ML17264B044
| ML17264B044 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/29/1997 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17264B042 | List: |
| References | |
| NUDOCS 9710020174 | |
| Download: ML17264B044 (5) | |
Text
Reporting Requirements 5.6 5.6 Reporting Requirements I
5.6.6 Ggl S I C. i,2.
PTLR (continued) c.
The FriaYjt7cag~NiNodJ:,:vs'ed,";-:ii;:;,:.deti);i$ je;::.:thee>'CS pressure and temp'erature and LTOP limits shall be those previously reviewed and approved by the NRC.
in NRC letter dated Hay K~&96PW.fRC"':~%pe'.'o9'a~lYdacuient>.
Specifically, the ~Ale e~nethodology ~~is described in the following documents:
1.
Letter from R.C. Mecredy, Rochester Gas and Electric Corporation (RGKE), to Document Control Desk,
- NRC, Att ti: ~i~I',",-,.6,::::::;,:,:gi,',,:,::im "Appl'l I
Facility Operating
- License, Revision-'to Reactor Coolant System (RCS)
Pressure and Temperature Limits Report (PTLR)fA8ijiiifjtrettiseTcaitySl 9'; Rejiiii!emi.ifts,"
"Rp'tet eehiigeri>VT':::,"',,:,::4'e"tl'eiiibsei:'"~4R,,";.;:;:1991.
C.t,(
2.
~
~
~
~
N II IISAP-lt t~
"-::IIP%
"Methodology Used to Develop Cold Overpressure Nil.ig t.i g Sp t S tp I t d Atg d t p,d t Id ti it t, 8
SS,
-'Pl'.,::,;l diig't P'," pg i!i!INII~S!
I 4.i.~
C,t,X d.
The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluencm period and for revisions or supplement thereto.
R.E.
Ginna Nuclear Power Plant 97i0020i74 9709'29 PDR ADQCK 05000244 P
PDR 5.0-22 Amendment No. g, g
Attachment III Proposed Technical Specifications Included Pages:
5.0-22
Reporting Requirements 5.6 5.6 Reporting Requirements
~
~
5.6.6 PTLR (continued) c.
The analytical methods used to determine the RCS pressure and temperature and LTOP limits shall be those previously reviewed and approved by the NRC in NRC letter dated
<NRC approval document>.
Specifically, the limits and methodology is described in the following documents:
1.
Letter from R.C. Hecredy, Rochester Gas and Electric Corporation (RG&E), to Document Control
- Desk, NRC, Attention: A.R. Johnson, "Application for Facility Operating
- License, Revision to Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
Administrative Controls Requirements,"
Attachment VI, September XX, 1997.
2.
WCAP-14040-NP-A, "Methodology Used to Develop Cold Overpressur e Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," Sections 1, 2, and 4, January 1996.
d.
'The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for revisions or supplement thereto.
R.E.
Ginna Nuclear Power Plant 5.0-22 Amendment No..g, PP
Attachment IV Ginna Station PTLR, Revision 2