ML050670522

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Technical Specification Bases
ML050670522
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 02/03/2005
From:
Entergy Nuclear
To:
Office of Nuclear Reactor Regulation
References
Download: ML050670522 (15)
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Text

03- FEB-05 Page: 90 DISTRIBUTION CONTROL LIST Document 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-DO01/6(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/IPEC,IP2/IP3 GSB-3B L 61 SIMULATOR 69 CONROY PAT 99 BARANSKI J (ALL)-

, TRAIN(UNIT 3/IPEC ONLY).

LICENSING/ROOM 205 48-2-A GSB-2D ST. EMERG. MGMT. OFFICE ..OFFSITE 102 BILYOU CHRISTINE I&C ONLY I&C SUPPORT 45-2-D 106 SIMULATOR INSTRUCT AREA TRG/3PT-DOO1-D006 ONLY) #48

  • 164 CONTROL ROOM & MASTER OPS(3PT-D00i/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 LEAH (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 t &518:.DOCUMENT CONTROL-DESK NRC (ALL EP'S) OFFSITE

^-' 527 MILIANO PATRICK . NRC/SR. PROJECT MANAGER .OFFSITE 529 FIELDS DEBBIE OUTAGE PLANNING IP3/OSB l wo

INDIAN POINT 3 TECHNICAL SPECIFICATION BASES INSTRUCTIONS FOR UPDATE: 13-02/25105 REMOVE INSERT a) List of Effective Sections; a) List of Effective Sections; 3 pages (Rev. 12) 4 pages (Rev. 13) b) Section 3.7.5; Rev. 0 b) Section 3.7.5; Rev. I 11 pages 9 pages

TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE SECTIONS BASES NUMBER EFFECTIVE BASES l NUMBER EFFECTIVE SECTION REV OF PAGES DATE SEC T ION REV OF PAGES DATE TbI of Cnt 1 4 105118/2001 .; WL':2Wt B 3.6 CONTAINMENT, , &' x;

_ _ :B 2.0f SAFETY- LIMITS;'-,-.. B 3.6.1 0 5 03/19/2001 B 2.1.1 l 0 l 5 103/1912001 B 3.6.2 0 9 03/19/2001 B 2.1.2 1 0 1 4 103119/2001 B 3.6.3 0 17 03/19/2001

,>-JB 3.,0 LCO;AND SR APPLICABILITY 4 2..->. B 3.6.4 0 3 03/19/2001 B 3.0 l 1 15 I 09/3012002 B 3.6.5 1 5 06/20t2003 4.h'.:1B 3.1 REACTIVITY CONTROL v&15 B 3.6.6 1 13 12/04/2002 B 3.1.1 0 6 03/1912001 B 3.6.7 0 6 03/19/2001 B 3.1.2 0 7 03/19/2001 B 3.6.8 0 6 03119/2001 B 3.1.3 1 7 10/27/2004 B 3.6.9 0 8 03/19/2001 B 3.1.4 0 13 03/19/2001 B 3.6.10 0 12 103/1912001 B 3.1.5 0 5 03/1912001 ... 9 B.37 PLANT SYSTEMS2.22,Ui -i-*

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 1 10 03/19/2001 B 3.1.8 0 7 03/1912001 B 3.7.3 1 7 05/18/2001

',_ 'B 3.2.POWER DISTRIBUTIONItIMITSMZ-1^i-" B 3.7.4 0 5 03/19/2001 B 3.2.1 0 7 03/19/2001 B 3.7.5 1 9 0212512005 B 3.2.2 B 3.2.3

[ 0 7

9 03/19/2001 03/19/2001 B 3.7.6 B 3.7.7 1

1 4

4 12/04/2002 12/17/2004 I

B 3.2.4 0 7 03/19/2001 B 3.7.8 0 . 7 03/19/2001

'-  :'ŽY'B3.3 INSTRUMENTATION 127PJZ>' 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 03/1912001 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 03/19/2001 B 3.3.8 1 4 03/17/2003 B 3.7.17 0 4 03/19/2001 IJ 2t B 3.4 REACTOR COOLANT SYSTEM5-r:t-Z.- A 2-i',-4,.'.-:.B 3.8 .ELECTRICALPOWEW 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 03119/2001_ 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 03/1912001 B 3.8.8 1 4 06/20/2003 B 3.4.9 2 5 06/20/2003 B 3.8.9 2 14 06/20/2003 B 3.4.10 0 5 03/19/2001 B 3.8.10 0 l 4 03/1912001 B 3.4.11 0 8 03/19/2001 s':Z.i 1B 3.9 REFUELING OPERATIO NSW B 3.4.12 1 20 10/27/2004 B 3.9.1 0 4 03119/2001 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 7 111/19/2001 B 3.9.4 0 4 03/19/2001 B 3.4.16 0 7 03/19/2001 B 3.9.5 0 4 03/19/2001

_________ - f ;B 3.5 ECCS i;.;f2::- 1_-___ -_zl__ B 3.9.6 0° 4 l03/19/2001 B 3.5.1 1 10 10/27/2004 B 3.5.2 0 13 03/19/2001 B 3.5.3 O 4 03/19/2001 B 3.5.4 0 9 03/1912001 INDIAN POINT 3 Page 1 of 4 Revision 13

BASES TECHNICAL SPECIFICATION TECHNICAL SPECIFICATION BASES 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 UPDATEPACKAGE 01-031901i?,f`By... a .>

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.

-, §.T R-.z;-  ;- BASES.UPDATE.PACKAGE 02 -05 180180f C Table of Contents 1 05/18/01 Title of Section B3.7.3 revised per Tech Spec Amend 207 B 3.7.3 1 05/18/01 Implementation of Tech Spec Amend 207

  • t,>iFv^K.s~<,,YBA^<_-~.,8S, B ES:UPDATE PACKAGE 03.191xiA\- ~N^$ tir 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 I. '.. 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.'

____- 'iBASESiUJPDA-TEJ-APCCA Kf0GEi4-02012202_n ja 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 01/22/02 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 0,1/22/02 Provide additional information regarding MCC in I Table B 3.8.9-1 per EVL-01-3-078 MULTI, Rev 0.

e BAS ESLUPDAT DPACKAGE ,5P0.3A0C K AG E a5im9300 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 13

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

__ _ CBASES' UPDATE PACKAGE 06-1 204024%',l!f:z,-,

B 3.3.2 3 12104102 Changes to reflect Tech Spec Amendment 213 regarding B 3.6.6 1 1.4% power uprate.

B3.7.1 1 B 3.7.6 1 l

Wrf;-$ BASESh UPDATE KPACKAGE 07'031 703"W 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.

,'^>,fj.* ' BASESiUPDATE:PACKAGE'08 0328037 B 3.4.9 1 03/28/2003 Changes to reflect Tech Spec Amendment 216 regarding relaxation of pressurizer level limits in MODE 3.

..... BASES DATE PACKAGE 09-062003*1 s 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 06120/2003 Implements Corrective Action 11 from CR-IP3-2002-02095; 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

-, , BAS ES URDATE PACKAGE O1 0-.1 070 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.

B 3.7.7 1 12/17/2004 Addition of valves CT-1 300 and CT-1 302 to Surveillance SR 3.7.7.2 to verify that all city water header supply isolation valves are open. Reflects Tech Spec

.__ .__.__Amendment 218.

,-'tp,5e i ij.'iAWSTBASESI UPDATE .PACKAGE 12-0'12405l.

B 3.7.11 3 01/24/2005 Temporary allowance for use of KI/SCBA for unfiltered inleakage above limit.

INDIAN POINT 3 Page 3of 4 Revision 13

TECHNICAL SPECIFICATION BASES REVISION HISTORY AFFECTED l lEFFECTIVEl SECTIONS REV DATE DESCRIPTION

INDIAN POINT 3 Page 4 of 4 Revision 13

AFW System B 3.7.5 B 3.7 PLANT SYSTEMS B 3.7.5 Auxiliary Feedwater (AFW) System BASES BACKGROUND The AFW System automatically supplies feedwater to the steam generators to remove'decay heat from the'Reactor Coolant System upon the loss of normal feedwater supply. The AFW pumps take suction from the condensate storage tank (CST) (LCO 3.7.6) and pump to the steam generator secondary side via a connection to the main feedwater (MFW) piping at'a point outside containment. The steam generators function as a heat sink for core-decay heat.' The heat'load is dissipated by releasing steam to the atmosphere from the steam generators via the main steam safety valves (MSSVs) (LCO 3.7.1) or atmospheric dump valves (LCO 3.7.4). If the main condenser is available, steam may be released via the steam bypass (High Pressure Steam Dump) valves and recirculated to the CST.

The AFW System consists of two motor driven AFW pumps and one steam turbine driven pump'configured into three trains. FSAR Section 10.2

'(Ref. 1) describes this configuration as two pumping loops using two different types of motive power to the pumps. One auxiliary feedwater K) loop utilizes a steam turbine driven pump and the other utilizes two motor driven pumps. Tecnical specifications describe this configuration as three trains because each motor driven pump provides 100% of AFW flow capacity, and, depending on steam conditions, the turbine driven pump capacity approaches 200% of the required capacity to the steam generators, as assumed in the accident analysis. The pumps are equipped with independent recirculation lines to prevent pump operation against a closed system.' Each motor driven AFW pump is powered from an independent power supply and feeds two steam generators. 'The steam turbine driven AFW pump receives steam from two main steam lines upstream of the main steam isolation valves. Each of the'steamfeed lines will suipply 100% of the requirements of the turbine driven AFW pump.

(continued)

INDIAN POINT 3 B 3.7. 5 Revision 1

I AFW System B 3.7.5 BASES BACKGROUND The AFW System is capable of supplying feedwater to the steam ->

(continued) generators during normal unit startup, shutdown, and hot standby conditions.

The turbine driven AFW pump supplies a common header capable of feeding all steam generators. Each of the steam generators can also.

be supplied by one of the two motor driven AFW pumps. Any of the .

three pumps at full flow is'sufficient to remove decay heat and cool the unit to residual heat removal (RHR) entry conditions. Thus, the requirement for diversity in motive power sources for the AFW System is met.

The AFW System is designed-to supply'sufficient water to the steam generator(s) to remove decay heat with.steam generator pressure at the setpoint of the MSSVs. Subsequently, the AFW System supplies sufficient water to cool the unit to RHR'eentry conditions, with steam released through the ADVs.

The motor driven pumps are actuated by any one of the following:

1) Low-low level in any steam generator:
2) Loss of voltage (Non SI blackout) on 480 VAC bus 2A/3A (starts AFW Pump 31) and.loss.of voltage (Non SI blackout) on 480 VAC bus 6A (starts AFW Pump 33); '>
  • 3). Safety Injection signal:;
4) Auto trip of either'main boiler feed'pump;
5) Manual actuation from the Control Room: and
6) Manual actuation locally at the pump room.

The steam turbine driven pump is actuated by any.one of the following:

1) Low-low level in two of the four steam generators;
2) Loss of voltage (Non SI blackout) on 480 VAC busses 2A/3A or 6A:

(continued)

INDIAN POINT 3 B 3.7.5-2 Revision 1.

_ -s

AFW System B 3:7:5 BASES BACKGROUND 3) Manual actuation

. . I; from the Control.. Room
and ')

KMCO t11nuea) ,.-,.

4) 'Manual actuation locally at the pump room.

The steam driven AFW pump must be throttled manually in order to bring

,the unit up to speed'after a start signal. 'In addition, the steam

'driven pump discharge flow control valves must be manually opened as necessary to provide'adequate auxiliary feedwater flow.

- The.. AFW System is. discussed

. . I ..

in the FSAR, Section 10.2 (Ref. 1).

I. . . . .I .

APPLICAB LE SAFETY ANALYSES The AFW System mitigates the consequencesof any event with

-loss of normal feedwater.

The design basis of the AFW System is to supply water to the steam generatbr'to remove decay heat and other residual heat by delivering-at least the minimum required flow rate to the steam generators at pressures~corresponding to the lowest steam generator safety valve set pressure plus accumulation.

In addition, the AF1CSystem must supply enough makeup water to replace. V) steam generator secondary inentory lost as the unit cools to MODE 4 i conditions. Sufficient AFW System flow must also be available to account for flow losses such as pump recirculation and line breaks.

, 1 The-limiting events that require the AFW System are as follows:

a. 'small break loss of coolant accident:
b. loss of AC sources: and
c. loss of feedwater.

The AFW turbine 'driven pumpactuates automatically when required to.

ensure an adequiti'feedwater supply to-the steam generators is available'during loss of power. ',Power-operated valves are provided for each AFW line to c6ntrol'the AFW flow to' each steam generator.

The AFW System satisfies',the requirements of Criterion 3 of 10 CFR 50.36.

- -- - *.... (continued)

..  :, , 1 INDIAN POINT 3 B 3.7. 3 . Revision 1

a AFW System B 3.7.5 BASES LCO This LCO provides assurance that the AFW System will perform its design safety function to mitigate the consequences of events that could result in overpressurization of the reactor coolant pressure boundary. Three independent AFW pumps are required to be OPERABLE to ensure the capability to maintain the plant in hot shutdown with a loss of offsite power and a single failure. This'is accomplished by powering two of the pumps from independent emergency buses. The third AFW pump is powered by a steam driven turbine supplied with steam from a source that is not isolated by closure of the MSIVs.

The AFW System'is configured into three trains. The AFW System is considered OPERABLE when the components and flow paths required to provide redundant AFW flow to the steam generators are OPERABLE. This requires that the two motor driven AFW pumps be OPERABLE, each supplying AFW to two separate steam generators. The turbine driven AFW pump is required to be OPERABLE with steam'supplies from each of two main steam lines upstream of the MSIVs,-and shall be capable of supplying AFW to all of the steam generators. The piping, valves.

instrumentation, and controls in the required flow paths also are required to be OPERABLE.

The LCO is modified by a Note indicating that one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.

The motor driven AFW pump required to be OPERABLE in Mode 4 must be capable of supporting the SG(s) being credited as the redundant decay heat removal path in accordance with LCO 3.4.6. RCS Loops - MODE 4.

This requirement ensures the"'ability to maintain the required level in the SG(s)-(and decay heat removalcapacity) during extended periods in Mode 4 with or without offsite power. Requiring only one OPERABLE AFW pump is'acceptable because of the reduced heat removal requirements and short period of time in MODE 4 during which the AFW is required and the insufficient steam'available in'MODE 4 to power the turbine driven AFW pump.

APPLICABILITY In MODES 1, 2. and 3, the AFW System Is required to be OPERABLE in the event that it is called upon to function when the MFW is lost. In addition, the AFW System is required to supply enough makeup water to replace the steam generator secondary inventory needed to achieve and maintain MODE 4 conditions.

InMODE 4, a motor driven AFW pump may be needed to support heat removal via the steam generators.

InMODE 5 or 6, the steam generators are not normally used for heat removal, and the AFW System isnot required.

(continued)

INDIAN POINT 3 B 3.7.5 -4 Revision 1

AFW System B 3.7.5 BASES-ACTIONS A.-1 If one of the two steam.supplies to the turbine'driven AFW train is inoperable.,.action must be taken to restore OPERABLE status within 7 days. The 7 day Completion Time is reasonable,.based on-the following reasons: -

a. The redundant OPERABLE steam'supply to the turbine driven AFW pump;
  • b. The availability of redundant OPERABLE motor-driven AFW pumps; and -

.c. The low probability of an event occurring.that requires the

. Inoperable steam supplyto the turbine driven AFW pump.

The second Completion Time for Required Action A.1 establishes a limit

  • on the maximum time allowed for any combination of Conditions to be inoperable during any continuous failure to meet this LCO.

The 10-day Completion Time provides a limitation time allowed.in this specified Condition after discovery of failure to meet the LCO. This

.. limit is considered reas'onable 'for situations inwhich Conditions A and B are entered concurrently.' The AND conn6ctor between 7 days and 10 days dictates that both Completion Times apply simultaneously, and

.the more restrictive must be met.

With one of-the required AFW trains (pump or flow path) inoperable in

- MODE 2, or-3 for reasons other than Condition A'.action must be taken to restore OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This Condition includes the loss 6f two.steam supply lines to the turbine driven AFW pump. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.Completion Time is reasonable.. based on redundant capabilities afforded by the AFW System, time needed for repairs, and the low probability of a DBA occurring during this time period.

-The second Completion Time-for Required Action B.1 establishes a limit on the maximum time allowed for any combination of Conditions to be

- inoperable during any continuous failure to meet this LCO.

(continued) U INDIAN POINT 3 B 3.7.5 -S Revision 1

I i _

AFW System B 3.7.5 BASES ACTIONS B.1 (continued)

The 10 day Completion Time provides a limitation time allowed in this specified Condition'after discovery'of failure to meet the LCO. This limit is considered reasonable for situations in which Conditions A.

and B are entered concurrently. The AND connector between 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 10 days dictates that both Completion Times apply simultaneously, and the more restrictive must be met.

C.1 and C.2 When Required Action A.1 or B.1 cannot be completed within the required Completion Time, or if two AFW trains are inoperable in MODE

1. 2, or 3, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.

The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

In MODE 4 with two AFW trains inoperable, operation is allowed to continue because only one motor driven pump AFW train is required in accordance with the Note that modifies the LCO. Although not required, the unit may continue to cool down and initiate RPiR.

X-If all three AFW trains are inoperable in MODE 1.'2, or 3, the unit is in a seriously degraded condition with no safety related means for conducting a cooldown, and only limited means for conducting a cooldown with nonsafety related equipment. In such a condition, the unit should not be perturbed by any action, including a power change.

that might result in a trip. The seriousness of this condition requires that action be started immediately to restore one AFW train to OPERABLE status.

Required Action D.1 is modified by a Note indicating that all required MODE changes or power reductions are suspended until one AFW train is restored to OPERABLE status. In this case. LCO 3.0.3 is not applicable because it could force the unit into a less safe condition.

(continued)

INDIAN POINT 3 B 3.7.5-6 Revision 1

AFW System B 3.7.5 BASES ACTIONS E.1 (continued)

In MODE 4, either the reactor coolant pumps or the RHR loops can be used to provide forced circulation. This i's addressed in LCO 3.4.6.

'RCS Loops-MODE 4.'- With one required AFW train inoperable, action must-be taken to immediately restore the inoperable train.to OPERABLE status. -The immediate Completion Time is consistent with LCO 3.4.6.

SURVEI LLANCE REQUIREMENTS  : . . . .. i, . :. I '

SR 3.7.5.1 \K>

Verifying the correct alignment for manual, power operated, and

  • automatic valves in the AFW System water and steam supply flow paths
  • provides assurance that the;proper flow paths will exist for AFW operation. -This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since they are verified to be in the correct position prior to locking, sealing, or securing. This SR also

.does not apply to valves that cannot be inadvertently misaligned, such as check valves. This Surveillance does not require any testing or valve manipulation;..rather, it involves verification 'that those valves capable of being mispositioned are in the correct position.

The 31 day Frequency is based on engineering judgment, is consistent with the procedural controls governing valve operation, and ensures correct valve positions.--

-This SR is modified by a Note that states the SR is not required in

  • :MODE 4. Not performing this SR in MODE 4 is acceptable for.the following reasons: AFW pumps are typically operated intermittently to keep the SGs filled when:in MODE 4, the -decay heat load is low; an RHR loop is required to be OPERABLE as the primary method of decay heat removal in Mode 4; and, the SG is required to be maintained at a level

-that ensures a significant.inventory is available as a heat sink before the AFW pump is.required.to refill the SG. These factors C.ensure that a significant amount of time would be available to complete any valve realignments needed to refill a SG when in Mode 4.

(continued)

INDIAN POINT 3 B 3.7.5"-7 Revision 1

AFW System B 3.7.5 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.7.5.2 Verifying that each AFW pump's developed head at'the flow test point is greater than or equal to the required developed head ensures that AFW pump performance has not degraded during the cycle. Flow and differential head are normal tests of centrifugal pump performance required by Section XI of the ASME Code (Ref 2). Because it is undesirable to introduce cold AFW into the steam generators.while they are operating, this testing is performed on recirculation flow. This test confirms one point on the pump design curve and is indicative of overall performance. Such inservice tests confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance. Performance of inservice testing discussed in the ASME Code,Section XI (Ref. 2) (only required at 3 month intervals) satisfies this requirement.

This SR is modified by a Note indicating that the SR should be deferred until suitable test conditions are established. This deferral is required because there is insufficient steam pressure to perform the test when SG pressure is < 600 psig.

SR 3.7.5.3 This SR verifies that AFW can be delivered to the appropriate steam generator in the event of any accident or transient that generates an ESFAS, by demonstrating that each automatic valve in the flow path actuates to its correct position on an actual or simulated actuation signal. This Surveillance is not required for valves that are locked, sealed, or otherwise secured in-the required position under administrative controls. The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a unit outage (i.'e., unit at less than or equal to 97% power and in preparation for main generator breaker opening with no plans to raise power between the time of the surveillance and breaker open) and the potential for an unplanned transient if-the Surveillance were performed with the reactor at full power. The 24 month Frequency is acceptable based on operating experience and the design reliability of the equipment.

This SR is modified by a Note that states the SR is not required in MODE 4. In MODE 4. the required AFW train is operated as necessary to maintain SG water level.

(continued).

B .7.-8 Rvison INDIN PINT INDIAN POINT 3 B 3.7.5 -8 Revision 1

AFW System B 3.7.5 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.7.5.-

This SR verifies that the AFW pumps will start in the event of any accident or transient that generates an ESFAS by demonstrating that each AFW pump starts automatically on an actual or simulated actuation signal in MODES 1. 2, and 3. In MODE 4, the required pump is operated as necessary and the autostart function is not required. The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a unit outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

This SR is modified by two Notes. Note 1 indicates that the SR be deferred until suitable test conditions are established. This deferral allows the test to be performed at rated conditions. Note 2 states that the SR is not required in MODE 4. In MODE 4, the required pump is operated as necessary to maintain.SG water level and the autostart function is not required. In MODE 4. the heat removal requirements would be less providing more time for operator action to manually start the required AFW pump.

REFERENCES 1. FSAR, Section 10.2.

2. ASME, Boiler and Pressure Vessel Code;Section XI.

INDIAN POINT 3 B 3.7.5 -9 Revision I

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