ML091950551
| ML091950551 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 08/05/2009 |
| From: | Boska J Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Boska J, NRR, 301-415-2901 | |
| References | |
| TAC MA4359, TAC MC5033 | |
| Download: ML091950551 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO.3 - CORRECTION TO TECHNICAL SPECIFICATIONS (TAC NOS. MA4359 AND MC5033)
Dear Sir or Madam:
The purpose of this letter is to issue the following typographical corrections to the Indian Point Nuclear Generating Unit No.3 (IP3) Technical Specifications (TSs).
By letter dated April 6, 2005, Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML050680066 and ML050970205, the Nuclear Regulatory Commission (NRC) issued License Amendment No. 226 to Facility Operating License (FOL) No.
DPR-64 for IP3. Although not a part of the amendment request, a typographical error was introduced on TS Page 3.5.3-1 by eliminating the word "testing" in the note for Limiting Condition for Operation 3.5.3.
Also, by letter dated April 14, 2005, ADAMS Accession Nos. ML050660112 and ML051080034, the NRC issued License Amendment No. 228 to FOL No. DPR-64 for IP3. The amendment revised the TSs by eliminating the requirements associated with hydrogen recombiners and hydrogen monitors. The marked-up TS pages correctly showed the change to remove footnote (d) from TS Table 3.3.3-1 by moving it to be footnote (c). However, there was a typographical error on the final TS Page 3.3.3-4 issued with the amendment, in which the Required Channels column for the Core Exit Thermocouples did not have footnote (d) replaced by footnote (c), as was approved by the amendment. There is currently no footnote (d) to this table, although it is still referenced on Page 3.3.3-4.
Please replace the corresponding pages from the TSs with the corrected TS pages 3.3.3-4 and 3.5.3-1 enclosed with this letter.
- 2 Please contact me at (301) 415-2901 if you have any questions on this issue.
Sincerely, C1Lo~
ah~.~. Boska, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosure:
Corrected TS Pages 3.3.3-4 and 3.5.3-1 cc w/encls: Distribution via Listserv
ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS-Shutdown LCO 3.5.3 One ECCS residual heat removal (RHR) subsystem and one ECCS recirculation subsystem shall be OPERABLE.
NOTE-------------------------------
An RHR train may be considered OPERABLE during alignment and operation for decay heat removal, and during valve testing, if capable of being manually realigned to the ECCS mode of operation.
APPLICABILITY:
MODE 4.
ACTIONS
NOTE----------------------
LCO 3.0.4.b is not applicable to the ECCS residual heat removal and ECCS recirculation subsystems.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Required ECCS residual heat removal (RHR) subsystem inoperable.
A.1 Initiate action to restore required ECCS RHR subsystem to OPERABLE status.
Immediately B.
Required ECCS Recirculation subsystem inoperable.
B.1 Restore required ECCS recirculation subsystem to OPERABLE status.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C.
Required Action and associated Completion Time of Condition B not met.
C.1 Be in MODE 5.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> INDIAN POINT 3 3.5.3-1 Amendment 226 Revised by letter dated August 5, 2009
PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 2)
Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM REQUIRED SR 3.3.3.2 FUNCTION REQUIRED CHANNELS ACTION D. I FREQUENCY I.
Neutron Flux
- 2.
RCS Hot Leg Temperature (Wide Range)
(ThO')
- 3.
RCS Cold Leg Temperature (Wide Range)
(Teo")
- 4.
RCS Pressure (Wi de Range)
- 5.
- 6.
Containment Water Level (Wide Range)
- 7.
Containment Water Level (Recirculation Sump)
- 8.
Containment Pressure
- g.
Automatic Containment Isolation Valve Position
- 10.
Containment Area Radiation (High Range)
- 11.
NOT USED
- 12.
Pressuri zer Level
- 13.
SG Water Level (Narrow Range)
- 14.
SG Water Level (Wide Range) and Auxiliary Feedwater Flow
- 15.
NOT USED
- 16.
Steam Generator Pressure
- 17.
Condensate Storage Tank Level
- 18.
Core Exit Thermocouples-Quadrant
- 19.
Core Ex it Thermocouples-Quadrant 2
- 20.
Core Exit Thermocouples-Quadrant 3
- 21.
Core Exi t Thermocoupl es-Quadrant 4
- 22.
Main Steam Line Radiation
- 23.
Gross Failed Fuel Detector
- 24.
RCS Subcooling Margin 2
per loop per loop 2
2 2
2 2
2 per penetration flow path{') (b) 2 2
2 per SG each per SG 2 per SG 2
2 (c) 2 (c) 2 (c) 2 (c) per steam 1i ne 2
2 F
24 months 24 months E
24 months E
24 months 24 months 24 months E
24 months 18 months F
24 months F
24 months 24 months 24 months 24 months, SGL 18 months, AFF E
24 months F
24 months E
24 months E
24 months 24 months E
24 months F
24 months F
24 months E
24 months See NOTES, next page.
INDIAN POINT 3 3.3.3-4 Amendment 228 Revised by letter dated August 5, 2009
- 2 Please contact me at (301) 415-2901 if you have any questions on this issue.
Sincerely, IRAI John P. Boska, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosure:
Corrected TS Pages 3.3.3-4 and 3.5.3-1 cc w/encls: Distribution via Listserv DISTRIBUTION:
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