ML051020136

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Update for IP3 Technical Requirements Manual
ML051020136
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 03/31/2005
From:
Energy Northwest, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
IP-SMM-AD-103, Rev 0
Download: ML051020136 (11)
v • d • e


Text

31-MAR- 05 Page: 91 DISTRIBUTION CONTROL LIST y rment Name: ITS/BASES/TRM CCNAME NAME DEPT LOCATION 1 OPS PROCEDURE GROUP SUPV. OPS PROCEDURE GROUP IP2 3 PLANT MANAGER'S OFFICE UNIT 3(UNIT 3/lPEC 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 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/lPEC 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 & 1P3 GSB-3B 61 SIMULATOR TRAIN(UNIT 3/IPEC ONLY) 48-2-A 69 CONROY PAT LICENSING/ROOM 205 _ GSB-2D 99 BARANSKI-J (ALL) ST. EMERG. MGMT. OFFICE OFFSITE

  • 106 SIMULATOR INSTRUCT AREA TRG/3PT-D001-D006 ONLY)___48

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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

- Entergy TO: DISTRIBUTION DATE: 4/512005 (Cirde one)

FROM: IPEC DOCUMENT CONTROL:

  • EEC or IP2 53'EL PHONE NUMBER: 271-7056 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please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s).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: 1P3 TECHNICAL REQUREMENTS MANUAL DOC # REV # TITLE INSTRUCTIONS

                                      • S EE ATTAC HED INSTRUCTION S*******************
                    • 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 I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH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).

N)1D NAME (PRINT) SIGNATURE DATE , CC#

UPDATE FOR IP3 TECHNICAL REQUIREMENTS MANUAL AFFECTED SECTION REMOVE INSERT List of Effective Sections Page 1 of 1 with Page 1 of I with Effective date 01/25/2005 Effective date 04/05/2005 Section 1.1 Revision 0 Revision I Pages 1.1-1 through 1.1-5 Pages 1.1-1 through 1.1-5 Section 3.3-J Revision 1 N/A - Section was DELETED Pages 3.3.J-1 through 3.3.J-5 Section 3.4-A Revision 0 Revision 1 Pages 3.4.A-1 through Pages 3.4.A-1 through 3.4.A-2 3.4.A-2

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LIST OF EFFECTIVE SECTIONS TRM EFFECTIVE TRM Page(s) EFFECTIVE SECTION X Page(s) DATE SECTION b DATE Table of 2 i through iii 12/04/2002 3.8.C 2 3.8.C-1 through 10 01/25/2005 Contents 3.8.D 0 3.8.D-1 through 2 03/19/2001 1.1 3 1.1-1 through 5 04/05/2005 3.9 0 3.9-1 03/19/2001 1.2 0 1.2-1 through 3 03/19/2001 4.0 0 4.0-1 03/19/2001 1.3 0 1.3-1 through 8 03/19/2001 5.0 4 5.0-1 through 7 08/24/2004 1.4 0 1.4-1 through 4 03/19/2001 2.0 0 2.0-1 03/19/2001 3.0 1 3.0-1 through 15 07/06/2001 3.1.A 1 3.1.A-1 through 8 07/06/2001 3.1.8 0 3.1.B-1 03/19/2001 3.1.C.1 1 3.1.C.1-1 through 8 03/06/2003 3.1.C.2 1 3.1.C.2-1 through 6 03/06/2003 3.2.A 0 3.2.A-1 03/19/2001 3.3.A 1 3.3.A-1 through 3 08/24/2004 3.3.B 3 3.3.B-1 through 12 10/28/2004 3.3.C 0 3.3.C-1 through 5 03/19/2001 3.3.D 2 3.3.D-1 through 20 09/0312003 3.3.E 1 3.3.E-1 through 3 08/24/2004 3.3.F 1 3.3.F-1 through 3 08124/2004 3.3.G 0 3.3.G-1 through 2 03/19/2001 3.3.H 1 3.3.H-1 through 2 08/24/2004

\1-j 3.3.1 ----- NOT USED 33 =-_ -DELETED --- 04/05/2005- :m: .:: __-_: - -.- .

I 7 3.4.A 1 3.4.A-1 through 2 04/05/2005 3.4.B 0 3.4.B-1 through 3 03/19/2001 3.4.C 0 3.4.C-1 through 2 03/19/2001 3.4.D 0 3.4.D-1 through 2 03/19/2001 3.5.A 0 3.5.A-1 through 2 03/19/2001 3.6 0 3.6-1 03/1912001 3.7.A.1 I 3.7.A.1-1 through 5 08/24/2004 3.7.A.2 2 3.7.A.2-1 through 3 08/24/2004 3.7.A.3 5 3.7.A.3-1 through 6 08/24/2004 3.7.A.4 3 3.7.A.4-1 through 3 08/24/2004 3.7.A.5 I1 3.7.A.5-1 through 3 08/24/2004 3.7.A.6 1 3.7.A.6-1 through 2 08/24/2004 3.7.A.7 2 3.7.A.7-1 through 4 08/24/2004 3.7.8 2 3.7.8-1 through 17 08/24/2004 3.7.C 0 3.7.C-1 through 8 03/19/2001 3.7.D 0 3.7.D-1 through 2 03/19/2001 3.7.E 0 3.7.E-1 through 2 03119/2001 3.8.A 0 3.8.A-1 through 5 03/19/2001 3.8.B 0 3.8.B-1 through 7 03/19/2001 Technical Requirements Manual (TRM) .

EFFECTIVE DATE 04/05/2005 Indian Point 3 1 of 1

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions NOTE----------------------------------------------------------

1. The defined terms of this section and the Improved Technical Specifications (ITS) appear in capitalized type and are applicable throughout these Technical Requirements and Bases. Some defined terms in the ITS are not found below because they are not used in the TRM.
2. Terms used in these Technical Requirements and Bases are as defined in the ITS or if not defined in the ITS they are as defined below.

Term Definition ACTIONS ACTIONS shall be that part of a Technical Requirement that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in conjunction with each possible interlock logic state and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output  %

devices.

AXIAL FLUX DIFFERENCE AFD shall be the difference in normalized flux (AFD) signals between the top and bottom halves of a two section excore neutron detector.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known input. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. Whenever a sensing element is replaced, the next required CHANNEL CALIBRATION shall include an inplace cross calibration that compares the other sensing elements with the recently installed sensing element.

The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated.

Technical Requirements Manual (TRM) (continued)

Indian Point 3 1.1-1 Revision 3

Definitions 1.1 1.1 Definitions CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL OPERATIONAL A COT shall be the injection of a simulated or TEST (COT) actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display, and trip functions. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

DEMONSTRATE DEMONSTRATE means that the Surveillance shall be performed ensuring a system is OPERABLE.

- - MASTER -RELAY7TEST _--- - A-MASTER RELAY-TEST-shall-consist-of energizing each _____

master relay and verifying the-OPERABILITY of e-a'ch' relay.

The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant loop temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

Technical Requirements Manual (TRM) (continued)

Indian Point 3 1.1-2 Revision 3

Definitions 1.1 1.1 Definitions QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper RATIO (QPTR) excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3216 MWt. I SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a. All rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn.

With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM; and

b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the hot zero power level.

=-SLAVE-REL-AY-TEST --- A-SLAVE-RELAY-TEST-shallconsist-otenergizing each_

slave relay and verifying the OPERABILITY of each slave:

relay. The SLAVE RELAY TEST shall include, as a minimum, a continuity check of associated testable actuation devices.

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

Technical Requirements Manual (TRM) (continued)

Indian Point 3 .Revision 3

Definitions 1.1 1.1 Definitions TRIP ACTUATING DEVICE A TADOT shall consist of operating the trip OPERATIONAL TEST actuating device and verifying the OPERABILITY of (TADOT) required alarm, interlock, display, and trip functions. The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the required accuracy.

VERIFY VERIFY means that verification of OPERABILITY is satisfied if the last surveillance test that was performed satisfactorily demonstrated system or component OPERABILITY. If any information is available that challenges OPERABILITY, then the OPERABILITY is questionable until it is demonstrated by performing another test. Information that can challenge OPERABILITY can be (but is not limited to) visual observation, or Problem Identification Discrepancy (PIDS),

Condition Reports (CR), or work requests written against the system that indicate the system or component is degraded and this degradation prevents the system or component from performing its design function(s). The existence of a PID, or CR or work request on a system or component does not in and of itself render a system or component inoperable until it is evaluated.

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Technical Requirements Manual (TRM) (continued)

Indian Point 3 1.1-4 Revision 3

Definitions 1.1 1.1 Definitions Table 1.1-1 (page 1 of 1)

MODES MODE TITLE REACTIVITY  % RATED AVERAGE REACTOR (d) CONDITION THERMAL COOLANT (Keff) POWER(a TEMPERATURE

) (OF)

I Power Operation > 0.99 >5 NA 2 Startup > 0.99 <5 NA 3 Hot Standby < 0.99 NA > 350 4 Hot Shutdown < 0.99 NA 350 > Tavg > 200 5 Cold Shutdown(b) < 0.99 NA < 200 6 NA. NA NA Refueling(C)

(a) Excluding decay heat (b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensioned.

(d) Applicable with fuel in the reactor vessel.

Technical Requirements Manual (TRM) (continued)

Indian Point 3 1.1 -5 Revision 3

Low Temperature Overpressure Protection (RCS 319 OF - 411 OF) 3.4.A 3.4 REACTOR COOLANT SYSTEM 3.4.A Low Temperature Overpressure Protection (RCS 319 0F - 411 0F)

TRO 3.4.A The pressurizer level shall be maintained at or below 73% (density compensated).

APPLICABILITY: MODES 3 AND 4, WITH RCS TEMPERATURE 2 319 0F AND < 411 OF.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

NOTE---------------------------

Action to restore pressurizer level may be delayed during a rapid cooldown provided a dedicated operator monitors pressurizer level and responds without delay and in a controlled manner to a rapid increase in level.

A. Pressurizer level greater A.1 Restore Pressurizer Level to below 73% Immediately than 73% (density (density compensated).

compensated).

OR

- I_ __

A.2 Reduce RCS temperature to < 319 0F Immediately OR A.3 Increase RCS temperature > 411 OF. Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRS 3.4.A.1 DEMONSTRATE that Pressurizer level meets TRO 30 minutes 3.4.A.

Technical Requirements Manual (TRM) (continued)

Indian Point 3 3.4.A-1 Revision 1

Low Temperature Overpressure Protection (RCS 319 CF -411 OF) 3.4.A BASES Protection of the reactor vessel and Reactor Coolant System (RCS) piping below 319 0F is provided by ITS 3.4.12, "Low Temperature Overpressure Protection (LTOP)." Similarly, at temperatures of 411OF and above, the RCS is protected from overpressure by ITS 3.4.10, "Pressurizer Safety Valves." Between these two temperatures, operator vigilance is relied upon to ensure that the RCS pressure remains below the applicable Appendix G Pressure-Temperature curve. The absence of automatic protection in this temperature range is an acceptable position that has been approved by the manufacturer and accepted by the USNRC (ref. 1), due to the increased ductility of metal at high temperatures.

It should also be noted that at high RCS pressures (i.e. greater than 1600 psig) an inadvertent Si actuation would not result in actual mass injection to the RCS (Ref. 2). A review of uncorrected Appendix G limits in reference 2 shows that for most temperatures above the LTOPS arming setpoint the allowable pressure exceeds 1600 psig. This provides assurance that the effects of a mass injection event (i.e. SI actuation) will be minimal.

Operating with a pressurizer bubble within this temperature range affords margin to ensure that Appendix G limits will not be exceeded while performing normal activities during heatup and cooldown. A pressurizer level of 73% (actual as extrapolated from the Operations curves that provide density compensation for the cold or hot calibrated instrumentation) will allow for minor thermal-hydraulic corrections that occur as the plant changes MODE and give the operators some time to respond in the event of an inadvertent SI actuation.

Most plant transients will be performed with a pressurizer level of 73% or less. In cases involving

.- rapid cooldown-(non-routine cooldown-at-the discretion of-the-Shift-Manager),-Operations may_ -:-_

desire a higher initial pressurizer level to allow for RCS fluid shrink during the cooldown process.. In that case, the pressurizer level of 73% may be exceeded, if a dedicated licensed operator watches pressurizer level for as long as the pressurizer level exceeds 73%. During such time, the licensed operator should be prepared to respond without delay and in a controlled manner to a sudden increase in pressurizer level.

For all other times, the pressurizer level shall remain below 73% (density compensation) when in this temperature range. If level exceeds 73%, the operators should take action without delay and in a controlled manner to place the RCS in a less vulnerable position. This would include the options of lowering the pressurizer level below 73%, increasing RCS temperature above 41 1'F, or reducing RCS temperature to less than 319 0F, where protection is assured by ITS 3.4.10, "Pressurizer Safety Valves," or ITS 3.4.12, mLTOPS," respectively.

REFERENCES:

1. Letter PENG-98-082, "Letter Report on Clarification of Basis for P-T Limits NYPA Indian Point 3", ABB-Combustion Engineering, April 1998.
2. LTR-SEE-03-207, "Indian Point Unit 3 - High Head Safety Injection System Flows for the Stretch Power Uprate (SPU) Program," September 26, 2003.
3. MISC-MPS-ER-005, "Indian Point 3 Final Report on Appendix G Reactor Vessel Pressure-Temperature Limits", ABB-Combustion Engineering, July 1991.

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Technical Requirements Manual (TRM) (continued)

Indian Point 3 3.4.A-2 Revision 1

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