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{{#Wiki_filter:Attachment II Marked Up Copy of R.E.Ginna Nuclear Power Plant Technical Specifications Included Pages: 5.0-22 9602i30388 960209 PDR ADGCK 05000244 P PDR~
{{#Wiki_filter:Attachment   II Marked Up Copy of R.E. Ginna Nuclear Power Plant Technical Specifications Included Pages:
eporting Requirements 5.6 5.6 Reporting Requirements 5.6.6 PTLR (continued)
5.0-22 9602i30388 960209 PDR   ADGCK   05000244 P                   PDR ~
C.d.The RCS pressure and temperature an limits shall be those previously reviewed and approve y the NRC i Amendment No.48.The acceptability of the P/T limits are documented in NRC letter,"R.E.Ginna-Acceptance for Referencing of Pressure Limits Report," Dece 995.Specifically, the limits and methodology are described in the following documen s: p~-r l.Amendment No.48 to Facility Operating License No.DPR-18, R.E.Ginna Nuclear Power Plant, Harch 6, 1992.2.Letter from C.I.Grimes, NRC, to R.A.Newton, Westinghouse Electric Corporation,"Acceptance for Referencing Topical Report WCAP-14040, Revision 1,'Hethodology used to Develop Cold Overpressure Hitigating System Setpoints and RCS Heatup and Cooldown Limit Curves'," October 16, 1995.3.Letter from R.C.Hecredy, Rochester Gas and Electric Corporation (RGEE), to Document Control Desk, NRC, Attention A.R.Johnson,"Technical Specifications Improvement Program, Reactor Coolant System (RCS)Pressure and Temperature Limits Report (PTLR)," December 8, 1995.The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluency period and for revisions or supplement thereto.R.E.Ginna Nuclear Power Plant 5.0-22 Amendment No.61 Attachment III Proposed Technical Specifications Included Pages: 5.0-22 eporting Requirements
 
~~5.6 5.6 Reporting Requirements 5.6.6 PTLR (continued) c~The RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC in Amendment No.48.The acceptability of the P/T limits are documented in NRC letter,"R.E.Ginna-Acceptance for Referencing of Pressure Limits Report," December 26, 1995.The analytical methods used to determine the LTOP limits shall be those previously reviewed by the NRC.Specifically, the P/T limits and LTOP methodology are described in the following documents:
eporting Requirements 5.6 5.6   Reporting Requirements 5.6.6         PTLR (continued)
l.Amendment No.48 to Facility Operating License No.DPR-18, R.E.Ginna Nuclear Power Plant, Harch 6, 1992.2.Letter from C.I.Grimes, NRC, to R.A.Newton, Westinghouse Electric Corporation,"Acceptance for Referencing Topical Report WCAP-14040, Revision 1,'Hethodology used to Develop Cold Overpressure Hitigating System Setpoints and RCS Heatup and Cooldown Limit Curves'," October 16, 1995.3.Letter from R.C.Hecredy, Rochester Gas and Electric Corporation (RGKE), to Document Control Desk, NRC, Attention A.R.Johnson,"Technical Specifications Improvement Program, Reactor Coolant System (RCS)Pressure and Temperature Limits Report (PTLR)," December 8, 1995.d.The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluency period and for revisions or supplement thereto.R.E.Ginna Nuclear Power Plant 5.0-22 Amendment No.g}}
C. The RCS pressure and temperature an         limits shall be those previously reviewed and approve       y the NRC i Amendment No. 48.     The acceptability of the P/T limits are documented in NRC letter, "R.E. Ginna-Acceptance for Referencing of Pressure Limits Report,"
Dece             995. Specifically, the limits and methodology are described in the following documen s: p~-r
: l. Amendment No. 48 to Facility Operating License No.
DPR-18, R.E. Ginna Nuclear Power Plant, Harch 6, 1992.
: 2. Letter from C. I. Grimes, NRC, to R.A. Newton, Westinghouse Electric Corporation, "Acceptance for Referencing Topical Report WCAP-14040, Revision 1,
                        'Hethodology used to Develop Cold Overpressure Hitigating System Setpoints and RCS Heatup and Cooldown Limit Curves'," October 16, 1995.
: 3. Letter from   R.C. Hecredy, Rochester Gas and Electric Corporation (RGEE), to Document Control Desk, NRC, Attention A.R. Johnson, "Technical Specifications Improvement Program, Reactor Coolant System (RCS)
Pressure and Temperature   Limits Report (PTLR),"
December 8, 1995.
: d. The PTLR   shall be provided to the NRC upon issuance for each reactor vessel fluency period and for revisions or supplement thereto.
R.E. Ginna Nuclear Power Plant           5.0-22                   Amendment No. 61
 
Attachment III Proposed Technical Specifications Included Pages:
5.0-22
 
                                                                    ~
eporting Requirements 5.6
                                                                                    ~
5.6   Reporting Requirements 5.6.6         PTLR (continued) c ~ The RCS pressure and temperature limits shall be those previously reviewed   and approved by the NRC in Amendment No.
: 48. The acceptability of the P/T limits are documented in NRC letter, "R.E. Ginna - Acceptance for Referencing of Pressure Limits Report," December 26, 1995. The analytical methods used to determine the LTOP limits shall be those previously reviewed   by the NRC. Specifically, the P/T limits   and LTOP methodology are described in the following documents:
: l. Amendment No. 48 to Facility Operating License No.
DPR-18, R.E. Ginna Nuclear Power Plant, Harch 6, 1992.
: 2. Letter from C.I. Grimes, NRC, to R.A. Newton, Westinghouse Electric Corporation, "Acceptance for Referencing Topical Report WCAP-14040, Revision 1,
                        'Hethodology used to Develop Cold Overpressure Hitigating System Setpoints and RCS Heatup and Cooldown Limit Curves'," October 16, 1995.
: 3. Letter from R.C. Hecredy, Rochester Gas and Electric Corporation (RGKE), to Document Control Desk, NRC, Attention A.R. Johnson, "Technical Specifications Improvement Program, Reactor Coolant System (RCS)
Pressure and Temperature   Limits Report (PTLR),"
December 8, 1995.
: d. The PTLR   shall be provided to the NRC upon issuance for   each reactor vessel fluency period and for revisions or supplement thereto.
R.E. Ginna Nuclear Power Plant         5.0-22                     Amendment No. g}}

Revision as of 18:08, 29 October 2019

Proposed Tech Specs Re Ltop Limits Using Util Proposed Methodology
ML17264A340
Person / Time
Site: Ginna Constellation icon.png
Issue date: 02/09/1996
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264A337 List:
References
NUDOCS 9602130388
Download: ML17264A340 (4)
v • d • e


Text

Attachment II Marked Up Copy of R.E. Ginna Nuclear Power Plant Technical Specifications Included Pages:

5.0-22 9602i30388 960209 PDR ADGCK 05000244 P PDR ~

eporting Requirements 5.6 5.6 Reporting Requirements 5.6.6 PTLR (continued)

C. The RCS pressure and temperature an limits shall be those previously reviewed and approve y the NRC i Amendment No. 48. The acceptability of the P/T limits are documented in NRC letter, "R.E. Ginna-Acceptance for Referencing of Pressure Limits Report,"

Dece 995. Specifically, the limits and methodology are described in the following documen s: p~-r

l. Amendment No. 48 to Facility Operating License No.

DPR-18, R.E. Ginna Nuclear Power Plant, Harch 6, 1992.

2. Letter from C. I. Grimes, NRC, to R.A. Newton, Westinghouse Electric Corporation, "Acceptance for Referencing Topical Report WCAP-14040, Revision 1,

'Hethodology used to Develop Cold Overpressure Hitigating System Setpoints and RCS Heatup and Cooldown Limit Curves'," October 16, 1995.

3. Letter from R.C. Hecredy, Rochester Gas and Electric Corporation (RGEE), to Document Control Desk, NRC, Attention A.R. Johnson, "Technical Specifications Improvement Program, Reactor Coolant System (RCS)

Pressure and Temperature Limits Report (PTLR),"

December 8, 1995.

d. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluency period and for revisions or supplement thereto.

R.E. Ginna Nuclear Power Plant 5.0-22 Amendment No. 61

Attachment III Proposed Technical Specifications Included Pages:

5.0-22

~

eporting Requirements 5.6

~

5.6 Reporting Requirements 5.6.6 PTLR (continued) c ~ The RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC in Amendment No.

48. The acceptability of the P/T limits are documented in NRC letter, "R.E. Ginna - Acceptance for Referencing of Pressure Limits Report," December 26, 1995. The analytical methods used to determine the LTOP limits shall be those previously reviewed by the NRC. Specifically, the P/T limits and LTOP methodology are described in the following documents:
l. Amendment No. 48 to Facility Operating License No.

DPR-18, R.E. Ginna Nuclear Power Plant, Harch 6, 1992.

2. Letter from C.I. Grimes, NRC, to R.A. Newton, Westinghouse Electric Corporation, "Acceptance for Referencing Topical Report WCAP-14040, Revision 1,

'Hethodology used to Develop Cold Overpressure Hitigating System Setpoints and RCS Heatup and Cooldown Limit Curves'," October 16, 1995.

3. Letter from R.C. Hecredy, Rochester Gas and Electric Corporation (RGKE), to Document Control Desk, NRC, Attention A.R. Johnson, "Technical Specifications Improvement Program, Reactor Coolant System (RCS)

Pressure and Temperature Limits Report (PTLR),"

December 8, 1995.

d. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluency period and for revisions or supplement thereto.

R.E. Ginna Nuclear Power Plant 5.0-22 Amendment No. g

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