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=Text=
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{{#Wiki_filter:_    . . _ _ _                                          ____ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ . . __ -_                _            ___. _ _._        ___ _ ._ _ _ _ _
ADMIN!sTRATIVE CONTROLS
                                                                                                                                                                                    .nsa 2.
WCAP-lo216-P-A, Rev. 1A,
* Relaxation of Constant Asial offset control /
                                    , Fg surveillance Technical specification," February 1994 (M Froprietary).
(Methodology for specifications 3.2.1 - Asial Flum Difference and 3.2.2 - Beat Flum Not Channel Factor.)
M          *WCAF=19 fit-P=h,        M . 2, "The-4981-Verei= ^f "::tinghewee-Beelvetion-m > _ i _ n g,ggy    ,.m
                                                                          .u.y..,                                        . u . . _ _ gwp                                    (
(Methodology for specification 3.2.2 - Heat Flux Hot Channel Factor.)
The (e.g.,core      operating limite shall be determined so that all appitcable limite fuel thermal-mechanical limite, core thermal-hydraulic limite, ICCS limite, nuclear limite auch as shutdown margin, and transient and accident analysie limits) of the safety analysis are met.
The ooR5 OPERATING LIMITS REPORT, including any mid-cycle revisione or supplements thereto, shall be provided upon Leeuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Adeinistrator and Resident Inspector.                                                                    ,-
ArmuAt crusat crwamaron artranrtrTr DATA arpom?
6.9.1.12 The number of teste (valid or invalid) and the numbeir of f ailures to start on demand for each diesel genetator shall be submitted to the NRC annually.
This report shall contain the information identified in Regulatory Position C.3.b
    ,                    of NRC Regulatory Guide 1.104, Revision 1, 1977.
t Intert A to pg 6.194 3a.          WCAP 12945 P, Vol. I.&,19921993, " Code Quallneation Document for Best Estimate LOCA Analysis". & Proprietary) 3b.
Letter, N. J. Lipamlo, (W) to R. C. Jones, (USNRC), " Revision to Westinghouse Uncertainty Methodology", NTD NRC 95-4575, Oct Mr                                                        5.
3c.        Letter, R. C. Jones (USNRC) to N. J. Lipamlo (W), " Acceptance for Refetencing of the Topical Report, WCAP 12945(P), Westingbouse Code Qualification Document for Best Estimate Loss of-Coolant Analysis", June 28,1996 3d    WCAP 12610-P A. " VANTAGE + Fuel Assembly Reference Core Report," April                                                                                M 1995 (W Proprietary).                                                                                                                                  N
                                                                                                                                                            ?
FAALEY-UNIT 1                                                          6-19a                                          AMENDMENT No.
9802190132 980212 PDR            ADOCK 05000348 P                                PDR
                              ._                                                                  ~ _
 
        .      .                                                                                        N ADMINISTRATIVE CONTROLS
: 2. WCAP-10216-P-A, Pev. 1A, " Relaxation of Constant Axial Offset control / Fg Surveillance Technical specification," February 1994 (W Proprietary).
(Hethodolcgy for specifications 3.2.1 - Axial Flux Difference and 3.2.2 - Heat Flux Hot channel Factor.)
3a. WCAPa 12945-P, Vol. I-IV, 1992-1993, " Code Qualification Docun. ant for Best Estimate LOCA Analysis." (H Proprietary)                                        '
3b. Letter, N. J. Liparulo, (W) to R. C. Jones, (USNRC), " Revision to Westinghoase Uncertainty Methodology," NTD-NRC-95-4575, Oct. 13, 1995.
3c. Letter, R. C. Jones (USNRC) to N. J. Liparulo (W), "Acceptanew for Referencing of the Topical Report, WCAP-12945(P), Westinghouse code Qualification Document for Dest Estimate Loss-of-Coolant Analysis,"
June 28, 1996.
3d. WCAP-12610-P-A, " VANTAGE + Fuel Assembly Reference Core Report,"
April 1995 (W Proprietary).
(Hethodology for specification 3.2.2 - Heat Flux Hot Chennel Factor.)
l l        The core operating li.nl*.s 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.
hENUAL 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 annually. This report shall contain the information identified in Regulat3ry Position C.3.b of NRC Regulatory Guide 1.108, Revision 1, 1977.
FARLEY-UNIT 1                                                6-19a          AMENDMENT NO.
                                                                      -                                    )
 
FNP Unit 2 Technical Specifications Power Uprate implementation Changedhrs -
Ufut2                                          Revision Page 619a                                      New Page (Replace TS Page 619a in February 14,1997 Submittal) l l
 
ADMINISTRATIVE CONThoLa                                                                                                  _
t                2.
tsCAP-10216-P-A, Rey, lA, ' Relax ti:n Cf Con; tant Amial Offset Control /
Fg surveillance Techni-al specificacion," February 1994 (M Proprietary) .
(Methodology for spect,fic4tions 3.2.1 - Axial Flum Difference and 3.2.2 - Beat Flux Not Channel Facter.)
w-          --
e
                        /.      - 1tCAP-10296-P= Ar-Revr-27 *the-1941-Verebr. of ";;tinghe eee-avekwet-ten-
                                  --Moden 'leb; ??l" c:d:,' ". veh-444NM-Peepe&etarytv u___ _ _% ~ _
e                        ._ _ A -    -C  '
(Methodolotsy "or specification 3.2.2 - Heat Flus Hot Channel                                                                                      l Factor.)
                                                                                                                                                                                        ]
The core operating limits shall be determined so that all applicable limits                                                                                  1 (e.g., f t**1 thennal-sechanical limits, core thermal-hydraulic limits, ICCs limits, nuclear limits such ai shutdown margin, and transient and accident analysis limit.,) of the safety analysis are met.
The CORE OPERATING !.!MITS REPORT, Jncluding any midacycle twvisions or supple,eents thereto, sba)1 be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with cspies to the Regional Administrator and Resident I.4spector.                                        ..'                                    _.                                                        1 ANNUAL DIESIL CENERATOR RELTAEftfTY DATA REDORT                                                                          -
6.9.1.12            The numbst of teste (valid or invalid) and the number of failures to start on dem.and for eacA diesel generator shall be submitted to the NRC annually.
This report shall cont %in the information identif hd in Aegulatory Position C.3.b of NRC Regulatory cuide 1.108, Revision 1, 1977.
I Insert A to pg 6.19a 3a.        WCAP 12945 P, Vol. IE, 19921993, " Code Qualification Document for Best Estiinate LOCA            sis". M Proprietary) 3b.        Letter, N. J. Liparuto, (W) to R. C. Jones, (USNRC), "Revhion to Westinghouse Uncertainty Methodology", NTD NRC 95 4575, Oct.15Q 3c.      Letter, R. C. Jones (USNRC) to N. J. Liparuto (W), " Acceptance or Referencing of the Topical Report, WCAP 12945(P), Westinghouse Code Qualification Document for
_m Ben  .~ Estimate loss-of-gJune 28,1996.
g 3d. WCAP-12619 P A," VANTAGE + Fuel Assembly Reference Core Report," April 1995 (W                                                                        g Proprietary).
l
__                                    x_ _ _                                                                                    - _  --
FARLEY-DNIT 2                                          (;- 19 e                                                                  AMENDMINT No.
 
4 A MINISTRATIVE CONTROLS
: 2. WCAP-10216-P-A, Rev. 1A, " Relaxation of Constant Axial offset control / Fg Surveillance Technical Specification," February 1994 (W Proprietary).
(Methodology for specifications 3.2.1 - Axial Flux Difference and 3.2.2 - Heat Flux Hot Channel Factor.)
3a. WCAP-12945-P, Vol. I-IV, 1992-1993, " Code Qualification Document for Best Estimate LOCA Analysis."              (H Proprittery)
: 30. Letter, N. J. Liparulo, (W) to R. C. Jones, (USNRC), " Revision to Westinghouse Uncettainty Methodology," NTD-NRC-95-4575, oct. 13, 1995.
3c. Letter, R. C. Jones (USNRC) to N. J. Liparulo (W), " Acceptance for Referencing of the Topical Report, WCAP-17J45(P), Westinghouse Code Qualification Document for Best Estimate Loss-of-Coolant Analysis,"
June 28, 1996.
3d. WCAP-12610-P-A, " VANTAGE + Fuel Assembly Reference Core Report,"
April 1995 (W Proprietary).
l              (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
The core operating limits shall be determined so that all applicable liinits (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 6.9.1.11                  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. Thio 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.
                                                                                                .u}}

Latest revision as of 21:25, 1 January 2021

Revised Proposed Changes to TS Page 6-19a for Power Uprate
ML20202F112
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 02/12/1998
From:
SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20202F109 List:
References
NUDOCS 9802190132
Download: ML20202F112 (5)
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Text

_ . . _ _ _ ____ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ . . __ -_ _ ___. _ _._ ___ _ ._ _ _ _ _

ADMIN!sTRATIVE CONTROLS

.nsa 2.

WCAP-lo216-P-A, Rev. 1A,

  • Relaxation of Constant Asial offset control /

, Fg surveillance Technical specification," February 1994 (M Froprietary).

(Methodology for specifications 3.2.1 - Asial Flum Difference and 3.2.2 - Beat Flum Not Channel Factor.)

M *WCAF=19 fit-P=h, M . 2, "The-4981-Verei= ^f "::tinghewee-Beelvetion-m > _ i _ n g,ggy ,.m

.u.y.., . u . . _ _ gwp (

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

The (e.g.,core operating limite shall be determined so that all appitcable limite fuel thermal-mechanical limite, core thermal-hydraulic limite, ICCS limite, nuclear limite auch as shutdown margin, and transient and accident analysie limits) of the safety analysis are met.

The ooR5 OPERATING LIMITS REPORT, including any mid-cycle revisione or supplements thereto, shall be provided upon Leeuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Adeinistrator and Resident Inspector. ,-

ArmuAt crusat crwamaron artranrtrTr DATA arpom?

6.9.1.12 The number of teste (valid or invalid) and the numbeir of f ailures to start on demand for each diesel genetator shall be submitted to the NRC annually.

This report shall contain the information identified in Regulatory Position C.3.b

, of NRC Regulatory Guide 1.104, Revision 1, 1977.

t Intert A to pg 6.194 3a. WCAP 12945 P, Vol. I.&,19921993, " Code Quallneation Document for Best Estimate LOCA Analysis". & Proprietary) 3b.

Letter, N. J. Lipamlo, (W) to R. C. Jones, (USNRC), " Revision to Westinghouse Uncertainty Methodology", NTD NRC 95-4575, Oct Mr 5.

3c. Letter, R. C. Jones (USNRC) to N. J. Lipamlo (W), " Acceptance for Refetencing of the Topical Report, WCAP 12945(P), Westingbouse Code Qualification Document for Best Estimate Loss of-Coolant Analysis", June 28,1996 3d WCAP 12610-P A. " VANTAGE + Fuel Assembly Reference Core Report," April M 1995 (W Proprietary). N

?

FAALEY-UNIT 1 6-19a AMENDMENT No.

9802190132 980212 PDR ADOCK 05000348 P PDR

._ ~ _

. . N ADMINISTRATIVE CONTROLS

2. WCAP-10216-P-A, Pev. 1A, " Relaxation of Constant Axial Offset control / Fg Surveillance Technical specification," February 1994 (W Proprietary).

(Hethodolcgy for specifications 3.2.1 - Axial Flux Difference and 3.2.2 - Heat Flux Hot channel Factor.)

3a. WCAPa 12945-P, Vol. I-IV, 1992-1993, " Code Qualification Docun. ant for Best Estimate LOCA Analysis." (H Proprietary) '

3b. Letter, N. J. Liparulo, (W) to R. C. Jones, (USNRC), " Revision to Westinghoase Uncertainty Methodology," NTD-NRC-95-4575, Oct. 13, 1995.

3c. Letter, R. C. Jones (USNRC) to N. J. Liparulo (W), "Acceptanew for Referencing of the Topical Report, WCAP-12945(P), Westinghouse code Qualification Document for Dest Estimate Loss-of-Coolant Analysis,"

June 28, 1996.

3d. WCAP-12610-P-A, " VANTAGE + Fuel Assembly Reference Core Report,"

April 1995 (W Proprietary).

(Hethodology for specification 3.2.2 - Heat Flux Hot Chennel Factor.)

l l The core operating li.nl*.s 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.

hENUAL 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 annually. This report shall contain the information identified in Regulat3ry Position C.3.b of NRC Regulatory Guide 1.108, Revision 1, 1977.

FARLEY-UNIT 1 6-19a AMENDMENT NO.

- )

FNP Unit 2 Technical Specifications Power Uprate implementation Changedhrs -

Ufut2 Revision Page 619a New Page (Replace TS Page 619a in February 14,1997 Submittal) l l

ADMINISTRATIVE CONThoLa _

t 2.

tsCAP-10216-P-A, Rey, lA, ' Relax ti:n Cf Con; tant Amial Offset Control /

Fg surveillance Techni-al specificacion," February 1994 (M Proprietary) .

(Methodology for spect,fic4tions 3.2.1 - Axial Flum Difference and 3.2.2 - Beat Flux Not Channel Facter.)

w- --

e

/. - 1tCAP-10296-P= Ar-Revr-27 *the-1941-Verebr. of ";;tinghe eee-avekwet-ten-

--Moden 'leb; ??l" c:d:,' ". veh-444NM-Peepe&etarytv u___ _ _% ~ _

e ._ _ A - -C '

(Methodolotsy "or specification 3.2.2 - Heat Flus Hot Channel l Factor.)

]

The core operating limits shall be determined so that all applicable limits 1 (e.g., f t**1 thennal-sechanical limits, core thermal-hydraulic limits, ICCs limits, nuclear limits such ai shutdown margin, and transient and accident analysis limit.,) of the safety analysis are met.

The CORE OPERATING !.!MITS REPORT, Jncluding any midacycle twvisions or supple,eents thereto, sba)1 be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with cspies to the Regional Administrator and Resident I.4spector. ..' _. 1 ANNUAL DIESIL CENERATOR RELTAEftfTY DATA REDORT -

6.9.1.12 The numbst of teste (valid or invalid) and the number of failures to start on dem.and for eacA diesel generator shall be submitted to the NRC annually.

This report shall cont %in the information identif hd in Aegulatory Position C.3.b of NRC Regulatory cuide 1.108, Revision 1, 1977.

I Insert A to pg 6.19a 3a. WCAP 12945 P, Vol. IE, 19921993, " Code Qualification Document for Best Estiinate LOCA sis". M Proprietary) 3b. Letter, N. J. Liparuto, (W) to R. C. Jones, (USNRC), "Revhion to Westinghouse Uncertainty Methodology", NTD NRC 95 4575, Oct.15Q 3c. Letter, R. C. Jones (USNRC) to N. J. Liparuto (W), " Acceptance or Referencing of the Topical Report, WCAP 12945(P), Westinghouse Code Qualification Document for

_m Ben .~ Estimate loss-of-gJune 28,1996.

g 3d. WCAP-12619 P A," VANTAGE + Fuel Assembly Reference Core Report," April 1995 (W g Proprietary).

l

__ x_ _ _ - _ --

FARLEY-DNIT 2 (;- 19 e AMENDMINT No.

4 A MINISTRATIVE CONTROLS

2. WCAP-10216-P-A, Rev. 1A, " Relaxation of Constant Axial offset control / Fg Surveillance Technical Specification," February 1994 (W Proprietary).

(Methodology for specifications 3.2.1 - Axial Flux Difference and 3.2.2 - Heat Flux Hot Channel Factor.)

3a. WCAP-12945-P, Vol. I-IV, 1992-1993, " Code Qualification Document for Best Estimate LOCA Analysis." (H Proprittery)

30. Letter, N. J. Liparulo, (W) to R. C. Jones, (USNRC), " Revision to Westinghouse Uncettainty Methodology," NTD-NRC-95-4575, oct. 13, 1995.

3c. Letter, R. C. Jones (USNRC) to N. J. Liparulo (W), " Acceptance for Referencing of the Topical Report, WCAP-17J45(P), Westinghouse Code Qualification Document for Best Estimate Loss-of-Coolant Analysis,"

June 28, 1996.

3d. WCAP-12610-P-A, " VANTAGE + Fuel Assembly Reference Core Report,"

April 1995 (W Proprietary).

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

The core operating limits shall be determined so that all applicable liinits (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 6.9.1.11 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. Thio 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.

.u

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