ML042660161
| ML042660161 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/10/2004 |
| From: | Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| IP-SMM-AD-103, Rev 0 | |
| Download: ML042660161 (9) | |
Text
A 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 I of I
- EnteWy CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES IPEC, P.O. Box 308, Buchanan, NY 10511 TO: DISTRIBUTION DATE: 9110/04 TRANSMITTAL NO:
(Circle one)
FROM: IPEC DOCUMENT CONTROL: KJ or 1P2 53'EL PHONE NUMBER: (914) 271-7054 The Document(s) identified below are forwarded for use. In accordance with IP-SMM-AD-1 03, please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s).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 TECHNICAL SPECIFICATIONS - AMENDMENT 222 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 I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH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 DOCUMENT(S).
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SIGNATURE DATE CC#
NAME (PRINT)
SIGNATURE DATE CC#
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Distribution of IP3 Technical Specification Amendment 222 (Approved by NRC August 18, 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 221)
Page 3, (Amendment 222)
TAB - List of Effective Pages Pages 1 through 3, (Amendment 221)
Pages 1 through 3, (Amendment 222)
TAB - List of Amendments Page 13 Page 13 TAB 3.5 - ECCS Page 3.5.1-1 (Amendment 205)
Page 3.5. 1 -1 (Amendment 222)
02-SEP-04 Page:
79 DISTRIBUTION CONTROL LIST DPument 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 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 (9 COPIES) 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 EP'S) 495 JOINT NEWS CENTER 496 L.GRANT(LRQ-OPS/TRAIN) 497 L.GRANT(LRQ-OPS/TRAIN) 500 L.GRANT (LRQ-OPS TRAIN) 501 L.GRANT (LRQ-OPS TRAIN) 512 L.GRANT (LRQ-OPS TRAIN) 513 L.GRANT (LRQ-OPS TRAIN) f518DOCUMENT ~CONTROLTDESK/'r 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-D001-D006 ONLY)
PROCUREMENT ENG.
NUCLEAR LICENSING LRQ (UNIT 3/IPEC ONLY)
LRQ (UNIT 3/IPEC ONLY)
TRAINING -
ILO CLASSES (UNIT 3/IPEC ONLY)
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)
EMER PLN (ALL EP'S)
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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
- 48
- 48
- 48 OFFSITE OFFSITE 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 40A1 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 3067.4 megawatts thermal (100% of rated power)
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 222 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 50.64(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. 222
INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 1 of 3 Page Amend 2
213 1
205 Table of Contents Section 3.0 2
205 i
205 1
205 3
205 ii 205 2
205 Section 3.2.3 iii 207 3
205 1
205 iv 210 4
212 2
205 v
207 5
205 3
205 Section 1.1 Section 3.1.1 4
205 1
205 1
[ 205 Section 3.2.4 2
205 Section 3.1.2 1
205 3
205 1
J 205 2
205 4
205 2
J 205 3
205 5
213 Section 3.1.3 4
205 6
205 1
205 Section 3.3.1 7
205 2
205 1
205 8
205 Section 3.1.4 2
205 Section 1.2 1
205 3
205 1
205 2
205 4
205 2
205 3
205 5
205 3
205 4
205 6
205 Section 1.3 5
205 7
205 1
205 Section 3.1.5 8
205 2
205 1
205 9
205 3
205 2
205 10 205 4
205 Section 3.1.6 11 205 5
205 1
205 12 205 6
205 2
205 13 205 7
205 3
205 14 205 8
205 Section 3.1.7 15 205 9
205 1
205 16 205 10 205 2
205 17 205 11 205 3
205 18 205 12 205 4
205 19 205 13 205 Section 3.1.8 20 205 Section 1.4 1
205 Section 3.3.2 1
205 2
205 1
205 2
205 Section 3.2.1 2
205 3
205 1
205 3
205 4
205 2
205 4
205 Section 2.0 3
205 5
205 1
205 Section 3.2.2 6
205 The latest amendment reflected in this list is: Amendment 222
INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 2 of 3 12 220 3
205 Section 3.4.13 4
205 1
1 205 5
205 2
205 Section 3.6.3 Section 3.4.14 1
205 1
205 2
205 2
205 3
205 3
205 4
205 4
205 5
205 5
205 6
205 Section 3.4.15 Section 3.6.4 1
205 1
l 205 2
205 Section 3.6.5 3
205 1
205 4
205 Section 3.6.6 Section 3.4.16 1
205 1
205 2
205 2
205 3
205 3
205 4
205 4
205 Section 3.6.7 Section 3.5.1 1
205 1
l 222 2
205 t
I o n
C a I
The latest amendment reflected in this list is: Amendment 222
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 The latest amendment reflected in this list is: Amendment 222
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 08/18/2004 220 Extension of the RCS pressure/temperature limits and corresponding OPS limits from 16.17 to 20 EFPY.
221 222 Extension of RCP flywheel inspection interval (from 10 years to 20 years) per TSTF 421.
Inoperable accumulator time extended from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per TSFT-370.
Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators LCO 3.5.1 APPLICABILITY:
Four ECCS accumulators shall be OPERABLE.
MODES 1 and 2.
MODE 3 with reactor coolant system pressure > 1000 psig.
- -- ----NOTES---. --..........................
- 1. In MODE 3, all accumulator discharge isolation valves may be closed and energized for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during the performance of reactor coolant system hydrostatic testing.
- 2. In MODE 3, one accumulator discharge isolation valve may be closed and energized for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for accumulator check valve leakage testing.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One accumulator A.1 Restore boron 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable due to concentration to boron concentration within limits of not within limits of SR 3.5.1.4.
B. One accumulator B.1 Restore accumulator to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable for OPERABLE status.
reasons other than Condition A.
(continued)
INDIAN POINT 3 3.5.1-1 Amendment 222