ML20217Q726
| ML20217Q726 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/20/1998 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20217Q717 | List: |
| References | |
| NUDOCS 9804130123 | |
| Download: ML20217Q726 (6) | |
Text
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FNP Unit i Technical Specifications Power Uprate Implementation Channed Pane Unit I geyision Page 6-19a New Page (Replace TS Page 6-19a In February 12,1998 Submittal) i 1
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9804130123 900403 PDH ADOCK 05000348 P
PDR s
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ADMINISTRATIVE CONTROLS 2.
WCAP-10216-P-A, Rev. 1A, " Relaxation Of Constant Axial Offset q
control / Fg Surveillance Technical Specification," February 1994 j
(H Proprietary).
l (Methodology for Specifications 3.2.1 - Axial Flux Difference and 3.2.2 - Heat Flux Hot Channel Factor.)
3a.
WCAP-12945-P-A, Volume 1, Revision 2, and Volumes 2 through 5, Revision 1, " Code Qualification Document for Best Estimate LOCA Analysis," March 1998 (H Proprietary).
3b.
WCAP-12610-P-A, " VANTAGE + Fuel Assembly Reference Core Report,"
April 1995 (H Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
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.
The CORE OPERATING LIMITS REPGAT, 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.
ANNUAL DIESEL GENERATOR RELIABILITY DATA REPORT 6.9.1.12 The number of tests (valid or invalid) and the number of i
failures to start on demand for each diesel generator shall be submitted I
to the NRC annually. This report shall contain the information identified in Regulatory Position C.3.b of NRC Regulatory Guide 1.108, Revision 1, 1977.
FARLEY-UNIT 1 6-19a AMENDMENT NO.
I ADMINISTRATIVE CONTROLS 2.
WCAP-10216-7-A, Rev. 1A, " Relaxation of constant Axial offset control /
Fg surveillance Technical Specification," February 1994 ()( Froprietary).
(Methodology for specifications 3.2.1 - Axial Flux Difference and 3.2.2 Best Flux Bot Channel Factor.)
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(Methodology for specification 3.2.2 - Heat Flux Mot Channel Factor.)
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ICCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CX)RE 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.
s ANNUAL DIESRL CENTRATOR RELTABILITY DATA REPORT 6.9.1.12 The number of tests (valid or invalid) and the number of failures to
' start on demand for each diesel generator shall be submitted to the NRC annually.
This report shall contain the information identified in Regulatory Position C.3.b of NRC Regulatory Guide 1.108, Revision 1, 1977.
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, %\\u 1, R visten2, ea %1aues 2 +hrouf 5,hi31oni, Insert A to pg 6.19a CW 3a.
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March p =Si WCAP-12610-P-A, " VANTAGE + Fuel Assembly Reference Core Report," April
.-F v-1995 (W Propdetary).
'"8 FARLEY-11 NIT 1 6-19a AMENDMENT No.
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FNP Unit 2 l
Technical Specifications l
Power Uprate Implementation I
Changed Page l
i Umt 2 Revision Page 6-19a New Page (Replace TS Page 6-19a In Febmary 12,1998 Submittal)
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1 ADMINISTRATIVE CONTROLS l
2.
WCAP-lo216-P-A, Rev. 1A, "Raiaxatien of Constant Axial offset Control /
Fg Surveillance Technical Specification," February 1994 ()( Proprietary).
(Methodology for Specifications 3.2.1 - Arial Flum Difference and 3.2.2 ~ Beat Flux Hot channel Factor.)
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";d;l ";ing "'25 'ed:," ". r:5 la"? $ "::; ict ri).
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(Methodology for Specification 3.2.2 - Heat Fluz Not Channel Factor.)
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydre.ulic limits, Fcc3 11.mits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATINC I,IMITS 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 Administratoc and Resident Inspector.
ANNUAL DTESRt CENTRATOR REttaBf tfTY DATA REPORT 6.9.1.12 The number of tests (valid or invalid) and the number of failures to start on demand for each diesel generator shall be submitted to the NRC annually.
This report shall cont.&in the information identified in Regulatory Position C.3.b of NRC Regulatory cuide 1.108, Revision 1, 1977.
i ghh hSys g!l Insert A to pg 6.19a g...
v 3a.
WCAP-12945, -^E.
2, !^^^ 1^^^, " Code Qualification Docurnent for Best Eshate W
- E Proprietaq), Q ggg w
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- WCAP-12610-P-A, " VANTAGE + Fuel Assembly Reference Core Report," April 1995 ()V g
Proprietary).
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- _Y FARLE -UNIT 2 6-19a AMENDMINT No.
ADMINISTRATIVE CONTROLS 2.
WCAP-10216-P-A, Rev. 1A, " Relaxation Of Constant Axial Offset Control / Fg Surveillance Technical Specification," February 1994 (H Proprietary).
(Methodology for Specifications 3.2.1 - Axial Flux Difference and 3.2.2 - Heat Flux Hot Channel Factor.)
3a.
WCAP-12945-P-A, Volume 1, Revision 2, and Volumes 2 through 5, Revision 1, " Code Qualification Document for Best Estimate LOCA Analysis," March 1998 (H Proprietary).
3b.
WCAP-12610-P-A, " VANTAGE + Fuel Assembly Reference Core Report,"
April 1995 (H Proprietary).
(Mathodology for Specification 3.2.2 - Heat Flux Het Channel Factor.)
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.
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.
ANNUAL DIESEL GENERATOR RELIABILITY DATA REPORT 6.9.1.12 The number of tests (valid or invalid) and the number of failures to start on demand for each diesel generator shall be submitted to the NRC snnually. This report shall contain the information identified in Regulatory Position C.3.b of NRC Regulatory Guide 1.108, Revision 1, 1977.
FARLEY-UNIT 2 6-19a AMENDMENT NO.
I