(Z) s F

x K(Z) for P > 0.5 P x W(Z)

F,"(Z) s F.

x K(Z) for P s 0.5 0.5 x W(I) where F *(Z) is obtained in Specification 4.2.2.2b. above, F,RTP is the F, limil, K(Z) is the nomalized F (Z) as a function of core height, P is the fraction of RATED THERMAL b ER, and W(Z) is the cycle depen-i dent function that accounts for power distribution transients encountered during nomal operation. F RTP, K(Z) and W(Z) are specifiedintheCOREOPERATINGLIMITSIEPORTasperSpecification 6.9.1.6.

e. Measuring F,(Z) according to' the following schedule:

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1. Upon achieving equilibrium condition after exceeding by 20% or more of RATED THERMAL POWER, the THERMAL POWER at which F,(Z) was i

l last determined *, or

2. At least once per 31 Effective Full Power Days, whichever occurs first.

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• Power level may be increased until the THERMAL POWER for extended operation l

has been achieved.

l COMANCHE PEAK - UNITS 1 AND 2 3/4 2-5 Unit 1 - Amendment No. 1, 6 e

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y POWER DISTRIBUTION LIMITS E

SURVEILLANCE REQUIREMENTS (Continued)

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. f. lWith measurements? indicating-

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. maximus' ? F c(Z) a p

'over Z: T(Ui hastincreased since the previous' determination.of F,c(Z) either of the?

following actions shall. be taken -

= 1)' Increase-F '(Z) by an allowance ;t2i as specified in theiCOLRland.

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verifythaT.thisvaluesatisfies.therelationshipin' Specification 4.2.2.2d, or D.C(Z) shall' be measured at least;once per 7i Effective Full Power-v 2)

F ays until two. successive maps-indicate that maximum : F,c(Z) is not' increasing.

over Z K(Z)i

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g. With:the relationships specified in Specification 4.2.2.'2d above not:

being satisfied:

1). Calculate the percent that F,(Z)' exceeds its '11mits by the fol-lowing expression:

maximum

' F.*(Z)1x ' WIZ) '

over Z 7 x K(Z)

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• x 100 for P > 0.5

. P;

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maximum"

" ~ F/(Z) x W(Z) over Z

@ x K(Z)

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> x 100 for P s; 0.5, and 0.5 g

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The following action shall be t'aken:

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Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the AFD limits specified in L

the CORE-OPERATING 1.IMITS REPORT by 1% AFD for each percent n

F (Z) exceeds its limits as determined in Specificat on 4,.2.2.2g.1.

Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reset the AFD alarm setpoints to L

these' modified limits.

p COMANCHE PEAK - UNITS 1 AND 2 3/4 2-6 Unit 1 - Amendment No.- 4,4,34 -

i Unit 2 - Amendment No. 20

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pW j, JADMINISTRATIVE' CONTROLS'-

1 (ANNUAL REPORTS'/ Continued)

-b.

The results'of specificLactivity analyses'in'which the. primary.

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coolant exceeded the limits of Specification 3.4.7.

The following.

information shall;be included::-(l). Reactor power history starting-1

'48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to.the first= sample in which thetlimit was exceeded

.(in graphic' and tabular _ format);- (2) Results' of the last: isotopic!

o analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit' was exceeded ~ and results 'of one-t c

analysis after the radiciodine activity was reduced to less than:

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. Each result. should include' date. and time of sampling and the" '

limit.

radiciodine concentrations; (3) Clean-up flow history starting _.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior. to the first sample in w11ch the,11mit' was exceeded;.

(4) Graph _of-the I-131 concentration (pC1/gn) and one other.

radioidine: isotope concentration (pCi/ge) as a function of time forf the duration of the specific activity above the steady-state level; i

9 and (5)LThe time duration when the. specific activity of the primary coolant exceeded the radiciodine limit.

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ANNUAL RADIOLOGICAL ENVIRONMENTAL' OPERATING REPORT

• t 6.9.1.3

- The Annual Radiological Environmental Operating. Report covering the ' operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The' report'shall. include summaries,..

interpretations, and analysis 'of trends.of'the.results of the Radiological j

Environmental Monitoring Program for the' reporting period..The material provided-shall be consistent with the objectives _ outlined in (1)tthe 0DCM, and i

(2) Sections.IV.B.2, IV.B.3,_and IV.C'of Appendix I to 10 CFR 50.

i ANNUAL RADI0 ACTIVE EFFLUENT RELEASE-REPORT **

'I 6.9.1.4 The Annual Radioactive Effluent Release Report covering the operation d

of the unit during the previous year shall be submitted prior to May 1 of each year.

The' report shall include a' summary of the quantities of radioactive-

' liquid and gaseous effluents and solid waste released from the unit. - The material provided shall be (1) consistent with the objectives outlined in the-

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ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.I.of 1

Appendix I to 10 CFR 50.

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MONTHLY OPERATING REPORTS I

6.9.1.5; Routine reports of operating statistics and shutdown experience, including documentation of a11~ challenges to'the PORVs or. safety valves, i

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• A single submittal may be made for a multiple unit station.-

• • A single submittaltmay be made for a multi-unit station. The submittal e

should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

COMANCHE PEAK - UNITS 1 AND 2 6-19 Unit 1 - Amendment No. 25 Unit 2 - Amendment No.11 L&,.. - _ _ _

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~ ADMINISTRATIVE' CONTROLS:

MDNTHLY OPERATING REPORTS (Continued)

- shall be submitted on a monthly b' asis to the U.S. ' Nuclear Regulatory f

' Commission, Document Control Desk, Washington, D.C. 20555, with a copy to the.

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- Regional Administrator of. the Regional Office-of. the NRC, no later than-the 15th of each month following.the calendar month covered by the report.

l CORE OPERATING LIMITS REPORT 6.9.1.6a ' Core operating liaits shall be established and documented in 'the CORE OPERATING LIMITS REPORT (COLR) before each' reload cycle or any remaining 1

part of a. reload cycle for the following-l

'l).

Moderator temperature coefficient BOL and EOL limits and 300 ppm sur-veillance limit for Specification 3/4.1.1.3, l

2). Shutdown Rod Insertion Limit for Specification 3/4.1.3.5, i

3). Control Rod Insertion Limits'for Specification 3/4.1.3.6, 4). AXIAL FLUX DIFFERENCE Limits and target band for Specification 3/4.2.1.,

5). Heat Flux Hot Channel Factor, K(Z), W(Z), F/", and the F/(Z) allowances for Specification 3/4.2.2, i

6). Nuclear Enthalpy Rise Hot Channel Factor Limit and the Power Factor Multiplier for Specification 3/4.2.3.

6.9.1.6b.The following analytical methods used to determine the core operating limits are for Units 1 and 2, unless otherwise stated, and shall be j

those previously approved by the NRC in:

1). WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"

f July 1985 (W Proprietary).

(Methodology for Specifications 3.1.1.3 -

Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion l

Limit, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3.- Nuclear Enthalpy Rise Hot Channel Factor.)

2). WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES -

i TOPICAL REPORT," September 1974 (W Proprietary).

(Methodology for

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Specification 3.2.1'- Axial Flux Difference [ Constant Axial Offset Control).)

j 3).

T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC I

January 31, 1980--

Attachment:

Operation and Safety Analysis Aspects of an Improved Load Follow Package.

(Methodology for Specification 3.2.1 - Axial Flux Difference [ Constant Axial Offset Control).)

4). NUREG-0800, Standard Review Plan, U.S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981.

Branch Technical Position j

CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, L

July 1981. (Methodology for Specification 3.2.1 - Axial Flux i

Difference [ Constant Axial Offset Control).)

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COMANCHE PEAK - UNITS 1 AND 2 6-20 Unit 1 - Amendment No. GrM,34 Unit 2 - Amendment No. 20 l

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\\ AmdNISTRATIVE CONTROLS

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, CORE QPERATING LIMITS REPORT-(Continued) l 1

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.5).1 WCAP-10216-P-A, Revision IA " RELAXATION OFLCONSTANT'AXIALLOFFSETJ

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l CONTROL F SURVEILLANCE TECHNICAL-SPECIFICATION," February 1994' (M 3 i

Proprietary).;(Methodology for Specification'3.2.2 - Heat-Flux' Hot z

- Channelf Factor-(W(z)- surveillance: requirements for F Methodology).);

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. ;6). 'WCAP-10079-P-A, "NOTRUMP, A N00AL TRANSIENT:SMALL BREAK'AND GENERALI l

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- NETWORK CODE," August 1985,(M Proprietary).

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r 7). WCAP-10054-P-A, " WESTINGHOUSE SMALL' BREAK ECCS EVALUATION MODEL USING-i g

THE NOTRUMP. CODE", August:1985, M Proprietary)..

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8)..:WCAP-11145-P-A, " WESTINGHOUSE SMALL' BREAK LOCA ECCS EVALUATION.MODEL'-

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. GENERIC-STUDY WITH THE NOTRUMP CODE", October 1986,-M: Proprietary).

9). l RXE-90-006-P, " Power Distribution' Control" Analysis: and Overtemperature.

~ N-16 and Overpower N-16 Trip Setpoint Methodology," February 1991..

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' (Methodology for Specification 3.2.l!- Axial Flux Difference, 3.2.2 -

i Heat Flux Hot' Channel Factor.):

10). RXE-88-102-P,;"TUE-1 Departure from Nucleate Boiling Correlation",

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January 1989.'

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l 11).:RXE-88-102-P, Sup. 1, "TUE-1 DN8 Correlation - Supplement 1",-

.l December 1990.

3 12). RXE-89-002,."VIPRE-01 Core Thermal-Hydraulic Ar.alysis Methods' for Comanche Peak Steam Electric Station Licensing Applications",; June-

- 1989.

-I 13). RXE-91-001, " Transient _ Analysis Methods for Comanche Peak Steam'

- Electric Station Licensing Applications",. February 1991..

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14)..RXE-91-002, " Reactivity Anomaly Events. Methodology", May 1991.

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6

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- Control Bank Insertion ~ Limits, 3.2.1 - Axial Flux Difference, 3.2.2 -

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Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)

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.i 15)._ RXE-90-007, "Large Break Loss of Coolant Accident Analysis 1

Methodology", December 1990.

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.16). TXX-88306, " Steam Generator Tube Rupture Analy' sis", March 15, 1988.

j 17). RXE-91-005, " Methodology for Reactor Core Response to Steamline Break-.

-l Events," May, 1991.

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COMANCHE PEAK - UNITS 1 AND 2 6-21 Unit 1 - Amendment No. 1,5,14,10,21,20,34 l

Unit 2 - Amendment No. 4,7,14,20 l

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ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)

Reference 18) is for Unit 2 only:

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

6.9.1.6c The core omrating limits shall be determined so that all applicable licits (e.g., fuel t termal-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.' d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or 6

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.

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t-e COMANCHE PEAK - UNITS 1 AND 2 6-2Ia Unit 1 - Amendment No. 21 Unit 2 - Amendment No. 7 l

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