ML062000369

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Update to IP3 Technical Specifications Bases
ML062000369
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 04/19/2006
From:
Entergy Nuclear Operations
To:
Office of Nuclear Reactor Regulation
References
IP-SMM-AD-103, Rev 0
Download: ML062000369 (12)
v • d • e


Text

19-APR-06 Page:

67 DISTRIBUTION CONTROL LIST cument Name:

ITS/BASES/TRM CC-NAME NAME I OPS PROCEDURE GROUP SUPV.

3 PLANT MANAGER'S OFFICE.

5 CONTROL ROOM (FL) 11 RES DEPARTMENT MANAGER 19 STEWART ANN 20 CHEMISTRY SUPERVISOR 21 TSC(IP3) 22 SHIFT MGR.(UDB e6+/-

)

23 LIS 25 SIMULATOR 28 RESIDENT INSPECTOR 32 EOF 47 CHAPMAN N 50 HAAS, CHERYL A.

61 SIMULATOR 69 CONROY PAT 99 BARANSKI J (ALL) 106 SIMULATOR INSTRUCT AREA 164 CONTROL ROOM (FL) 273 FAISON CHARLENE 319 L.GRANT (LRQ-OPS TRAIN) 354 L.GRANT(LRQ-OPS/TRAIN) 357 L.GRANT(ITS/INFO ONLY) 424 GRANT LEAH 474 OUELLETTE P 489 CLOUGHNESSY PAT 492 WORK CONTROL 493 OPERATIONS FIN TEAM 494 AEOF/A.GROSJEAN(ALL EP'S) 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) 518 DOCUMENT CONTROL DESK DEPT OPS PROCEDURE GROUP UNIT 3(UNIT 3/IPEC ONLY)

OPS (-3P-O0t/S( I P3 / I PEC)

RES (UNIT 3/IPEC ONLY)

LICENSING CHEMISTRY DEPARTMENT EEC BUILDING OPERATIONS (UNIT 3)

LICENSING & INFO SERV TRAIN(UNIT 3/IPEC ONLY)

US NRC 88' ELEVATION E-PLAN (ALL EP'S)

BECHTEL WESTINGHOUSE ELECTRIC TRAIN(UNIT 3/IPEC ONLY)

LICENSING/ROOM 205 ST.

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NUCLEAR LICENSING LRQ (UNIT 3/IPEC ONLY)

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PLAN & MGMT INC PLANT SUPPORT TEAM OPERATIONS 72' ELEV 33 TURBIN DECK E-PLAN (EOP'S ONLY)

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LOCATION IP2 IP2 IP3 45-4-A GSB-2D 45-4-A IP2 IP3 OFFSITE 48-2-A IP2 EOF OFFSITE OFFSITE 48-2-A GSB-2D OFFSITE

  1. 48 IP3 WPO-12
  1. 48
  1. 48 48-2-A
  1. 48 OFFSITE GSB-3B IP2 45-1-A WPO-12D
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  1. 48 OFFSITE A~oo

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

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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 Af e

CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES TO: DISTRIBUTION DATE:

7/3/06 PHONE NUMBER: 271-7057

-FROM: IPEC DOCUMENT CONTROL 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 ITSIBASES/TRM DOC#

REV#

TITLE INSTRUCTIONS

                                • FOLLOW THE 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 CC#

INDIAN POINT 3 TECHNICAL SPECIFICATION BASES INSTRUCTIONS FOR UPDATE:

20-07106106 Pages are to be inserted into your controlled copy of the IP3 Technical Specifications Bases following the instructions listed below. The TAB notation indicates which section the pages are located.

Remove Page

.Insert Page TAB - List Of Effective Sections List of Effective Sections, Rev. 19 1 List of Effective Sections, Rev. 20 (5 pages)

(5 pages)

TAB 3.9 - Boron Concentration B 3.9.1, Rev. 0 B 3.9.1, Rev. 1 (4 pages)

(4 pages)

Page 1 of 1

TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE SECTIONS BASES NUMBER EFFECTIVE SECTION REV OF PAGES DATE TbI of Cnt 2

4 8/10/2005 B 2.0 SAFETY LIMITS B 2. 1.1 1 I 4

J06/03/2005 B 2.1.2 j1 4

06/03/2005 B 3.0 LCO AND SR APPLICABILITY,

B 3.0 2

16 t08/10/2005 B 3.1 REACTIVITY CONTROL B 3.1.1 1

6 06/03/2005 B 3.1.2 0

7 03/19/2001 B 3.1.3 1

7 10/27/2004 B 3.1.4 0

13 03/19/2001 B 3.1.5 0

5 03/19/2001 B 3.1.6 0

6 03/19/2001 B 3.1.7 0

8 03/19/2001 B 3.1.8 0

7 03/19/2001 B 3.2 POWER DISTRIBUTION LIMITS B 3.2.1 0

7 03/19/2001 B 3.2.2 1

7 J06/03/2005 B 3.2.3 0

9 03/19/2001 B3.2.4 0

7 03/19/2001 B 3.3 INSTRUMENTATION B 3.3.1 2

58 06/03/2005 B 3.3.2 4

45 04/11/2005 B 3.3.3 3

18 08/10/2005 B 3.3.4 1

6 08/10/2005 B 3.3.5 1

6 10/27/2004 B 3.3.6 1

8 04/11/2005 B 3.3.7 1

6 04/11/2005 B 3.3.8 2

4 06/03/2005 B 3.4 REACTOR COOLANT SYSTEM -

B 3.4.1 1

6 06/03/2005 B 3.4.2 0

3 03/19/2001 B 3.4.3 2

9 06/03/2005 B 3.4.4 0

4 03/19/2001 B 3.4.5 0

6 03/19/2001 B 3.4.6 1

6 06/03/2005 B 3.4.7 0

7 03/19/2001 B 3.4.8 0

4 03/19/2001 B 3.4.9 3

5 06/03/2005 B 3.4.10 0

5 03/19/2001 B 3.4.11 1

7 08/10/2005 B 3.4.12 2

19 08/10/2005 B 3.4.13 3

6 06/03/2005 B 3.4.14 0

10 03/19/2001 B 3.4.15 3

7 08/10/2005 B 3.4.16 2

6 08/10/2005 B 3.5 ECCS B 3.5.1 1

10 10/27/2004 B 3.5.2 2

13 09/16/2005 B 3.5.3 1

4 08/10/2005 BASES NUMBER EFFECTIVE SECTION REV OF PAGES DATE B 3.6 CONTAINMENT_

B 3.6.1 0

5 03/19/2001 B 3.6.2 1

9 06/03/2005 B 3.6.3 0

17 03/19/2001 B 3.6.4 0

3 03/19/2001 B 3.6.5 1

5 06/20/2003 B 3.6.6 2

13 06/03/2005 B 3.6.7 1

6 06/03/2005 B 3.6.8 1

1 08/10/2005 B 3.6.9 1

8 06/03/2005 B 3.6.10 2

12 09/16112005

_B 3.7 PLANT SYSTEMS -

B 3.7.1 2

6 06/03/2005 B 3.7.2 1

10 06/03/2005 B 3.7.3 1

7 05/18/2001 B 3.7.4 1

4 08/10/2005 B 3.7.5 3

9 08/10/2005 B 3.7.6 2

4 06/03/2005 B 3.7.7 1

4 12/17/2004 B 3.7.8 1

7 06/03/2005 B 3.7.9 2

9 06/0312005 B 3.7.10 1

3 06/03/2005 B 3.7.11 5

7 08/1012005 B 3.7.12 1

4 04/11/2005 B 3.7.13 3

7 06/03/2005 B 3.7.14 1

3 04/11/2005 B 3.7.15 0

5 03/19/2001 B 3.7.16 0

6 03/19/2001 B 3.7.17 1

4 06/03/2005 B 3.8 ELECTRICAL POWER B 3.8.1 3

30 11/04/2005 B 3.8.2 0

7 03/19/2001 B 3.8.3 0

13 03/19/2001 B 3.8.4 1

11 01/2212002 B 3.8.5 0

4 03/19/2001 B 3.8.6 0

8 03/19/2001 B 3.8.7 1

8 06/20/2003 B 3.8.8 1

4 06/20/2003 B 3.8.9 2

14 06/20/2003 B 3.8.10 0

4 03/19/2001 B 3.9 REFUELING OPERATIONS B 3.9.1 1

4 07106/2006 B 3.9.2 0

4 03/19/2001 B 3.9.3 2

7 06/03/2005 B 3.9.4 0

4 03/19/2001 B 3.9.5 0

4 03/19/2001 B 3.9.6 2

3 04/11/2005 I

S83.5.4 1 0 1

9 103/19/2001 INDIAN POINT 3 "Page 1 -of 5 Revision 20

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 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 UPDATE PACKAGE 02-051801 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

05/18/01 Implementation of Tech Spec Amend 207 BASES UPDATE PACKAGE 03-111901 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 icontrol 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 04-012202 :,.--

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

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

BASES UPDATE PACKAGE 05-093002 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 5 Revision 20

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

-__ =BASES UPDATE PACKAGE 06-120402.

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

B 3.7.6 1

B 3.7 1...

BASES UPDATE PACKAGE 07-031703 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.

BASES UPDATE PACKAGE 08-032803

ýB 3.4.9 I

1 103/28/2003 Changes to reflect Tech Spec Amendment 216 regarding I_

Irelaxation of pressurizer level limits in MODE 3.

BASES UPDATE PACKAGE 09-062003.,

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-IP3-2002-02095; 4 FCUs should be in operation to assure representative measurement of containment air temperature.

B 3.7.11 2

06/2012003 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 BASES UPDATE PACKAGE 10-102704 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 201EFPY (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.

BASES UPDATE PACKAGE 11-121004 B 3.7.7 1

12/17/2004 Addition "of valves CT-1300 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.

BASES UPDATE PACKAGE 12-012405 B 3.7.11 3

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

INDIAN POINT 3 Page 3 of 5 Revision 20

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.

BASES UPDATE PACKAGE 14-030705 B 3.9.6 1

03/07/2005 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.

BASES UPDATE PACKAGE 15-041105 B 3.3.2 4

04/11/2005 Changes to reflect AST as per Tech Spec Amendment i3 3.3.6 1

224.

B. 3.3.7 1

B 3.7.11 4

NOTE: In addition to the AST changes to B. 3.7.11, the B 3.7.12 1

temporary allowance for use of KI/SCBA for unfiltered B 3.7.14 1

inleakage above limit is being removed. Tracer Gas B 3.9.6 2

testing is complete.

BASES UPDATE PACKAGE 16-060305 B 2.1.1 1

06/03/2005 Changes to reflect SPU as per Tech Spec Amendment B 2.1.2 1

225.

B 3.1.1 1

B 3.2.2 1

B 3.3.1 2

B 3.3.8 2

B 3.4.1 1

63.4.3 2

B 3.4.6 1

B 3.4.9 3

B 3.4.13 3

B 3.4.16 1

B 3.5.2 1

B 3.6.2 1

B 3.6.6 2

B 3.6.7 1

83.6.9 1

B 3.6.10 1

B 3.7.1 2

B 3.7.2 1

B 3.7.5 2

B 3.7.6 2

B 3.7.8 1

B 3.7.9 2

B 3.7.10 1

B 3.7.13 3

B 3.7.17 1

B 3.9.3 2

INDIAN POINT 3 Page 4 of,5

'Revision 20

TECHNICAL SPECIFICATION BASES REVISION HISTORY AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION BASES UPDATE PACKAGE 17-081005 TOC 2

08/1012005 B 3.3.3, B 3.68 - Removal of Hydrogen Recombiners from the bases as per Technical Specification Amendment B 3.0 2

228. B 3.3.3 is also affected by Amendment 226.

B 3.3.3 3

B 3.7.11 - Add reference that if the primary coolant source of containment is in question, refer to ITS 5.5.2.

B 3.3.4 1

All other bases changes for this revision are associated B 3.4.11 1

with Technical Specification Amendment 226 regarding increase flexibility in Mode Restraints.

B 3.4.12 2

B 3.4.15 3

B 3.4.16 2

B 3.5.3 1

B 3.6.8 1

B 3.7.4 1

B 3.7.5 3

83.7.11 5

B 3.8.1 2

_BASES UPDATE PACKAGE 18-091605 B 3.5.2 2

09/16/2005 Reflect implementation of ER-04-2-029 as part of Stretch Power Uprate,(SPU) - HHSI Modification.

B 3.6.10 2

Update LCO and Condition B to clarify required actions

,consistent with FSAR.

BASES UPDATE PACKAGE 19-110405 B 3.8.1 3

11/04/2005 [Include operability criteria for 138 kV and 13.8 kV offsite I

Icircuits.

BASES UPDATE PACKAGE 20-070606 B 3.9.1 1 1 07/06/2006 Clarification on effective method for ensuring shutdown I

I Imargin.

INDIAN POINT 3 Page 5 of *5 Revision,20

Boron Concentration B 3.9.1 B 3.9 REFUELING OPERATIONS B 3.9.1 Boron Concentration BASES BACKGROUND The limit on the boron concentrations of the Reactor Coolant System (RCS) and the refueling cavity (which includes the refueling canal) during refueling ensures that the reactor remains subcritical during MODE 6.

Refueling boron concentration is the soluble boron concentration in the coolant in each of these volumes having direct access to the reactor core during refueling.

The soluble boron concentration offsets the core reactivity and is measured by chemical analysis of a representative sample of the coolant in each of the volumes.

The refueling boron concentration limit is specified in the COLR.

Plant procedures ensure the specified boron concentration in order to maintain an overall core reactivity'of keff < 0.95 during fuel handling, with control rods and fuel assemblies assumed to be in the most adverse configuration (least negative reactivity) allowed by plant procedures.

GDC 26 of 10 CFR 50, Appendix A, requires that two independent reactivity control systems of different design principles be provided (Ref. 1).

One of these systems must be capable of holding the reactorcore subcritical under cold conditions.

The Chemical and Volume Control System (CVCS) is the system capable of maintaining the reactor subcritical in cold conditions by maintaining the boron concentration.

The reactor is brought to shutdown conditions before beginning operations to open the reactor vessel for refueling.

After the RCS is cooled and depressurized and the vessel head is unbolted, the head is slowly removed to form the refueling cavity.

The refueling canal and the refueling cavity are then flooded with borated water from the refueling water storage tank.

(continued)

INDIAN POINT 3 6 3.9.1 - 1 Revision 1

Boron Concentration B 3.9.1 BASES BACKGROUND (continued)

The pumping action of the RHR System in the RCS and the natural circulation due to thermal driving heads in the reactor vessel and refueling cavity mix the added concentrated boric acid with the water in the refueling canal.

The RHR System is in operation during refueling (see LCO 3.9.4, "Residual Heat Removal (RHR) and Coolant Circulation-High Water Level," and LCO 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level") to provide forced circulation in the RCS and assist in maintaining the boron concentrations in the RCS and the refueling cavity above the COLR limit.

APPLICABLE SAFETY ANALYSES During refueling operations, the reactivity condition of the core is consistent with the initial conditions assumed for the boron dilution accident in the accident analysis and is conservative for MODE 6.

The boron concentration limit specified in the COLR is based on the core reactivity at the beginning of each fuel cycle (the end of refueling) and includes an uncertainty allowance.

The required boron concentration and the plant refueling procedures, that include use of two independent checks to verify correct fuel assembly and location, ensure that the keff of the core will remain

< 0.95 during the refueling operation.

Hence, at least a 5% Ak/k margin of safety is established during refueling.

During refueling, the water volume in the spent fuel pit, the transfer canal, the refueling canal, the refueling cavity, and the reactor vessel form a single mass.

As a result, the soluble boron concentration is relatively the same in each of these volumes.

The 2).

LCO limiting boron dilution accident analyzed occurs in MODE 5 (Ref.

A detailed discussion of this event is provided in Bases for 3.1.1, "SHUTDOWN MARGIN (SDM)."

The RCS boron concentration satisfies Criterion 2 of 10 CFR 50.36.

(continued)

K1_>

INDIAN POINT 3 B 3.9.1 - 2 Revision 1

Boron -Concentration 8 3.9.1 BASES LCO The LCO requires that a minimum boron concentration be maintained in all filled portions of the RCS and the refueling cavity (which includes the refueling canal) while in MODE 6.

The boron concentration limit specified in theCOLR ensures that a core keff of

< 0.95 is maintained during fuel handling operations.

Violation of the.LCO could lead to an inadvertent criticality during MODE 6.

APPLICABILITY This LCO is applicable in MODE 6 to ensure that the fuel in the reactor vessel will remain subcritical.

The required boron concentration ensures a keff : 0.95.

Above MODE 6, L[O 3.1.1, "SHUTDOWN MARGIN {SDM)" ensures that an adequate amount of negative reactivity is available to shut down the reactor and maintain it subcritical.

ACTIONS A.1 and A.2 Continuation of CORE ALTERATIONS or positive reactivity additions (including actions to reduce boron concentration) is contingent upon maintaining the unit in compliance with the LCO.

If the boron concentration of any coolant volume in the RCS or the refueling cavity is less than its limit, all operations involving CORE ALTERATIONS or positive reactivity additions must be suspended immediately.

Suspension of CORE ALTERATIONS and positive reactivity additions shall not preclude moving a component to a safe position.

A.3 In addition to irmmediately suspending CORE ALTERATIONS or positive reactivity additions, boration to restore the concentration must be initiated immediately.

In determining the required combination of boration flow rate and concentration, no unique Design Basis Event must be satisfied.

The only requirement is to restore the boron concentration to its required value as soon as possible.

(continued)

INDIAN *POINT 3 13 3.9.1 - 3

ýRevision 1

Boron Concentration B 3.9.1 BASES K,_>

ACTIONS A.3 (continued)

In order to raise the boron concentration as soon as possible, the operator should begin boration with the best source available for unit conditions.

Once actions have been initiated, they must be continued until the boron concentration is restored.

The restoration time depends on the amount of boron that must be injected to reach the required concentration.

SURVEILLANCE REQUIREMENTS SR 3.9.1.1 This SR ensures that the coolant boron concentration in the RCS and the refueling cavity is within the COLR limits.

For sampling purposes, the refueling cavity and canal are considered a single volume.

The boron concentration of the coolant in each volume is determined periodically by chemical analysis.

A minimum Frequency of once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is a reasonable amount of time to verify the boron concentration of representative samples.

The Frequency is'based on operating experience, which has shown 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to be adequate.

REFERENCES

1.

10 CFR 50, Appendix A.

2.

FSAR, Chapter 14.

INDIAN POINT 3

,B 3.9.1.- 4 Revision I

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