ML12356A072
| ML12356A072 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/02/2013 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Pickett D NRR/DORL/LPL1-1 301-415-1364 | |
| References | |
| TAC ME7367 | |
| Download: ML12356A072 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 2, 2013 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
CORRECTION LETTER TO LICENSE AMENDMENT NO. 270 - INDIAN POINT NUCLEAR GENERATING UNIT NO.2 (TAC NO. ME7367)
Dear Sir or Madam:
By letter dated November 28,2012. the Commission issued Amendment No. 270 to Facility Operating License No. DPR-26 for the Indian Point Nuclear Generating Unit No.2. The amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated October 18, 2011, as supplemented by letters dated April 27, and October 2.
2012.
The amendment changed TS 3.3.3, "Post Accident Monitoring (PAM) Instrumentation,"
Table 3.3.3-1, "Post Accident Monitoring Instrumentation," by revising the existing requirement for two channels of the Containment Water Level (Containment Sump) function and two channels of the Containment Sump Water Level (Recirculation Sump) function to two Containment Water Level channels.
We recently recognized that TS Table 3.3.3-1 was issued with the wrong page number. A corrected page is enclosed. Please feel free to contact me at 301-415-1364 if you have any questions.
Sincerely,
~vp~
Douglas V. Pickett, Senior Project Mc;mager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosure:
As stated cc w/encl: Distribution via Listserv
3.3.3 PAM Instrumentation Table 3.3.3-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONDITION FUNCTION REQUIRED CHANNELS REFERENCED FROM REQUIRED ACTION D.1
- 1.
Reactor Coolant System (RCS) Hot Leg Temperature (Wide Range)
- 2.
RCS Cold Leg Temperature (Wide Range)
- 3.
RCS Pressure (Wide Range)
- 4.
Reactor Vessel Level Indication System (RVLlS)
- 5.
Containment Water Level (Containment and Recirculation Sump)
- 6.
NOT USED
- 7.
Containment Pressure
- 8.
Containment Pressure (High Range)
- 9.
Containment Area Radiation (High Range)
- 10.
NOT USED 11. Pressurizer Level
- 12.
Steam Generator (SG) Water Level (Narrow Range)
- 13.
Steam Generator Water Level (Wide Range)
- 14.
Condensate Storage Tank level
- 15.
Core Exit Temperature Quadrant
- 16.
Core Exit Temperature - Quadrant 2
- 17.
Core Exit Temperature Quadrant 3
- 18.
Core Exit Temperature - Quadrant 4
- 19.
Auxiliary Feedwater Flow
- 20.
Steam Generator Pressure
- 21.
RCS Subcooling Margin Monitor
- 22.
RWST Level 1 per loop (a)
E 1 per loop (b)
E 2
E 2
F 2(d)
E 2
E 2
E 2
F 2
E 2 per steam generator E
4 E
2 F
2 trains(c)
E 2 trains(C)
E 2 trains(C)
E 2 trains(C)
E 4
E 2 per steam line E
2 E
2 E
(a)
The required redundant channel for each of the four loops of RCS hot leg temperature is a qualified Core Exit Temperature train in the quadrant associated with that loop.
(b)
The required redundant channel for each of the four loops of RCS cold leg temperature is any channel of steam generator pressure for that loop.
(c)
A CET train consists of two core exit thermocouples (CETs).
(d)
Only met by L T-3300 and L T-3301 or L T-939 and L T*941 to ensure redundant power supplies.
INDIAN POINT 2 3.3.3 - 4 Amendment No. 270
January 2, 2013 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 SUB,JECT:
CORRECTION LEDER TO LICENSE AMENDMENT NO. 270 - INDIAN POINT NUCLEAR GENERATING UNIT NO.2 (TAC NO. ME7367)
Dear Sir or Madam:
By letter dated November 28,2012, the Commission issued Amendment No. 270 to Facility Operating License No. DPR-26 for the Indian Point Nuclear Generating Unit NO.2. The amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated October 18, 2011, as supplemented by letters dated April 27, and October 2, 2012.
The amendment changed TS 3.3.3, "Post Accident Monitoring (PAM) Instrumentation,"
Table 3.3.3-1, "Post Accident Monitoring Instrumentation," by revising the existing requirement for two channels of the Containment Water Level (Containment Sump) function and two channels of the Containment Sump Water Level (Recirculation Sump) function to two Containment Water Level channels.
We recently recognized that TS Table 3.3.3-1 was issued with the wrong page number. A corrected page is enclosed. Please feel free to contact me at 301-415-1364 if you have any questions.
Sincerely, IRA!
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL1-1 RtF RidsNrrDorl RidsNrrDorlLpl1-1 RidsOgcRp RidsNrrDorlDpr RidsAcrsAcnw _MailCTR RidsRgn1 MailCenter RidsNrrPMlndianPoint RidsNrrLAKGoidstein ADAMS ACCESSION NO.: ML12356A072 LPL1-1/PM LPL1-1/LA DPickett KGoldstein 12/31/12 12/27/12 OFFICIAL RECORD COpy LPL1-1/BC GWilson 13