ML050750042

From kanterella
Jump to navigation Jump to search
Technical Specification Bases
ML050750042
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 02/03/2005
From:
Entergy Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
IP-SMM-AD-103, Rev 0
Download: ML050750042 (10)
v • d • e


Text

3-FEB-05 Page: 90 DISTRIBUTION CONTROL LIST bocument Name: ITS/BASES/TRM CC NAME 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) 11 RES DEPARTMENT MANAGER RES (UNIT 3/IPEC ONLY) 45-4-A 16 SICARD MIKE 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 55 GSB TECHNICAL LIBRARY A MCCALLION/IPECIP2/IP3 GSB-3B 61 SIMULATOR TRAIN(UNIT 3/IPEC ONLY) 48-2-A LICENSING/ROOM 205 GSB-2D b 69 CONROY PAT 99 BARANSKI J (ALL) 102 BILYOU CHRISTINE I&C ONLY ST. EMERG. MGMT. OFFICE I&C SUPPORT OFFSITE 45-2-D 106 SIMULATOR INSTRUCT AREA TRG/3PT-DO01-D006 ONLY) #48 164 CONTROL ROOM & MASTER OPS(3PT-D001/6(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 GRANT LEAR (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 2 489 CLOUGHNESSY PAT PLANT SUPPORT TEAM GSB-3B 491 ORLANDO TOM (MANAGER) PROGRAMS/COMPONENTS ENG 45-3-G 492 FSS UNIT 3 OPERATIONS K-IP-I210 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 (518 DOCUMENT CONTROL DESK NRC (ALL EP'S) OFFSITE 527 MILIANO PATRICK NRC/SR. PROJECT MANAGER OFFSITE 529 FIELDS DEBBIE OUTAGE PLANNING IP3/OSB

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

- Enfergy 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 1 EEntergy CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES TO: DISTRIBUTION DATE: 0310712005 TRANSMITTAL NO:

(Cirde one)

FROM: IPEC DOCUMENT CONTROL: EEC or 1P2 53'EL PHONE NUMBER: 271-7440 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 TECH SPEC BASES DOC # REV# TITLE INSTRUCTIONS INDEX - REMOVE YOUR CURRENT COPY AND REPLACE WITH ATTACHED UPDATED INDEX THE FOLLOWING PROCEDURE HAS BEEN REVISED, PLEASE REMOVE YOUR CURRENT C,-OPY AND REPLACE WITH ATTACHED UPDATED REVISION:

SECTION 3.9.6 REV 1 - EFFECTIVE IMMEDIATELY

                      • 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).

SIGNATURE SIGNATURE DATE DATE CC#

NAME (PRINT)

NAME (PRINT)

INDIAN POINT 3 TECHNICAL SPECIFICATION BASES INSTRUCTIONS FOR UPDATE: 14-03107105 REMOVE INSERT a) List of Effective Sections; a) List of Effective Sections; 4 pages (Rev. 13) 4 pages (Rev. 14) b) Section 3.9.6; Rev. 0 b) Section 3.9.6; Rev. 1 4 pages 3 pages

TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE SECTIONS BASES NUMBER EFFECTIVE BASES NUMBER I EFFECTIVE SECTION REV OF PAGES DATE SECTION REV OF PAGES DATE Tbl of Cnt 1 1 _ 4 105118/2001 -_ ;-> -- B;:3.6 CONTAINMENT_________

- B 2.0 SAFETY LIMITiS t

  • B 3.6.1 0 5 03/19/2001 B2.1.1 I 01 5 03/1912001 B 3.6.2 0 9 03/19/2001 B 2.1.2 °0 4 103/19/2001 B 3.6.3 0 17 03/19/2001 B 3.0 LCO AND SR APPLICABILITY; +;Z- B 3.6.4 0 3 03/19/2001 B3.0 1 1 1 15 l 09/30/2002 B 3.6.5 1 5 06/20/2003 B 3.1 REACTIVITYCONTROL? B 3.6.6 1 13 12/04/2002 B 3.1.1 0 6 03119/2001 B 3.6.7 0 6 03/19/2001 B 3.1.2 0 7 03/19/2001 B 3.6.8 0 6 03/19/2001 B 3.1.3 1 7 10/27/2004 B 3.6.9 0 8 03/19/2001 8 3.1.4 0 13 03/19/2001 B 3.6.10 0 12 03/19/2001 B 3.1.5 0 5 03/19/2001 B 3.7 PLANT SYSTEMS B 3.1.6 0 6 03/19/2001 B 3.7.1 1 6 12/04/2002 B 3.1.7 0 8 03/19/2001 B 3.7.2 0 10 03/19/2001 B 3.1.8 0 7 03/19/2001 B 3.7.3 1 7 05/18/2001 B 3.2 POWER DISTRIBUTION LIMITS;--- B 3.7.4 0 5 03/19/2001 B3.2.1 0 7 03/19/2001 B 3.7.5 1 9 02/25/2005 B 3.2.2 0 7 03/1912001 B 3.7.6 1 4 12/04/2002 B 3.2.3 0 9 03119/2001 B 3.7.7 1 4 12/17/2004 B 3.2.4 0 7 03/1912001 B 3.7.8 0 7 03/19/2001 B 3.3 1NSTRUMENTATION - B 3.7.9 1 9 09/30/2002 B 3.3.1 1 59 09/30/2002 B 3.7.10 0 3 03/19/2001 B 3.3.2 3 45 12104/2002 B 3.7.11 3 9 01/24/2005 B 3.3.3 2 19 09/30/2002 B 3.7.12 0 4 03/19/2001 B 3.3.4 0 7 03/19/2001 B 3.7.13 2 7 06/20/2003 B 3.3.5 1 6 10/27/2004 B 3.7.14 0 3 03/19/2001 B 3.3.6 0 10 03/19/2001 B 3.7.15 0 5 03/19/2001 B 3.3.7 0 6 03/19/2001 B 3.7.16 0 6 03/1912001 B 3.3.8 1 4 03/17/2003 B 3.7.17 0 4 03/19/2001 B 3.4 REACTOR COOLANT SYSTEMIA:'-..- _ --

_ B 3.8 ELECTRICAL POWER; '

B 3.4.1 0 6 03/19/2001 B 3.8.1 1 32 01/22/2002 B 3.4.2 0 3 03/19/2001 B 3.8.2 0 7 03/19/2001 B 3.4.3 1 9 10/27/2004 B 3.8.3 0 13 03/19/2001 B 3.4.4 0 4 03/1912001 B 3.8.4 1 11 01/22/2002 B 3.4.5 0 6 03/19/2001 B 3.8.5 0 4 03/19/2001 B 3.4.6 0 6 03/19/2001 B 3.8.6 0 8 03/19/2001 B 3.4.7 0 7 03/19/2001 B 3.8.7 1 8 06/20)2003 B 3.4.8 0 4 03/19/2001 B 3.8.8 1 4 06/20/2003 B 3.4.9 2 5 06/20/2003 B 3.8.9 l 2 14 06/20/2003 B 3.4.10 0 5 03/19/2001 B 3.8.10 0 4 03/19/2001 B 3.4.11 0 8 03/19/2001 B 3.9 REFUELING OPERATIONS-. z-B 3.4.12 1 20 10/27/2004 B 3.9.1 0 4 03/19/2001 B 3.4.13 2 6 11119/2001 B 3.9.2 0 4 03/19/2001 B 3.4.14 0 10 03/19/2001 B 3.9.3 1 8 03/17/2003 B 3.4.15 2 7 11/19/2001 B 3.9.4 0 4 03119/2001 B 3.4.16 0 7 03/1912001 B 3.9.5 0 4 03/19/2001

_____:_-  !; B 3.5 ECCS ; ______* B 3.9.6 1 3 0310712005 B 3.5.1 1 10 10/27/2004 I B 3.5.2 0 13 03119/2001 B 3.5.3 0 4 03/19/2001 B 3.5.4 0 9 _ 03/19/2001 INDIAN POINT 3 Page I of 4 Revision 14

TECHNICAL SPECIFICATION BASES TECHNICAL REVISION HISTORY REVISION HISTORY FOR BASES AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION Initial issue of Bases derived from NUREG-1431, in ALL 0 03/19/01 conjunction with Technical Specification Amendment 205 for conversion of 'Current Technical Specifications' to

'Improved Technical Specifications'.

_ ^ BASES UPDATE PACKAGE 01-031901.

Changes regarding containment sump flow monitor per B 3.4.13 1 03/19/01 NSE 01-3-018 LWD Rev 0.

B 3.4.15 Change issued concurrent with Rev 0.

. _ BASES PDATEPACKAGE2051801' Table of Contents 1 05/18/01 Title of Section B 3.7.3 revised per Tech Spec Amend 207 B 3.7.3 1 05/18101 Implementation of Tech Spec Amend 207

_______ ____ .BASESUPDATE PACKAGE 03-111901. 0ffij:

Correction to statement regarding applicability of Function B 3.3.2 1 11/19/01 5, to be consistent with the Technical Specification.

Changes to reflect reclassification of certain SG narrow B 3.3.3 1 11/19/01 range level instruments as QA Category M per NSE 97 439, Rev 1.

Changes to reflect installation of a new control room alarm B 3.4.13 2 11/19/01 for VC Sump Pump Running'. Changes per NSE 01 B 3.4.15 018, Rev 1 and DCP 01-3-023 LWD.

Clarification of allowable flowrate for CRVS in 'incident B 3.7.11 1 11/19/01 mode with outside air makeup.'

- BASES UPDATE PACKAGE -01220 -<

B 3.3.2 2 01/22/02 Clarify starting logic of 32 ABFP per EVL-01-3-078 MULTI, Rev 0.

B 3.8.1 1 01/22102 Provide additional guidance for SR 3.8.1.1 and Condition

_Statements A.1 and B.1 per EVL-01-3-078 MULTI, Rev 0.

B 3.8.4 1 01/22/02 Revision of battery design description per plant modification and to reflect Tech Spec Amendment 209.

B 3.8.9 1 01/22/02 Provide additional information regarding MCC in Table B 3.8.9-1 per EVL-01-3-078 MULTI, Rev 0.

>z- BASES UPDATE PACKAGE 05093002 m- W.$'7, B 3.0 1 09/30/02 Changes to reflect Tech Spec Amendment 212 regarding delay period for a missed surveillance. Changes adopt TSTF 358, Rev 6.

B 3.3.1 1 09/30/02 Changes regarding description of turbine runback feature

__ per EVAL-99-3-063 NIS.

B 3.3.3 2 09/30/02 Changes to reflect Tech Spec Amendment 211 regarding CETs and other PAM instruments.

B 3.7.9 1 09/30/02 Changes regarding SWN 1 and -2 valves per EVAL-00-3-095 SWS, Rev 0.

INDIAN POINT 3 Page 2 of 4 Revision 14

TECHNICAL SPECIFICATION BASES REVISION HISTORY AFFECTED 1 EFFECTIVE SECTIONS REV DATE DESCRIPTION

,--*,) BASES >--- X-UPDATEPAMCKAGE06-120402 -V}s -- 0 B 3.3.2 .3 12/04/02 Changes to reflect Tech Spec Amendment 213 regarding B 3.6.6 1 1.4% power uprate.

B 3.7.1 1 B3.7.6 1

  • UPDATE -PACKAGE07-0317036  ;. 77 77t7

__ _ 3___-7B ?i B 3.3.8 1 03/17/2003 Changes to reflect Tech Spec Amendment 215 regarding B 3.7.13 1 implementation of Alternate Source Term analysis B 3.9.3 1 methodology to the Fuel Handling Accident.

__________ ___ BA<iSES UPDATE PACKAGE 08-03I;0n-B 3.4.9 1 l 03/28/2003 Changes to reflect Tech Spec Amendment 216 regarding l A relaxation of pressurizer level limits in MODE 3.

_________ ____ _________ UPDATE PACKAGE 0 .62003 - -

B 3.4.9 2 06/20/2003 Changes to reflect commitment for a dedicated operator

. per Tech Spec Amendment 216.

B 3.6.5 1 06/20/2003 Implements Corrective Action 11 from CR-1P3-2002-02095; 4 FCUs should be in operation to assure representative measurement of containment air temperature.

B 3.7.11 2 06/20/2003 Correction to Background description regarding system response to Firestat detector actuation per ACT 02-62887.

B 3.7.13 2 06/20/2003 Revision to Background description of FSB air tempering units to reflect design change per DCP 95-3-142.

B 3.8.7 1 06/20/2003 Changes to reflect replacement of Inverter 34 per DCP-B 3.8.8 1 06/20/2003 01-022.

B 3.8.9 2 06/20/2003

________ ,__4 jQ, BASES UPDATE PACKAGE 10-10270 -. '

B 3.1.3 1 10/27/2004 Clarification of the surveillance requirements for TS 3.1.3 per 50.59 screen.

B 3.3.5 1 10/27/2004 Clarify the requirements for performing a Trip Actuating Device Operational Test (TADOT) on the 480V degraded grid and undervoltage relays per 50.59 screen.

B 3.4.3 1 10/27/2004 Extension of the RCS pressure/temperature limits and corresponding OPS limits from 16.17 to 20 EFPY (TS B 3.4.12 1 Amendment 220).

B 3.5.1 1 10/27/2004 Changes to reflect Tech Spec Amendment 222 regarding extension of completion time for Accumulators.

f- BASES UPDATE PACKAGE 11-1-2100-- - - -

B 3.7.7 1 12/17/2004 Addition of valves CT-1300 and CT-1302 to Surveillance SR 3.7.7.2 to verify that all city water header supply isolation valves are open. Reflects Tech Spec Amendment 218.

_________ if- -  ?< ~ -BASES UPDATE PACKAGE 12-01 2405 w. - -

B 3.7.11 3 01/2412005 Temporary allowance for use of Kl/SCBA for unfiltered inleakage above limit.

INDIAN POINT 3 Page 3 of 4 Revision 14

TECHNICAL SPECIFICATION BASES REVISION HISTORY AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION

'___.______ BASES UPDATE PACKAGE 13-022505 -

B 3.7.5 1 02/25/2005 Clarification on Surveillance Requirement 3.7.5.3 as it relates to plant condition/frequency of performance of Auxiliary Feedwater Pump full flow testing.

__-______BASESE PDATE PACKAGE 14-030705: jE B 3.9.6 1 03/0712005 Changes to reflect that the decay time prior to fuel movement is a minimum of 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> per Tech Spec Amendment 215.

I INDIAN POINT 3 Page 4 of 4 Revision 14

Refueling Cavity Water Level B 3.9.6 B 3.9 REFUELING OPERATIONS B 3.9.6 Refueling Cavity Water Level BASES BACKGROUND The movement of irradiated fuel assemblies or performance of CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts, within containment requires a minimum water level of 23 ft above the top of the reactor vessel flange. During refueling, this maintains sufficient water level in the containment, refueling canal.

fuel transfer canal, refueling cavity, and spent fuel pit. Sufficient water is necessary to retain iodine fission product activity In the water in the event of a fuel handling accident (Refs. 1 and 2).

Sufficient iodine activity would be retained to limit offsite doses from the accident to within RG 1.183 limits (Ref. 4). I APPLICABLE SAFETY ANALYSES During CORE ALTERATIONS and movement of Irradiated fuel assemblies, the water level in the refueling canal and the refueling cavity is an initial condition design parameter in the analysis of a fuel handling accident in containment, as postulated by Regulatory Guide 1.25 (Ref. 1). In the Fuel Handling Accident (FHA) analysis (Ref. 5). a fuel assembly is assumed to be dropped and damaged during refueling. It is assumed that all of the fuel rods in one assembly are damaged to the extent that all of the gap activity is released. The fuel handling accident is described in Reference 2.

Doses from the FHA are calculated in accordance with the Alternate Source Term methodology of Regulatory Guide 1.183 (Ref. 4). For water level of 23 ft or greater above the fuel, RG 1.183 specifies an overall decontamination factor of 200. There is no retention of noble gases in the water. The decay time prior to fuel movement is a minimum of 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />. Credit is not taken for removal of iodine by filters, nor is credit taken for isolation of release paths.

Using RG 1.183 methodology, all calculated offsite and control room doses are determined to be within the RG 1.183 specified fractions of the 10CFR5O.67 limits for decay periods of > 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />.

(continued)

INDIAN POINT 3 B 3.9.6-1 Revision 1

Refueling Cavity Water Level B 3.9.6 BASES APPLICABLE SAFETY ANALYSES (continued)

Further reductions in the amount of radioactivity potentially released following a fuel handling accident inside containment are expected because the containment will be isolated either automatically or through operator action following a fuel handling accident.

Specifically. LCO 3.3.6, Containment Purge System and Pressure Relief Line Isolation Instrumentation. requires the Operability of radiogas monitors R-11 and R-12, either of which could generate an automatic isolation signal, during the movement of Irradiated fuel.

Refueling cavity water level satisfies Criterion 2 of 10 CFR 50.36.

ICO A minimum refueling cavity water level of 23 ft above the reactor vessel flange Is required to ensure that the radiological consequences of a postulated fuel handling accident Inside containment are within acceptable limits, as per Reference 6.

APPLICABILITY LCO 3.9.6 is applicable during CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts, and when moving irradiated fuel assemblies within containment. The LCO minimizes the possibility of a fuel handling accident in containment that is beyond the assumptions of the safety analysis. If irradiated fuel assemblies are not present in containment, there can be no significant radioactivity release as a result of a postulated fuel handling accident. Requirements for fuel handling accidents in the spent fuel pool are covered by LCO 3.7.14, 'Spent Fuel Pit Water Level."

ACTIONS A.1 and A.2 With a water level of < 23 ft above the top of the reactor vessel flange, all operations involving CORE ALTERATIONS or movement of irradiated fuel assemblies within the containment shall be suspended immediately to ensure that a fuel handling accident cannot occur.

The suspension of CORE ALTERATIONS and fuel movement shall not preclude completion of movement of a component to a safe position.

(continued)

INDIAN POINT 3 B 3.9.6- 2 Revision 1

Refueling Cavity Water Level B 3.9.6 BASES SURVEILLANCE REQUIREMENTS SR 3.9.6.1 Verification of a minimum water level of 23 ft above the top of the reactor vessel flange ensures that the design basis for the analysis of the postulated fuel handling accident during refueling operations is met. Water at the required level above the top of the reactor vessel flange limits the consequences of damaged fuel rods that are postulated to result from a fuel handling accident inside containment (Ref. 2).

The Frequency of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is based on engineering judgment and is considered adequate in view of the large volume of water and the normal procedural controls of valve positions, which make significant unplanned level changes unlikely.

REFERENCES 1. Regulatory Guide 1.25, March 23. 1972.

2. FSAR, Section 14.2.
3. NUREG-0800, Section 15.7.4.
4. Regulatory Guide 1.183. July 2002.
5. Letter INT 02-29 Westinghouse Electric Co., Radiological Consequences of a Fuel Handling Accident. May 2002.
6. Safety Evaluation Report for Amendment No. 215 to Facility Operating License No. DPR-64. March 17. 2003.

INDIAN POINT 3 B 3.9.6 -3 Revision 1

Retrieved from "https://kanterella.com/w/index.php?title=ML050750042&oldid=2595103"