ML042660161

From kanterella
Jump to navigation Jump to search
IPEC Site Management Manual, Revision 0 to IP-SMM-AD-103
ML042660161
Person / Time
Site: Indian Point Entergy icon.png
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)
v • d • e


Text

A IPEC SITE QUALITY RELATED IP-SMM-AD-103 Revision 0

- Entergy MANAGEMENT ADMINISTRATIVE PROCEDURE MANUAL

  1. 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:

(Circleone)

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please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s).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 I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH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).

NAME (PRINT) SIGNATURE DATE DATE CC#

CC#

.,..Ylr NAME (PRINT) SIGNATURE A00 (

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, Pages 1 through 3, (Amendment 221) (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 DEPT LOCATION 1 OPS PROCEDURE GROUP SUPV. OPS PROCEDURE GROUP IP2 3 PLANT MANAGER'S OFFICE UNIT 3(UNIT 3/IPEC ONLY) IP2 5 CONTROL ROOM & MASTER OPS (3PT-D001/6 (U3/IPEC) IP3(ONLY) 6 OPERATIONS MANAGER OPS/FRED SMUTNY 45-3-D 9 MYERS VALERIE SYSTEM ENG. 72'ELEVATION IP2 4329 11 RES DEPARTMENT MANAGER RES (UNIT 3/IPEC ONLY) 45-4-A 16 BOCCIO JOHN I&C OFFICE (SUPERVISOR) 45-2-A 19 STEWART ANN LICENSING GSB-2D 20 CHEMISTRY SUPERVISOR CHEMISTRY DEPARTMENT 45-4-A 21 TSC(IP3) EEC BUILDING IP2 22 SHIFT MGR.(LUB-001-GEN) OPS (UNIT 3/IPEC ONLY) IP3 23 LIS LICENSING & INFO SERV OFFSITE 25 SIMULATOR TRAIN(UNIT 3/IPEC ONLY) 48-2-A 28 RESIDENT INSPECTOR US NRC 88' ELEVATION IP2 32 EOF E-PLAN (ALL EP'S) EOF 47 CHAPMAN N BECHTEL OFFSITE 50 TADEMY L. SHARON WESTINGHOUSE ELECTRIC OFFSITE

. 54 NUC ENGINEERING LIBRARY 55 REFERENCE LIBRARY 61 SIMULATOR DOC (UNIT 3/IPEC ONLY)

REC/TRN(UNT 3/IPEC ONLY)

TRAIN(UNIT 3/IPEC ONLY)

WPO/7A BLDG/17 48-2-A 69 CONROY PAT LICENSING/ROOM 205 GSB-2D 99 BARANSKI J (ALL) ST. EMERG. MGMT. OFFICE OFFSITE 102 BILYOU CHRISTINE I&C ONLY I&C SUPPORT 45-2-D 106 SIMULATOR INSTRUCT AREA TRG/3PT-D001-D006 ONLY) #48 164 CONTROL ROOM & MASTER OPS(3PT-DO01/6(U3/IPEC) IP3(ONLY) 207 TROY M PROCUREMENT ENG. 1A 273 FAISON CHARLENE NUCLEAR LICENSING WPO-12 319 L.GRANT (LRQ-OPS TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 354 L.GRANT(LRQ-OPS/TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 357 L.GRANT(ITS/INFO ONLY) TRAINING - ILO CLASSES 48-2-A 424 HULBERT TRACY (9 COPIES) (UNIT 3/IPEC ONLY) #48 474 OUELLETTE P ENG., PLAN & MGMT INC OFFSITE 483 SCHMITT RICHIE MAINTENANCE ENG/SUPV 45-1-A 484 HANSLER ROBERT REACTOR ENGINEERING 72'UNIT 2 485 DRAKE RICH DESIGN ENG/GSB/3RD FLOOR GSB-3B 489 CLOUGHNESSY PAT PLANT SUPPORT TEAM GSB-3B 491 ORLANDO TOM (MANAGER) PROGRAMS/COMPONENTS ENG 45-3-G 492 PETACHI CHRISTA WC/ONE STOP SHOP IP-K-4321 493 OPERATIONS FIN TEAM 33 TURBIN DECK 45-1-A 494 AEOF/A.GROSJEAN(ALL EP'S) E-PLAN (EOP'S ONLY) WPO-12D 495 JOINT NEWS CENTER EMER PLN (ALL EP'S) EOF 496 L.GRANT(LRQ-OPS/TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 497 L.GRANT(LRQ-OPS/TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 500 L.GRANT (LRQ-OPS TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 501 L.GRANT (LRQ-OPS TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 512 L.GRANT (LRQ-OPS TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 513 L.GRANT (LRQ-OPS TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 f518DOCUMENT ~CONTROLTDESK/'r NRC (ALL EP'S) OFFSITE 527 MILIANO PATRICK NRC/SR. PROJECT MANAGER 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 Ca 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 8 205 9 210 10 205 11 221 12 205 13 205 14 205 15 205 16 205 17 205 18 205 19 205 20 205 21 205 22 205 23 205 24 219 25 205 26 205 27 205 28 205 29 205 30 206 31 206 32 205 33 205 34 205 35 217 36 205 37 205 38 205 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 Use of Best-Estimate Large-Break Loss of 05/06/2003 Coolant Accident analysis methodology (WCAP 12945) 218 Revise City Water surveillance to reflect 08/04/2003 addition of (backflow preventer) valves 219 Revise Ventilation Filter Testing Program 10/30/2003 to adopt ASTM D3803 charcoal filter testing requirements per GL 99-02.

220 Extension of the RCS pressure/temperature 12/03/2003 limits and corresponding OPS limits from 16.17 to 20 EFPY.

221 Extension of RCP flywheel inspection interval 07/02/2004 (from 10 years to 20 years) per TSTF 421.

222 Inoperable accumulator time extended from 08/18/2004 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 Four ECCS accumulators shall be OPERABLE.

APPLICABILITY: 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.

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

Retrieved from "https://kanterella.com/w/index.php?title=ML042660161&oldid=2609937"