ML031490020
| ML031490020 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/09/2003 |
| From: | Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 28182 IP-SMM-AD-103, Rev 0 | |
| Download: ML031490020 (9) | |
Text
05-MAY-03 Page:
DISTRIBUTION CONTROL LIST
! cument Name: ITS/BASES/TRM CC_NAME NAME DEPT LOCATION LR___(UNIT_3/___EC_ONLY) __________
497 L.GRANT(LRQ-OPS/TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 .
500 C.STELLATO(NRQ-OPS TRN) NRQ (UNIT 3/IPEC ONLY) #48 501 C.STELLATO(NRQ-OPS TRN) NRQ (UNIT 3/IPEC ONLY) #48 512 C.STELLATO(NRQ-OPS TRN) NRQ (UNIT 3/IPEC ONLY) #48 513 C.STELLATO(NRQ-OPS TRN) NRQ (UNIT 3/IPEC ONLY) #48 518 DOCUMENT CONTROL DESK NRC (ALL EP'S) OFFSITE 527 MILIANO PATRICK NRC/SR. PROJECT MANAGER OFFSITE 528 PETACHI CHRISTA WC/ONE STOP SHOP IP2 529 DECLEMENTE VINNIE OPS/(TYPE A DWG LG/ONLY) IP3/2ND FL KO\
A# IPEC SITE QUALITY RELATED IP-SMM-AD-103 Revision 0 15'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
~~Entergy CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES TO: DISTRIBUTION DATE: 5120103 TRANSMITTAL NO: 28182 (Circle one)
FROM: IPEC DOCUMENT CONTROL: EEC or IP2 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please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s).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: ITSIBASESITRM - TECH SPEC AMENDMENT 217 DOC # I REV # I TITLE I 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 I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH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 v5 O CC#
Distribution of IP3 Technical Specification Anndment 217 (Approved by NRC May 6, 2003)
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 216) Page 3, (Amendment 217)
TAB - List of Effective Pages Pages I through 3, Pages I through 3, (Amendment 216) (Amendment 217)
TAB - List of Amendments No pages removed Page 13 TAB 5.0 - Administrative Controls Page 5.0 - 35 (Amendment 205) Page 5.0 - 35 (Amendment 217)
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 : 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. 215 facility at steady state reactor core Power 3-17-2003 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. 217 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. 217
INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 1 of 3 Page Amend 2 213 205 7 205 Table of Contents Section 3.0 2 205 8 213 i 205 1 205 205 9 213 ii 205 2 205 Section 3.2.3 10 205 iii 207 3 205 1 205 11 213 iv 210 4 212 2 205 12 205 v 207 5 205 3 - 205 13 205 Section 1.1 Section 3.1.1 4 205 Section 3.3.3 1 205 1 L 205 Section 3.2.4 1 211 2 205 Section 3.1.2 1 205 2 211 3 205 1 J 205 2 205 3 205 4 205 2 205 3 205 4 211 5 213 Section 3.1.3 4 205 5 211 6 205 1 205 Section 3.3.1 Section 3.3.4 7 205 2 205 1 205 1 205 8 205 Section 3.1.4 2 205 2 1 205 Section 1.2 1 205 3 205 Section 3.3.5 1 205 2 205 4 205 1 205 2 205 3 205 5 205 2 j 205 3 205 4 205 6 205 Section 3.3.6 Section 1.3 5 205 7 205 1 205 1 205 Section 3.1.5 8 205 2 205 2 205 1 [ 205 9 205 3 205 3 205 2 205 10 205 4 205 4 205 Section 3.1.6 11 205 5 1 205 5 205 1 205 12 205 Section 3.3.7 6 205 2 205 13 205 1 205 7 205 3 205 14 205 2 205 8 205 Section 3.1.7 15 205 3 205 9 205 1 205 16 205 Section 3.3.8 10 205 2 205 17 205 1 215 11 205 3 205 18 205 2 205 12 205 4 205 19 205 Section 3.4.1 13 205 Section 3.1.8 20 205 1 f 205 Section 1.4 1 205 Section 3.3.2 2 j 205 1 205 2 205 1 205 Section 3.4.2 2 205 Section 3.2.1 2 205 1 l 205 3 205 1 205 3 205 Section 3.4.3 4 205 2 205 4 205 1 205 Section 2.0 3 205 5 205 2 205 1 l 205 Section 3.2.2 6 205 3 213 The latest amendment reflected in this list is: Amendment 217
INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 2 of 3 4 c 213 12 l 213 3 205 13 1 205 5 ~213 Section 3.4.13 4 205 Section 3.7.3 Section 3.4.4 1 205 5 205 1 207 1 1 205 2 205 Section 3.6.3 2 207 Section 3.4.5 Section 3.4.14 1 205 3 207 1 205 1 205 2 205 Section 3.7.4 2 205 2 205 3 205 1 205 3 205 3 205 4 205 2 205 Section 3.4.6 4 205 5 205 Section 3.7.5 1 205 5 205 6 205 1 205 2 205 Section 3.4.15 Section 3.6.4 2 205 3 205 1 205 1 l 205 3 205 Section 3.4.7 2 205 Section 3.6.5 4 205 1 205 3 205 1 l 205 Section 3.7.6 l
4 2 205 205 Section 3.6.6 205 1
_ I _
3 205 Section 3.4.16 1 l 205 205 Section 3.4.8 1 1 205 2 205 Section 3.7.7 1 205 2 1 205 3 205 1 205 2 205 3 1 205 4 205 2 205 Section 3.4.9 4 1 205 Section 3.6.7 Section 3.7.8 1 1 216 Section 3.5.1 1 205 1 205 2 l216 1 205 205 2 205 Section 3.4.10 2 205 Section 3.6.8 Section 3.7.9 1 205 3 j 205 ________J 205 1 205 2 j 205 Section 3.5.2 2 205 2 205 Section 3.4.11 1 205 Section 3.6.9 3 205 1 205 2 205 1 l 205 Section 3.7.10 2 205 3 j 205 2 1 205 1 l 205 3 205 4 j 205 Section 3.6.10 Section 3.7.11 Section 3.4.12 Section 3.5.3 1 205 1 l205 1 205 1 205 2 205 2 IZ~ 205 2 205 2 205 205 Section 3.7.12 3 205 Section 3.5.4 4 205 1 1 205 4 205 1 T 205 Section 3.7.1 Section 3.7.13 5 205 2 205 1 205 1 215 6 205 Section 3.6.1 2 205 2 I 205 7 205 1 205 3 213 Section 3.7.14 8 205 2 205 4 205 I l 205 9 213 Section 3.6.2 Section 3.7.2 Section 3.7.15 10 213 1 l 205 1 205 1 205 11 213 2 205 2 205 2 205 The latest amendment reflected in this list is: Amendment 217
.> e !
INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 3 of 3 Section 3.7.16 1 205 8 205 1 205 2 205 9 210 2 205 3 205 10 205 3 205 Section 3.8.8 11 205 Section 3.7.17 1 l_205 12 205 1 [ 205 2 205 13 205 Section 3.8.1 Section 3.8.9 14 205 1 205 1 205 15 205 2 205 2 205 16 205 3 205 Section 3.8.10 17 205 4 205 1 T 205 18 205 5 205 2 205 19 205 6 205 Section 3.9.1 20 205 7 205 1 205 21 205 8 205 Section 3.9.2 22 205 9 205 1 205 23 205 10 205 2 205 24 205 Section 3.8.2 Section 3.9.3 25 205 1 205 1 215 26 205 2 205 2 215 27 205 3 205 3 215 28 205 4 205 Section 3.9.4 29 205 Section 3.8.3 1 J 205 30 206
_1 205 2 205 31 206 205 Section 3.9.5 32 205 3 205 1 205 33 205 4 205 2 205 34 205 205 Section 3.9.6 35 217 Section 3.8.4 1 205 36 205 I
1 216 Section 4.0 37 205 2 216 1 205 38 205 3 216 2 205 Section 3.8.5 3 205 1 205 Section 5.0 2 205 1 205 Section 3.8.6 2 205 1 205 3 205 2 205 4 205 3 205 5 205 4 205 6 205 Section 3.8.7 7 205 The latest amendment reflected in this list is: Amendment 217
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)
Reporting Requi rements Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981. (Specification 3.2.3, Axial Flux Difference (AFD) (Constant Axial Offset Control));
3a. WCAP-12945-P-A, Volume I (Revision 2) and Volumes 2 through 5 (Revision 1), "Code Qualification Document for Best-Estimate Loss-of-Coolant-Accident Analysis," March 1998 (Westinghouse Proprietary);
3b. NOT USED 3c. NOT USED 3d. WCAP-10054-P-A, "SMALL BREAK ECCS EVALUATION MODEL USING NOTRUMP CODE," (W Proprietary). (Specification 3.2.1, Heat Flux Hot Channel Factor (FQ(Z));
3e. WCAP-10079-P-A, "NOTRUMP NODAL TRANSIENT SMALL BREAK AND GENERAL NETWORK CODE," (W Proprietary). (Specification 3.2.1, Heat Flux Hot Channel Factor (FQ(Z))); and 3f. WCAP-12610, "VANTAGE+ Fuel Assembly Report," (W Proprietary).
(Specification 3.2.1, Heat Flux Hot Channel Factor).
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any midcycle revisions or supplements, shall be provided for each reload cycle to the NRC.
5.6.6 NOT USED INDIAN POINT 3 5.0 - 35 Amendment 217