ML042360026
| ML042360026 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/28/2004 |
| From: | Entergy Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML042360026 (9) | |
Text
2 8-JUL- 04 Page:
78 DISTRIBUTION CONTROL LIST
- ument Name:
ITS/BASES/TRM CCNAME NAME 1 OPS PROCEDURE GROUP SUPV.
3 PLANT MANAGER'S OFFICE 5 CONTROL ROOM & MASTER 6 OPERATIONS MANAGER 9 MYERS VALERIE 11 RES DEPARTMENT MANAGER 16 BOCCIO JOHN 19 STEWART ANN 20 CHEMISTRY SUPERVISOR 21 TSC(IP3) 22 SHIFT MGR.(LUB-001-GEN) 23 LIS 25 SIMULATOR 28 RESIDENT INSPECTOR 32 EOF 47 CHAPMAN N 50 TADEMY L. SHARON 54 NUC ENGINEERING LIBRARY S
55 REFERENCE LIBRARY 61 SIMULATOR 69 CONROY PAT 99 BARANSKI J (ALL) 102 BILYOU CHRISTINE I&C ONLY 106 SIMULATOR INSTRUCT AREA 164 CONTROL ROOM & MASTER 207 TROY M 273 FAISON CHARLENE 319 L.GRANT (LRQ-OPS TRAIN) 354 L.GRANT(LRQ-OPS/TRAIN) 357 L.GRANT(ITS/INFO ONLY) 424 HULBERT TRACY(7COPIES) 474 OUELLETTE P 483 SCHMITT RICHIE 484 HANSLER ROBERT 485 DRAKE RICH 489 CLOUGHNESSY PAT 491 ORLANDO TOM (MANAGER) 492 PETACHI CHRISTA 493 OPERATIONS FIN TEAM 494 AEOF/A.GROSJEAN(ALL EPtS) 495 JOINT NEWS CENTER 496 L.GRANT(LRQ-OPS/TRAIN) 497 L.GRANT(LRQ-OPS/TRAIN) 500 L.GRANT (LRQ-OPS TRAIN)
P5 501 L.GRANT (LRQ-OPS TRAIN) 512 L.GRANT (LRQ-OPS TRAIN) 513 L.GRANT (LRQ-OPS TRAIN) 518 DOCUMENT CONTROL DESK 527 MILIANO PATRICK DEPT LOCATION OPS PROCEDURE GROUP UNIT 3(UNIT 3/IPEC ONLY)
OPS/FRED SMUTNY SYSTEM ENG. 72'ELEVATION RES (UNIT 3/IPEC ONLY)
I&C OFFICE (SUPERVISOR)
LICENSING CHEMISTRY DEPARTMENT EEC BUILDING OPS (UNIT 3/IPEC ONLY)
LICENSING & INFO SERV TRAIN(UNIT 3/IPEC ONLY)
US NRC 88' ELEVATION E-PLAN (ALL EP'S)
BECHTEL WESTINGHOUSE ELECTRIC DOC (UNIT 3/IPEC ONLY)
REC/TRN(UNT 3/IPEC ONLY)
TRAIN(UNIT 3/IPEC ONLY)
LICENSING/ROOM 205 ST. EMERG. MGMT. OFFICE I&C SUPPORT TRG/3PT-DO01-D006 ONLY)
PROCUREMENT ENG.
NUCLEAR LICENSING LRQ (UNIT 3/IPEC ONLY)
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ENG., PLAN & MGMT INC MAINTENANCE ENG/SUPV REACTOR ENGINEERING DESIGN ENG/GSB/3RD FLOOR PLANT SUPPORT TEAM PROGRAMS/COMPONENTS ENG WC/ONE STOP SHOP 33 TURBIN DECK E-PLAN (EOP'S ONLY)
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NRC (ALL EP'S)
NRC/SR. PROJECT MANAGER IP2 IP2 IP3(ONLY) 45-3-D IP2 4329 45-4-A 45-2-A GSB-2D 45-4-A IP2 IP3 OFFSITE 48-2-A IP2 EOF OFFSITE OFFSITE WPO/7A BLDG/17 48-2-A GSB-2D OFFSITE 45-2-D
- 48 IP3(ONLY) 1A WPO-12
- 48
- 48 48-2-A
- 48 OFFSITE 45-1-A 72'UNIT 2 GSB-3B GSB-3B 45-3-G IP-K-4321 45-1-A WPO-12D EOF
- 48
- 48
- 48
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IPEC SITE QUALITY RELATED IP-SMM-AD-103 Revision 0 Entergy MANAGEMENT ADMINISTRATIVE PROCEDURE MANUAL INFORMATIONAL USE Page 13 of 21 ATTACHMENT 10.1 SMM CONTROLLED DOCUMENT TRANSMITTAL FORM SITE MANAGEMENT MANUAL CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES Page 1 of I i --Enterv CONTROLLED DOCUMENT yTRANSMITTAL FORM - PROCEDURES IPEC, P.O. Box 308, Buchanan, NY 10511 TO: DISTRIBUTION DATE: 8/11104 TRANSMITTAL NO:
Cirde one)
FROM: IPEC DOCUMENT CONTROL:
or IP2 53'EL PHONE NUMBER: (914) 271-7054 The Document(s) identified below are forwarded for use. In accordance with IP-SMM-AD-103, please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s). Sign and return the receipt acknowledgement below within fifteen (15) working days.
AFFECTED DOCUMENT:
IP3 I TECHNICAL SPECIFICATIONS AMENDMENT 221 DOC#
REV#
TITLE INSTRUCTIONS
- SEE ATTACHED INSTRUCTIONS ******
- PLEASE NOTE EFFECTIVE DATE***********
RECEIPT OF THE ABOVE LISTED DOCUMENT(S) IS HEREBY ACKNOWLEDGED. I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH EFFECTIVE DATE(S) (IF APPLICABLE) AS SHOWN ON THE DOCUMENTYS).
$7f NAME (PRINT)
SIGNATURE v
DATE CC#
NAME (PRINT)
SIGNATURE DATE CC#
Distribution of iP3 Technical Specification Amendment 221 (Approved by NRC July 2, 2004)
Pages are to be inserted into your controlled copy of the IP3 Technical Specifications following the instructions listed below. The TAB notation indicates which section the pages are located.
REMOVE PAGES INSERT PAGES TAB - Facility Operating License Page 3, (Amendment 220)
Page 3, (Amendment 221)
TAB - List of Effective Pages Pages 1 through 3, (Amendment 220)
Pages 1 through 3, (Amendment 221)
Page 13 TAB - List of Amendments Page 13 TAB 5.0 - Administrative Controls Page 5.0-11 (Amendment 205)
Page 5.0-1 1 (Amendment 22 1)
C.
This amended license shall be deemed to contain and is subject to the conditions specified In the following Commission regulations in 10 CFR Chapter l: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level ENO is authorized to operate the Amdt. 213 facility at steady state reactor core Power 11-26-2002 levels not in excess of 3067A megawatts thermal (100% of rated power)
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 221 are hereby incorporated in the License. ENO shall operate the facility in accordance with the Technical Specifications.
(3)
(DELETED)
(4)
(DELETED)
D.
(DELETED)
Amdt. 46 2-16-83 E.
(DELETED)
Amdt. 37 5-14-81 F.
This amended license is also subject to appropriate conditions by the New York State Department of Environmental Conservation in its letter of May 2, 1975, to Consolidated Edison Company of New York, Inc., granting a Section 401 certification under the Federal Water Pollution Control Act Amendments of 1972.
G.
ENO shall fully implement and maintain in effect Amdt. 81 all provisions of the Commission-approved physical 6-6-88 security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and CFR 50.54(p).
The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Indian Point 3 Nuclear Power Plant Physical Security Plan," with revisions submitted through December 14,1987; "Indian Point 3 Nuclear Power Plant Amendment No. 221
INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 1 of 3 Page I Amend Table of Contents 205 ii 205 iii 207 iv 210 v :
207 Section 1.1 205 2
205 3
205 4
205 5
213 6
205 7
205 8
205 Section 1.2 1
205 2
205 3
J205 Section 1.3 205 2
205 3
205 4
205 5
205 6
205 205 8
205 9
205 10 205 11 205 12 205 13 205 Section 1.4 1
205 2
205 3
205 4
205 Section 2.0 1
l 205 2
li 213 1
205 Section 3.0 2
205 E 1
205 3
205 2
205 Section 3.2.3 3
205 1
205 4
212 2
205 5
205 3
205 Section 3.1.1 4
205 1
l 205 Section 3.2.4 Section 3.1.2 1
205 1
205 2
205 2
205 3
205 Section 3.1.3 4
205 1
205 Section 3.3.1 2
205 1
205 Section 3.1.4 2
205 1
205 3
205 2
205 4
205 3
205 5
205 4
205 6
205 5
205 7
205 Section 3.1.5 8
205 1
205 9
205 2
l 205 10 205 Section 3.1.6 11 205 1
205 12 205 2
205 13 205 3
205 14 205 Section 3.1.7 15 205 1
205 16 205 2
205 17 205 3
205 18 205 4
205 19 205 Section 3.1.8 20 205 1
205 Section 3.3.2 2
205 1
205 Section 3.2.1 2
205 1
205 3
205 2
205 4
205 3
205 5
205 Section 3.2.2 6
205 latest amendment reflected in this list is: Amendment 221 The
INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 2 of 3 The latest amendment reflected in this list is: Amendment 221
INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 3 of 3 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 205 210 205 221 205 205 205 205 205 205 205 205 205 205 205 205 219 205 205 205 205 205 206 206 205 205 205 217 205 205 205 I
The latest amendment reflected in this list is: Amendment 221
Entergy Nuclear Operations, Inc Indian Point 3 Nuclear Power Plant License Amendments Page 13 AMENDMENT SUBJECT LETTER DATE 217 218 Use of Best-Estimate Large-Break Loss of Coolant Accident analysis methodology WCAP 12945)
Revise City Water surveillance to reflect addition of (backflow preventer) valves 219 Revise Ventilation Filter Testing Program to adopt ASTM D3803 charcoal filter testing requirements per GL 99-02.
05/06/2003 08/04/2003 10/30/2003 12/03/2003 07/02/2004 220 221 Extension of the RCS pressure/temperature limits and corresponding OPS limits from 16.17 to 20 EFPY.
Extension of RCP flywheel inspection interval (from 10 years to 20 years) per TSTF 421
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
- i.
Limitations on the annual and quarterly doses to a member of the public from iodine-131, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and
- j.
Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
Component Cyclic or Transient Limit 5.5.5 This program provides controls to track the FSAR, Section 4.1.5. cyclic and transient occurrences to ensure that components are maintained within the design limits.
Reactor Coolant Pump Flywheel Inspection Program 5.5.6 This program shall provide for the inspection of each reactor coolant pump flywheel. The program shall include inspection frequencies and acceptance criteria. The inspection frequency will ensure that each reactor coolant pump flywheel is surface and volumetrically inspected at 20-year intervals.
(continued)
INDIAN POINT 3 5.0 - 11 Amendment 221