ML22242A007
| ML22242A007 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/17/2022 |
| From: | Duke Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML22242A007 (28) | |
Text
Duke Energy Date: BllZl:ZO:Z:Z Distribution:
Document Transmittal #: TR-NUC-CN-014687
- 1. (CNS) U S NUC REG WASHINGTON DC DOCUMENT TRANSMITTAL FORM
Purpose:
m.u_e
- 2. Andrews, Sherry E
- 3. Byers, Kaitlyn Released By:
~BOO C2at1:m! R2i!d
- 6.
CNS COMPL FILE (ORIG)X Issue SLC RevisiQns Dotument Management
- 7.
- 8.
- 9.
CNS RP SHIFT LAB CNSDCRM@duke-energy,tom
- 11. CONTROL ROOM SSA
- 12. Edmond, Russell L
- 13. Lowery, Tonya Sullivan
- 14. Mironenko, Artur N
- 15. OPS TRAINING
- 16. Owens, Lori
- 17. Pursley, Sandy
- 18. WESTINGHOUSE ELECTRIC CO LLC Page 1 of 1 Document ID
~1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 LICN - CN - CNS-SLC-16.2 - 001 - ISSUED FYI IE FYIIE FYIIE FYIJ LP FYIIE FYII E FYI IE FYI IE FYI IE FYI IE FYIJ LP FYI IE FYII E FYIIE FYIIE FYI IE FYI JE FYI IE LICN - CN - CNS-SLC-16.5 002 - ISSUED FYIIE FYIJE FYIIE FYIILP FYI IE FYIIE FYIJE FYIIE FYIJE FYIJE FYI JLP FYIIE FYIIE FYIIE FYIJE FYIIE FYIJE FYIIE LICN - CN - CNS-SLC-16.6 002 - ISSUED FYI IE FYIIE FYII E FYI JLP FYI IE FYIIE FYIIE FYI IE FYII E FYIIE FYIILP FYI IE FYIIE FYI IE FYII E FYI IE FYI IE FYIIE LICN - CN - CNS-SLC-16.7 007 - ISSUED FYI IE FYI IE FYIIE FYIJ LP FYI IE FYI IE FYIIE FYI IE FYIIE FYII E FYIJ LP FYI IE FYIIE FYII E FYI IE FYIIE FYIIE FYI IE LICN - CN - CNS-SLC-16.9 002 - ISSUED FYI IE FYIIE FYIIE FYI JLP FYIIE FYIJE FYIIE FYI JE FYIIE FYI IE FYIILP FYIIE FYII E FYI IE FYI IE FYIIE FYII E FYIIE LICN - CN - CNS-SLC-LOES - 111 - ISSUED FYI IE FYIIE FYI IE FYI I LP FYIIE FYIIE FYIIE FYIIE FYI IE FYII E FYI I LP FYIIE FYII E FYIIE FYI IE FYI IE FYIIE FYIIE LICN - CN - CNS-SLC-Manual-TOC - 016 -
FYIIE FYIIE FYIIE FYIILP FYIIE FYI IE FYIIE FYI IE FYIIE FYIIE FYIILP FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE ISSUED Remarks: Cl".fS Reg Affai[:ii URdi!tiD9 bi!td t2Rie:;, 1:.sue i!II SLC [eitisi2ns,
SECTION 16.1 16.2 16.3 16.5 16.5-1 16.5-2 16.5-3 16.5-4 16.5-5 16.5-6 16.5-7 16.5-8 16.5-9 16.5-10 16.6 16.6-1 16.6-2 16.6-3 I
16.6-4 TITLE INTRODUCTION APPLICABILITY DEFINITIONS TABLE OF CONTENTS COMMITMENTS RELATED TO REACTOR COOLANT SYSTEM
.PAGE 16.1-1 16.2-1 16.3-1 Reduced Inventory and Mid-Loop Operation with Irradiated 16.5-1-1 Fuel in the Core Deleted Chemistry 16.5-3-1 Pressurizer 16.5-4-1 Structural Integrity 16.5-5-1 Reactor Coolant System (RCS) Vents 16.5-6-1 Steam Generator (SG) Pressure/Temperature Limitation 16.5-7-1 Deleted Deleted Deleted COMMITMENTS RELATED TO ENGINEERED SAFETY FEATURES Containment Sump Deleted Inlet Door Position Monitoring System Chlorine Detectors and Associated Circuitry 16.6-1-1 16.6-3-1 16.6-4-1 16.6-5 Residual Heat Removal/Containment Spray Sump Pump 16.6-5-1 Interlock 16.7 COMMITMENTS RELATED TO INSTRUMENTATION 16.7-1 16.7-2 16.7-3 A TWS Mitigation System Actuation Circuitry (AMSAC)
Seismic Instrumentation Meteorological Instrumentation Catawba Units 1 and 2 16.7-1-1 16.7-2-1 16.7-3-1 Rev.ision 16
TABLE OF CONTENTS SECTION TITLE PAGE 16.7-4 Loose-Part Detection System 16.7-4-1 16.7-5 Turbine Overspeed Protection 16.7-5-1 16.7-6 RN Discharge Instrumentation 16.7-6-1 16.7-7 Movable lncore Detectors 16.7-7-1 16.7-8 Groundwater Level 16.7-8-1 16.7-9 Standby Shutdown System (SSS) 16.7-9-1 16.7-10 Radiation Monitoring for Plant Operations 16.7-10-1 16.7-11 Position Indication System - Shutdown 16.7-11-1 16.7-12 Position Indication System -Test Exception 16.7-12-1 16.7-13 Auxiliary Feedwater (AFW) Pump Turbine Steam Supply 16.7-13-1 Piping Temperature Monitoring System 16.7-14 Trip of All Main Feedwater Pumps Turbine Trip 16.7-14-1 Instrumentation 16.7-15 Hydrogen Monitors 16.7-15-1 16.7-16 Reactor Trip Breaker and Solid State Protection System 16.7-16-1 (SSPS) Logic Train Out of Service Commitments 16.7-17 Spent Fuel Pool (SFP) Wide Range (WR) Level 16.7-17-1 Instrumentation 16.7-18 Leading Edge Flow Meter (LEFM) System 16.7-18-1 16.8 COMMITMENTS RELATED TO ELECTRICAL POWER SYSTEMS 16.8-1 Containment Penetration Conductor Overcurrent Protective16.8-1-1 Devices (CPCOPDs) 16.8-2 230 kV Switchyard Systems 16.8-2-1 16.8-3 230 kV Switchyard 125 VDC Power System 16.8-3-1 16.8-4 6900 V Standby Transformers 16.8-4-1 16.8-5 Diesel Generator Supplemental Testing Requirements 16.8-5-1 16.9 COMMITMENTS RELATED TO AUXILIARY SYSTEMS Catawba Units 1 and 2 ii Revision 16
TABLE OF CONTENTS SECTION TITLE PAGE 16.9-1 Fire Suppression Water Systems 16.9-1-1 16.9-2 Sprinkler and Spray Systems 16.9-2-1 16.9-3 CO2 Systems 16.9-3-1 16.9-4 Fire Hose Stations 16.9-4-1 I
16.9-5 Fire Rated Assemblies 16.9-5-1 16.9-6 Fire Detection Instrumentation 16.9-6-1 16.9-7 Boration Systems Flow Path - Shutdown 16.9-7-1 16.9-8 Boration Systems Flow Paths - Operating 16.9-8-1 16.9-9 Boration Systems Pumps - Shutdown 16.9-9-1 16.9-10 Boration Systems Charging Pumps - Operating 16.9-10-1 16.9-11 Boration Systems B.orated Water Source - Shutdown 16.9-11-1 16.9-12 Boration Systems Borated Water Sources - Operating 16.9-12-1 16.9-13 Snubbers 16.9-13-1 16.9-14 Lake Wylie Water Temperature 16.9-14-1 16.9-15 Auxiliary Building Filtered Exhaust System (ABFVES) 16.9-15-1 Filter Cooling Bypass Valves 16.9-16 Fuel Handling Ventilation Exhaust System (FHVES) 16.9-16-1 Filter Cooling Bypass Valves 16.9-17 Refueling Operations - Decay Time 16.9-17-1 16.9-1,8 Deleted 16.9-19 Refueling Operations - Manipulator Crane 16.9-19-1 16.9-20 Refueling Operations - Crane Travel - Spent Fuel Storage 16.9-20-1 Pool Building 16.9-21 Refueling Operations - Storage Pool Water Level 16.9-21-1 16.9-22 Control Room Area Ventilation System - Intake Alarms 16.9-22-1 16.9-23 Fire Hydrants 16.9-23-1 Catawba Units 1 and 2 iii Revision 16
SECTION 16.9-24 16.9-25 16.9-26 16.10 16.10-1 16.10-2 16.10-3 16.10-4 16.10-5 16.11 16.11-1 16.11-2 16.11-3 16.11-4 16.11-5 16.11-6 16.11-7 16.11-8 16.11-9 16.11-10 16.11-11 16.11-12 TITLE TABLE OF CONTENTS Alternate Cooling for Charging Pumps Tornado Isolation Dampers PAGE 16.9-24-1 16.9-25-1 Commitments Associated With Movement of Non-Recently 16.9-26-1 Irradiated Fuel Assemblies COMMITMENTS RELATED TO STEAM AND POWER CONVERSION SYSTEMS Steam Vent to Atmosphere 16.10-1-1 Condenser Circulating Water System 16.10-2-1 Auxiliary Feedwater (AFW) Flow Control Valve Air 16.10-3-1 Accumulators Motor Driven Auxiliary Feedwater Pump Pit (WL) Sump 16.10-4-1 Pumps Auxiliary Feedwater Turbine Driven Pump Pit (WL) Sump 16.10-5-1 Pumps COMMITMENTS RELATED TO RADIOACTIVE WASTE MANAGEMENT Liquid Effluents Radioactive Liquid Effluent Monitoring Instrumentation Dose Liquid Radwaste Treatment System Chemical Treatment Ponds Gaseous Effluents Radioactive Gaseous Effluent Monitoring Instrumentation Dose - Noble Gases Dose - lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form Gaseous Radwaste Treatment System Solid Radioactive Wastes Total Dose 16.11-1-1 16.11-2-1 16.11-3-1 16.11-4-1 16.11-5-1 16.11-6-1 16.11-7-1 16.11-8-1 16.11-9-1 16.11-10-1 16.11-11-1 16.11-12-1 Catawba Units 1 and 2 iv Revision 16
TABLE OF CONTENTS SECTION TITLE PAGE 16.11-13 Monitoring Program 16.11-13-1 16.11-14 Land Use Census 16.11-14-1 16.11-15 lnterlaboratory Comparison Program 16.11-15-1 16.11-16 Annual Radiological Environmental Operating Report and 16.11-16-1 Radioactive Effluent Release Report 16.11-17 Liquid Holdup Tanks 16.11-17-1 16.11-18 Explosive Gas Mixture 16.11-18.-1 16.11-19 Gas Storage Tanks 16.11-19-1 16.11-20 Explosive Gas Monitoring Instrumentation 16.11-20-1 16.11-21 Major Changes to Liquid, Gaseous, and Solid Radwaste 16.11-21-1 Treatment Systems 16.12 COMMITMENTS RELATED TO RADIATION PROTECTION 16.12-1 Sealed Source Contamination 16.12-1-1 16.13 COMMITMENTS RELATED TO CONDUCT OF OPERATIONS 16.13-1 Fire Brigade 16.13-1-1 16.13-2 Deleted 16.13-3 Deleted 16.13-4 Minimum Station Staffing Requirements 16.13-4-1 Catawba Units 1 and 2 V
Revision 16
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE TABLE OF CONTENTS 16 08/17/22 16.1 1
08/27/08 16.2 3
08/17/22 16.3 1
08/21/09 16.5-1 7
03/30/21 16.5-2 Deleted 16.5-3 2
09/19/19 16.5-4 1
01/27/22 16.5-5 1
01/28/10 16.5-6 3
08/17/22 16.5-7 2
02/06/15 16.5-8 Deleted 16.5-9 Deleted 03/02/21 16.5-10 Deleted 16.6-1 0
10/09/02 16.6-2 Deleted 16.6-3 2
01/27/22 16.6-4 3
08/17/22 16.6-5 3
07/07/20 16.7-1 1
08/21/09 16.7-2 4
02/03/11 16.7-3 5
11/21/19 16.7-4 2
08/21/09 16.7-5 7
06/01/22 Catawba Units 1 and 2 Page 1 Revision 111
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.7-6 3
06/10/16 16.7-7 2
06/14/22 16.7-8 2
08/21/09 16.7-9 15 08/17/22 16.7-10 10 01/27/22 16.7-11 1
08/21/09 16.7-12 1
08/21/09 16.7-13 3
06/10/16 16.7-14 1
08/21/09 16.7-15 2
01/27/22 16.7-16 0
06/08/09 16.7-17 0
02/10/15 16.7-18 0
05/10/16 16.8-1 8
01/27/22 16.8-2 3
12/18/19 16.8-3 2
06/14/22 16.8-4 2
11/05/07 16.8-5 3
08/21/09 16.9-1 10 01/29/19 16.9-2 6
08/03/17 16.9-3 5
07/03/18 16.9-4 5
09/11/17 16.9-5 11 10/08/19 16.9-6 12 07/03/18 Catawba Units 1 and 2 Page 2 Revision 111
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.9-7 4
08/21/09 16.9-8 5
08/21/09 16.9-9 3
08/21/09 16.9-10 5
08/21/09 16.9-11 3
08/21/09 16.9-12 3
02/10/15 16.9-13 4
09/27/16 16.9-14 1
09/25/06 16.9-15 2
08/21/09 16.9-16 2
08/21/09 16.9-17 0
10/09/02 16.9-18 Deleted 16.9-19 3
02/20/12 16.9-20 0
10/09/02 16.9-21 1
10/13/16 16.9-22 3
08/17/22 16.9-23 5
08/03/17 16.9-24 2
10/24/06 16.9-25 2
08/21/09 16.9-26 1
11/15/18 16.10-1 1
08/21/09 16.10-2 1
10/24/06 16.10-3 1
08/21/09 16.10-4 0
08/04/20 Catawba Units 1 and 2 Page 3 Revision 111
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.10-5 1
03/16/21 16.11-1 1
07/27/13 16.11-2 9
07/07/22 16.11-3 0
10/09/02 16.11-4 1
08/21/09 16.11-5 0
10/09/02 16.11-6 3
08/03/15 16.11-7 14 05/03/22 16.11-8 0
10/09/02 16.11-9 0
10/09/02 16.11-10 1
08/21/09 16.11-11 1
03/20/03 16.11-12 0
10/09/02 16.11-13 1
07/27/13 16.11-14 0
10/09/02 16.11-15 0
10/09/02 16.11-16 1
10/24/11 16.11-17 0
10/09/02 16.11-18 1
08/21/09 16.1,1-19 0
10/09/02 16.11-20 3
11/21/19 16.11-21 0
10/09/02 16.12-1 0
10/09/02 16.13-1 1
08/03/17 16.13-2 Deleted Catawba Units 1 and 2 Page4 Revision 111
SECTION 16.13-3 16.13-4 Catawba Units 1 and 2 LIST OF EFFECTIVE SECTIONS REVISION NUMBER Deleted 4
Page 5 REVISION DATE 10/04/21 Revision 111
Applicability 16.2 16.2,, APPLICABILITY This section provides the general requirements applicable to each of the
- COMMITMENTS and Testing Requirements within Section 16.0, Selected Licensee Commitments (SLCs).
16.2.1 COMMITMENTS shall be met during the MODES or other specified conditions in the Applicability.
16.2.2 Upon discovery of a failure to meet a COMMITMENT, the associated REMEDIAL ACTION(S) shall be met, except as provided in SLC 16.2.10, SLC 16.2.11, and SLC 16.2.12. If the COMMITMENT is met or is no longer applicable prior to expiration of the specified time interval, completion of the REMEDIAL ACTION(S) is not required, unless otherwise stated.
16.2.3 Deleted.
16.2.4 COMMITMENTS including the associated REMEDIAL ACTIONS shall apply to each unit individually unless otherwise indicated as follows:
- a.
Whenever.the COMMITMENT refers to systems or components which are shared by both units, the REMEDIAL ACTIONS will apply to both
.units simultaneously. This will be indicated in the REMEDIAL ACTIONS; b.
C.
Whenever the COMMITMENT applies to only one unit, this will be identified in the APPLICABILITY section of the COMMITMENT; and Whenever certain portions of a COMMITMENT contain operating parameters, setpoints, etc., which are different for each unit, this will be identified in parentheses or footnotes. (For example, "...flow rate of 54,000 cfm (Unit 1) or43,000 cfm (Unit 2)... ".)
16.2.5 Testing Requirements shall be met during the OPERATIONAL MODES or other specified conditions in the Applicability for individual COMMITMENTS unless otherwise stated in an individual Testing Requirement or Reference.
Failure to meet a Testing Requirement, whether such failure is experienced J.,
during the performance of the Testing Requirement.or between performances of the Testing Requirement, shall be failure to meet the COMMITMENT.
Failure to perform a Testing Requirement within the specified Frequency shall be failure to meet the COMMITMENT except as provided in SLC 16.2.7.
Testing Requirements do not have to be performed on non-functional equipment or variables outside specified limits.
Catawba Units 1 and 2 16.2-1 Revision 3
.J
Applicability 16.2 16.2.6 The specified Frequency for each Testing Requirement is met if the Testing Requirement is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
For Frequencies specified as "once," the above interval extension does not apply.
If a Completion Time requires periodic performance on a "once per... " basis, the above Frequency extension applies to each performance after the initial performance.
Exceptions to this SLC are stated in the individual SLCs.
16.2.7 If it is discovered that a Testing Requirement was not performed within its specified Frequency, then compliance with the requirement to declare the COMMITMENT not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Testing Requirement. A risk evaluation shall be performed for any Testing Requirement delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and the risk impact shall be managed.
If the Testing Requirement is not performed within the delay period, the COMMITMENT must immediately be declared not met, and the applicable REMEDIAL ACTIONS must be entered.
When the Testing Requirement is performed within the delay period and the Testing Requirement is not met, the COMMITMENT must immediately be declared not met, and the applicable REMEDIAL ACTIONS must be entered.
16.2.8 Deleted.
16.2.9 Testing Requirements shall apply to each unit individually unless otherwise indicated as stated in SLC 16.2.4 for individual COMMITMENTS or whenever certain portions of a COMMITMENT contain testing parameters different for each unit, which will be identified in parentheses or footnotes.
16.2.10 Under certain extenuating circumstances, as determined appropriate by the Station Manager.or his/her designee, it may be acceptable to deviate from the requirements of a COMMITMENT. Such deviation shall only be authorized for a limited time period (typically 14 days or less) and only after the appropriate justification has been prepared, approved, and concurred with by the Station Manager or his/her designee. This deviation shall be implemented in accordance with existing approved procedures. This is an exception to SLC 16.2.2.
Catawba Units 1 and 2 16.2-2 Revision 3
Applicability 16.2 16.2.11 Equipment removed from service or declared non-functional to comply with REMEDIAL ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its FUNCTIONALITY or the FUNCTIONALITY of other equipment. This is an exception to SLC 16.2.2 for the system returned to service under administrative control to perform the required testing to demonstrate FUNCTIONALITY.
16.2.12 When a supported system COMMITMENT is not met solely due to a support system COMMITMENT not being met, the Conditions and REMEDIAL ACTIONS associated with this supported system are not required to be entered. Only the support system REMEDIAL ACTIONS are required to be entered. This is an exception to SLC 16.2.2 for the supported system.
When a support system's REMEDIAL ACTION directs a supported system to be declared non-functional or directs entry into Conditions and REMEDIAL ACTIONS for a supported system, the applicable Conditions and REMEDIAL ACTIONS shall be entered in accordance with SLC 16.2.2.
Catawba Units 1 and 2 16.2-3 Revision 3
RCS Vents 16.5-6 16.5
- REACTOR COOLANT SYSTEM 16.5-6 Reactor Coolant System (RCS) Vents
. COMMITMENT One RCS vent path consisting of at least two valves in series powered from emergency buses shall be FUNCTIONAL and closed at each of the following locations:
- a.
Reactor vessel head, and
- b.
--- ----NOTE--------
lf using a power operated relief valve (PORV) as a vent path, the PORV block valve is not required to be closed if the PORV is OPERABLE (MODES 1, 2, and 3) or FUNCTIONAL (MODE 4).
Pressurizer steam space APPLICABILITY:
MODES 1, 2, 3, and 4.
REMEDIAL ACTIONS A.
CONDITION REQUIRED ACTION COMPLETION TIME One RCS vent path non-A.1 Initiate action to close and Immediately functional.
remove power from all valves in the non-functional vent path.
A.2 Restore the non-functional 30 days vent path to FUNCTIONAL status.
(continued)
Catawba Units 1 and 2 16.5-6-1 Revision 3
RCS Vents 16.5-6 REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
Both RCS vent paths B.1 Initiate action to close and Immediately non-functional.
remove power from all valves in the non-functional vent paths.
AND B.2 Restore at least one non-72 hours functional vent path to FUNCTIONAL status.
C.
Required Action and C. 1 Initiate a Condition Report Immediately associated Completion in accordance with the Time not met.
Corrective Action Program.
TESTING REQUIREMENTS TEST FREQUENCY TR 16.5-6-1 ----- ----------NOTE--------
This TR shall be performed during MODE 5 or MODE 6.
BASES Demonstrate that each RCS vent path is FUNCTIONAL by cycling each valve in the vent path through at least one complete cycle of full travel from the control room.
18 months RCS vents are provided to exhaust noncondensible gases and/or steam from the primary system that could inhibit natural circulation core cooling. The FUNCTIONALITY of at least one RCS vent path from the reactor vessel head, and the pressurizer steam space ensures the capability exists to perform this function. There are no manual isolation valves in either RCS vent path.
Catawba Units 1 and 2 16.5-6-2 Revision 3
BASES (continued)
RCS Vents 16.5-6 The valve redundancy of the RCS vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve, power supply or control system does not prevent isolation of the vent path.
A Condition Report initiated from Action C should include evaluation of loss of function to exhaust non-condensable gases, loss of ability to provide inventory control for standby shutdown facility events as a letdown path, and loss of alternate letdown path for other accident events.
The function, capabilities, and testing requirements of the RCS vent systems are consistent with the requirements of Item 11.B.1 of NUREG-0737, "Clarification of TM I Action Plan Requirements", November 1980.
REFERENCES
- 1.
Catawba Units 1 and 2 Letter from NRC to Gary R. Peterson, Duke, Issuance of Improved Technical Specifications Amendments for Catawba, September 30, 1998.
16.5-6-3 Revision 3
Chlorine Detectors and Associated Circuitry 16.6-4 16.6 ENGINEERED SAFETY FEATURES 16.6-4 Chlorine Detectors and Associated Circuitry COMMITMENT Four chlorine detectors and associated circuitry (two per control room intake), with their Alarm Setpoints adjusted to actuate at a chlorine concentration of:::_ 5 ppm, shall be FUNCTIONAL.
APPLICABILITY:
All MODES.
REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One chlorine detector A.1 Restore the non-functional 30 days and/or associated equipment to circuitry non-functional FUNCTIONAL status.
in one or both control room intakes.
B.
Required Action and B.1
NOTE-----------
associated Completion With both intakes isolated, Time of Condition A not both Control Room Area met.
Ventilation System (CRAVS) trains are inoperable and the applicable Conditions and Required Actions of Technical Specification 3.7.10 shall be entered and followed.
Isolate affected control 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> room intake(s).
(continued)
Catawba.Units 1 and 2 16.6-4-1 Revision 3
Chlorine Detectors and Associated Circuitry 16.6-4 REMEDIAL ACTIONS (continued)
C.
CONDITION Both chlorine detectors and/or associated circuitry non-functional in one or both control room intakes.
REQUIRED ACTION C.1
---NOTE------------
With both intakes isolated, both CRA VS trains are inoperable and the applicable Conditions and Required Actions of Technical Specification 3.7.10 shall be entered and followed.
Isolate affected control room intake(s).
COMPLETION TIME Immediately TESTING REQUIREMENTS TEST FREQUENCY TR 16.6-4-1 Perform COT.
6 months TR 16.6-4-2 Perform CHANNEL CALIBRATION.
18 months BASES The FUNCTIONALITY of the chlorine detectors and associated circuitry is provided as a defense-in-depth measure to ensure that sufficient capability is available to promptly detect and respond to an accidental chlorine release. The capability for the protection of control room personnel is consistent with the recommendations of Regulatory Guide 1.95, Revision 1, January 1977, "Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release."
Regulatory Guide 1.95 states in Section C.2 that the capability to manually isolate the control room should be provided "... if a chlorine container having an inventory of 150 lbs. or less is stored more than 100 meters from the control room or its fresh air intakes.... " All chlorine containers at Catawba are stored or used at least 158 meters (520 feet) from the nearest control room outside air intake and the inventory of chlorine in any single "container is less than or equal to 100 lbs. (Note that Catawba only uses 50-lb. cylinders with a maximum of two cylinders manifolded together.) Thus, automatic isolation/closure of an intake is Catawba Units 1 and 2 16.6-4-2 Revision 3
Chlorine Detectors and Associated Circuitry 16.6-4 BASES (continued)
REFERENCES not required and it is acceptable to leave an intake open for a limited time period even if a single detector on an intake were to alarm. This follows the implied logic of the Regulatory Guide that if the quantity of gaseous chlorine onsite is small enough, it is not credible to assume a chlorine container failure results in a significant impact to the control room. This position is documented in calculation CNC-1211.00-00-0124.
The REMEDIAL ACTIONS described above are consistent with the guidance provided in Regulatory Guide 1.78, Revision 0, June 1974, "Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release," and Regulatory Guide 1.95. Regulatory Guide 1.78 states in Section C.3 that
"... the release of any hazardous chemical to be stored on the nuclear plant site in a quantity greater than 100 lbs. should be considered... " for its impact on control room habitability. Catawba does not allow any gaseous chlorine containers greater than 100 lbs. on site. There are also no credible accident scenarios that would cause the failure of more than 100 lbs. of chlorine.
- 1.
- 2.
Letter from NRC to Gary R. Peterson, Duke, Issuance of Improved Technical Specifications Amendments for Catawba, September 30, 1998.
Letter from NRC to G.R. Peterson, Duke, Issuance of Amendments 191/183, June 28, 2001.
Catawba Units 1 and 2 16.6-4-3 Revision 3
16.7 INSTRUMENTATION 16.7-9 Standby Shutdown System (SSS)
COMMITMENT The SSS shall be FUNCTIONAL.
APPLICABILITY:
MODES 1, 2, and 3.
REMEDIAL ACTIONS CONDITION REQUIRED ACTION A.
SSS non-functional.
A.1 Restore SSS to FUNCTIONAL status.
B.
Total accumulative B.1 Declare the standby LEAKAGE from makeup pump non-unidentified LEAKAGE, functional and enter identified LEAKAGE, Condition A.
and reactor coolant pump seal LEAKAGE >
20 gpm.
C.
A required cell in a 24-C.1 Enter Condition A.
Volt battery bank is <
1.36 volts on float charge.
D.
Required Action and D. 1 Prepare and submit a associated Completion Special Report to the NRC Time of Condition A not outlining the extent of met.
repairs required, schedule for completing repairs, and basis for continued operation.
Catawba Units 1 and 2 16.7-9-1 sss 16.7-9 COMPLETION TIME 7 days Immediately Immediately 14 days Revision 15
TESTING REQUIREMENTS TEST TR 16.7-9-1 Verify that the electrolyte level of each SSS diesel starting 24-Volt battery is.::: the low mark and,:s the high mark.
TR 16.7-9-2 Verify that the overall SSS diesel starting 24-Volt battery voltage is.::: 24 volts on float charge.
TR 16.7-9-3 Verify that the requirements of SLC 16.9-21 are met and the boron concentration in the storage pool is.::: the minimum specified in the COLR.
TR 16.7-9-4 Verify the fuel level in the SSS diesel generator fuel storage tank is.::: 67 inches.
TR 16.7-9-5 Verify the SSS diesel generator starts from ambient conditions and operates for.::: 30 minutes at.::: 700 kW.
TR 16.7-9-6 Verify that the electrolyte level of each SSS 250/125-Volt battery is above the plates.
TR 16.7-9-7 Verify the total SSS 250/125-Volt battery terminal voltage is.::: 258/129 volts on float charge.
TR 16.7-9-8 Perform CHANNEL CHECK of each SSS instrumentation device.
TR 16.7-9-9 Verify the fuel oil properties of new and stored fuel oil for the SSS diesel generator are tested in accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing Program.
TR 16.7-9-10 Verify that the individual battery cell voltage of the required cells in the SSS diesel starting 24-Volt battery is
.::: 1. 36 volts on float charge.
Catawba Units 1 and 2 16.7-9-2 sss 16.7-9 FREQUENCY 7 days 7 days 7 days 31 days 31 days 31 days 31 days 31 days In accordance with the Diesel Fuel Oil Testing Program 92 days (continued)
Revision 15
TESTING REQUIREMENTS continued TEST TR,16.7-9-11 Verify that the Standby Makeup Pump's developed head at the test flow point is ~ the required developed head, in accordance with the lnservice Testing Program.
TR,16.7-9-12 Verify that the specific gravity of the SSS 250/125-Volt battery is appropriate for continued service of the battery.
TR 16.7-9-13 Subject the SSS diesel generator to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.
TR *16.7-9-14 Verify that the SSS diesel starting 24-Volt batteries, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration.
TR 16.7-9-15 Verify that the SSS diesel starting 24-Volt battery-to-battery and terminal connections are clean, tight, and free of corrosion.
TR 16.7-9-16 Verify that the SSS 250/125-Volt batteries, cell plates, and battery racks show no visual indications of physical damage or abnormal deterioration.
TR :16.7-9-17 Verify that the SSS 250/125-Volt battery-to-battery and terminal connections are clean, tight, free of corrosion, and coated with anti-corrosion material.
TR 16.7-9-18 Verify that the steam turbine driven auxiliary feedwater pump and controls from the Standby Shutdown Facility I
function as designed from the SSS.
TR 16.7-9-19 Perform CHANNEL CALIBRATION of each SSS
- instrumentation device.
Catawba Units 1 and 2 16.7-9-3 sss 16.7-9 FREQUENCY 92 days 92 days 18 months 18 months 18 months 18 months 18 months 18 months 18 months (continued)
Revision 15
sss 16.7-9 TESTING REQUIREMENTS (continued)
TEST FREQUENCY TR 16.7-9-20 Verify proper installation of pressurizer insulation.
18 months TR 16.7-9-21 Verify pressurizer heaters powered from the SSS have a 18 months capacity of?, 63.5 kW measured at motor control center SMXG.
TR 16.7-9-22 Verify flowpath from the reactor vessel head through the 18 months BASES valves powered from the SSS is unobstructed.
The SSS is designed to mitigate the consequences of certain postulated fire, security, and station blackout incidents by providing capability to maintain MODE 3 conditions and by controlling and monitoring vital systems from locations external to the main control room. This capability is consistent with the requirements of 10 CFR Part 50.48(c).
When the SSS is under Condition A and it is anticipated that Condition D will be utilized, establish the bases for continued operation (including any supporting actions) prior to entering Condition D. Risks associated with the continued operation under Condition D are evaluated and managed through existing processes and procedures. These risk contributors, risk insights, risk-informed information, and/or risk mitigation actions assessed and managed during periods when Condition Dis applied, are to be included in the 14-day special report.
The TESTING REQUIREMENTS ensure that the SSS systems and components are capable of performing their intended functions. The required level in the SSS diesel generator fuel storage tank ensures sufficient fuel for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> uninterrupted operation. It is assumed that, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, either offsite power can be restored or additional fuel can be added to the storage tank.
Although the standby makeup pump is not nuclear safety related and was not designed according to ASME Code requirements, it is tested quarterly to ensure its FUNCTIONALITY. The TESTING REQUIREMENT concerning the standby makeup pump water supply ensures that an adequate water volume is available to supply the pump continuously for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Total accumulative LEAKAGE is calculated in the NC System Leakage Calculation procedure as identified + unidentified + seal leakoff (References 2 and 3). The REMEDIAL ACTION limit of 20 gpm total accumulative LEAKAGE provides additional margin to allow for Catawba Units 1 and 2 16.7-9-4 Revision 15
- BASES (continued) sss 16.7-9 instrument inaccuracy, and for the predicted increase in seal leakoff rate due to heatup of the reactor coolant pump seal injection water supply temperature following the SSS event (due to spent fuel pool heatup).
Following the increase in seal injection temperature, the standby makeup pump flow of 26 gpm is sufficient to provide in excess of this total accumulative LEAKAGE, thereby assuring that reactor coolant system inventory is maintained at MODE 3 conditions. The supporting evaluation is provided in CNC-1223.04-00-0072 (Ref. 4).
A visual inspection of the diesel starting 24-volt batteries, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance. Since the battery cell jars are not transparent, a direct visual inspection of the cell plates cannot be performed. Instead, the cell plates are inspected for physical damage and abnormal deterioration by: 1) visually inspecting the jar sides of each cell for excessive bowing and/or deformation, and 2) visually inspecting the electrolyte of each cell for abnormal appearance.
Verifying individual cell voltage while on float charge for the SSS diesel starting 24-Volt batteries ensures that each cell is capable of supporting its intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or battery cell) in a fully charged state. The battery cell voltage limit of 1.36 volts is consistent with the nominal design voltage of the battery and is based on the manufacturer's recommended minimum float charge voltage for a fully charged cell with adequate capacity. The 24-Volt starting battery is designed with two battery banks, each battery bank contains 20 individual battery cells. The 24-Volt starting battery has sufficient capacity margin to maintain SSS diesel starting functionality with one cell in each battery bank to be fully degraded with a voltage< 1.36 volts. The 24-Volt starting battery is required to have 19 individual battery cells per battery bank to maintain SSS diesel starting functionality with sufficient capacity margin.
The battery sizing calculation accounts for one degraded cell in each battery bank by assuming the degraded cells undergo a worst case polarity reversal during SSS diesel starting. The supporting evaluation is provided in CNC-1381.06-00-0056 (Ref.12).
Verification of proper installation of pressurizer insulation ensures that pressurizer heat losses during an SSS event do not exceed the capacity of the pressurizer heaters powered from the SSS.
Testing of the pressurizer heater capacity ensures the full capacity of the heaters is available to maintain a steam bubble in the pressurizer during an SSS event. The acceptance criterion includes an allowance for the voltage drop in the power cables between the SSS and the pressurizer and measurement uncertainty.
Catawba Units 1 and 2 16.7-9-5 Revision 15
sss 16.7-9 BASE~ (continued)
REFERENCES Testing of the flowpath from the reactor vessel head to the pressurizer relief tank ensures sufficient flow capacity for reactor coolant inventory control during an SSS event.
- 1.
Letter from NRC to Gary R. Peterson, Duke, Issuance of
- Improved Technical Specifications Amendments for Catawba, September 30, 1998.
- 2.
PT/1(2)/A/4150/001D, NC System Leakage Calculation.
- 3.
PT/1(2)/A/4150/001I, Manual NC Leakage Calculation.
- 4.
CNC-1223.04-00-0072, Reactor Coolant Pumps No. 1 Seal Leakoff Annunciator Alarm Setpoint for Unit 1 and Unit 2.
- 5.
CNS-1560.SS-00-0001, Design Basis Specification for the Standby Shutdown Facility.
- 6.
Catawba Technical Specification Amendments 206/200, July 10, 2003.
- 7.
Catawba UFSAR, Section 18.2.4.
- 8.
Catawba License Renewal Commitments, CNS-1274.00 0016, Section 4.5.
- 9.
CNC-1223.03-00-*0033, Determination of Pressurizer Heater Capacity Powered from the SSF Diesel.
- 10.
Catawba Nuclear Station 10 CFR 50.48(c) Fire Protection Safety Evaluation (SE).
- 11.
10 CFR 50.48(c), Fire Protection.
- 12.
CNC-1381.06-00-0056, SSF Diesel Generator Battery Sizing Calculation.
- 13.
UFSAR Table 18-1.
- 14.
UFSAR Section 18.3.1.
Catawba Units 1 and 2
- 16.7-9-6 Revision 15
CRAVS - Intake Alarms 16.9-22 16.9. AUXILIARY SYSTEMS 16.9-22 Control Room Area Ventilation System (CRAVS) - Intake Alarms COMMITMENT
--NOTE---------
Applicable to the CRAVS smoke alarms only. The chlorine detection alarm is addressed in SLC 16.6-4, Chlorine Detectors and Associated Circuitry and the CRA VS radiation detection alarm is addressed in SLC 16.7-10, Radiation Monitoring for Plant Operations.
The CRA VS Intake Alarms shall be FUNCTIONAL.
APPLICABILITY:
All MODES.
REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
CRAVS smoke intake A.1 Establish a fire watch 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> alarm non-functional for one or both control room intakes.
TESTING REQUIREMENTS TEST patrol once per hour at the affected control room intake(s).
TR 16.9-22-1 Verify that on a Smoke Density-High test signal, an alarm is received in the control room.
Catawba Units 1 and 2 16.9-22-1 FREQUENCY 18 months Revision 3
BASES CRAVS - Intake Alarms 16.9-22 The CRAVS Intake Alarms provide operator information relative to smoke, chlorine and radiation concentrations at each control room intake. Operators use this information to align the CRAVS to ensure that the control room will remain habitable for operations personnel during and following accident conditions.
The REMEDIAL ACTION for non-functional smoke intake alarms is consistent with that for non-functional fire detection instrumentation. The fire detection instrumentation requirements are discussed in SLC 16.9-6, Fire Detection Instrumentation.
REFERENCES
- 1.
Letter from NRC to Gary R. Peterson, Duke, Issuance of Improved Technical Specifications Amendments for Catawba, September 30, 1998.
- 2.
SLC 16.6-4, Chlorine Detectors and Associated Circuitry
- 3.
SLC 16.7-10, Radiation Monitoring for Plant Operations Catawba Units 1 and 2 16.9-22-2 Revision 3-