ML20055G986

Proposed Tech Specs Removing cycle-specific Core Parameters for Placement in Core Operating Limits Rept

ML20055G986
Person / Time
Site:	Callaway
Issue date:	07/18/1990
From:	UNION ELECTRIC CO.
To:
Shared Package
ML20055G985	List: ML20055G984 ML20055G986
References
NUDOCS 9007250009
Download: ML20055G986 (3)

Text

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, ULNRC-2253 L

3 ADMIN!3iRATTM CONTROL 5 -

-L MONTHLY OPERATfMG REPORT t

'j I 7 6.9.1.8 Routine reports of operating statistics and shutdown experience.

including documentation of all challenges to the pressurizer PORVs or RCS

" . safety valves. shall be sutaitted on a monthly basis to the Director. Office of Resourca Management, L.S. Nuclear Regulatory Connission. Washington D. C.

20555 with a copy to the NRC Regional Office, no later than the 15th of each nunth following* the calencer month covered by the report. - ,

^~'NN "",05 L i T ':"*0"7 4

% 9,1.9 The Wft functions for No'rsal and AESTRICTID AFD OPERATION and p, L .~

core value-foan(.r APLND ()as required) shall be established oad for at  !

T~ thall be maintained available in the Control Acom. Th its shall i' -M be estab11shed1md implemented on a time scale consistent w normal proco-(

'M b dural changes. N The analytica's methods used nerate the W i SL *

• those previously reviewed and ap unctions and APLND shall be

W J AL 4b NRC'. If changes to these methods are coemed necessary, they w< evaluated in accordance with gg,)

10 CFR 50.59 and submitted to for av and approval prior to their use if the change is date to involve an 1swed safety question or

• if such a change would re amendment of previou uhaitted documentation.

A report coa ng.the W(r) fMDctions ks a function of core r burnup. 11 cable) and APLN shall be provided to the NRC Dec ht(and Desk Control ,

. copies to the Regional Aeninistrator and the Assident Inspec in 30. days of their implementation. +

SPECIALJtPORTS 6.9.2 Special Aeports shall be submitted to the Aegional Administrator of the NAC Regd.onal Office within the time period specified for each report.

s B 6.10 RECORD RtltNTION In addition to the applicable record retention requirements of Title 10. Code

.: of Federal Regulations, the following records shall be retained for at least the minimum period indicated S

} o~'

6.10.1 The following receres shall be retained for at least 5 years:

a. Ancords and logs of unit operation covering time interval at each power levell f '

l 9  %^^G ^^^f, ""r-- Distribution Control and Load Followine _

j- b WCAP*9272-A. "Westingh-se iwi ; d'*= r % ;; i riethodolo

-ri -..-

i WCAP-10216-P-A. " pal-tm .. 6enstant Axial Offset'C5hhv1,gy." ' and_

1 A;;'11 e Technical Specification." . ;;

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I CAtt m Ay - uMIT 1 s-ti Amenement No as, s0 a

9007250009 F 900713 ' '

_ F;DR ADOCK 050004s3 PDC '

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)- 1 ULNRC-2253 W O JULSERT_ B ( ADD TO PAGE 6-21).

[

CORE OPERATING LIMITS REPORT

\~

6.9.1.9 Core operating limits shall be established and documented-in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following

[ a. Moderator Temperature Coefficient DOL and EOL Jimits and p 300 ppm surveillance limit for Specification 3/4.1.1.3, i l-i

b. Shutdown Bank Insertion Limit for Specification i 3/4.1.3.5, I' c. Control Bank Insertion Limits for Specification '

3/4.1.3.6,

d. Axial Flux Difference Limitn, target band, and APLND fgp Specification 3/4.2.1, P

e. HeabDFlux Hot Channel Factor, F ,

g{g), ggg)NO' APL and W(Z)RAFDO f r Specifi8ation 3/4.2.2,

f. Nuclear Enthalpy hise Hot Channel Factor F and Power Factor Multiplier, PF 3g, limitsforSpecifkEa, tion ,

3/4.2.3.

The analytical methods usea to determino the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents,

n. WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY", July 1985 (W Proprietary).

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

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

Enthalpy Rise Hot Channel Factor.

bl. WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD ,

FOLLOWING PROCEDURES - TOPICAL REPORT", September 1974 (W Proprietary).

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

b2. T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC) January 31, 1980 --

Attachment:

Operation "

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

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

v. , . t -1._

9 ~ , .+ Q l l J -

D*l*' i -ULNRC-2253

~. : .. . . .

b3. NUREG-0800, Standard Review Plan, U.S. Nuclear Regulatory-Commission, Section 4.3, Nuclear Design,1 July 1981. Branch Technical-Position.CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC),

Rev =2, July.1981, h

,  :(Methodology for Specification 3.2.1 --Axial Flux Difference (Constant-Axial Offset Control').)

-c. WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL' OFFSET

' CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION",

June 1983 (H Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel-Factor (FQ %ethodology for W(Z) surveillance requirements),

d'- WCAP-30266-P-A, REV. 2, "THE 1981 VERSION OF

' WESTINGHOUSE EVALUATION MODEL USINC BASH CODE", March 1987.(W Proprietary).

(Methodology for 3pecification 3.2.2 - Heat Flux Hot Channel Factor).

The core 1 operating limits shall be determined so that all

applicable limits (e.g., fuel thermal-mechanical limits, core thermalhydraulic limite,_ nuclear _ limits such as shutdown margin,

. and transient and accident analysis limits) of the-safety analysis are met.

HThe CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements shall be provided, upon issuance for each s reload cycle,'to'the NRC Document ~ Control Desk with copies to the Regionel Administrator and Resident Inspector, s

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