Text

Changes Made to the Technical Requirements Manual
	ML101121087
Person / Time
Site:	Watts Bar
Issue date:	04/20/2010
From:	Krich R; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML101121087 (34)
	v • d • e

Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing April 20, 2010 10 CFR 50.4 10 CFR 50.71(e)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390

Subject:

Changes Made to the Technical Requirements Manual The purpose of this letter is to provide the NRC with copies of the changes that have been made to the Watts Bar Nuclear Plant (WBN), Unit 1, Technical Requirements Manual (TRM), through Revision 45. This information is provided in accordance with WBN, Unit 1 TRM Section 5.1, "Technical Requirements Control Program," and 10 CFR 50.71(e).

These changes have been implemented at WBN, Unit 1, during the period since the last update of the TRM on September 22, 2008 and meet the criteria described within the TRM control program for which prior NRC approval is not required. The updates to the TRM are provided in the enclosures listed below. - WBN, Unit 1, Technical Requirements Manual - Table of Contents - WBN, Unit 1, Technical Requirements Manual - Changed Pages WBN, Unit l's TRM is incorporated by reference into the Updated Final Safety Analysis Report (UFSAR). Due to this, this letter certifies that the content of this update accurately presents the changes made since the previous submittal.

There are no regulatory commitments associated with this submittal. Please direct any questions concerning this matter to Kevin Casey, Senior Project Manager at (423) 751-8523.

printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 April 20, 2010 I certify that the foregoing is true and correct.

Respectfull R. M. Krich

Enclosures:

1.

WBN,.Unit 1, Technical Requirements Manual - Table of Contents

2.

WBN, Unit 1, Technical Requirements Manual - Changed Pages cc (Enclosures):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant WBN, Unit 1, Technical Requirements Manual - Table of Contents

TABLE OF CONTENTS TECHNICAL REQUIREMENTS TABLE OF CONTENTS L IS T O F T A B LE S.........................................................................................................................................

v L IS T O F F IG U R E S.......................................................................................................................................

vi LIST OF ACRONYMS....................................................................................................................

vii LIST OF EFFECTIVE PAGES....................................................................................................................

viii 1.0 USE AND APPLICATION................................................................................................

1.1-1 1.1 D efinitio ns..........................................................................................................

1.1-1 1.2 Logical Connectors.............................................................................................

1.2-1 1.3 Completion Times...............................................................................................

1.3-1 1.4 F re q ue ncy...........................................................................................................

1.4-1 TR 3.0 APPLICABILITY...............................................................................................................

3.0-1 TR 3.1 REACTIVITY CONTROL SYSTEMS..............................................................................

3.1-1 TR 3.1.1 Boration Systems Flow Paths, Shutdown.........................................................

3.1-1 TR 3.1.2 Boration Systems Flow Paths, Operating.........................................................

3.1-3 TR 3.1.3 Charging Pump, Shutdown............. :..................................................................

3.1-5 TR 3.1.4 Charging Pumps, Operating..............................................................................

3.1-6 TR 3.1.5 Borated Water Sources, Shutdown...................................................................

3.1-8 TR 3.1.6 Borated Water Sources, Operating...................................................................

3.1-10 TR 3.1.7 Position Indication System, Shutdown..............................................................

3.1-13 TR 3.3 INSTRUMENTATION......................................................................................................

3.3-1 TR 3.3.1 Reactor Trip System (RTS) Instrumentation.....................................................

3.3-1 TR 3.3.2 Engineered Safety Features Actuation System (ESFAS) Instrumentation.....................................................

3.3-5 TR 3.3.3 Movable Incore Detectors..................................................................................

3.3-12 TR 3.3.4 Seismic Instrumentation.....................................................................................

3.3-14 TR 3.3.5 Turbine Overspeed Protection...........................................................................

3.3-18 TR 3.3.6 Loose-Part Detection System............................................................................

3.3-20 TR 3.3.7 Plant Calorimetric Measurement............................

3.3-22 TR 3.3.8 Hydrogen Monitors.............................................................................................

3.3-24 TR 3.4 REACTOR COOLANT SYSTEM (RCS).........................................................................

3.4-1 TR 3.4.1 Safety Valves, Shutdown...................................................................................

3.4-1 TR 3.4.2 Pressurizer Temperature Limits.........................................................................

3.4-3 TR 3.4.3 RCS Vents..........................................................................................................

3.4-5 TR 3.4.4 Chemistry..........................................................................................................

3.4-7 TR 3.4.5 Piping System Structural Integrity......................................................................

3.4-10 TR 3.6 CONTAINMENT SYSTEMS............................................................................................

3.6-1 TR 3.6.1 Ice Bed Temperature Monitoring System..........................................................

3.6-1 TR 3.6.2 Inlet Door Position Monitoring System..............................................................

3.6-4 TR 3.6.3 Lower Compartment Cooling (LCC) System...............................................

3.6-6 (continued)

Watts Bar-Unit 1 Technical Requirements Last Updated Revision 45

TABLE OF CONTENTS (continued)

TR 3.7 TR 3.7.1 TR 3.7.2 TR 3.7.3 TR 3.7.4 TR 3.7.5 TR 3.8 TR 3.8.1 TR 3.8.2 TR 3.8.3 TR 3.8.4 TR 3.9 TR 3.9.1 TR 3.9.2 TR 3.9.3 TR 3.9.4 5.0 5.1 PLANT SYSTEM S................................................

I........................................................... 3.7-1 Steam Generator Pressure/

Tem perature Lim itations.......................................................................

3.7-1 Flood Protection Plan.........................................................................................

3.7-3 Snubbers.............................................................................................................

3.7-10 Sealed Source Contam ination...........................................................................

3.7-22 Area Tem perature M onitoring........................................................................... 3.7-26 ELECTRICAL POW ER SYSTEM S.................................................................................

3.8-1 Isolation Devices................................................................................................

3.8-1 Containment Penetration Conductor Overcurrent Protection Devices................................................................................

3.8-5 Motor-Operated Valves Thermal Overload Bypass Devices...................................................................................

3.8-10 Subm erged Com ponent Circuit Protection.......................................................

3.8-17 REFUELING O PERATIO NS..........................................................................................

3.9-1 Decay Tim e.........................................................................................................

3.9-1 Com m unications.................................................................................................

3.9-2 Refueling M achine..............................................................................................

3.9-3 Crane Travel - Spent Fuel Storage Pool Building.............................................

3.9-5 ADM INISTRA TIVE CO NTRO LS....................................................................................

5.0-1 Technical Requirem ents (TR) Control Program...............................................

5.0-1 (continued)

Watts Bar-Unit 1 Technical Requirements ii

TABLE OF CONTENTS (continued)

BASES B 3.0 TECHNICAL REQUIREMENTS (TR) AND TECHNICAL SURVEILLANCE REQUIREMENTS (TSR)

A P P LIC A B ILITY.................................................................................................

B 3.0-1 B 3.1 REACTIVITY CONTROL SYSTEMS..............................................................................

B 3.1-1 B 3.1.1 Boration Systems Flow Paths, Shutdown............................

B 3.1-1 B 3.1.2 Boration Systems Flow Paths, Operating.......................................................................

B 3.1-5 B 3.1.3 Charging Pump, Shutdown.............................................................................................

B 3.1-9 B 3.1.4 Charging Pumps, Operating....................................

B 3.1-11 B 3.1.5 Borated Water Sources, Shutdown...............................................................

B 3.1-14 B 3.1.6 Borated Water Sources, Operating.................................................................................

B 3.1-18 B 3.1.7 Position Indication System, Shutdown......................................................................

B 3.1-23 B 3.3 INSTRUMENTATION.....................................................................................................

B 3.3-1 B 3.3.1 Reactor Trip System (RTS) Instrumentation...................................................................

B 3.3-1 B 3.3.2 Engineered Safety Features Actuation System (ESFAS) Instrumentation.....................................................

B 3.3-4 B 3.3.3 Movable Incore Detectors................................................................................................

B 3.3-7 B 3.3.4 Seismic Instrumentation..................................................................................................

B 3.3-10 B 3.3.5 Turbine Overspeed Protection.........................................................................................

B 3.3-14 B 3.3.6 Loose-Part Detection System........................................................................................

B 3.3-18 B.3.3.7 Plant Calorimetric Measurement.....................................................................................

B 3.3-21 B 3.3.8 Hydrogen Monitors..........................................

B 3.3-25 B 3.4 REACTOR COOLANT SYSTEM (RCS).........................................................................

B 3.4-1 B 3.4.1 Safety Valves, Shutdown.................................................................................................

B 3.4-1 B 3.4.2 Pressurizer Temperature Limits......................................................................................

B 3.4-4 B 3.4.3 R C S V ents........................................................................................................................

B 3.4-7 B 3.4.4 C hem istry.........................................................................................................................

B 3.4-10 B 3.4.5 Piping System Structural Integrity....................................................................................

B 3.4-14 B 3.6 CONTAINMENT SYSTEMS..........................................................................................

B 3.6-1 B 3.6.1 Ice Bed Temperature Monitoring System............................

B 3.6-1 B 3.6.2 Inlet Door Position Monitoring System.......................................................... :................. B 3.6-6 B 3.6.3 Lower Compartment Cooling (LCC) System..................................................................

B 3.6-10 B 3.7 PLANT SYSTEMS...........................................................................................................

B 3.7-1 B 3.7.1 Steam Generator Pressure/Temperature Limitations.....................................................

B 3.7-1 B 3.7.2 Flood Protection Plan.......................................................................................................

B 3.7-4 B 3.7.3 S nubbers...........................................................................................................................

B 3.7-12 B 3.7.4 Sealed Source Contamination.........................................................................................

B 3.7-18 B 3.7.5 Area Temperature Monitoring..........................................................................................

B 3.7-22 (continued)

Watts Bar-Unit I iii Technical Requirements Last Updated Revision 45

TABLE OF CONTENTS (continued)

B 3.8 B 3.8.1 B 3.8.2 B 3.8.3 B 3.8.4 B 3.9 B 3.9.1 B 3.9.2 B 3.9.3 B 3.9.4 ELECTRICAL POW ER SYSTEM S.................................................................................

B 3.8-1 Isolation Devices...............................................................................................................

B 3.8-1 Containment Penetration Conductor O vercurrent Protection Devices.........................................................................

B 3.8-7 Motor-Operated Valves Thermal O verload Bypass Devices..................................................................................

B 3.8-15 Subm erged Com ponent Circuit Protection.....................................................................

B 3.8-19 REFUELING O PERATIO NS.........................................................................................

B 3.9-1 Decay Tim e..........................................................................................................

............. B 3.9-1 Com m unications...............................................................................................................

B 3.9-3 Refueling M achine...........................................................................................................

B 3.9-5 Crane Travel - Spent Fuel Storage Pool Building.......................................................................................................

B 3.9-8 Watts Bar-Unit 1 Technical Requirements iv

LIST OF TABLES Table No.

Title Page 1.1-1 MODES.............................................................

1.1-6 3.3.1-1 Reactor Trip System Instrumentation Response Times...................................

3.3-3 3.3.2-1 Engineered Safety Features Actuation System Response Times....................................................

3.3-7 3.3.4-1 Seismic Monitoring Information.........................................................................

3.3-17 3.7.3-1 Snubber Visual Inspection Acceptance Criteria................................................

3.7-14 3.7.3-2 Snubber Visual Inspection Surveillance Frequency.........................................

3.7-15 3.7.3-3 Snubber Transient Event Inspection.................................................................

3.7-17 3.7.3-4 Snubber Functional Testing Plan.......................................................................

3.7-18 3.7.3-5 Snubber Functional Testing Acceptance Criteria.............................................

3.7-20 3.7.5-1 Area Temperature Monitoring............................................................................

3.7-29 3.8.3-1 Motor-Operated Valves Thermal Overload Devices Which Are Bypassed Under Accident Conditions..........................................

3.8-12 3.8.4-1 Submerged Components With Automatic De-energization Under Accident Conditions..................................................................

3.8-19 Watts Bar-Unit 1 v

Technical Requirements

LIST OF FIGURES Fiqure No.

Title Page 3.1.6 Boric Acid Tank Limits Based on RWST Boron Concentration....................... 3.1-12a 3.7.3-1 Sample Plan B for Snubber Functional Test.....................................................

3.7-21 LIST OF MISCELLANEOUS REPORTS AND PROGRAMS Core Operating Limits Report Watts Bar-Unit 1 Technical Requirements vi Last Updated Revision 21

LIST OF ACRONYMS Acronym Title ABGTS Auxiliary Building Gas Treatment System ACRP Auxiliary Control Room Panel ASME American Society of Mechanical Engineers AFD Axial Flux Difference AFW Auxiliary Feedwater System ARO All Rods Out ARFS Air Return Fan System ARV Atmospheric Relief Valve BOC Beginning of Cycle CCS Component Cooling Water System CFR Code of Federal Regulations COLR Core Operating Limits Report CREVS Control Room Emergency Ventilation System CSS Containment Spray System CST Condensate Storage Tank DNB Departure from Nucleate Boiling ECCS Emergency Core Cooling System EFPD Effective Full-Power Days EGTS Emergency Gas Treatment System EOC End of Cycle ERCW Essential Raw Cooling Water ESF Engineered Safety Feature ESFAS Engineered Safety Features Actuation System HEPA High Efficiency Particulate Air HVAC Heating, Ventilating, and Air-Conditioning LCC Lower Compartment Cooler LCO Limiting Condition For Operation MFIV Main Feedwater Isolation Valve MFRV Main Feedwater Regulation Valve MSIV Main Steam Line Isolation Valve MSSV Main Steam Safety Valve MTC Moderator Temperature Coefficient NMS Neutron Monitoring System ODCM Offsite Dose Calculation Manual PCP Process Control Program PIV Pressure Isolation Valve PORV Power-Operated Relief Valve PTLR Pressure and Temperature Limits Report QPTR Quadrant Power Tilt Ratio RAOC Relaxed Axial Offset Control RCCA Rod Cluster Control Assembly RCP Reactor Coolant Pump RCS Reactor Coolant System RHR Residual Heat Removal RTP Rated Thermal Power RTS Reactor Trip System RWST Refueling Water Storage Tank SG Steam Generator SI Safety Injection SL Safety Limit SR Surveillance Requirement UHS Ultimate Heat Sink Watts Bar-Unit 1 vii Technical Requirements

TECHNICAL REQUIREMENTS LIST OF EFFECTIVE PAGES Page Number i

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Revisions Revision 0 Revision 1 Revision 2 Revision 3 Revision 4 Revision 5 Revision 6 Revision 7 Revision 8 Revision 9 Revision 10 Revision 11 Revision 12 Revision 13 Revision 14 Revision 15 Revision 16 Revision 17 Revision 18 Revision 19 Revision 20 Revision 21 Revision 22 TECHNICAL R LIST OF EFFECTIV Issued 09-30-95 12-06-95 01-04-96 02-28-96 08-18-97 08-29-97 09-08-97 09-12-97 09-22-97 10-10-97 12-17-98 01-08-99 01-15-99 03-30-99 04-07-99 04-07-99 04-13-99 05-25-99 08-03-99 10-12-99 03/13/00 04/13/00 07/07/00 EQUIREMENTS MANUAL E PAGES - REVISION LISTING SUBJECT Initial Issue Submerged Component Circuit Protection Area Temperature Monitoring - Change in MSSV Limit Turbine Driven AFW Pump Suction Requirement Time-frame for Snubber Visual Exams Performance of Snubber Functional Tests at Power Revised Actions for Turbine Overspeed Protection Change OPAT/OTAT Response Time Clarification of Surveillance Frequency for Position Indication System Revised Boron Concentration for Borated Water Sources ICS Inlet Door Position Monitoring - Channel Check Computer-Based Analysis for Loose Parts Monitoring Removal of Process Control Program from TRM Deletion of Power Range Neutron Flux High Negative Rate Reactor Trip Function Submerged Component Circuit Protection Submerged Component Circuit Protection Submerged Component Circuit Protection Flood Protection Plan Submerged Component Circuit Protection Upgrade Seismic Monitoring Instruments Added Notes to Address Instrument Error for Various Parameters COLR, Cycle 3, Rev 2 Elimination of Response Time Testing xii Last Updated Revision 22 Watts Bar-Unit 1 Technical Requirements

Revisions Revision 23 Revision 24 Revision 25 Revision 26 Revision 27 Revision 28 Revision 29 Revision 30 Revision 31 Revision 32 Revision 33 Revision 34 Revision 35 Revision 36 Revision 37 Watts Bar-Unit 1 Technical Requirements TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES - REVISION LISTING Issued SUBJECT 01/22/01 Plant Calorimetric (LEFM) 03/19/01 TRM Change Control Program per 50.59 Rule 05/15/01 Change in Preventive Maintenance Frequency for Molded Case Circuit Breakers 05/29/01 Change CVI Response Time from 5 to 6 Seconds 01/31/02 Change pH value in the borated water sources due to TS change for ice weight reduction 02/05/02 Refueling machine upgrade under DCN D-50991-A 02/26/02 Added an additional action to TR 3.7.3 to perform an engineering evaluation of inoperable snubber's impact on the operability of a supported system.

06/05/02 Updated TR 3.3.5.1 to reflect implementation of the TIPTOP program in a Technical Instruction (TI).

10/31/02 Correct RTP to 3459 MWt (PER 02-9519-000) 09/17/03 Editorial correction to Bases for TSR 3.1.5.3.

10/14/03 Updated TRs 3.1.5 and 3.1.6 and their respective bases to incorporate boron concentration changes in accordance with change packages WBN-TS-02-14 and WBN-TS-03-017.

05/14/04 Revised Item 5, "Source Range, Neutron Flux" function of Table 3.3.1-1 to provide an acceptable response time of less than or equal 0.5 seconds. (Reference TS Amendment 52.)

04/06/05 Revised Table 3.3.2-1, "Engineered Safety Features Actuation systems Response Times," to revise containment spray response time and to add an asterisk note to notation 13 of the table via Change Package WBN-TS-04-16.

09/25/06 Revised the response time for Containment Spray in Table 3.3.2-1 and the RTNDT values in the Bases for TR 3.7.1. Both changes result from the replacement of the steam generators, 11/08/06 Revised TR 3.1.5 and 3.1.6 and the Bases for these TRs to update the boron concentration limits of the RWST and the BAT.

xiii Last Updated Revision 37

TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES REVISION LISTING Revisions Issued SUBJECT Revision 38 11/29/06 Updated the TRM to be consistent with Tech Spec Amendment

55. TRM Revision 38 modified the requirements for mode change limitations in TR 3.0.4 and TSR 3.0.4 by incorporating changes similar to those outlined in TSTF-359, Revision 9.

(TS-06-24)

Revision 39 04/16/07 Updated the TRM to be consistent with Tech Spec Amendment 42.

TRM Revision 39 modified the requirements of TSR 3.0.3 by incorporating changes similar to those outlined in TSTF-358.

(TS-07-03)

Revision 40 05/24/07 Updated the TRM and Bases to remove the various requirements for the submittal of reports to the NRC. (TS-07-06)

Revision 41 05/25/07 Revision 41 updates the Bases of TR 3.1.3, 3.1.4 and 3.4.5 to be consistent with Technical Specification Amendment 66. This amendment replaces the references to Section XI of the ASME Boiler and Pressure Vessel Code with the ASME Operation and Maintenance Code for Inservice Testing (IST) activities and removes reference to "applicable supports" from the IST program.

Revision 42 03/20/2008 Revision 42 updates Figure 3.1.6 to remove the 240 TPBAR Limit.

Revision 43 07/17/2008 Revision 43 removes a reporting requirement from TR 3.7.4, "Sealed Source Contamination." The revision also updates the Bases for TR 3.7.4.

Revision 44 10/10/2008 Revision 44 updates Table 3.3.1-1 to be consistent with the changes approved by NRC as Tech Spec Amendment 68.

Revision 45 02/23/2009 Added TR 3.3.8, "Hydrogen Monitors," and the Bases for TR 3.3.8.

This change is based on Technical Specification (TS) Amendment 72 which removed the Hydrogen Monitors (Function 13 of LCO 3.3.3) from the TS.

Watts Bar-Unit 1 xiv Technical Requirements Last Updated Revision 45 WBN, Unit 1, Technical Requirements Manual - Changed Pages

RTS Instrumentation TR 3.3.1 Table 3.3.1-1 (Page 1 of 2)

Reactor Trip System Instrumentation Response Times FUNCTIONAL UNIT RESPONSE TIME

1.

Manual Reactor Trip

2.

Power Range, Neutron Flux N.A.

a. High

b. Low

3.

Power Range, Neutron Flux

a.

High Positive Rate

b.

High Negative Rate

4.

Intermediate Range, Neutron Flux

5.

Source Range, Neutron Flux

< 0.5 second(')

< 0.5 second(I 1

N.A.

Deleted N.A.

< 0.5 seconds(')

< 8 seconds(

1 )

8 seconds(')

I

6.

Overtemperature AT

7.

Overpower AT

8.

Pressurizer Pressure

a.

Low

b. High

< 2 seconds

_ 2 seconds

9.

Pressurizer Water Level-High N.A.

(continued)

(1)

Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from the detector output or input of first electronic component in channel.

05/14/04 3.3-3 Revision 7, 13, 34 Watts Bar-Unit 1 Technical Requirements

RTS Instrumentation TR 3.3.1 Table 3.3.1-1 (Page 2 of 2)

Reactor Trip System Instrumentation Response Times FUNCTIONAL UNIT RESPONSE TIME I

10.

11.

12.

13.

14.

Reactor Coolant Flow - Low Undervoltage-Reactor Coolant Pumps Underfrequency-Reactor Coolant Pumps Steam Generator Water Level-Low-Low Turbine Trip

a.

Low Fluid Oil Pressure

b.

Turbine Stop Valve Closure Safety Injection Input from ESF Reactor Trip System Interlocks Reactor Trip Breakers Reactor Trip Breaker UV and ST Automatic Trip and Interlock Logic

< 1.2 seconds

< 1.5 seconds(2)

_ 0.6 second(3)

< 2 seconds(4)

N.A.

15.

16.

17.

18.

19.

(2)

Includes sensor delay time, adjustable time delay, logic and breaker trip times, gripper release (150 msec.) and EMF decay time (250 msec.).

(3)

Includes sensor delay time, adjustable time delay, logic and breaker trip times and gripper release time (150 msec.).

(4)

With Trip TimeDelay (TTD) = 0 seconds.

Watts Bar-Unit 1 Technical Requirements 3.3-4 10/09/08 Revision 44

Plant Calorimetric Measurement TR 3.3.7 TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.7.1 Verify availability of the LEFM using the self-diagnostics feature Prior to performance indicated by the LEFM Normal/Alert/Fail status indication, as of SR 3.3.1.2.

displayed on the plant computer system, is not in Fail status.

Watts Bar-Unit 1 Technical Requirements 3.3-23 01/22/01 Revision 23

Hydrogen Monitors TR 3.3.8 TR 3.3 INSTRUMENTATION TR 3.3.8 Hydrogen Monitors TR 3.3.8 Two Hydrogen Monitors shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One Hydrogen Monitor A.1 Restore required channel to 30 days inoperable.

OPERABLE status.

B.

Required Action and B.1 Document in accordance with In accordance with associated Completion the Corrective Action Program.

the Corrective Action Time of Condition A not Program.

met.

C.

Two hydrogen monitors C.1 Restore one hydrogen monitor 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable, to OPERABLE status.

D.

Required Action and D.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C not AND met.

D.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Watts Bar-Unit 1 3.3-24 Revision 45

Hydrogen Monitors TR 3.3.8 TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.8.1 Perform CHANNEL CHECK.

31 days TSR 3.3.8.2 Perform COT.

31 days TSR 3.3.8.3 Perform CHANNEL CALIBRATION.

18 months Watts Bar-Unit 1 3.3-25 Revision 45

THIS PAGE INTENTIONALLY LEFT BLANK

Snubbers TR 3.7.3 6

5 4

C 3

2 1

Continue testing region N = 36.49 + 18.18C Accept region

. -1.

ý.

30 40 50 60 70 80 90 100 110 120 130 N.

N =

Total number of snubbers tested C =

Number of snubbers which do not meet functional test acceptance criteria FIGURE 3.7.3-1 Sample Plan B for Snubber Functional Test Watts Bar-Unit 1 Technical Requirements 3.7-21 09/30/95

Sealed Source Contamination TR 3.7.4 TR 3.7 PLANT SYSTEMS TR 3.7.4 Sealed Source Contamination TR 3.7.4 APPLICABILITY:

The removable contamination shall be < 0.005 microcuries for each sealed source containing radioactive material > 100 microcuries of beta and/or gamma emitting material or > 5 microcuries of alpha emitting material.

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME NOTE A.

Sealed source TR 3.0.3 is not applicable.

c o n ta m in a tio n n o t w ith in limit.

A.1 Remove sealed source Immediately from use.

AND A.2.1 Decontaminate and repair Prior to sealed source.

returning the sealed source to use.

OR A.2.2 Dispose of sealed source in In accordance accordance with NRC with NRC regulations.

regulations.

I Watts Bar-Unit 1 Technical Requirements 3.7-22 07/17/08 Revision 43

Hydrogen Monitors B 3.3.8 B 3.3 INSTRUMENTATION B 3.3.8 Hydrogen Monitors BASES BACKGROUND Hydrogen Monitors are provided to detect high hydrogen concentration conditions that represent a potential for containment breach from a hydrogen explosion. This variable is also important in verifying the adequacy of post-accident mitigating actions. Hydrogen concentration may also be used to determine whether or not the Hydrogen Ignitors should be started or other action taken. Containment hydrogen instrumentation consists of two trains on separate power supplies with a range of 0-10% (by volume) hydrogen concentration.

By rule change in 2003, 10 CFR 50.44 (Ref. 1) no longer defined a design basis Loss of Coolant Accident (LOCA) hydrogen release, and eliminated the requirements for hydrogen control systems to mitigate such a release. The installation of Hydrogen Recombiners and/or vent and purge systems required by 50.44(b)(3) prior to revision in 2003 was intended to address the limited quantity and rate of hydrogen generation that was postulated from a design basis LOCA.

The Commission found that this hydrogen release was not risk significant because the design-basis LOCA hydrogen release did not contribute to the conditional probability of a large release up to approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the onset of core damage. In addition, these systems were ineffective at mitigating hydrogen releases from risk significant accident sequences that could threaten Reactor Building integrity. The Improved Standard Technical Specifications (ISTS) at the time stated that Hydrogen Recombiners met 10 CFR 50.36(c)(2)(ii)

Criterion 3 (accident mitigation). As stated in the rule change, since Hydrogen Recombiners are no longer required to respond to a LOCA, the Hydrogen Recombiners no longer meet Criterion 3 or any of the other criteria for retention in the Technical Specifications (TSs). Therefore, the new rule states that the requirements related to Hydrogen Recombiners currently in the ISTS no longer meet the criteria of 10 CFR 50.36(c)(2)(ii) for retention in the TSs and may be eliminated.

With the elimination of the design-basis LOCA hydrogen release, the Hydrogen Monitors are also no longer required to mitigate design basis accidents and, therefore, the Hydrogen Monitors do not meet the definition of a safety-related component as defined in 10 CFR 50.2 (Ref. 2). Regulatory Guide (RG) 1.97 (Ref. 3) Category 1 instrumentation is intended for key variables that most directly indicate the accomplishment of a safety function for design basis accident events. The Hydrogen Monitors no longer meet the definition of Category 1 in RG 1.97. As part of the rulemaking to revise 50.44 the Commission found that Category 3, as defined in RG 1.97, is an appropriate categorization for the Hydrogen Monitors because the monitors are required to (continued)

Wafts Bar-Unit 1 B 3.3-25 Revision 45

Hydrogen Monitors B 3.3.8 BASES BACKGROUND (continued) diagnose beyond design basis accidents. Hydrogen monitoring is not the primary means of indicating a significant abnormal degradation of the reactor coolant pressure boundary and has been found to not be risk-significant.

Therefore, the rule making stated that hydrogen monitoring equipment requirements no longer meet the criteria of 50.36(c)(2)(ii) for retention in TSs and, therefore, may be removed from the TSs.

APPLICABLE SAFETY ANALYSES As stated in the BACKGROUND section, the Hydrogen Monitors are no longer required for mitigation of design basis accidents. Based on this, the Hydrogen Monitors do not meet the definition of a safety-related component.

However, the elimination of Hydrogen Recombiners in accordance with Technical Specification Task Force (TSTF)-447, Rev. 1 (Ref. 4), was contingent on each licensee maintaining the capability to monitor hydrogen concentrations in the Reactor Building during beyond design basis accidents. This TR maintains that commitment (Ref. 5).

TR Two Hydrogen Monitors are required to be OPERABLE to ensure that the necessary equipment will be available to monitor the hydrogen concentration within containment during significant beyond design-basis accident conditions (Ref. 5).

APPLICABILITY The Hydrogen Monitors are required to be OPERABLE in MODES 1, 2 and 3. In MODES 4, 5, and 6, unit conditions are such that the likelihood of an event that would require Hydrogen Monitors is low; therefore, the monitors are not required to be OPERABLE in these MODES.

ACTIONS A.1 Condition A applies when one Hydrogen Monitor is inoperable. Required Action A.1 requires restoring the inoperable channel to OPERABLE status within 30 days. The 30 day Completion Time is based on operating experience and takes into account the remaining OPERABLE Hydrogen Monitor, the passive nature of the instrument (no critical automatic action is assumed to occur from these instruments), and the low probability of a beyond design basis event occurring during the 30 day Completion Time.

(continued)

Wafts Bar-Unit 1 B 3.3-26 Revision 45

Hydrogen Monitors B 3.3.8 BASES ACTIONS B._I (continued)

Condition B applies when the Required Action and associated Completion Time for Condition A are not met. This Required Action specifies that the failure to comply with the 30 day Completion Time must be documented in the Corrective Action Program so that the impact of the inoperable equipment with regard to continued plant operation may be evaluated. Consideration should be given to alternate means, such as core damage assessments performed under the Severe Accident Management Guidelines during the extended period the one Hydrogen Monitor is inoperable. During normal operations the probability of occurrence of a beyond design basis accident is low and therefore, continued plant operation should not be significantly impacted. However, the actions required to restore the inoperable monitor should be pursued in a manner that is commensurate with the component's importance to safety.

C.A Condition C applies when two Hydrogen Monitors are inoperable. Required Action C. 1 requires the restoration of one hydrogen monitor channel to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

D.1 Condition D applies when the Required Action and associated Completion Time of Condition C is not met and requires that the plant must be brought to a MODE where the requirements of this TR do not apply. To achieve this status, the plant must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

TECHNICAL SR 3.3.3.1 SURVEILLANCE REQUIREMENTS Performance of the CHANNEL CHECK once every 31 days ensures that a gross instrumentation failure has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels (continued)

Wafts Bar-Unit 1 B 3.3-27 Revision 45

Hydrogen Monitors B 3.3.8 BASES TECHNICAL monitoring the same parameter should read approximately the same value.

SURVEILLANCE Significant deviations between the two instrument channels could be an REQUIREMENTS indication of excessive instrument drift in one of the channels or of something (continued) even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the unit staff, based on a combination of the channel instrument uncertainties, including isolation, indication, and readability. If a channel is outside the criteria, it may be an indication that the sensor or the signal processing equipment has drifted outside its limit. If the channels are within the criteria, it is an indication that the channels are OPERABLE.

The Frequency of 31 days is based on operating experience that demonstrates that channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the LCO required channels.

SR 3.3.3.2 A COT is performed on each Hydrogen Monitor every 31 days to ensure the channel will perform the intended function. The 31 day Frequency is based on the known reliability of the Hydrogen Monitors, and has been shown to be acceptable through operating experience.

For this SR, a COT is satisfied by performance of a calibration check of the analyzer with zero, span, and at least one known gas and verification of alarm display functions. System flows shall be verified against target values and reagent and calibration gas supplies should be checked.

SR 3.3.3.3 A CHANNEL CALIBRATION is performed every 18 months, or approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies that the channel responds to measured parameter with the necessary range'and accuracy. The Frequency is based on operating experience and consistency with the typical industry refueling cycle.

(continued)

Wafts Bar-Unit 1 B 3.3-28 Revision 45

Hydrogen Monitors B 3.3.8 BASES REFERENCES

1.

10 CFR 50.44, "Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors," October 16, 2003.

2.

10 CFR 50.2, "Definition of Safety Related Structures, Systems, and Components."

3.

Regulatory Guide 1.97, Revision 2, December 1980, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident."

4.

TSTF-447, Revision 1, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors."

5.

Commitment (NCO080031001) made in TVA's letter dated September 4, 2008, to maintain a hydrogen monitoring system capable of diagnosing beyond design basis accidents.

Watts Bar-Unit 1 B 3.3-29 Revision 45

THIS PAGE INTENTIONALLY LEFT BLANK

Sealed Source Contamination B 3.7.4 BASES (continued)

ACTIONS Since this TR is applicable at all times, the Required Actions have been modified by a Note stating that the provisions of TR 3.0.3 do not apply.

A..1 With a sealed source having removable contamination in excess of the limits, the sealed source should be withdrawn from use immediately. The immediate Completion Time reflects the importance of preventing the contamination from spreading.

A.2.1 and A.2.2 If the sealed source contamination is not within the specified limit and the sealed source has been removed from use, the sealed source must be decontaminated and repaired, otherwise, disposal of the sealed source is required. If the sealed source is to be decontaminated and repaired, it must be done prior to returning the sealed source to use. If disposal of the sealed source is to be done, it must be completed in accordance with NRC regulations.

TECHNICAL SURVEILLANCE REQUIREMENTS Notes have been added to this section stating that the licensee or other persons specifically authorized by the NRC shall perform the TSRs, and that the test methods used shall have a detection sensitivity of greater than or equal to 0.005 microcurie per test sample.

TSR 3.7.4.1 This surveillance determines every 6 months that the removable contamination is less than 0.005 microcuries for each sealed source. The 6-month Frequency is frequent enough to identify a leaking or contaminated sealed source without.

having extensive spreading of contamination.

This surveillance is modified by several Notes. The Notes state that this TSR is only applicable to sources in use, to sources with half-lives of more than 30 days, and to sources in any form other than gas. Also, this TSR is not applicable to startup sources and fission detectors previously subjected to core flux.

(continued)

Watts Bar-Unit 1 Technical Requirements B 3.7-19 07/17/08 Revision 43

Sealed Source Contamination B 3.7.4 BASES TECHNICAL SURVEILLANCE REQUIREMENTS (continued)

TSR 3.7.4.2 This surveillance determines within 6 months prior to use or transfer to another licensee that the removable contamination is less than 0.005 microcuries for each sealed source and fission detector. This Frequency is adequate to identify a leaking or contaminated sealed source or fission detector to avoid extensive contamination.

This surveillance is modified by two Notes. The first Note states that this TSR is only applicable to sealed sources not in use. The second Note states that sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed in use.

TSR 3.7.4.3 This surveillance determines that the removable contamination is less than 0.005 microcuries for each startup source and fission detector. This test should be performed on each startup source and incore fission detector within 31 days prior to being installed in the core or being subjected to core flux. It also should be performed following any repairs or maintenance to the source. This Frequency ensures that the startup source or fission detector is not leaking or contaminated over the specified limit.

This Surveillance is modified by a Note stating this TSR only applies to startup sources and incore fission detectors that are not in use.

(continued)

Watts Bar-Unit 1 Technical Requirements B 3.7-20 09/30/95

ML101121087

Text

Subject:

Enclosures:

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