Text

To IPEC Site Management Manual, IP-SMM-AD-103, IP3 Its/Bases
	ML072480163
Person / Time
Site:	Indian Point
Issue date:	07/06/2007
From:	; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	IP-SMM-AD-103, Rev 0
	Download: ML072480163 (17)
	v • d • e

July 6, 2007 DISTRIBUTION CONTROL LIST Document Name: IP3 ITS / BASES CC#

11 19 20 21 22 23 25 28 32 47 50 61 69 99 106 164 273 319 354 357 424 474 489 492 493 494 496 497 500 501 512 513 518 NAME OPS PROC GP SUPERVISOR CONTROIJROOM.

RES DEPARTMENT MGR CONROY, PAT -.....

CHEMISTRY SUPERVISOR TSC (IP3)

SHIFT MANAGER LIS SIMULATOR RESIDENT INSPETOR EOF CHAPMAN, N SCOZZARO, ANTHONY SIMULATOR CONROY, PAT KRAUS, KEVINV SIM INSTRUCT AREA CONTROL ROOM FAISON, CHARLENE GRANT, LEAH GRANT, LEAH GRANT, LEAH GRANT, LEAH OUELLETTE P CLOUGHNESSY, PAT UNIT 3 FSS OPERATIONS FIN TEAM AOEF / A. GROSSJEAN GRANT, LEAH GRANT, LEAH GRANT, LEAH GRANT, LEAH GRANT, LEAH GRANT, LEAH DOC CONTROL DESK DEPARTMENT OPS PROCEDURE GROUP OPERATIONS RES LICENSING / ROOM 205 CHEMISTRY DEPARTMENT 53' ELEVATION OPERATIONS LICENSING & INFO SERVICE TRAINING US NRC 88' ELEVATION E-PLAN BECHTWL WESTINGHOUSE ELECTRIC TRAINING LICENSING / ROOM 205 ST. EMERGENCY MGMT. OFFICE TRAINING OPERATIONS NUCLEAR LICENSING LRQ TRAINING LRQ TRAINING ILO TRAINING TRAINING ENG, PLAN & MGMT INC PLANT SUPPORT TEAM 53' ONE STOP SHOP LOCATION 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

48 IP3 WPO-12

48

48 48-2-A

48 OFFSITE GSB/3B IP2 45-1-A WPO/12-D

48

48

48

48

48

48 OFFSITE 33 TURBIN DECK E-PLAN LRQ TRAINING LRQ TRAINING LRQ TRAINING LRQ TRAINING LRQ TRAINING LRQ TRAINING NRC

IPEC SITE QUALITY RELATED IP-SMM-AD-103 Revision 0 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 1 isEn tergy CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES.

TO: DISTRIBUTION DATE:

8/27/07 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please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s).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 retum the receipt acknowledgement below within fifteen (15) working days.

AFFECTED DOCUMENT:

IP3 ITS/BASES/TRM DOC#

REV#

TITLE INSTRUCTIONS

- - - - FOLLOW THE ATTACHED INSTRUCTIONS****************************

....... E.NOTE.EFFECTIVE..

""'****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#

NAME (PRINT)

SIGNATURE DATE CC#

Distribution of IP3 Technical Specification Amendment 234.

(Approved by NRC August 16, 2007)

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

Page 1 of 1 (4)

ENO pursuant to the Act and 10 CFR Parts 30, 40 and 70, Amdt. 203 to receive, possess, and use in amounts as required any 11/27/00 byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)

ENO pursuant to the Act and 10 CFR Parts 30 and 70, to Amdt. 203 possess, but not separate, such byproduct and special 11/27/00 nuclear materials as may be produced by the operation of the facility.

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 I: 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 facility at steady state reactor core power levels not in excess of 3216 megawatts thermal (100% of rated power).

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 234 are hereby incorporated in the License. ENO shall operate the facility in accordance with the Technical Specifications.

(3)

(DELETED)

Amdt. 205 2-27-01 4 -DE-E-T-E-D-)

Amdt. 205 2-27-01 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.

Amendment No. 234

INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 1 of 3 Page Amend Section 3.0 2

l205 1

229 3

1 205 Table of Contents 2

1 226 Section 3.2.3 233 3

1229 1

1205 233 4

1 212 2

205 U

233.

5

.226..

3

.205 iv 233 Section 3.1.1 4

205 Section 1.1 1

205 Section 3.2.4._

.1 205 Section 3.1.2 1 "

205 2

205 1

1205 2

205 3

224 2

205 3

205 4

233 Section 3.1.3 4

205 5

225 1

T 205 Section 3.3.1 6

205 2

205 1

205 7

205 Section 3.1.4 2

205 8

205 1

205 3

205 Section 1.2 2

205 4

205 1

205 3

205 5

205 2

205 4

205 6

205 3

205 5

205 7

205 Section 1.3 Section 3.1.5 8

205 1

205 9

205 2

1 205 10 205 3

205 Section 3.1.6 11

.205

-4205....

.205-----

205--.

5 205 2

205 13 225 6

205 3

205 14 205 7

205 Section 3.1.7 15 225 8

205 1

205 16 205 9

205 2

205 17 205 10 205 3

205 18 205 11 205 4

205 19 234 12 205 Section 3.1.8 20 234 13 205 1

205 Section 3.3.2 Section 1.4 2

1 205 1

205 1

205 Section 3.2.1 2

205 2

234 1

205 3

205 2

205 4

205 3

205 5

205

{ Section 2.0 Section 3.2.2 6

205 1

225 1

205 7

205 The latest amendment reflected in this list is: Amendment 234

INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 2 of 3 The latest amendment reflected in this list is: Amendment 234

INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 3 of 3 1

205 r3

]T232 2

205 I 4

232 3

205 5

234 4

205 6

234.

Section 3.8.7

' 7 205

1..

205 1..

f8

--205 2

205 9

210

... 3.-

234 J.

I

[10 J232 Section 3.8.8 11 232 1

205 12 205 12 205 13 233 Section 3.8.9 14 233 1

205 15 233 2

205 16 Deleted Section 3.8. 10 17 Deleted 1

205 18 Deleted 2

205 19 Deleted Section 3.9.1 20 205 1

-F205 21 224 Section 3.9.2 22 224 U

1 I

I205 23 224 2

205 24 234 Section 3.9.3 25 224 1

215 26 232 3

215 28 205 Section 3.9.4 29 205 1

205 30 234 2

205 31 225 Section 3.9.5 32 227 1

205 33 227 2

205 3 4 225 Section 3.9.6 35 225 1

1 205 36 233 Section 4.0 37 232 1

205 38 232 2

205 39 232 3

205 40 232 Section 5.0 41 232 1

205 2

205 The latest amendment reflected in this list is: Amendment 234

Entergy Nuclear Operations, Indian Point 3 Nuclear Power License Amendments SUBJECT Inc Plant Page 14 232 233

.234 Adoption of TSTF-258, TSTF-308, and Related Administrative Control Changes Based on NUREG-1431 Adoption of TSTF-449 Steam Generator Tube Integrity Adoption of TSTF-485 and Miscellaneous Editorial Changes LETTER DATE 12/13/2006.

02/13/2007 08/16/2007

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS).

The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time.

Performance of the Surveillance initiates the subsequent interval.

Although the. Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility.

The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1. (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO).

If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Example 1.4-3), then SR 3.0.3 becomes applicable.

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable.

The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.

(continued)

INDIAN POINT 3 1.4 - 2 Amendment 234

RPS Instrumentation 3.3.1

'Table 3.3.1-1 (page 7 of 8)

Reactor Protection System Instrumentation Note 1: Overtemoerature AT The Overtemperature AT Function Allowable Value shall not exceed the following Trip Setpoint by more than 2.8% of AT span:

AT:ATo Ki-KX 0+r S)[.. T K(p-PK)-f (A 1)

Where:

AT is measured RCS AT, OF.

ATO is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec"'.

T is the measured RCS average temperature, OF.

T' is the nominal T,,, at RTP,

[ *]F.

P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure,

> [ * ] psig V, > [*] sec f1(AI) = [ * ]

0% of

[. * ]

2 <

[*]

sec K3 Ž_ [ * ]/psig

{[*] - (q"-qb)}

when RTP when

{ (qt qb) - [*]}

when q,

qb

[ *]-

qt " qb

_* [ * ]% RTP RTP < q - q

[ * ]

RTP

> [ * ] % RTP Where q, and qb are percent RTP core*,-respec-ti-velyi -and -q+ %

percent RTP.

in the upper and lower halves of the

-is-the total-THERMAL-POWER in - -

The values denoted with [ * ] are specified in the COLR.

INDIAN POINT 3 3.3.1-19 Amendment 234

RPS Instrumentation.

3.3.1 Table 3.3.1-1 (page 8 of 8)

Reactor Protection System Instrumentation Note 2:

Overpower AT The Overpower AT Function Allowable Value shall not exceed the following Trip. Setpoint by more than 1.8% of AT span:

AT*:5ATo{ K 4 K-5 (ir 3s) T -K6 (T - T")f(A I)}

Where:

AT is measured RCS AT, OF.

AT, is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec-.

T is the measured RCS average temperature, OF.

T" is the nominal. To at RTP, 5 [ * ]-F.

K4 K5

[ * ]

K > [ * ] /*F for increasing T*,,

K6 _ [ * ] /OF when T > T"

[ * ] /OF for decreasing Tav,

[ * ] /OF when T T"

T3[*

sec f,(AI) = [ * ]

The values denoted with [ * ] are specified in the COLR.

INDIAN POINT 3 3.3.1-20 Amendment 234

CRVS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Ventilation System (CRVS)

LCO 3.7.11 Two CRVS trains shall be OPERABLE.

APPLICABI~LIY:

ACTIONS MMDES 1, 2, 3, 4.

CONDITION REPJJIRED ACTION CRMLETION TIME A.

One CRVS train inoperable.

A.1 Restore CRVS train to 7 days OPERABLE status.

B.

Two CRVS trains inoperable.

B.1 Restore one CRVS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Carpletion Time of Condition A or B not met.

AN)

C.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months INDIAN POINT 3 3.7.11-1 Amendment 234

Inverters - Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, 7 days and alignment to required 120V AC vital instrument buses.

SR 3.8.7.2

--Verify manual-transfer of the AC power source 24 months for VIB 34 from inverter 34 to each required CVT.

INDIAN POINT 3 3.8.7 - 3 Amendment 234

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 for comparable positions, except for the following:

a.

The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8. September 1975; and

b.

The operations manager shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 except for the SRO license requirement which shall be in accordance with Technical Specification 5.2.2.e.

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator.(SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

INDIAN POINT 3 5.0 - 5 Amendment 234

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a.

The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978; b..

The.emergency operating proce.dures.-requi.red to implement-the requirements of NUREG-0737 and to NUREG-0737, Supplement 1,. as stated in Generic Letter 82-33;

c.

Quality assurance for effluent and environmental monitoringi

d.

Fire Protection Program implementation; and

e.

All programs specified in Specification 5.5.

INDIAN POINT 3 5.0 - 6 Amendment 234

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Ventilation Filter Testing Program (VFTP)

(continued)

c.

Demonstrate for each system that a laboratory test of a sample of the charcoal adsorber shows the methyl iodide removal efficiency specified below when tested in accordance with ASTM D3803-1989, subject to clarification below, at a temperature of 860F and a relative humidity of 95%..

Methyl iodide removal.

ASTMD3803'1989 Ventilation System efficiency Clarification M*:

Control Room

> 95.5 78 ft/min face velocity Ventilation System Containment Fan Cooler

> 85 59 ft/min face velocity Units

___________(continued)

INDIAN POINT 3 5.0 - 24 Amendment 234

Programs and Manuals

.5.5 5.5 Programs and Manuals 5.5.15 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J,.

Option B, as modified by approved exemptions.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak Test Program, dated September 1995" as modified by the following exception:

ANS 56.8-.1994,.Section 3.3..1l;. WCCPPS i solation. valves, are.. not Type...

C tested.

The maximum allowable primary containment leakage rate, La,.at a minimum test pressure equal to.P,, shall be 0.1% of primary containment air weight per day. P, is the peak calculated containment internal pressure related to the design basis accident.

Leakage acceptance criteria are:

a.

Containment leakage rate acceptance criterion is < 1.0 L,.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 L. for the Type B and C tests and < 0.75 L, for Type A tests;

b.

Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is < 0.05 L. when tested at > P8,

2)

For each door, leakage rate is < 0.01 L. when pressurized to > P,

c.

Isolation Valve Seal Water System leakage rate acceptance criterion is 14,700 cc/hr at > 1.1 P,.

d.

Acceptance criterion for leakage into containment from isolation valves sealed with the service water system is < 0.36 gpm per fan (continued)

INDIAN POINT 3 5.0 -

30 Amendment 234

ML072480163

Text

Navigation menu

Search