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{{#Wiki_filter:4 ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATINC LIMITS REPORT roJA>ant rotc u~PlP)Db 6.9.1.6.1 Core operation Lxmzts shaLL be established and documented in the CORE OPERATINC LIMITS REPORT pz ior to each reload cycle, or'prior to any remaining portion oE a reload cycle, Eoz'he foLLowing:
{{#Wiki_filter:4 ADMINISTRATIVE CONTROLS 6.9.1.6     CORE OPERATINC             LIMITS                 REPORT roJA       >
R+(ocL~ah Zns~4 (r~z.>Py)a.The shutdown rod insez'tion Limits oE Specification 3.1.3.5.b.The control rod insertion limits of Specification 3.1,3.6.c.The axiaL flux difference of Specification 3.2.1.d.The surveiLlance requirements of Specifications 4.2.2.2, 4.2.2.3, and 4.2.2''.9.1.6.2 The analytical methods used to determine the coze operating Limits shaLL be those previously reviewed and approved by the NRC, speciEicaLly those described in the EoLlowing documents.'cplacc, bdlf'L macr~k (nex<+4 a~b.WCAP-10216-P-A, Relaxation of Constant Axial Offset ControL FO SurveilLance TechnicaL SpeciEication, 1983~WCAP-9272-P-A, Westinghouse Reload Safety EvaLuation MethodoLogy, 19B5.6.9,1.6.3,The coze operating Limits shall be determined so that alL appLicable Limits (e.g., fuel thirmalmechanical limits, core thermal-hydrauLic limits, nucLear Limits such as shutdown margin, and transient and accident anaLysis Limits)of the safety analysis are met.6.9.1.6.4 The CORE OPERATINC LIMITS REPORT, including any mid-cycle revisions or suppLements, shaLL be provided, upon issuance Eor each zeload cycLe, to the NRC Document ControL Desk, with copies to the Regional Administrator and Resident Inspector.
ant rotc u~ PlP )Db 6.9.1.6.1     Core operation             Lxmzts shaLL be established and documented in the CORE OPERATINC LIMITS REPORT pz                 ior to                 each reload cycle, or 'prior to any remaining portion oE a reload cycle,                   Eoz'he foLLowing:
SPECIAL REPORTS 6.9.2 SpeciaL reports shalL be submitted to the Regional Administrator of the Regional, Office of the NRC within the time period specified Eor each report.6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements oE Title LQ, Code of FederaL Regulations, the EoLLowing records shaLL be retained Eor at least the minimum period indicated.
: a. The shutdown rod               insez'tion Limits                 oE Specification 3.1.3.5.
C 6.10.2 The EoLLowing records shaLL be zetained Eor at Least 5 years:.a.Records and logs of unit operation covering time intervaL at each power LeveL$SHEARON HARRIS.-UNIT 1 6-24 Amendment No.g, 7$>A ,.9i02060099
R+(ocL
.9.i.Oi 28 PDR ADOCK 05000400 P PDR INSERT A: a.II, b.C~d.e.Moderator Temperature Coefficient Positive and Negative Limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, Shutdown Bank Insertion Limits for Specification 3/4.1.3.5, Control Bank Insertion Limits for Specification 3/4.1.3.6, Axial Flux Difference Limits, target band, and APL for Specification 3/4.2.1, Heat Flux Hot Channel Factor, F, K(Z), W(Z), APL and W(Z)BL RTP ND for Specification 3/4.2.2, Enthalpy Rise Hot Channel Factor, F<H 9 and Power Factor Multiplier, RTP PF<H for Specification 3/4.2.3.INSERT B: a.b.C~d.e.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).WCAP-11914,"SAFETY EVALUATION SUPPORTING A MORE NEGATIVE EOL MODERATOR TEMPERATURE COEFFICIENT TECHNICAL SPECIFICATION FOR H EARON RI C OWE NT" u ust 1988 (W Proprietary).
  ~ah            b. The   control rod insertion limits of Specification 3.1,3.6.
Apped~b~>kC Safety EVa.luatSOn Ct~ge.mO.q BR, IR 8'(Metho o ogy for Specification
Zns~4          c. The axiaL           flux difference of Specification 3.2.1.
...3-Moderator emperature Coefficient).
(r ~z.>Py)
WCAP-10216-P-A,"RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F SURVEILLANCE TECHNICAL SPECIPICATION", JUNE 1988 (N Peopeietae)).(Methodology for Specifications 3.2.1-Axial Flux Difference (Relaxed Axial Offset Control)and 3.2.2-,Heat Flux Hot Channel Factor (F~Methodology for W(Z)surveillance requirements).)
: d. The   surveiLlance requirements of Specifications 4.2.2.2, 4.2.2.3,                                 and 4.2.2 '
WCAP-10266-P-A, Rev.2,"The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).(Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor).WCAP-8385,"POWER DISTRIBUTION CONTROL AND LOAD F 0 U S CA R 0" temb r 1974 (W Pro rietary)HAP'oval g i'd<lS~$M EV~la~+AO~
The  analytical
date.airy l l9 V7~et o o y or peer xca on..-]a Flux Difference (Constant Axial Offset Control)~).WCAP-11837-P-A,"EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", January 1990 (W Proprietary).
                                  '.9.1.6.2 methods used to determine the coze operating Limits shaLL be those     previously reviewed                             and approved by the NRC, speciEicaLly those described in the EoLlowing documents.'cplacc, a~   WCAP-10216-P-A, Relaxation                               of Constant Axial Offset ControL   FO bdlf'L            SurveilLance TechnicaL SpeciEication,                                 1983 ~
macr~k Reload Safety EvaLuation MethodoLogy, (nex<+4 b.
WCAP-9272-P-A, Westinghouse 19B5.
6.9,1.6.3,The       coze operating Limits shall be determined so that alL appLicable Limits (e.g., fuel thirmalmechanical limits, core thermal-hydrauLic limits, nucLear Limits such as shutdown margin, and transient and accident anaLysis Limits) of the safety analysis are met.
6.9.1.6.4     The CORE OPERATINC LIMITS REPORT, including any mid-cycle revisions or suppLements,       shaLL be provided, upon issuance Eor each zeload cycLe, to the NRC Document ControL Desk, with copies to the Regional Administrator and Resident Inspector.
SPECIAL REPORTS 6.9.2     SpeciaL reports shalL be submitted to the Regional Administrator of the Regional, Office of the NRC within the time period specified Eor each report.
6.10   RECORD RETENTION 6.10.1     In addition to the applicable record retention requirements oE Title                                     LQ, Code   of FederaL Regulations, the EoLLowing records shaLL be retained Eor at least the minimum period indicated.                                         C 6.10.2     The EoLLowing records                               shaLL be   zetained Eor at Least 5 years:
                .a. Records and logs                   of unit operation covering time intervaL at                 each power LeveL$
SHEARON   HARRIS.- UNIT             1                                 6-24                     Amendment No. g, 7$ > A
  , .9i02060099       .9.i.Oi 28 PDR     ADOCK     05000400 P                       PDR
 
INSERT A:
: a. Moderator Temperature Coefficient Positive and Negative Limits and II, 300 ppm surveillance limit for Specification 3/4.1.1.3,
: b. Shutdown Bank   Insertion Limits for Specification 3/4.1.3.5, C~  Control Bank Insertion Limits for Specification 3/4.1.3.6,
: d. Axial Flux Difference Limits, target band,             and APL     for Specification 3/4.2.1,
: e. Heat Flux Hot Channel Factor, for Specification 3/4.2.2, F, RTP K(Z), W(Z),     APLND and W(Z)BL RTP Enthalpy Rise Hot Channel Factor,         F<H     9 and Power   Factor Multiplier, PF<H for Specification 3/4.2.3.
INSERT B:
: a. 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).
: b. WCAP-11914, "SAFETY EVALUATION SUPPORTING A MORE NEGATIVE EOL MODERATOR TEMPERATURE COEFFICIENT TECHNICAL SPECIFICATION FOR H                   EARON     RI C       OWE     NT"     u ust 1988 (W Proprietary). Apped~ b~ >kC Safety EVa.luatSOn Ct~ge.     mO.q BR, IR 8' (Metho o ogy for Specification . . .3 Moderator emperature Coefficient).
C~  WCAP-10216-P-A, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F SURVEILLANCE TECHNICAL SPECIPICATION", JUNE 1988 (N Peopeietae)).
(Methodology   for Specifications 3.2.1         Axial     Flux Difference (Relaxed Axial Offset Control)     and 3.2.2 -,Heat Flux Hot Channel Factor (F~
Methodology   for W(Z)   surveillance requirements).)
: d. WCAP-10266-P-A, Rev. 2, "The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).
(Methodology   for Specification 3.2.2         Heat     Flux Hot Channel Factor).
: e. WCAP-8385, "POWER DISTRIBUTION CONTROL AND LOAD F                 0             U S
                    "     temb r 1974 (W Pro rietary) HAP'oval                         S~$ M CA R 0                                                                g i'd<l EV~la~+AO~     date.           airy   l   l9 V7 ~
et o o y or peer xca           on   . .         ]a   Flux Difference (Constant Axial Offset Control) ). ~
WCAP-11837-P-A, "EXTENSION OF       METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", January 1990       (W Proprietary).
 
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Latest revision as of 06:35, 22 October 2019

Proposed Tech Specs Re Core Operating Limits Rept
ML18009A791
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 01/28/1991
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18009A790 List:
References
NUDOCS 9102060099
Download: ML18009A791 (3)
v • d • e


Text

4 ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATINC LIMITS REPORT roJA >

ant rotc u~ PlP )Db 6.9.1.6.1 Core operation Lxmzts shaLL be established and documented in the CORE OPERATINC LIMITS REPORT pz ior to each reload cycle, or 'prior to any remaining portion oE a reload cycle, Eoz'he foLLowing:

a. The shutdown rod insez'tion Limits oE Specification 3.1.3.5.

R+(ocL

~ah b. The control rod insertion limits of Specification 3.1,3.6.

Zns~4 c. The axiaL flux difference of Specification 3.2.1.

(r ~z.>Py)

d. The surveiLlance requirements of Specifications 4.2.2.2, 4.2.2.3, and 4.2.2 '

The analytical

'.9.1.6.2 methods used to determine the coze operating Limits shaLL be those previously reviewed and approved by the NRC, speciEicaLly those described in the EoLlowing documents.'cplacc, a~ WCAP-10216-P-A, Relaxation of Constant Axial Offset ControL FO bdlf'L SurveilLance TechnicaL SpeciEication, 1983 ~

macr~k Reload Safety EvaLuation MethodoLogy, (nex<+4 b.

WCAP-9272-P-A, Westinghouse 19B5.

6.9,1.6.3,The coze operating Limits shall be determined so that alL appLicable Limits (e.g., fuel thirmalmechanical limits, core thermal-hydrauLic limits, nucLear Limits such as shutdown margin, and transient and accident anaLysis Limits) of the safety analysis are met.

6.9.1.6.4 The CORE OPERATINC LIMITS REPORT, including any mid-cycle revisions or suppLements, shaLL be provided, upon issuance Eor each zeload cycLe, to the NRC Document ControL Desk, with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 6.9.2 SpeciaL reports shalL be submitted to the Regional Administrator of the Regional, Office of the NRC within the time period specified Eor each report.

6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements oE Title LQ, Code of FederaL Regulations, the EoLLowing records shaLL be retained Eor at least the minimum period indicated. C 6.10.2 The EoLLowing records shaLL be zetained Eor at Least 5 years:

.a. Records and logs of unit operation covering time intervaL at each power LeveL$

SHEARON HARRIS.- UNIT 1 6-24 Amendment No. g, 7$ > A

, .9i02060099 .9.i.Oi 28 PDR ADOCK 05000400 P PDR

INSERT A:

a. Moderator Temperature Coefficient Positive and Negative Limits and II, 300 ppm surveillance limit for Specification 3/4.1.1.3,
b. Shutdown Bank Insertion Limits for Specification 3/4.1.3.5, C~ Control Bank Insertion Limits for Specification 3/4.1.3.6,
d. Axial Flux Difference Limits, target band, and APL for Specification 3/4.2.1,
e. Heat Flux Hot Channel Factor, for Specification 3/4.2.2, F, RTP K(Z), W(Z), APLND and W(Z)BL RTP Enthalpy Rise Hot Channel Factor, F<H 9 and Power Factor Multiplier, PF<H for Specification 3/4.2.3.

INSERT B:

a. 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).

b. WCAP-11914, "SAFETY EVALUATION SUPPORTING A MORE NEGATIVE EOL MODERATOR TEMPERATURE COEFFICIENT TECHNICAL SPECIFICATION FOR H EARON RI C OWE NT" u ust 1988 (W Proprietary). Apped~ b~ >kC Safety EVa.luatSOn Ct~ge. mO.q BR, IR 8' (Metho o ogy for Specification . . .3 Moderator emperature Coefficient).

C~ WCAP-10216-P-A, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F SURVEILLANCE TECHNICAL SPECIPICATION", JUNE 1988 (N Peopeietae)).

(Methodology for Specifications 3.2.1 Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 -,Heat Flux Hot Channel Factor (F~

Methodology for W(Z) surveillance requirements).)

d. WCAP-10266-P-A, Rev. 2, "The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).

(Methodology for Specification 3.2.2 Heat Flux Hot Channel Factor).

e. WCAP-8385, "POWER DISTRIBUTION CONTROL AND LOAD F 0 U S

" temb r 1974 (W Pro rietary) HAP'oval S~$ M CA R 0 g i'd<l EV~la~+AO~ date. airy l l9 V7 ~

et o o y or peer xca on . . ]a Flux Difference (Constant Axial Offset Control) ). ~

WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", January 1990 (W Proprietary).

Jl

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