Text

And Edwin I. Hatch Nuclear Plant - Supplement to Licensing Amendment Request for the Implement Technical Specification Task Force 425 - A. Revision 3
	ML110530184
Person / Time
Site:	Hatch, Farley
Issue date:	02/21/2011
From:	Ajluni M; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-11-0141
	Download: ML110530184 (50)
	v • d • e

Mark J. Ajluni, P.E.

Southern Nuclear Nuclear Licensing Director Operating Company, Inc.

40 Inverness Center Post Office Box 1295 Alabama 35201 Tel 205.992.7673 Fax 205.992.7885 February 21, 2011 SOUTHERN'\\'

COMPANY Docket Nos.: 50-321 50-348 NL-11-0141 50-366 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Supplement to Licensing Amendment Request for Joseph M. Farley Nuclear Plant and Edwin I. Hatch Nuclear Plant to Implement Technical Specification Task Force 425 - A, Revision 3 Ladies and Gentlemen:

By letters dated October 29,2010, Southern Nuclear Operating Company submitted license amendment requests for Joseph M. Farley Nuclear Plant (FNP) and Edwin I. Hatch Nuclear Plant (HNP) for approval to relocate specific surveillance frequencies to a licensee-controlled program with the implementation of Nuclear Energy Institute (NEI) 04-10, Revision 1 "Risk -Informed Technical Specification Initiative 5b, Risk - Informed Method for Control of Surveillance Frequencies. "

Subsequent to the submittals described above, editorial errors were identified. contains the corrections and resolutions related to the FNP submittal. contains the corrections and resolutions related to the HNP submittal and a revised Table 2 containing the 10 "Supporting Requirements (SRs) Not Met" and the five CAT I SRs findings and resolutions that resulted from the Regulatory Guide (RG) 1.200 PRA peer review.

U. S. Nuclear Regulatory Commission NL-11-0141 Page 2 Mr. M. J. Ajluni states he is Director - Nuclear Licensillg of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.

This letter contains no NRC commitments. If you have any questions, please contact Jack Stringfellow at (205) 992-7037.

Respectfully submitted, M. J. Ajluni Nuclear Licensing Director Swom to and subscribed before me thi£ day ~""40011.

y commission expires: II~-t4 MJAlSY Allac

Enclosures:

1. FNP License Amendment Request Dated October 29,2010 Submittal Corrections

2. HNP License Amendment Request Dated October 29, 2010 Submittal Corrections

U. S. Nuclear Regulatory Commission NL-11-0141 Page 3 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. L. M. Stinson, Vice President - Fleet Operations Support Mr. D. R. Madison, Vice President - Hatch Ms. P. M. Marino, Vice President - Engineering RType:<Farley=CFA04.054; Hatch=CHA02.004 U. S. Nuclear Regulatory Commission Mr. V.M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley, Hatch and Vogtle Mr. P. G. Boyle, NRR Project Manager Mr. E. L. Crowe, Senior Resident Inspector - Farley Mr. E. D. Morris, Senior Resident Inspector - Hatch Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer State of Georgia Mr. Allen Barnes, Environmental Director Protection Division

Supplement to licensing Amendment Request for Joseph M. Farley Nuclear Plant and Edwin I. Hatch Nuclear Plant to Implement Technical Specification Task Force 425 - A, Revision 3 FNP License Amendment Request Dated October 29, 2010 Submittal Corrections to NL-11-0141 FNP License Amendment Request dated October 29, 2010 Submittal Corrections contains the following revisions to the FNP License Amendment Request dated October 29, 2010 submittal.

Editorial Error The following SRs were included in the Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups; however, the marked-up pages for these SRs were not included in the submittal for FNP:

3.3.2.10 3.4.2.1 3.4.14.1 3.6.2.1 3.7 3.7.10.4 SR 3.4.1.3 is listed twice in the Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups SR 3.4.11.4 was included in scope of the FNP submittal to implement TSTF 425; however, this SR is a cycle 16 specific SA.

This SR is being removed from the Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups and the scope of the FNP submittal to implement TSTF 425.

SR 3.5.3.2 and SR 3.7.17.1 were inadvertently excluded from the Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups.

Resolution The SRs listed were deleted from the Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Markups. A revised cross reference table is included in Enclosure

1.

The duplicate SR was deleted from the Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark. A revised cross reference table is included in Enclosure 1

SR 3.4.11.4 was deleted from the Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups. Revised marked-up and clean typed pages and a revised cross reference table are included in.

SR 3.5.3.2 and SR 3.7.17.1 were added to the Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups. A revised cross reference table is included in Enclosure

1.

E1-2 to NL-11-0141 FNP License Amendment Request dated October 29, 2010 Submittal Corrections Revised Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups

Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance TSTF-425 FNP Units 1 Description and 2 I

Shutdown Margin (SDM) 3.1.1 3.1.1 I

! Verify SDM to be within the limits specified in the COLR 3.1.1.1 3.1.1.1 I Core Reactivity 3.1.2 3.1.2 Verify measured core reactivity 3.1.2.1 3.1.2.1 Rod Group Alignment Limits 3.1.4 3.1.4 I

Verify individual rod positions within alignment limit.

3.1.4.1 3.1.4.1 i

Verify rod freedom of movement (trippability) 3.1.4.2 3.1.4.2 Shutdown Bank Insertion Limits 3.1.5 3.1.5 I Verify each shutdown bank is within the insertion limits specified 3.1.5.1 3.1.5.1 in the COLR.

Control Bank Insertion Limits 3.1.6 3.1.6 I

Verify each control bank insertion is within the insertion limits 3.1.6.2 3.1.6.2 specified in the COLA.

I Verify sequence and overlap limits specified in the COLR 3.1.6.3 3.1.6.3 Physics Tests Exceptions MODE 2 3.1.8 3.1.8 Verify the RCS lowest loop average temperature 3.1.8.2 3.1.8.2 i

Verify THERMAL POWER 3.1.8.3 3.1.8.3 Verify SDM is within the limits specified in the COLA.

3.1.8.4 3.1.8.4 Fa(Z) 3.2.1 3.2.1 Verify Fa(Z) is within steady state limit.

3.2.1.1 3.2.1.1 i

Verify Fo(Z) is within the transient limit.

3.2.1.2 3.2.1.2 I

FNAH 3.2.2 3.2.2

Verify FNt.H is within limits specified in the COLA.

3.2.2.1 3.2.2.1 AFD 3.2.3 3.2.3 I

Verify AFD within limits for each OPERABLE excore channel 3.2.3.1 3.2.3.1 QPTR 3.2.4 3.2.4 Verify QPTR is within limit by calculation 3.2.4.1 3.2.4.1 Verify QPTR is within limit using the movable incore detectors.

3.2.4.2 Confirm that the normalized symmetric power distribution is 3.2.4.2 I

consistent with QPTA.

i RTS Instrumentation 3.3.1 3.3.1 I

Perform CHANNEL CHECK.

3.3.1.1 3.3.1.1 Compare results of calorimetric heat balance calculation to 3.3.1.2 3.3.1.2 power range channel output.

Compare results of the incore detector measurements to 3.3.1.3 3.3.1.3

Nuclear Instrumentation System (NIS) AFD.

Perform T ADOT 3.3.1.4 3.3.1.4 Perform ACTUATION LOGIC TEST 3.3.1.5 3.3.1.5 Perform TADOT 3.3.1.6 Calibrate excore channels to agree with incore detector 3.3.1.6 13.3.1.9 measurements.

Perform COT 3.3.1.7 3.3.1.7 Perform COT 3.3.1.8 3.3.1.8 Perform T ADOT 3.3.1.9 Perform CHANNEL CALIBRATION.

3.3.1.10 3.3.1.10 Perform CHANNEL CALIBRATION.

3.3.1.11 Perform CHANNEL CALIBRATION 3.3.1.12 E1-4

Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Description Perform COT Perform TADOT i Perform T ADOT

Verify RTS RESPONSE TIME is within limits ESFAS Instrumentation Perform CHANNEL CHECK Perform ACTUATION LOGIC TEST

Perform ACTUATION LOGIC TEST Perform MASTER RELAY TEST Perform COT Perform SLAVE RELAY TEST Perform T ADOT Perform T ADOT

Perform CHANNEL CALIBRATION.

i Verify ESFAS RESPONSE TIMES are within limit.

PAM Instrumentation Perform CHANNEL CHECK for each required instrumentation channel that is normally energized.

Perform CHANNEL CALIBRATION

Remote Shutdown System i Perform CHANNEL CHECK Verify each required control circuit and transfer switch is capable of performing the intended function Perform CHANNEL CALIBRATION for each required instrumentation channel.

Perform T ADOT of the reactor trip breaker open/closed indication.

LOP DG Start Instrumentation Perform CHANNEL CHECK Perform T ADOT Perform CHANNEL CALIBRATION Verify ESF RESPONSE TIME within limit.

Containment Purge and Exhaust Isolation Instrumentation Perform CHANNEL CHECK Perform ACTUATION LOGIC TEST

Perform MASTER RELAY TEST Perform ACTUATION LOGIC TEST Perform MASTER RELAY TEST Perform COT Perform SLAVE RELAY TEST Perform TADOT Perform CHANNEL CALIBRATION Verify ESF RESPONSE TIME within limit.

CREFS Actuation Instrumentation Perform CHANNEL CHECK Perform COT Perform ACTUATION LOGIC TEST TSTF-425 3.3.1.13 3.3.1.14 3.3.1.15 3.3.1.16 3.3.2 3.3.2.1 3.3.2.2 3.3.2.3 3.3.2.4 3.3.2.5 3.3.2.6 3.3.2.7 3.3.2.8 3.3.2.9 3.3.2.10 3.3.3 3.3.3.1 3.3.3.2 3.3.4 3.3.4.1 3.3.4.2 3.3.4.3 3.3.4.4 3.3.5 3.3.5.1 3.3.5.2 3.3.5.3 3.3.6 3.3.6.1 3.3.6.2 3.3.6.3 3.3.6.4 3.3.6.5 3.3.6.6 3.3.6.7 3.3.6.8 3.3.6.9 3.3.7 3.3.7.1 3.3.7.2 3.3.7.3 FNP Units 1 and2 3.3.1.11 3.3.1.12 3.3.1.14 3.3.2 3.3.2.1 3.3.2.2 3.3.2.3 3.3.2.4 3.3.2.8 3.3.2.5 3.3.2.6 3.3.2.7 3.3.2.9 3.3.3 3.3.3.1 3.3.3.2 3.3.4 3.3.4.1 3.3.4.2 3.3.4.3 3.3.5 3.3.5.1 3.3.5.2 3.3.5.3 3.3.6 3.3.6.1 I

3.3.6.2 I

3.3.6.3 3.3.6.4 3.3.6.5 3.3.6.6 3.3.6.7 3.3.6.8 3.3.7 I

3.3.7.1 3.3.7.2 3.3.7.3 E1-5 I

i Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Description I Perform MASTER RELAY TEST Perform ACTUATION LOGIC TEST Perform MASTER RELAY TEST Perform SLAVE RELAY TEST Perform T ADOT Perform CHANNEL CALIBRATION i PRF Actuation Instrumentation i Perform CHANNEL CHECK Perform COT Perform ACTUATION LOGIC TEST Perform MASTER RELAY TEST Perform SLAVE RELAY TEST Perform T ADOT

. Perform CHANNEL CALIBRATION FBACS Actuation Instrumentation Perform CHANNEL CHECK Perform COT Perform ACTUATION LOGIC TEST Perform T ADOT Perform CHANNEL CALIBRATION BOPS Perform CHANNEL CHECK Perform COT Perform CHANNEL CALIBRATION RCS Pressure, Temperature, and Flow DNB Limits Verify pressurizer pressure Verify RCS average temperature Verify RCS total flow

Verify by measurement that RCS total flow rate I Verify by precision heat balance that RCS total flow Reactor Coolant System (RCS)

Verify RCS Tava in each loop RCS PIT Limits Verify RCS pressure, RCS temperature, and RCS heatup and cooldown rates are within the limits specified in the PTLR.

RCS Loops MODES 1 and 2

. Verify each RCS loop is in operation.

i RCS Loops MODES 3 Verify required RCS loops are in operation.

Verify steam generator secondary side water levels Verify correct breaker alignment and indicated power RCS Loops MODES 4 Verify required RHR or RCS loop is in operation.

Verify SG secondary side water levels Verify correct breaker alignment and indicated power are available to each required pump.

RCS Loops - MODE 5, Loops Filled E1-6 TSTF-425 3.3.7.4 3.3.7.5 3.3.7.6 3.3.7.7 3.3.7.8 3.3.7.9 3.3.8 3.3.8.1 3.3.8.2 3.3.8.3 3.3.8.4 3.3.8.5 3.3.9 3.3.9.1 3.3.9.2 3.3.9.3 3.4.1 3.4.1.1 3.4.1.2 3.4.1.3 3.4.1.4 3.4.2 3.4.2.1 3.4.3 3.4.3.1 3.4.4 3.4.4.1 3.4.5 3.4.5.1 3.4.5.2 3.4.5.3 3.4.6 3.4.6.1 3.4.6.2 3.4.6.3 3.4.7 FNP Units 1 and 2 3.3.7.4 3.3.7.5 3.3.7.6 3.3.7.7 3.3.8 3.3.8.1 3.3.8.2 3.3.8.3 3.3.8.4 3.3.8.5 3.3.8.6 3.3.8.7 3.4.1 3.4.1.1 3.4.1.2 3.4.1.3 3.4.1.4 3.4.3 3.4.3.1 3.4.4 3.4.4.1 3.4.5 3.4.5.1 3.4.5.2 3.4.5.3 3.4.6 3.4.6.1 3.4.6.2 3.4.6.3 3.4.7

Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Description Verify required RHR loop is in operation.

Verify SG secondary side water level Verify correct breaker alignment and indicated power are available to each required RHR pump.

ReS Loops - MODE 5, Loops Not Filled Verify required RHR loop is in operation.

Verify correct breaker alignment and indicated power are available to each required RHR pump.

Pressurizer Verify pressurizer water level Verify capacity of each required group of pressurizer heaters Verify required pressurizer heaters are capable of being powered from an emergency power supply.

Pressurizer PORVs Perform a complete cycle of each block valve.

Perform a complete cycle of each PORV.

Perform a complete cycle of each PORV using the backup PO RV control system.

Perform a complete cycle of each solenoid air control valve and check valve on the air accumulators in PORV control systems.

Verify PORVs and block valves are capable of being powered from emergency power sources.

LTOP System Verify a maximum of [one] [HPI] pump is capable of injecting into the RCS.

Verify a maximum of one charging pump is capable of injecting into the RCS.

Verify each accumulator is isolated.

Verify RHR suction valve is open for each required RHR suction relief valve Verify required RCS vent ~ r2.071 square inches open.

Verify each required RHR suction relief valve setpoint.

Verify PORV block valve is open for each required PORV.

Verify associated RHR suction isolation valve is locked open with operator power removed for each required RHR suction relief valve.

Perform a COT on each required PORV, excluding actuation.

Perform CHANNEL CALIBRATION for each required POAV actuation channel.

ReS Operational LEAKAGE Verify RCS operational LEAKAGE is within limits by performance of RCS water inventory balance.

Verify primary to secondary LEAKAGE ReS PIV Leakage Verify leakage from each RCS PIV Verify RHA System auto closure interlock prevents the valves I from being opened with a simulated or actual RCS pressure E1-7 TSTF-425 3.4.7.1 3.4.7.2 3.4.7.3 3.4.8 3.4.8.1 3.4.8.2 3.4.9 3.4.9.1 3.4.9.2 3.4.9.3 3.4.11 3.4.11.1 3.4.11.2 3.4.11.3 3.4.11.4 3.4.12 3.4.12.1 3.4.12.2.

3.4.12.3 3.4.12.4 3.4.12.5 3.4.12.6 3.4.12.7 3.4.12.8 3.4.12.9 3.4.13 3.4.13.1 3.4.13.2 3.4.14 3.4.14.1 3.4.14.2 FNP Units 1 and 2 3.4.7.1 3.4.7.2 3.4.7.3 3.4.8 3.4.8.1 3.4.8.2 3.4.9 3.4.9.1 3.4.9.2 3.4.9.3 3.4.11 3.4.11.1 3.4.11.2 3.4.11.3 3.4.12 3.4.12.1 3.4.12.2 3.4.12.3 3.4.12.4 3.4.12.5 3.4.13 3.4.13.1 3.4.13.2 3.4.14 3.4.14.2 i

Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Description SlQnal Verify RHR System auto closure interlock causes the valves to close automatically with a simulated or actual RCS pressure

. signal RCS Leakage Detection Instrumentation Perform CHANNEL CHECK of the required containment atmosphere radioactivity monitor.

Perform COT of the required containment atmosphere radioactivity monitor.

Perform CHANNEL CALIBRATION of the required containment sump monitor.

Perform CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor.

Perform CHANNEL CALIBRATION of the required containment air cooler condensate flow rate monitor.

RCS Specific Activity Verify reactor coolant gross specific activity Verify reactor coolant DOSE EQUIVALENT 1-131 specific I activity Determine E from a sample taken in MODE 1 RCS Loop Isolation Valves Verify each RCS loop isolation valve is open and power is removed from each loop isolation valve operator RCS Loops - Test Exceptions Verify THERMAL POWER Accumulators Verify each accumulator isolation valve is fully open Verify borated water volume in each accumulator Verify nitrogen cover pressure in each accumulator Verify boron concentration in each accumulator Verify power is removed from each accumulator isolation valve operator when RCS pressure ECCS - Operating Verify the following valves are in the listed position with power to the valve operator removed.

Verify each ECCS manual, power operated, and automatic valve in the flow path, Verify ECCS piping is full of water.

Verify each ECCS automatic valve in the flow path Verify each ECCS pump starts automatically Verify, for each ECCS throttle valve Verify, by visual inspection, each ECCS train containment sump suction inlet ECCS - Shutdown Verify the following valves are in the listed position with power to the valve operator removed.

RWST E1-8 TSTF-425 3.4.12.3 3.4.15 3.4.15.1 3.4.15.2 3.4.15.3 3.4.15.4 3.4.15.5 3.4.16 3.4.16.1 3.4.16.2 3.4.16.3 3.4.17 3.4.17.1 3.4.19 3.4.19.1 3.5.1 3.5.1.1 3.5.1.2 3.5.1.3 3.5.1.4 3.5.1.5 3.5.2 3.5.2.1 3.5.2.2 3.5.2.3 3.5.2.5 3.5.2.6 3.5.2.7 3.5.2.8 3.5.4 FNP Units 1 and 2 3.4.14.3 3.4.15 3.4.15.1 3.4.15.2 3.4.15.3 3.4.15.4 3.4.16 3.4.16.1 3.4.16.2 3.4.16.3 i

3.5.1 3.5.1.1 3.5.1.2 3.5.1.3 3.5.1.4 3.5.1.5 i

3.5.2 3.5.2.1 I

3.5.2.2 3.5.2.4 3.5.2.5 3.5.2.6 3.5.2.7 3.5.3 3.5.3.2 3.5.4 I

Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Description Verify RWST borated water temperature Verify RWST borated water volume Verify RWST boron concentration Seal Injection Flow Verify manual seal injection throttle valves are adjusted

Eccs Recirculation Fluid pH Control System Perform a visual inspection of the ECCS Recirculation Fluid pH Control System and verify BIT Verify BIT borated water temperature Verify BIT borated water volume Verify BIT boron Containment Air Locks (Atmospheric, Subatmospheric, Ice Condenser, and Dual)

Verify only one door in the air lock can be opened at a time.

Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)

I Verify each [42] inch purge valve is sealed closed,

Verify each [81 inch purQe valve is closed

Verify each containment isolation manual valve and blind flange Cycle each weight or spring loaded check valve Perform leakaQe rate testinQ for containment purQe valves Verify each automatic containment isolation valve Cycle each weight or spring loaded check Verify each [ ] inch containment purge valve is blocked to restrict the valve from openinQ Verify the combined leakage rate for all shield building bypass leakaQe paths Containment Pressure Verify containment pressure is within limits.

Containment Air Temperature Verify containment average air temperature is within limits Containment Spray and Cooling Systems Verify each containment spray manual, power operated, and automatic valve Operate each required containment coolinQ train fan unit Verify each containment cooling train cooling water flow rate Verify each automatic containment spray valve in the flow path Verify each containment spray pump starts automatically on an actual or simulated actuation siQnal.

Verify each containment coolinQ train starts automatically Verify each spray nozzle is unobstructed.

Spray Additive System (Atmospheric, Subatmospheric, Ice Condenser, and Dual)

Verify each spray additive manual, power operated, and automatic valve in the flow path Verify spray additive tank solution volume TSTF-425 3.5.4.1 3.5.4.2 3.5.4.3 3.5.5 3.5.5.1 3.5.6 3.5.6.1 3.5.6.2 3.5.6.3 3.6.2 3.6.2.2 3.6.3 3.6.3.1 3.6.3.2 3.6.3.3 3.6.3.6 3.6.3.7 3.6.3.8 3.6.3.9 3.6.3.10 3.6.3.11 3.6.4 3.6.4.1 3.6.5 3.6.5.1 3.6.7 3.6.7.1 3.6.7.2 FNP Units 1 and 2 3.5.4.1 3.5.4.2 3.5.4.3 3.5.5 3.5.5.1 3.5.6 3.5.6.1 i

I I

3.6.2 3.6.2.2 3.6.3 3.6.3.1 3.6.3.2 3.6.3.5 3.6.3.6 i

I i

3.6.4 3.6.4.1 3.6.5 3.6.5.1 3.6.6 3.6.6.1 I

3.6.6.2 3.6.6.3 3.6.6.5 3.6.6.6 3.6.6.7 3.6.6.8 E1-9

Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance TSTF-425 FNP Units 1 Description and 2 I

Verify spray additive tank [NaOH] solution 3.6.7.3 i

Verity each spray additive automatic valve in the flow path.

3.6.7.4 Verify spray additive flow [rate] from each solution's flow path.

3.6.7.5 Shield Building (Dual and Ice Condenser) 3.6.8 Verify annulus negative pressure 3.6.8.1 Verify shield building structural integrity 3.6.8.2 Verify the shield building can be maintained 3.6.8.3 HMS (Atmospheric, Ice Condenser and Dual) 3.6.9 3.6.8 i

Operate each HMS train for;::: 15 minutes.

3.6.9.1 3.6.8.1 Verify each HMS train flow rate on slow speed 3.6.9.2 3.6.8.2 Verify each HMS train starts on an actual or simulated actuation 3.6.9.3 3.6.8.3 i signal.

HIS (Ice Condenser) 3.6.10 Energize each HIS train power supply breaker and verify 3.6.10.1 Verify at least one hydrogen ignitor is OPERABLE in each 3.6.10.2 containment region.

Energize each hydrogen ignitor and verify temperature 3.6.10.3 I

Reactor Cavity Hydrogen Dilution System 3.6.9 Operate each Reactor Cavity Hydrogen Dilution train 3.6.9.1 i

i Verify each Reactor Cavity Hydrogen Dilution train 3.6.9.2 i ICS (Atmospheric and Subatmoapheric) 3.6.11 Operate each ICS train 3.6.11.1 Verify each ICS train actuates on an actual or simulated 3.6.11.3 actuation signal.

I Verify each ICS filter bypass damper can be opened 3.6.11.4 SBACE (Dual and Ice Condenser) 3.6.13 I

Operate each SBACS train 3.6.13.1 Verify each SBAC train actuates on an actual or simulated 3.6.13.3 actuation signal

Verify each SBACS filter bypass damper can be opened.

3.6.13.4 Verify each SBACS train 'flow rate 3.6.13.5 ARS (Ice Condenser) 3.6.14 Verify each ARS fan starts on an actual or simulated actuation 3.6.14.1

signal Verify, with the ARS fan dampers closed, each ARS fan motor 3.6.14.2

! Verify, with the ARS fan not operating, 3.6.14.3 Verify each motor operated valve in the hydrogen collection 3.6.14.4 header Ice Bed (Ice Condenser) 3.6.15 Verify maximum ice bed temperature 3.6.15.1 Verify total mass of stored ice...

3.6.15.2

Verify that the ice mass of each basket sampled 3.6.15.3 i

Verify, by visual inspection, accumulation of ice on structural 3.6.15.4

members Verify, by chemical analysis of the stored ice in at least one 3.6.15.5 randomly selected ice basket from each ice condenser bay, that ice bed:

E1-10

Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance TSTF-425 FNP Units 1 I

Description and 2 Visually inspect, for detrimental structural wear, cracks, 3.6.15.6 corrosion, or other damage, two ice baskets from each group of bays Verify, by chemical analysis, that ice added to the ice condenser 3.6.15.7 meets the boron concentration and pH requirements of SR 3.6.15.5.

Ice Condenser Doors (Ice Condenser) 3.6.16 Verify all inlet doors indicate closed by the Inlet Door Position 3.6.16.1 I

Monitoring System.

Verify, by visual inspection, each intermediate deck door is 3.6.16.2 i closed and not impaired by ice, frost, or debris.

I Verify, by visual inspection, each inlet door is not impaired by 3.6.16.3 ice, frost, or debris.

i Verify torq ue 3.6.16.4 Perform a torque test 3.6.16.5 Verify for each intermediate deck door 3.6.16.6 I

Verify, by visual inspection, each top deck [door]

3.6.16.7 Divider Barrier Integrity (Ice Condenser) 3.6.17 I

Verify, by visual inspection, that the seals and sealing surfaces 3.6.17.2 of each personnel access door and equipment hatch I

Remove two divider barrier seal test coupons and verify 3.6.17.4

Visually inspect 3.6.17.5 i Containment Recirculation Drains (Ice Condenser) 3.6.18 Verify, by visual inspection 3.6.18.1 Verify for each ice condenser floor drain 3.6.18.2 MSIVs I 3.7.2 Verify each MSIV actuates 3.7.2.2 MFIVs and MFRVs and [Associated Bypass Valves]

3.7.3 I

Verify each MFIV, MFRV 3.7.3.2 ARVs 3.7.4 Verify one complete cycle of each ARV.

3.7.4.1 Verify one complete cycle of at least one manual isolation valve 3.7.4.2 in each ARV Line.

I ADVs 3.7.4 Verify one complete cycle of each ADV.

3.7.4.1 Verify one complete cycle of each ADV block valve.

3.7.4.2 AFWSystem 3.7.5 3.7.5

Verify each AFW manual, power operated, and automatic valve 3.7.5.1 3.7.5.1

in each water flow path,

Verify each AFW automatic valve that is not locked 3.7.5.3 3.7.5.3 Verify each AFW pump starts automatically 3.7.5.4 3.7.5.4 Verify the turbine driven AFW pump steam admission valves 3.7.5.5 open when air is supplied from their respective air accumulators.

CST 3.7.6 3.7.6 Verify the CST level 3.7.6.1 3.7.6.1 CCWSystem 3.7.7 3.7.7 Verify each CCW manual, power operated, and automatic valve 3.7.7.1 3.7.7.1 E1-11

Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups i

Technical Specification Section Title/Surveillance

, TSTF-425 FNP Units 1 I Description and 2 I

Verify each CCW automatic valve in the flow 3.7.7.2 3.7.7.2 Verify each CCW pump starts automatically on an actual or 3.7.7.3 3.7.7.3

. simulated actuation signal.

j i SWS 3.7.8 3.7.8 Verify each SWS manual, power operated, and automatic valve 3.7.8.1 3.7.8.1 I

in the flow path servicing safety related equipment i

Verify each SWS automatic valve in the flow path 3.7.8.2 3.7.8.2 Verify each SWS pump starts 3.7.8.3 3.7.8.3 Verify the integrity of the SWS buried piping by visual inspection 3.7.8.4 of the ground area.

UHS 3.7.9 3.7.9

Verify water level of UHS 3.7.9.1 3.7.9.1 Verify average water temperature of UHS 3.7.9.2 3.7.9.2 i

Operate each cooling tower fan 3.7.9.3 Verify each cooling tower fan starts automatically on an actual 3.7.9.4 i

or simulated actuation signal.

i Control Room 3.7.10 i

Operate each CREFS Pressurization train 3.7.10.1 Verify each CREFS train actuates 3.7.10.3 I

CREFS 3.7.10 i

Operate each CREFS train 3.7.10.1 Verify each CREFS train actuates 3.7.10.3 Verify one CREFS train can maintain positive pressure 3.7.10.4 I

CRACS 3.7.11 Verify each CRACS train 3.7.11.1 i

CREATCS 3.7.11 I

i Verify each CREATCS train 3.7.11.1 iPRF 3.7.12 Verify two PRF trains aligned to the SFPR.

3.7.12.1 Operate each PRF train 3.7.12.2 I

Verify each PRF train actuates 3.7.12.4 i

i i

Verify one PRF train can maintain a pressure 3.7.12.5 i Verify one PRF train can maintain a slightly negative pressure 3.7.12.6 I

i ECCS PREACS 3.7.12 i

Operate each ECCS PREACS train 3.7.12.1 I

Verify each ECCS PREACS train actuates 3.7.12.3 i

Verify one ECCS PREACS train can maintain a pressure 3.7.12.4 i

Verify each ECCS PREACS filter bypass damper can be closed 3.7.12.5

FBACS 3.7.13 Operate each FBACS train 3.7.13.1 I

Verify each FBACS train actuates 3.7.13.3 I

Verify one FBACS train can maintain a pressure 3.7.13.4 i

Verify each FBACS filter bypass damper can be closed 3.7.13.5 PREACS 3.7.14 Operate each PREACS train 3.7.14.1 Verify each PREACS train actuates 3.7.14.3 Verify one PREACS train can maintain a pressure 3.7.14.4 E1-12

Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Description Verify each PREACS filter bypass damper can be closed Fuel Storage Pool Water Level Verify the fuel storaqe pool water level Fuel Storage Pool Boron Concentration Verify the fuel storage pool boron concentration is within limit.

Secondary Specific Activity Verify the specific activity Cask Storage Area Boron Concentration Cask Loading Operations Verify the cask storage area boron concentration is within limit.

ESF Room Coolers Verify each ESF Room Cooler system manual valve servicing safety-related equipment Verify each ESF Room Cooler fan starts automatically AC Sources - Operating Verify correct breaker alignment and indicated power availability for each [required] oftsite circuit.

Verify each DG starts from standby conditions Verify each DG is synchronized and loaded and operates Verify each day tank Check for and remove accumulated water from each day tank I Verify the fuel oil transfer system operates Verify each DG starts from standby Verify [automatic [and] manual] transfer of AC power sources Verify each DG rejects a load greater than or equal to its associated single largest post-accident load Verify each DG does not trip and voltage is maintained Verify on an actual or simulated loss of oftsite power signal Verify on an actual or simulated Engineered Safety Feature (ESF) actuation Signal each DG auto-starts from standby condition Verify each DG's noncritical automatic trips are bypassed Verify each DG's automatic trips are bypassed Verify each DG operates Verify each DG starts and achieves...

TSTF-425 3.7.14.5 3.7.15 3.7.15.1 3.7.16 3.7.16.1 3.7.18 3.7.18.1 3.8.1 3.8.1.1 3.8.1.2 3.8.1.3 3.8.1.4 3.8.1.5 3.8.1.6 3.8.1.7 3.8.1.8 3.8.1.9 3.8.1.10 3.8.1.11 3.8.1.12 3.8.1.13 3.8.1.14 3.8.1.15 FNP Units 1 and 2 I

3.7.13 3.7.13.1 3.7.14 I

3.7.14.1 3.7.16 3.7.16.1 3.7.17 I

3.7.17.1 3.7.19 3.7.19.1 I

3.7.19.2 3.8.1 3.8.1.1 I

3.8.1.2 I

3.8.1.3 3.8.1.4 I

3.8.1.5 I

3.8.1.6 3.8.1.7 3.8.1.8 3.8.1.9 I

3.8.1.10 3.8.1.11 3.8.1.12 3.8.1.13 E1-13

Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Descri ption Verify each DG Verify, with a DG operating in test mode and connected to its bus, an actual or simulated ESF actuation signal overrides the test mode Verify interval between each sequenced load block Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal Verify each DG does not trip and voltage I Verify when started simultaneously from standby condition Diesel Fuel Oil, Lube Oil, and Starting Air Verify each fuel oil storage tank Verify lubricating oil inventory Verify each DG air start receiver pressure Check for and remove accumulated water from each fuel oil storage tank.

DC Sources* Operating Verify battery terminal voltage Verify no visible corrosion at battery terminal Verify battery celis, cell plates, and racks show no visual indication of physical damage or abnormal deterioration.

! Remove visible terminal corrosion, verify battery cell-to-cell and terminal connections are coated with anti-corrosion material.

i Verify post-to-post battery connection resistance

! Verify each required Auxiliary Building battery Verify battery capaCity i Verify each battery charge Verify battery capacity Battery Cell Parameters Verify battery cell parameters Verify battery cell parameters Verify average electrolyte temperature of representative cells Battery Parameters Verify each battery float current I Verify each battery pilot cell voltage Verify each battery connected cell electrolyte level Verify each battery pilot cell temperature Verify each battery connected cell voltage Verify battery capacity Eerters - Operating Verify correct inverter voltage, [frequency]. And alignment to required AC vital buses Inverters - Shutdown Verify correct inverter voltage, [frequency,] and alignments to TSTF-425 3.8.1.16 3.8.1.17 3.8.1.18 3.8.1.19 3.8.1.20 3.S.3 3.8.3.1 3.8.3.2 3.8.3.4 3.8.3.5 3.S.4 3.8.4.1 3.8.4.2 3.8.4.3 3.8.6 3.8.6.1 3.8.6.2 3.8.6.3 3.8.6.4 3.8.6.5 3.8.6.6 3.S.7 3.8.7.1 3.S.S 3.8.8.1 FNP Units 1 and 2 3.8.1.14 3.8.1.15 I

3.8.1.16 3.8.1.17 3.8.1.18 3.8.1.19 I

3.S.3 3.8.3.1 3.8.3.2 3.8.3.4 3.S.4 3.8.4.1 3.8.4.2 3.8.4.3 3.8.4.4 3.8.4.5 3.8.4.6 3.8.4.7 3.8.4.8 3.S.6 3.8.6.1 3.8.6.2 3.8.6.3 3.8.7 3.8.7.1 13.8.8.1 E1-14

i Technical Specification Cross Reference for FNP Units 1 and 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Description required AC vital buses.

Distribution Systems - Operating Verify correct breaker alignments and voltage to [required] AC, DC, and AC vital bus electrical power distribution subsystems.

Distribution Systems - Shutdown Verify correct breaker alignments and voltage to required AC, DC, and AC vital bus electrical power distribution subsystems.

Boron Concentration Verify boron concentration is within the limit specified in the COLR.

Unborated Water Source Isolation Water Verify each valve that isolates unborated water sources is secured in the closed position.

Nuclear Instrumentation Perform CHANNEL CHECK Perform CHANNEL CALIBRATION Containment Penetrations Verify each required containment penetration is in the required status.

Verify each required containment purge and exhaust valve actuates to the isolation position on an actual or simulated actuation siqnal.

Verify the capability to install the equipment hatch.

RHR and Coolant Circulation - High Water Level Verify one RHR loop is in operation and circulating reactor coolant at a flow rate RHR and Coolant Circulation - Low Water Level Verify one RHR loop is in operation and circulating reactor coolant at a flow rate Verify correct breaker alignment and indicated power available to the required RHR pump that is not in operation.

Refueling Cavity Water Level Verify refueling cavity water level TSTF-425 FNP Units 1 and 2 3.8.9 3.8.9 3.8.9.1 3.8.9.1 3.8.10 3.8.10 3.8.10.1 3.8.10.1 3.9.1 3.9.1 3.9.1.1 3.9.1.1 3.9.2 3.9.2.1 3.9.3 3.9.2 3.9.3.1 3.9.2.1 3.9.3.2 3.9.2.2 3.9.4 3.9.3 3.9.4.1 3.9.3.1 3.9.4.2 3.9.3.2 3.9.3.3 3.9.5 3.9.4 3.9.5.1 3.9.4.1 3.9.6 3.9.5 3.9.6.1 3.9.5.1 3.9.6.2 3.9.5.2 3.9.7 3.9.6 3.9.7.1 3.9.6.1 E1-15 to NL-11-0141 FNP License Amendment Request dated October 29, 2010 Submittal Corrections Revised marked-up and clean typed pages for FNP SR 3.4.11.4.

E1-16

Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS SR 3.4.11.2 SR 3.4.11.3 SR 3.4.11.4 SURVEILLANCE

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

Not required to be performed prior to entry into MODE 3.

Perform a complete cycle of each PORV during MODE3 or 4.

Perform a complete cycle of each PORV using the backup PORV control system.

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

Required to be performed only for Unit 2 for the remainder of operating cycle 16.

Check power available to the Unit Two PORV block valve Q2B31 MOV8000B.

FREQUENCY

!18 months! +-1 Insert 1

!18 months!......, Insert 1 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Farley Units 1 and 2 3.4.11-4 Amendment No. ~ (Unit 1)

Amendment No. ~ (Unit 2)

3.4.11 Pressurizer PORVs SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.2

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

Not required to be performed prior to entry into MODE 3.

In accordance with Perform a complete cycle of each PORV during the Surveillance MODE30r 4.

Frequency Control Program SR 3.4.11.3 Perform a complete cycle of each PORV using the I n accordance with backup PORV control system.

the Surveillance Frequency Control Program SR 3.4.11.4

No-rE--------------------------------

Required to be performed only for Unit 2 for the remainder of operating cycle 16.

Check power available to the Unit Two PORV block 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months valve Q2631 MOV80006.

Farley Units 1 and 2 3.4.11-4 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

Supplement to Licensing Amendment Request for Joseph M. Farley Nuclear Plant and Edwin I. Hatch Nuclear Plant to Implement Technical Specification Task Force 425 - A, Revision 3 HNP License Amendment Request Dated October 29,2010 Submittal Corrections to NL-11-0141 HNP License Amendment Request dated October 29, 2010 Submittal Corrections contains the following revisions to the HNP License Amendment Request dated October 29, 2010 submittal.

Editorial Error SR 3.1.7.3 (HNP Units 1 and 2) and SR 3.6.1.3.12 (HNP Unit 1) were inadvertently excluded from the Technical Specification Cross Reference for HNP Units 1 and 2 and TSTF 425 Mark ups.

The marked-up page for SR 3.1.7.5 was missing the "Insert 1" Identifier in the HNP TSTF 425 Licensing Amendment Request.

The marked-up and clean typed pages for SR 3.4.9.5 and SR 3.4.9.6 were inadvertently not included in the submittal for Unit 2 only (Unit 1 marked-up and clean types pages were included in the submittal); however, SR 3.4.9.5 and SR 3.4.9.6 were included in the Technical Specification Cross Reference for HNP Units 1 and 2 and TSTF 425 Mark ups.

Table 2 containing the 10 "Supporting Requirements (SRs) Not Met" and the five CAT I SRs findings and resolutions that resulted from the Regulatory Guide (RG) 1.200 PRA peer review only listed the word "finding" and not a description of the finding.

Resolution SR 3.1.7.3 (HNP Units 1 and 2) and SR 3.6.1.3.12 (HNP Unit 1) added to the Technical Specification Cross Reference for HNP Units 1 and 2. A revised cross reference table is included in Enclosure 1.

A revised SR 3.1.7.5 marked-up page is included in Enclosure 2.

Revised marked-up and clean typed pages are included in Enclosure 2 for SR 3.4.9.5 and SR 3.4.9.6 for Unit 2 only.

A description of the finding from the RG 1.200 peer review was added to Table 2 and is being resubmitted.

E2-2 to NL-11-0141 HNP License Amendment Request dated October 29, 2010 Submittal Corrections Revised Documentation of PRA Technical Adequacy for HNP E2-3

Documentation of PRA Technical Adequacy I~~~ ~

~"

Table 2 Resolution of the Hatch PRA Peer Review F&Os associated 10 "SR not Met" SRs F&O#

Review LeveP Resolution The Status of Resolution by the SNC Element IE-A6-1-2 IE-A6 Reviewed I E Notebook.

Include the additionallEs in the The IEs identified in the notebook have been (SR not Section 6, 3.16, Appendix A.

analysis. It would appear panel added to the model as well as the common met CC-II)

The FMEA that was failures would be very unlikely cause failure considerations. Two of the performed identified except for specific types of buses were not modeled as IEs because numerous IEs resulting from events, especially spatially they serve only to feed two that were added failure of individual or multiple related events.

as IEs. The two buses not modeled as IEs electrical panels, however, are modeled as support for systems; one of these IEs were not included the supported systems is in itself modeled as in the analysis. The notebook a special initiator. The special initiator indicates that these new IEs modeling for the Hatch PRA not only would be considered in a considers what causes a transient/scram but future revision of the PRA.

also what would require a shutdown per Technical Specifications.

IE-B2-1-7 IE-B2 Reviewed the II:::. Notebook Describe the process for The IE notebook has been revised to include (SR CC-and found that the grouping systematically grouping the IEs to a full discussion of IE grouping. This 1111/111 Not process for the IEs was not ensure:

comment has been addressed.

met) provided as required by the SR. Selection and screening, (a) Events can be considered modeling and quantification similar in terms of plant response, process are included, success criteria, timing, and the however effect on the operability and performance of operators and relevant mitigating systems: or (b) Events can be subsumed into a group and bounded by the worst case impacts within the new group.

E2-4

Documentation of PRA Technical Adequacy Table 2 Resolution of the Hatch PRA Peer Review F&Os associated 10 "SR not Met" SRs

~~~~~~~~~~~~

~

~ ~~~~-

,-----~~~~

~

F&O#

Review Levell Resolution The Status of Resolution by the SNC Element IE-BS-1-7 IE-BS Reviewed the IE Notebook Describe the process for This comment has been added to the IE (SR Not and found that the grouping systematically grouping IEs to notebook. There are no subsumed events in met CC II) process for the I Es was not ensure:

the Hatch PRA model.

provided as required by the SR. Selection and screening, (a) Events can be considered modeling and quantification similar in terms of plant response, process are included, success criteria, timing, and the however.

effect on the operability and performance of operators and relevant mitigating systems; or (b) Events can be subsumed into a group and bounded by the worst case impacts within the new group.

E2-5

Documentation of PRA Technical Adequacy Table 2 Resolution of the Hatch PRA Peer Review F&Os associated 10 "SR not Met" SRs F&O#

Review Levell Resolution The Status of Resolution by the SNC Element AS-B3-1-9 AS-B3 (SR Reviewed the AS Notebook.

Include additional detail for each The detail required by this finding has been Not met Generally the discussion of accident sequence. Particularly, added to the accident sequence notebook.

CCIIIIIIII) the accident sequence there was no mention of the The sequence descriptions have a modeling is adequate.

generation of harsh environments discussion of Environmental Conditions. The However some affecting temperature, pressure, Hatch PRA does not typically rely on enhancements would be debris, water levels or humidity equipment or operator actions in an area beneficial:

that could impact the success of where a severe environment is encountered.

the system (1) Discussion of environmental conditions associated with sequences.

(2) Interface between accident sequences and plant damage states.

SC-B5-3-1 SC-B5 (SR No evidence could be found Check the reasonableness and A comparison table for the Hatch PRA was Not met in the PRA documentation acceptability of the results of the developed for Success Criteria based on CCI/II/III) that a check for thermal/hydraulic and any other input from other SWR facilities (i.e. Pilgram, reasonableness, as required analysis used to support the Cooper, LaSalle, and Nine Mile POint) by SR SC-S5, was success criteria. Document in performed. Section 4.2 of the the SC Notebook how this SC Notebook states that a reasonableness was performed.

comparison of the success criteria modeled for other SWRs will be performed in a future PRA update.

-~~~~

~

~~~-~~~

E2-6

Documentation of PRA Technical Adequacy Table 2 Resolution of the Hatch PRA Peer Review F&Os associated 10 "SR not Met" SRs F&O#

Review Element SC-C1-5-4 SC-C3 (SR Not met CCI/II/III)

IFSN-A10-IFSN-A10 4-5 (SR Not met CCI/II/II)

Level' The success criteria hierarchy is documented in the PRA SC NOTEBOOK and supplemented in the PRA AS NOTEBOOK and individual system notebooks. However, it is difficult to see which systems are credited for a specific initiating event not to mention which initiators impact a specific system.

In the development process of the flooding scenarios there is no credit taken for the manual isolation of floods.

This approach was assumed to be conservative however, the propagation of flood water would be expanded if no operator action was taken therefore, affecting more areas and SSC's than initially projected.

Resolution The success criteria should be captured in tabular from in the SC document. Having this information in one place will alleviate confusion when performing PRA applications and upgrades. Additionally, it will facilitate peer reviews. Provide a summary of success criteria for available mitigating systems and human actions for each initiating group.

Operator actions should be developed and added to the scenario development and the PRA model to reflect how the plant would be operated in the event of this scenario. It may be beneficial to consider use of mitigation event trees to assure that all mitigation issues are considered.

The Status of Resolution by the SNC A success criteria summary table has been added to the SC notebook. This table in addition to the extreme detail already provided makes the Success Criteria notebook extremely informative.

The PRA model used in the peer review contained over 100 flood initiators. No screening was done based on operator action input. This finding was addressed by screening the initiators to 24 and applying HRA for these scenarios to mitigate the results.

E2-7

Documentation of PRA Technical Adequacy Table 2 Resolution of the Hatch PRA Peer Review F&Os associated 10 "SR not Met" SRs F&O#

Review Level' Resolution The Status of Resolution by the SNC Element I FOU-AS-I FOU-AS In the development process Operator actions should be The PRA model used in the peer review 4-S (SR Not of the flooding scenarios developed and added to the contained over 100 flood initiators. No met there is no credit taken for the scenario development and the screening was done based on operator CCI/IIIIII) manual isolation of floods.

PRA model to reflect how the action input. This finding was addressed by This approach was assumed plant would be operated in the screening the initiators to 24 and applying to be conservative however, event of this scenario. It may be HRA for these scenarios to mitigate the the propagation of flood water beneficial to consider use of results.

would be expanded if no mitigation event trees to assure operator action was taken that all mitigation issues are therefore, affecting more considered.

areas and SSC's than initially projected.

IFOU-A6-IFOU-A6 A very conservative approach Consider more realistic operator This item has been addressed for I FOU-AS 2-7 (SR Not was taken with respect to the actions for floods when action 4-S.

met impact of flooding on operator has to be taken outside the main CCI/JI/II) actions. By reviewing the control room.

model it was determined that all operator actions are failed (set to 1.0) if the action takes place outside the control room and the associated system is impacted by the flood.

-~

.......-.~........._-

......._.-L-

E2-8

Documentation of PRA Technical Adequacy Table 2 Resolution of the Hatch PRA Peer Review F&Os associated 10 "SR not Met" SRs F&O#

Review Level' Resolution The Status of Resolution by the SNC Element MU-C1-5-8 MU-C1 The identified changes in Recommend developing a This comment refers to the model update (SR Not PRA input are prioritized and database for use by PRA. Such process. These procedures are under met Cat then put into the plant's a database should have revision. Presently, model change 1/11/111) corrective action program.

prioritization clearly delineated.

requirements tend to be governed by the use The current process involves This would allow a dynamic of the corrective action program.

a handwritten entry into a assessment of the cumulative diary and a duplicate entry impact of pending changes.

into the plant's corrective Additionally, this will allow the action program. This process more significant changes to be is cumbersome, inefficient, incorporated before less and prone to human errors.

significant ones

,~~"

Table 2 Resolution of the Hatch PRA Peer~view F&Os associated with the 5 CATJmet only SRs F&O#

Review LeveP Resolution The Status of Resolution by the SNC Element LE-C3-7-2 LE-C3 (SR No documentation of Review significant progression Statements have been added to L2 NB Cat I met) review of significant sequences to support evaluations Section 7 of notebooks, as well as Appendix accident progression required in applicable SR K to note that significant accident sequences sequences resulting in Capability Category.

resulting in LERF were reviewed and credit LERF could be found.

for continued operation or repair (beyond LOOP recovery) was not judged to be credible. Cat 1111/111 is considered met for this SA.

E2-9

Documentation of PRA Technical Adequacy Table 2 Resolution of the Hatch PRA Peer Review F&Os associated with the 5 CAT I met only SRs F&O#

Review Element LE-C10-7 LE-C10 (SR 2

Cat I met)

LE-C12-7 LE-C12 (SR 2

Cat I met)

LE-C13-7 LE-C13 (SR 4

Cat I met)

Levell No documentation of review of significant accident progression sequences resulting in LERF could be found.

No documentation of review of significant accident progression sequences resulting in LERF could be found.

Class V sequences are assumed to lead directly to LERF without evaluation of scrubbing of releases.

Resolution Review significant progression sequences to support evaluations required in applicable SR Capability Category Review significant progression sequences to support evaluations required in applicable SR Capability Category Perform a containment bypass analysis as described in SR LE C13 The Status of Resolution by the SNC Statements have been added to L2 NB Section 7 of notebooks as well as Appendix K to note that significant accident sequences resulting in LERF were reviewed and credit for continued operation or repair (beyond LOOP recovery) was not judged to be credible. Cat II is considered met for this SA.

Statements have been added to L2 NB Section 7 of notebooks as well as Appendix K to note that significant accident sequences resulting in LERF were reviewed and credit for continued operation or repair (beyond LOOP recovery) was not judged to be credible. Cat II is considered met for this SA.

Text enhanced in Appendix 0 of notebooks (Footnote 6 added to Table HAS) and similarly in Section 7.7. The analysis regarding scrubbing is approached with engineering judgment. Only scrubbing for low pressure sequences is considered and then the value is low. This basis is acceptable and the use of scrubbing is considered in the uncertainty analysis. Cat 111111 is considered met for this SA.

E2-10

Documentation of PRA Technical Adequacy Table 2 Resolution of the Hatch PRA Peer Review F&Os associated with the 5 CAT I met only SRs F&O#

Review Level' Resolution The Status of Resolution by the SNC Element IE-A9-1-4 IE-A9 (SR Cat Reviewed I E Notebook, Include other sources of OE in Several sources are available to determine I met)

Section 3.1.9, and the search for IE precursors.

plant specific initiating events. When Appendix D. Although preparing the I E notebook, SNC reviewed interviews with plant the following sources. For each source, operations personnel is a appropriate section has also been identified.

source of plant operating experience, the approach

1. Plant Specific Events: [Table 3-4; taken (interview one Appendix C (LERs)]

person) cannot be considered a reasonably

2. Plant Systems: [Appendix B - FMEA]

complete review of plant specific operating

3. LOCA inside Containment [3.2.3]

experience. The SR requires a review of plant

4. LOCA outside Containment [3.2.3]

specific operating experience and there are

5. Multiple Failures [3.1.6]

a variety of OE sources that could have been

6. Interview [3.1.9; Appendix E]

considered but were not (e.g., LERs, SOERs)

As a result of these reviews, additional special initiating events were identified and have been modeled.

E2-11 to NL-11-0141 HNP License Amendment Request dated October 29, 2010 Submittal Corrections Revised Technical Specification Cross Reference for HNP Units 1 and 2 and TSTF 425 Mark ups E2-12

Technical Specification Cross Reference for HNP Unit 1 and Unit 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance TSTF-HNP Unit HNP Unit r

Description*

425 1

2 Control Rod Operability 3.1.3 3.1.3 3.1.3 Control rod position 3.1.3.1 3.1.3.1 3.1.3.1 Notch test - fully withdrawn control rod one notch 3.1.3.2 3.1.3.2 3.1.3.2 Notch test - partially withdrawn control rod one notch 3.1.3.3 3.1.3.3 3.1.3.3 Control Rod Scram Times 3.1.4 3.1.4 3.1.4 Scram time testing 3.1.4.2 3.1.4.2 3.1.4.2 Control Rod Scram Accumulators 3.1.5 3.1.5 3.1.5 Control rod scram accumulator pressure 3.1.5.1 3.1.5.1 3.1.5.1 Rod Pattern Control 3.1.6 3.1.6 3.1.6 Verify control rods comply with BPWS 3.1.6.1 3.1.6.1 3.1.6.1 SLC System 3.1.7 3.1.7 3.1.7 Volume of sodium pentaborate 3.1.7.1 3.1.7.1 3.1.7.1 Temperature of sodium pentaborate 3.1.7.2 3.1.7.2 3.1.7.2 Verify temperature of pump suction 3.1.7.3 3.1.7.3 3.1.7.3 Continuity of explosive charge 3.1.7.4 3.1.7.4 3.1.7.4 Concentration of boron solution 3.1.7.5 3.1.7.5 3.1.7.5 Manual/power operated valve position 3.1.7.6 3.1.7.6 3.1.7.6 Pump flow rate 3.1.7.7 Flow through one SLC subsystem 3.1.7.8 3.1.7.8 3.1.7.8 Heat traced piping is unblocked 3.1.7.9 3.1.7.9 3.1.7.9 I

SDV Vent and Drain Valve 3.1.8 3.1.8 3.1.8 Each SDV vent & drain valve open 3.1.8.1 3.1.8.1 3.1.8.1 I

Cycle each SDV vent & drain valve fully closed/open 3.1.8.2 3.1.8.2 3.1.8.2 position I

Each SDV vent & drain valve closes on receipt of scram 3.1.8.3 3.1.8.3 3.1.8.3 APLHGR 3.2.1 3.2.1 3.2.1 APLHGA less than or equal to limits 3.2.1.1 3.2.1.1 3.2.1.1 MCPR 3.2.2 3.2.2 3.2.2 MCPA greater than or equal to the limits 3.2.2.1 3.2.2.1 3.2.2.1 LHGR 3.2.3 3.2.3 3.2.3 LHGA less than or equal to limits 13.2.3.1 3.2.3.1 3.2.3.1 APRM Gain and Setpoints 3.2.4 MFLPD is within limits 3.2.4.1 APRM setpoints or gains are adjusted for calculated 3.2.4.2 MFLPD RPS Instrumentation 3.3.1.1 3.3.1.1 3.3.1.1 Channel Check 3.3.1.1.1 3.3.1.1.1 3.3.1.1.1 Absolute diff. between APRM channels & calculated power 3.3.1.1.2 3.3.1.1.2 3.3.1.1.2 Adjust channel to conform to calibrated flow 3.3.1.1.3 i

Channel Functional Test (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering Mode 2) 3.3.1.1.4 3.3.1.1.4 3.3.1.1.4 Channel Functional Test 3.3.1.1.5 3.3.1.1.5 3.3.1.1.5 Verify lAM and APRM 3.3.1.1.7 3.3.1.1.7 Calibrate the local power range monitors.

3.3.1.1.6 3.3.1.1.8 3.3.1.1.8 I

I Channel Functional Test 3.3.1.1.7 3.3.1.1.9 3.3.1.1.9 i

Calibrate the trip Units 3.3.1.1.8 Channel Functional test (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering Mode 2) 3.3.1.1.10 3.3.1.1.10 Channel Calibration (for Function 2.a) 3.3.1.1.9 E2-13

i Technical Specification Cross Reference for HNP Unit 1 and Unit 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Description*

Verify Turbine Stop Valve - Closure Perform Channel Functional Test Perform Channel Calibration (for Function 1)

Verify the APRM Flow Biased Simulated Thermal Power Perform Logic System Functional Test Verify the RPS Response Time is within limits Verify OPRM is not bypassed SRM Instrumentation Perform Channel Check Verify an Operable SRM detector is located Perform Channel Check Verify count rate Perform Channel Functional Test Channel Functional Test (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2)

Perform Channel Calibration Control Rod Block Instrumentation Channel Functional Test Channel Functional Test (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after in Mode 2)

Channel Functional Test (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after in Mode 1)

Verify the RBM Verify the RWM Channel Functional Test (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after shutdown position)

Channel Calibration Feedwater & Main Turbine High Water Level Trip Instrument Perform Channel Check Perform Channel Functional Test Perform Channel Calibration Perform Logic System Functional Test PAM Instrumentation Perform Channel Check Perform Channel Calibration Remote Shutdown System Perform Channel Check Verify each required control circuit and transfer switch Perform Channel Calibration EOC-RPT Instrumentation Perform Channel Functional Test Calibrate the trip units Perform Channel Calibration Perform 10Qic System Functional Test Verify TSV, TCV, Trip Oil Pressure are not bypassed Verify the EOC-RPT System Response Time is within limits Determine RPT breaker interruption time ATWS-RPT Instrumentation Perform channel check TSTF 425 3.3.1.1.14 3.3.1.1.10 3.3.1.1.11 3.3.1.1.12 3.3.1.1.13 3.3.1.1.15 3.3.1.2 3.3.1.2.1 3.3.1.2.2 3.3.1.2.3 3.3.1.2.4 3.3.1.2.5 3.3.1.2.6 3.3.1.2.7 3.3.2.1 3.3.2.1.1 3.3.2.1.2 3.3.2.1.3 3.3.2.1.4 3.3.2.1.5 3.3.2.1.6 3.3.2.1.7 3.3.2.2 3.3.2.2.1 3.3.2.2.2 3.3.2.2.3 3.3.2.2.4 3.3.3.1 3.3.3.1.1 3.3.3.1.2 3.3.3.2 3.3.3.2.1 3.3.3.2.2 3.3.3.2.3 3.3.4.1 3.3.4.1.1 3.3.4.1.2 3.3.4.1.3 3.3.4.1.4 3.3.4.1.5 3.3.4.1.6 3.3.4.1.7 3.3.4.2 3.3.4.2.1 HNP Unit 1

3.3.1.1.11 3.3.1.1.12 3.3.1.1.13 3.3.1.1.15 3.3.1.1.16 3.3.1.1.17 3.3.1.2 3.3.1.2.1 3.3.1.2.2 3.3.1.2.3 3.3.1.2.4 3.3.1.2.5 3.3.1.2.6 3.3.1.2.7 3.3.2.1 3.3.2.1.1 3.3.2.1.2 3.3.2.1.3 3.3.2.1.4 3.3.1.2.5 3.3.2.1.6 3.3.2.1.7 3.3.2.2 3.3.2.2.1 3.3.2.2.2 3.3.2.2.3 3.3.3.1 3.3.3.1.1 3.3.3.1.2 3.3.3.2 3.3.3.2.1 3.3.3.2.2 3.3.3.2.3 3.3.4.1 3.3.4.1.1 3.3.4.1.3 3.3.4.1.4 3.3.4.1.2 3.3.4.1.5 3.3.4.1.6 3.3.4.2 3.3.4.2.1 HNP Unit I 2

3.3.1.1.11 3.3.1.1.12 3.3.1.1.13 3.3.1.1.15 3.3.1.1.16 3.3.1.1.17 3.3.1.2 3.3.1.2.1 3.3.1.2.2 3.3.1.2.3 3.3.1.2.4 3.3.1.2.5 3.3.1.2.6 3.3.1.2.7 3.3.2.1 3.3.2.1.1 3.3.2.1.2 3.3.2.1.3 3.3.2.1.4 3.3.2.1.5 3.3.2.1.6 3.3.2.1.7 3.3.2.2 3.3.2.2.1 3.3.2.2.2 3.3.2.2.3 3.3.3.1 3.3.3.1.1 3.3.3.1.2 3.3.3.2 3.3.3.2.1 3.3.3.2.2 3.3.3.2.3 3.3.4.1 3.3.4.1.1 3.3.4.1.3 3.3.4.1.4 3.3.4.1.2 3.3.4.1.5 3.3.4.1.6 3.3.4.2 3.3.4.2.1 E2-14

Technical Specification Cross Reference for HNP Unit 1 and Unit 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance TSTF-HNP Unit HNP Unit Description""

425 1

2 Perform channel functional test 3.3.4.2.2 3.3.4.2.2 3.3.4.2.2 I

Calibrate the trip units 3.3.4.2.3 i

Perform channel calibration 3.3.4.2.4 3.3.4.2.3 3.3.4.2.3 Perform logic system functional test 3.3.4.2.5 3.3.4.2.4 3.3.4.2.4 i

ECCS Instrumentation 3.3.5.1 3.3.5.1 3.3.5.1 Perform channel check 3.3.5.1.1 3.3.5.1.1 3.3.5.1.1 Perform channel functional test 3.3.5.1.2 3.3.5.1.2 3.3.5.1.2 Calibrate the trip unit 3.3.5.1.3 Perform channel functional test 3.3.5.1.3 3.3.5.1.3 i

Perform channel calibration 3.3.5.1.4 3.3.5.1.4 3.3.5.1.4 Perform channel calibration 3.3.5.1.5 Perform logic system functional test 3.3.5.1.6 3.3.5.1.5 3.3.5.1.5 I

Verify the ECCS Response time is within limits 3.3.5.1.7 RCIC System Instrumentation 3.3.5.2 3.3.5.2 3.3.5.2 i

Perform channel check 3.3.5.2.1 3.3.5.2.1 3.3.5.2.1 Perform channel functional test 3.3.5.2.2 3.3.5.2.2 3.3.5.2.2 Calibrate the trip units 3.3.5.2.3 I

Perform channel calibration 3.3.5.2.4 Perform channel functional test 3.3.5.2.3 3.3.5.2.3 i

Perform channel calibration 3.3.5.2.5 3.3.5.2.4 3.3.5.2.4 Perform logic system functional test 3.3.5.2.6 3.3.5.2.5 3.3.5.2.5

Primary Containment Isolation Instrumentation 3.3.6.1 3.3.6.1 3.3.6.1 I

Perform channel check 3.3.6.1.1 3.3.6.1.1 3.3.6.1.1 Perform channel functional test 3.3.6.1.2 3.3.6.1.2 3.3.6.1.2 i

Calibrate the trip unit 3.3.6.1.3 Perform channel calibration 3.3.6.1.4 3.3.6.1.3 3.3.6.1.3 Perform channel functional test 3.3.6.1.5 I

Perform channel calibration 3.3.6.1.6 3.3.6.1.4 3.3.6.1.4 Perform channel calibration 3.3.6.1.5 3.3.6.1.5 i

Perform logic system functional test 3.3.6.1.7 3.3.6.1.6 3.3.6.1.6 Verify isolation system response time is within limits 3.3.6.1.8 3.3.6.1.7 Secondary Containment Isolation Instrumentation 3.3.6.2 3.3.6.2 3.3.6.2 i

Perform channel check 3.3.6.2.1 3.3.6.2.1 3.3.6.2.1 Perform channel functional test 3.3.6.2.2 3.3.6.2.2 3.3.6.2.2 Calibrate the trip unit 3.3.6.2.3 Perform channel calibration 3.3.6.2.4 3.3.6.2.3 3.3.6.2.3 Perform channel calibration 3.3.6.2.5 3.3.6.2.4 3.3.6.2.4 i

Perform logic system functional test 3.3.6.2.6 3.3.6.2.5 3.3.6.2.5 Verify the isolation system response time is within limits 3.3.6.2.7 LLS Instrumentation 3.3.6.3 3.3.6.3 3.3.6.3 Perform channel check 3.3.6.3.1 3.3.6.3.1 3.3.6.3.1 I

Perform channel functional test for portion (outside) 3.3.6.3.2 3.3.6.3.2 3.3.6.3.2 i

Perform channel functional test for portion (inside) 3.3.6.3.3 3.3.6.3.3 3.3.6.3.3 Perform channel functional test 3.3.6.3.4 3.3.6.3.4 3.3.6.3.4 Calibrate the trip unit 3.3.6.3.5 Perform channel calibration 3.3.6.3.6 3.3.6.3.5 3.3.6.3.5 E2-15

i Technical Specification Cross Reference for HNP Unit 1 and Unit 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Description*

Perform logic system functional test MCREC System Instrumentation Perform channel check Perform channel functional test Calibrate the trip units Perform channel calibration Perform logic system functional test LOP Instrumentation Perform channel check Perform channel functional test Perform channel calibration Perform logic system functional test

. RPS Electric Power Monitoring Perform channel functional test Perform channel calibration Perform a system functional test Recirculation Loops Operating Verify recirculation loop jet pump flow mismatch Jet Pumps Verify for each circulation loop S/RVs Verify the function safety function lift setpoints of the S/RVs Verify each required S/RV opens when manually actuated RCS Operational LEAKAGE Verify RCS unidentified and total/unidentified LEKAGE RCS PIV Leakage Verify equivalent leakage of each RCS PIV RCS Leakage Detection Instrumentation Perform a channel check Perform a channel functional test Perform a channel calibration RCS Specific Activity Verify reactor coolant DOSE EQUIVALENT 1-131 RHR Shutdown Cooling System - Hot Shutdown Verify one RHR shutdown cooling subsystem RHR Shutdown Cooling System - Cold Shutdown Verify one RHR shutdown coolinQ subsystem RCS PIT Limits Verify RCS pressure, temperature, heatup/cooldown (PTLR)

Verify reactor vessel flange and head flange (PTLR)(tensioning)

Verify reactor vessel flange and head flange (PTLR)(30 min.)

Verify reactor vessel flanQe and head flanQe (PTLR)(MODE TSTF 425 3.3.6.3.7 3.3.7.1 3.3.7.1.1 3.3.7.1.2 3.3.7.1.3 3.3.7.1.4 3.3.7.1.5 3.3.8.1 3.3.8.1.1 3.3.8.1.2 3.3.8.1.3 3.3.8.1.4 3.3.8.2 3.3.8.2.1 3.3.8.2.2 3.3.8.2.3 3.4.1 3.4.1.1 3.4.2 3.4.2.1 3.4.3 3.4.3.1 3.4.3.2 3.4.4 3.4.4.1 3.4.5 3.4.5.1 3.4.6 3.4.6.1 3.4.6.2 3.4.6.3 3.4.7 3.4.7.1 3.4.8 3.4.8.1 3.4.9 3.4.9.1 3.4.10 3.4.10.1 3.4.10.7 3.4.10.8 3.4.10.8 3.4.10.9 HNP Unit 1

3.3.6.3.6 3.3.7.1 3.3.7.1.1 3.3.7.1.2 3.3.7.1.3 3.3.7.1.4 3.3.8.1 3.3.8.1.1 3.3.8.1.2 3.3.8.1.3 3.3.8.1.4 3.3.8.2 3.3.8.2.1 3.3.8.2.2 3.3.8.2.3 3.4.1 3.4.1.1 3.4.2 3.4.2.1 3.4.3 3.4.4 3.4.4.1 3.4.5 3.4.5.1 3.4.5.2 3.4.5.3 3.4.6 3.4.6.1 3.4.7 3.4.7.1 3.4.8 3.4.8.1 3.4.9 HNP Unit I 2

3.3.6.3.6 3.3.7.1 3.3.7.1.1 3.3.7.1.2 3.3.7.1.3 3.3.7.1.4 3.3.8.1 3.3.8.1.1 3.3.8.1.2 3.3.8.1.3 3.3.8.1.4 3.3.8.2 3.3.8.2.1 3.3.8.2.2 3.3.8.2.3 3.4.1 3.4.1.1 3.4.2 3.4.2.1 3.4.3 3.4.4 3.4.4.1 3.4.5 3.4.5.1 3.4.5.2 3.4.5.3 3.4.6 3.4.6.1 3.4.7 3.4.7.1 3.4.8 3.4.8.1 3.4.9 E2-16

Technical Specification Cross Reference for HNP Unit 1 and Unit 2 and TSTF 425 Mark ups I

Technical Specification Section Title/Surveillance Description*

TSTF 425 HNP Unit 1

HNP Unit 2

I 4}

Verify ACS pressure, temperature, heatup/cooldown jspec) 3.4.9.1 3.4.9.1 Verify reactor vessel flange and head flange 3.4.9.5 3.4.9.5 Verify reactor vessel flange and head flange temperatures 3.4.9.6 3.4.9.6 Reactor Steam Dome Pressure 3.4.11 3.4.10 3.4.10 Verify reactor steam dome pressure 3.4.11.1 3.4.10.1 3.4.10.1

. ECCS* Operating 3.5.1 3.5.1 3.5.1 Verify for each ECCS injection/spray subsystem the piping 3.5.1.1 3.5.1.1 3.5.1.1 Verify each ECCS injection/spray subsystem manual, power 3.5.1.2 3.5.1.2 3.5.1.2 Verify ADS air supply header pressure 3.5.1.3 3.5.1.3 3.5.1.3 Verify the AHA System cross tie value is closed 3.5.1.4 3.5.1.4 3.5.1.4 Verify each LPCI Inverter output voltage 3.5.1.5 Verify each recirculation pump discharge valve 3.5.1.6 3.5.1.6 3.5.1.6 Verify the following ECCS pumps develop specified flow 3.5.1.7 rate Verify reactor pressure and HPCI pump can develop flow 3.5.1.8 3.5.1.8 3.5.1.8 rate Verify reactor pressure and HPCI pump can develop flow 3.5.1.9 3.5.1.9 3.5.1.9 rate Verify each ECCS injection/spray subsystem actuates 3.5.1.10 3.5.1.10 3.5.1.10 Verify the ADS actuates on an actual or simulated signal 3.5.1.11 3.5.1.11 3.5.1.11 Verify each ADS valve relief mode actuator strokes 3.5.1.12 3.5.1.12 i

Verify each ADS valve opens when manually actuated Verify each ECCS injection/spray subsystem ECCS 3.5.1.12 3.5.1.13 i

I response ECCS - Shutdown 3.5.2 3.5.2 3.5.2 Verify the suppression pool water level 3.5.2.1 3.5.2.1 3.5.2.1 Verify for each require core spray (CS) subsystem 3.5.2.2 3.5.2.2 3.5.2.2 Verify the piping is filled with water 3.5.2.3 3.5.2.3 3.5.2.3 Verify each required ECCS injection/spray subsystem 3.5.2.4 3.5.2.4 3.5.2.4 position Verify each required ECCSpump develops flow rate 3.5.2.5 Verify each required ECCS injection/spray subsystem 3.5.2.6 3.5.2.6 3.5.2.6 actuates RCIC System 3.5.3 3.5.3 3.5.3 Verify the ACIC System piping is filled with water 3.5.3.1 3.5.3.1 3.5.3.1 Verify each ACIC System manual, power, automatic 3.5.3.2 3.5.3.2 3.5.3.2 Verify the ACIC pump can develop a flow rate 3.5.3.3 3.5.3.3 3.5.3.3 Verify the ACIC pump can develop a flow rate 3.5.3.4 3.5.3.4 3.5.3.4 Verify the ACIC System actuates on signal 3.5.3.5 3.5.3.5 3.5.3.5

Primary Containment 3.6.1.1 3.6.1.1 3.6.1.1 Verify drywell to suppression chamber differential pressure 3.6.1.1.2 3.6.1.1.2 3.6.1.1.2 Primary Containment Air Lock 3.6.1.2 3.6.1.2 3.6.1.2 Verify only one door in the primary containment air lock 3.6.1.2.2 3.6.1.2.2 3.6.1.2.2 PCIVs 3.6.1.3 3.6.1.3 3.6.1.3 Verify each 18 inch primary containment purge valve is 3.6.1.3.1 sealed E2-17

Technical Specification Cross Reference for HNP Unit 1 and Unit 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance TSTF-HNP Unit HNP Unit I

Description*

425 1

2 I

Verify each 18 inch primary containment purge valve is 3.6.1.3.2 3.6.1.3.1 3.6.1.3.1 I

closed Verify primary containment isolation manual valve (outside) 13.6.1.3.3 3.6.1.3.2 3.6.1.3.2 i

Verify continuity of TIP shear isolation valve explosive 3.6.1.3.5 3.6.1.3.4 3.6.1.3.4 charge Verify isolation time of each power operated automatic 3.6.1.3.6 PCIV Perform leakage rate testing for primary containment 3.6.1.3.7 purges Verify the isolation time of each MSIV 3.6.1.3.8 Verify each automatic PCIV actuates to isolation position 3.6.1.3.9 3.6.1.3.7 3.6.1.3.7 Verify each reactor instrumentation line EFC 3.6.1.3.10 3.6.1.3.8 3.6.1.3.8 Remove and test the explosive squib 3.6.1.3.11 3.6.1.3.9 3.6.1.3.9 Verify each [ ] inch primary containment purge valve is 3.6.1.3.15 -------... -.. _-

I blocked Cycle each 18 inch excess flow isolation damper 3.6.1.3.12 3.6.1.3.13 Drywell Pressure 3.6.1.4 3.6.1.4 3.6.1.4 Verify drywell pressure is within limit 3.6.1.4.1 3.6.1.4.1 3.6.1.4.1 Drywell Air Temperature 3.6.1.5 3.6.1.5 3.6.1.5 Verify drywell average air temperature is within limit 3.6.1.5.1 3.6.1.5.1 3.6.1.5.1 LLS Valves 3.6.1.6 3.6.1.6 3.6.1.6 Verify each LLS valve opens when manually actuated 3.6.1.6.1 3.6.1.6.1 3.6.1.6.1 Verify the LLS System actuates on a signal 3.6.1.6.2 3.6.1.6.2 3.6.1.6.2 Reactor Building-to-Suppression Chamber Vacuum 3.6.1.7 3.6.1.7 3.6.1.7 Breakers Verify each vacuum breaker is closed 3.6.1.7.1 3.6.1.7.1 3.6.1.7.1 Perform a functional test of each vacuum breaker 3.6.1.7.2 Verify the opening setpoint of each vacuum breaker 3.6.1.7.3 3.6.1.7.3 3.6.1.7.3

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.8 3.6.1.8 3.6.1.8 Verify each vacuum breaker is closed 3.6.1.8.1 3.6.1.8.1 3.6.1.8.1 Perform a functional test of each required vacuum breaker 3.6.1.8.2 3.6.1.8.2 3.6.1.8.2 Verify the opening setpoint of each required vacuum 3.6.1.8.3 3.6.1.8.3 3.6.1.8.3 breaker MSIV LCS 3.6.1.9 3.6.1.9 3.6.1.9 Operate each MSIV LCS blower 3.6.1.9.1 Verify electrical continuity of each inboard MSIV LeS 3.6.1.9.2 subsystem Perform a system functional test of each MSIV LCS 3.6.1.9.3 subsystem Suppression Pool Average Temperature 3.6.2.1 3.6.2.1 3.6.2.1 Verify suppression pool average temperature is within limits 3.6.2.1.1 3.6.2.1.1 3.6.2.1.1 Suppression Pool Water Level 3.6.2.2 3.6.2.2 3.6.2.2 Verify suppression pool water level is within limits 3.6.2.2.1 3.6.2.2.1 3.6.2.2.1 Suppression Pool Cooling 3.6.2.3 3.6.2.3 3.6.2.3 I

Verify each RHR suppression pool cooling subsystem 3.6.2.3.1 3.6.2.3.1 3.6.2.3.1 Verify each RHR pump develops a flow rate 3.6.2.3.2 RHR Suppression Pool Spray 3.6.2.4 3.6.2.4 3.6.2.4 E2-18

Technical Specification Cross Reference for HNP Unit 1 and Unit 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Description*

Verify each RHR suppression pool spray subsystem Verify each RHR pump develops a flow rate Verify each suppression pool spray nozzle is unobstructed Drywell~to~Suppression Chamber Differential Pressure Verify drywell-to-suppression chamber differential pressure Drywell Cooling System Fans Operate each required drywell cooling system fan Verify each required drywell cooling system fan flow rate Primary Containment Oxygen Concentration Verify primary containment oxygen concentration is within limits CAD System Verify liquid nitrogen is contained in the CAD System Verify each CAD subsystem manual, power, and automatic Verify;:: 2000 gal of liquid nitrogen are contained Secondary Containment Verify secondary containment vacuum Verify all secondary containment eqUipment hatches are closed Verify one secondary containment access door Verify secondary containment can be drawn down Verify the secondary containment can be maintained Verify required SGT subsystems can be drawn down Verify required SGT subsystems can be maintained SCIVs Verify each secondary containment isolation manual valve Verify the isolation time of each power operated, auto SCIV Verify each automatic SCIV actuates to the isolation pOSition SGTSystem Operate each SGT subsystem with heaters operating Verify each SGT subsystem actuates Verify each SGT fiber cooler bypass damper can be opened RHRSW System Verify each RHRSW manual, power, and automatic valve PSW System and UHS Verify the water level of each PSW cooling tower basin Verify the water level of each PSW pump well of the intake Verify the averaQe water temperature of UHS Operate each PSW cooling tower fan Verify each PSW subsystem manual, power, and automatic Verify each PSW subsystem actuates DG 1 B SSW System Verify each DG 1B SSW System manual, power, automatic Verify the DG 1B SSW System pump starts automatically MCREC System Operate each MCREC subsystem E2-19 TSTF~

425 3.6.2.4.1 3.6.2.4.2 3.6.2.5 3.6.2.5.1 3.6.3.1 3.6.3.1.1 3.6.3.1.2 3.6.3.2 3.6.3.2.1 3.6.3.3 3.6.3.3.1 3.6.3.3.2 3.6.4.1 3.6.4.1.1 3.6.4.1.2 3.6.4.1.3 3.6.4.1.4 3.6.4.1.5 3.6.4.2 3.6.4.2.1 3.6.4.2.2 3.6.4.2.3 3.6.4.3 3.6.4.3.1 3.6.4.3.3 3.6.4.3.4 3.7.1 3.7.1.1 3.7.2 3.7.2.1 3.7.2.2 3.7.2.3 3.7.2.4 3.7.2.5 3.7.3 3.7.3.1 3.7.3.2 3.7.4 3.7.4.1 HNP Unit HNP Unit 1

2 3.6.2.4.1 3.6.2.4.1 3.6.2.4.2 3.6.2.4.2 3.6.3.3 3.6.3.3.1 3.6.3.2 3.6.3.2 3.6.3.2.1 3.6.3.2.1 3.6.3.1 3.6.3.1.2 3.6.3.1.1 3.6.4.1 3.6.4.1 3.6.4.1.1 3.6.4.1.1 3.6.4.1.2 3.6.4.1.2 3.6.4.1.3 3.6.4.1.3 3.6.4.1.4 3.6.4.1.4 3.6.4.2 3.6.4.2 3.6.4.2.1 3.6.4.2.1 3.6.4.2.2 3.6.4.2.2 3.6.4.2.3 3.6.4.2.3 3.6.4.3 3.6.4.3 3.6.4.3.1 3.6.4.3.1 3.6.4.3.3 3.6.4.3.3 3.7.1 3.7.1 3.7.1.1 3.7.1.1 3.7.2 3.7.2 3.7.2.1 3.7.2.1 3.7.2.2 3.7.2.2 3.7.2.3 3.7.2.3 3.7.3 3.7.3 3.7.3.1 3.7.3.1 3.7.3.2 3.7.3.2 3.7.4 3.7.4 3.7.4.1 3.7.4.1

Technical Specification Cross Reference for HNP Unit 1 and Unit 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance TSTF-HNP Unit HNP Unit Description*

425 1

2 I

Verify each MCREC subsystem actuates 3.7.4.3 3.7.4.3 3.7.4.3 Verify MCREC subsystem can maintain a positive pressure 3.7.4.4 3.7.4.4 3.7.4.4 i

Control Room AC System 3.7.5 3.7.5 3.7.5 Verify each control room AC subsystem can remove heat 3.7.5.1 3.7.5.1 3.7.5.1 I

, load Main Condenser Offgas 3.7.6 3.7.6 3.7.6 I

Verify the gross gamma activity rate of the noble gasses 3.7.6.1 3.7.6.1 3.7.6.1 Main Turbine Bypass System 3.7.7 3.7.7 3.7.7 Verify one complete cycle of each main turbine bypass 3.7.7.1 3.7.7.1 3.7.7.1 valve Perform a system functional test 3.7.7.2 3.7.7.2 3.7.7.2 Verify the turbine bypass system response time 3.7.7.3 3.7.7.3 3.7.7.3 Spent Fuel Storage Pool Water Level 3.7.8 3.7.8 3.7.8 Verify the spent fuel storage pool water level 3.7.8.1 3.7.8.1 3.7.8.1 AC Sources - Operating 3.8.1 3.8.1 3.8.1 Verify correct breaker alignment and indicated power 3.8.1.1 3.8.1.1 3.8.1.1 availability Verify each DG starts from standby conditions 3.8.1.2 3.8.1.2 3.8.1.2 Verify each DG is synchronized and loaded and operates 3.8.1.3 3.8.1.5 3.8.1.5 Verify each day tank contains fuel oil 3.8.1.4 3.8.1.3 3.8.1.3 Check for and remove accumulated water from each day 3.8.1.5 3.8.1.4 3.8.1.4 tank Verify the fuel oil transfer system operates to transfer fuel oil 3.8.1.6 Verify each DG starts from standby conditions 3.8.1.7 Verify automatic and manual transfer of unit power supply 3.8.1.8 3.8.1.6 3.8.1.6 Verify each DG rejects a load 3.8.1.9 3.8.1.7 3.8.1.7 Verify each DG does not trip and voltage is maintained 3.8.1.10 3.8.1.8 3.8.1.8 Verify on an actual or simulated loss of offsite power signal 3.8.1.11 3.8.1.9 3.8.1.9 Verify on actual or simulated ECCS signal each DG auto-3.8.1.12 3.8.1.10 3.8.1.10 I

start Verify each DG's automatic trips are bypassed 3.8.1.13 3.8.1.11 3.8.1.11 i

Verify each DG operates 3.8.1.14 3.8.1.12 3.8.1.12 Verify each DG starts and achieves steady state voltage 3.8.1.15 3.8.1.13 3.8.1.13 Verify each DG synchronizes, transfers, runs to ready-to-3.8.1.16 3.8.1.14 3.8.1.14 load Verify a DG operating in test mode an ECCS signal 3.8.1.17 3.8.1.15 3.8.1.15 overrides Verify interval between each sequences load block 3.8.1.18 3.8.1.16 3.8.1.16 Verify de-enerQization, load sheddinQ, and DG auto-start 3.8.1.19 3.8.1.17 3.8.1.17 Verify DG achieves voltage and frequency 3.8.1.20 3.8.1.18 3.8.1.18 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 3.8.3 3.8.3 Verify each fuel oil storage tank contains fuel 3.8.3.1 3.8.3.1 3.8.3.1 Verify lube oil inventory 3.8.3.2 3.8.3.2 3.8.3.2 Verify each Dg air start receiver pressure 3.8.3.4 3.8.3.4 3.8.3.4 Check for and remove accumulated water from each fuel 3.8.3.5 3.8.3.6 3.8.3.6 i tank Verify each Unit 2 and swing DG fuel oil transfer (automatic) -....----_........ -...

3.8.3.5 3.8.3.5 E2-20

Technical Specification Cross Reference for HNP Unit 1 and Unit 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance TSTF*

HNP Unit HNP Unit I Description*

425 1

2 Verify each Unit 2 and swing DG fuel oil transfer (manual) 3.8.3.7 3.8.3.7

DC Sources - Operating 3.8.4 3.8.4 3.8.4 Verify battery terminal voltage 3.8.4.1 3.8.4.1 3.8.4.1 I

Verify each required battery charger 3.8.4.2 3.8.4.6 3.8.4.6 Verify battery capacity is adequate 3.8.4.3 3.8.4.7 3.8.4.7 Verify no visible corrosion at battery terminals and 3.8.4.2 3.8.4.2 connecters Verify battery cells, cell plates, and racks show no damage 3.4.8.3 3.4.8.3 Remove visible corrosion and verify anti-corrosion material 3.8.4.4 3.8.4.4 Verify battery connection resistance 3.8.4.5 3.8.4.5 Verify Battery capacity 3.8.4.8 3.8.4.8 Battery Parameters 3.8.6 Verify each battery float current 3.8.6.1 Verify each battery pilot cell voltage 3.8.6.2 I

Verify each battery connected cell electrolyte level 3.8.6.3 Verify each battery pilot cell temperature 3.8.6.4 Verify each battery connected cell voltage 3.8.6.5 Verify battery capacity 3.8.6.6 I

i Inverters - Operating 3.8.7 Verify correct inverter voltage, frequency, and alignment 3.8.7.1 i

Inverters - Shutdown 3.8.8 Verify correct inverter voltage, frequency, and alignment 3.8.8.1 Battery Cell Parameters 3.8.6 3.8.6 Verify battery cell parameters (Category A) 3.8.6.1 3.8.6.1 Verify battery cell parameters (Category B) 3.8.6.2 3.8.6.2 Verify average electrolyte temperature 3.8.6.3 3.8.6.3 Distribution Systems - Operating 3.8.9 3.8.7 3.8.7 Verify correct breaker alignments and voltage 3.8.9.1 3.8.7.1 3.8.7.1 Distribution Systems - Shutdown 3.8.10 3.8.8 3.S.8 Verify correct breaker alignments and voltage 3.8.10.1 3.8.8.1 3.8.8.1

Refueling Equipment Interlocks 3.9.1 3.9.1 3.9.1 I

Perform channel functional test 3.9.1.1 3.9.1.1 3.9.1.1 Refuel Position One-Rod-Out Interlock 3.9.2 3.9.2 3.9.2 i

Verify reactor mode switch locked in refuel position 3.9.2.1 3.9.2.1 3.9.2.1 Perform channel functional test 3.9.2.2 3.9.2.2 3.9.2.2

Control Rod Position 3.9.3 3.9.3 3.9.3 Verify all control rods are fully inserted 3.9.3.1 3.9.3.1 3.9.3.1 Control Rod OPERABILITY - Refueling 3.9.5 3.9.5 3.9.5 Insert each withdrawn control rod at least one notch 3.9.5.1 3.9.5.1 3.9.5.1 Verify each withdrawn control rod scram accumulator 3.9.5.2 3.9.5.2 3.9.5.2 pressure RPY Water Level - Irradiated Fuel 3.9.6 3.9.6 3.9.6 Verify RPV water level 3.9.6.1 3.9.6.1 3.9.6.1 RPY Water Level - New Fuel or Control Rods 3.9.7 Verify RPV water level 3.9.6.1 RHR - High Water Level 3.9.8 3.9.7 3.9.7 Verify one RHR shutdown cooling subsystem is operating 3.9.8.1 3.9.7.1 3.9.7.1 E2-21

Technical Specification Cross Reference for HNP Unit 1 and Unit 2 and TSTF 425 Mark ups Technical Specification Section Title/Surveillance Description*

RHR - Low Water Level Verify one RHR shutdown cooling subsystem is operating Reactor Mode Switch Interlock Testing Verify all control rods are fully inserted Verify no CORE ALTERATIONS are in progress Single Control Rod Withdrawal-Hot Shutdown Verify all control rods are disarmed Verify all control rods are fully inserted Single Control Rod Withdrawal - Cold Shutdown Verify all control rods are disarmed Verify all control rods are fully inserted Verify a control rod withdrawal block is inserted Single CRD Removal - Refueling Verify all control rods are fully inserted Verify all control rods are disarmed Verify a control rod withdrawal block is inserted Verify no CORE AL TERATIONS are in progress Multiple Control Rod Withdrawal-Refueling Verify the four fuel assemblies are removed I

I Verify all other control rods in core cells are inserted Verify fuel assemblies being loaded are in compliance SDM Test - Refueling Verify no other CORE ALTERATIONS are in progress Verify CRD charging water header pressure Recirculation Loops - Testing Verify LCO requirements Verify thermal power during physics test Training Startups Verify all operable IRM channels Verify average reactor coolant temperature TSTF~

425 3.9.9 3.9.9.1 3.10.2 3.10.2.1 3.10.2.2 3.10.3 3.10.3.2 3.10.3.3 3.10.4 3.10.4.2 3.10.4.3 3.10.4.4 3.10.5 3.10.5.1 3.10.5.2 3.10.5.3 3.10.5.5 3.10.6 3.10.6.1 3.10.6.2 3.10.6.3 3.10.8 3.10.8.4 3.10.8.6 3.10.9 3.10.9.1 3.10.9.2 3.10.10 3.10.10.1 3.10.10.2 HNP Unit HNP Unit 1

2 i

3.9.8 3.9.8 3.9.8.1 3.9.8.1 I

3.10.2 3.10.2 3.10.2.1 3.10.2.1 3.10.2.2 3.10.2.2 3.10.3 3.10.3 3.10.3.2 3.10.3.2 3.10.3.3 3.10.3.3 3.10.4 3.10.4 3.10.4.2 3.10.4.2 3.10.4.3 3.10.4.3 3.10.4.4 3.10.4.4 3.10.5 3.10.5 3.10.5.1 3.10.5.1 3.10.5.2 3.10.5.2 3.10.5.3 3.10.5.3 3.10.5.5 3.10.5.5 3.10.6 3.10.6 3.10.6.1 3.10.6.1 3.10.6.2 3.10.6.2 3.10.6.3 3.10.6.3 3.10.8 3.10.8 3.10.8.4 3.10.8.4 3.10.8.6 3.10.8.6 E2-22 to NL-11-0141 HNP License Amendment Request dated October 29,2010 Submittal Corrections Revised marked-up page for HNP SR 3.1.7.5 for Unit 2 only E2-23

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.1.7.1 Verify available volume of sodium pentaborate solution is within the Region A limits of Figure 3.1.7-1.

SR 3.1.7.2 Verify temperature of sodium pentaborate solution is within the Region A limits of Figure 3.1.7-2.

SR 3.1.7.3 Verify temperature of pump suction piping is within the Region A limits of Figure 3.1.7-2.

SR 3.1.7.4 Verify continuity of explosive charge.

SR 3.1.7.5 Verify the concentration of sodium pentaborate in solution is within the Region A limits of Figure 3.1.7-1.

SR 3.1.7.6 Verify each SLC subsystem manual and power operated valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.

HATCH UNIT2 3.1-18 SLC System 3.1.7 FREQUENCY 24 Ral:lFs Insert 1

+--1 24 Rams Insert 1

+--1 31 days Insert 1

+--1 AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or sodium pentaborate is added to solution AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the Region A limits of Figure 3.1.7-2 31 days

+--1 Insert 1 (continued)

Amendment No. :f..35 to NL-11-0141 HNP License Amendment Request dated October 29, 2010 Submittal Corrections Revised marked-up and clean typed pages for SR 3.4.9.5 and SR 3.4.9.6 for Unit 2 only E2-25

3.4.9 SR 3.4.9.4 SR 3.4.9.5 SR 3.4.9.6

N0TE-----------------------------

Only required to be met in MODES 1, 2, 3, and 4 during startup of a recirculation pump.

Verify the difference between the reactor coolant temperature in the recirculation loop to be started and the RPV coolant temperature is ::;; 50°F.

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

Only required to be met when tensioningl detensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange temperatures are;:: 90°F.

Insert 1

N0 T ------ --------------------

Only required to be met when he re tor vessel head is tensioned.

Verify reactor vessel flange and hea temperatures are;:: 90°F.

RCS PIT Limits FREQUENCY Once within 15 minutes prior to starting an idle recirculation pump Once within 30 minutes prior to tensioningl detensioning the reactor vessel head boltin studs and Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS mperature is OaF in MODE 4, and Once within minutes after R S temperature is

1 OF in MODE 4, and HATCH UNIT2 3.4-21 Amendment No.1Ht]

3.4.9 RCS PIT limits SURVEILLANCE REQUIREMENTS (continued)

SR 3.4.9.4 SR 3.4.9.5 SR 3.4.9.6 SURVEILLANCE

NO TE -----------------------------

Only required to be met in MODES 1, 2, 3, and 4 during startup of a recirculation pump.

Verify the difference between the reactor coolant temperature in the recirculation loop to be started and the RPV coolant temperature is s 50°F.

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

Only required to be met when tensioningl detensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange temperatures are;:: 90°F.

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

Only required to be met when the reactor vessel head is tensioned.

Verify reactor vessel flange and head flange temperatures are;:: 90°F.

HATCH UNIT 2 3.4-21 FREQUENCY Once within 15 minutes prior to starting an idle recirculation pump Once within 30 minutes prior to tensioningl detensioning the reactor vessel head bolting studs and in accordance with the Surveillance Frequency Control Program Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature is s 120°F in MODE 4.

and in accordance with the Surveillance Frequency Control Program (continued)

Amendment No.

3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.9.6 (continued)

RCS PIT Limits FREQUENCY Once within 30 minutes after RCS temperature is s 100°F in MODE 4, and in accordance with the Surveillance Frequency Control Program HATCH UNIT2 3.4-22 Amendment No.

RCS PIT Limits 3.4.9 1400 L

"v INITIAL RTndt VALUES ARE 32 24'F FOR BELTLINE.

1300 54 26'F FOR UPPER VESSEL, i

AND 50'F FOR BOTTOM HEAD 1200 i

1100 HEATUP/COOLDOWN RATE 20'F'/HR 01 I

iii Q.

I

'-" 1000 c

w BELTLINE CURVES

~

x:

ADJUSTED AS SHOWN:

900 Il.

0 I

EFPV SHIrT ('r) 20 43.5 I

...J I

w BOO Vl I

Vl W

I BELTLINE CURVES e:::

700 ADJUSTED AS SHOWN:

0 I-EF'PV SHIFT ('F)

U 32 4B.0 w

0::

600

~

t:

BELTLINE CURVES 500

E ADJUSTED AS SHOWN:

J I

I I

EF'PV SHIFT ('F) w 54 53.7 e:::

l 400 i

Vl I

Vl W

I e:::

I Il.

312 PSIG 300 I

I

-BELTLINE LIMITS AND UPPER VESSEL LIMITS r----:

200 BELTLINE I

A==SYSTEM AND I

FLANGE HYDROTEST LIMITS BOTTOM REGION HEAD f--i-WITH FUEL IN THE BOTTOM HEAD LIMITS OO"F 100 r

eS"F I

VESSEL I

0 I

I o

50 100 150 200 250 300 350 400 (ACAD I F3491 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 3.4.9-1 (page 1 of 1)

Pressure/Temperature Limits for Inservice Hydrostatic and Inservice Leakage Tests HATCH UNIT2 3.4-23 Amendment No. I

v t e Letter Sequence Supplement
TAC:ME5055, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B (Approved, Closed)
Initiation Request Acceptance... Supplement Administration Questions Answers Results Approval Other:
MONTHYEAR2011-02-21 [Table View]

ML110530184

Text

Enclosures:

Navigation menu

Search