CNS-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes: Difference between revisions
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{{#Wiki_filter:I ((_-..DUKE CNS-16-050 | {{#Wiki_filter:I ~- | ||
* July 12, 2016 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 | Kelvin Henderson | ||
((_-..DUKE Vice President | |||
~JENERGYm Catawba Nuclear Station Duke Energy CN01VP 14800 Concord Road York, SC 29745 o: 803.701.4251 f: 803.701.3221 CNS-16-050 | |||
* 10 CFR 50.71(e) | |||
July 12, 2016 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 | |||
==Subject:== | ==Subject:== | ||
Duke Energy Carolinas, LLC Catawba Nuclear Station, Unit 1 and Unit 2 Docket Nos. 50-413 and 50-414 UFSAR/Selected Licensee Commitment Changes | Duke Energy Carolinas, LLC Catawba Nuclear Station, Unit 1 and Unit 2 Docket Nos. 50-413 and 50-414 UFSAR/Selected Licensee Commitment Changes Pursuant to 10CFR 50. 71 (e), please find attached changes to the Catawba Nuclear Station Selected Licensee Commitments Manual. This document constitutes Chapter 16 of the Updated Final Safety Analysis Report (UFSAR). | ||
Any questions regarding this information should be directed to Tolani Owusu, Regulatory Affairs, at (803) 701-5385. | |||
I certify that I am a duly authorized officer of Duke Energy Carolinas, LLC, and that the information contained herein accurately represents changes made to Chapter 16 of the UFSAR sinceJ previous submittal. | I certify that I am a duly authorized officer of Duke Energy Carolinas, LLC, and that the information contained herein accurately represents changes made to Chapter 16 of the UFSAR sinceJ previous submittal. | ||
Kelvin Henderson Vice President, Catawba Nuclear Station Attachment | Kelvin Henderson Vice President, Catawba Nuclear Station Attachment | ||
July 12, 2016 | U.S. Nuclear Regulatory Commission July 12, 2016 Page 2 xc: Catherine Haney, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Michael Orenak NRC Project Manager (CNS) | ||
U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 0-8G9A 11555 Rockville Pike Rockville, MD 20852 J.D. Austin, Senior Resident Inspector Catawba Nuclear Station | |||
Units 1 and 2 ** .. | |||
.. , Page 2 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 3 08/21/09 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 0 10/09/02 '16.9-19 3 02/20/12 16.9-20 0 10/09/02 16.9-21 0 10/09/02 16.9-22 1 08/21/09 16.9-23 4 10/24/11 16.9-24 2 10/24/06 16.9-25 2 08/21/09 16.9-26 0 03/05/12 16.10-1 1 08/21/09 16.10-2 1 10/24/06 16.10-3 1 08/21/09 16.11-1 1 07/27/13 LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.11-2 4 02/10/15 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 9 02/10/15 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 16.11-19 0 10/09/02 16.11-20 2 ' 03/28/16 16.11-21 o* 10/09/02 16.12-1 0 10/09/02 16.13-1 0 10/09/02 16.13-2 Deleted 16.13-3 Deleted | Duke Energy | ||
The following shall be FUNCTIONAL: | ~~DUKE CN01VP I 4800 Concord Road | ||
Instrument Loops | ~ ENERGY~ York, SC 29745 July 12, 2016 Re: Catawba Nuclear Station Selected Licensee Commitments Manual Revision Date: 06/10/2016 Attached are revisions to the Catawba Nuclear Station Selected Licensee Commitments Manual. Please remove and replace the following pages: | ||
REMOVE THESE PAGES INSERT THESE PAGES LIST OF EFFECTIVE SECTIONS Pages 1 through 5 Pages 1 through 5 Revision 64 Revision 65 TAB 16.7-6 16.7-6-1 through 16.7-6-3 16.7-6-1through16.7-6-3 Revision 2 Revision 3 | |||
* TAB 16.7-13 | |||
RN Pump A Flow Hi/Low RN Pump B Flow Hi/Low RN Pump A Flow Hi/Low RN Pump B Flow Hi/Low Whenever the associated unit's RN train is required to be OPERABLE. | : 16. 7-13-1 through 16. 7-13-5 16.7-13-1through167-13-5 Revision 2 Revision 3 If you have any questions concerning the contents of this package update, contact Toni Lowery at (803)701-5 ~ | ||
Catawba Units 1 and 2 16.7-6-1 Revision 3 RN Discharge Instrumentation 16.7-6 REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more instrument A.1.1 Ensure associated RN Immediately loop(s) and/or pump(s) are not in service. annunciator(s) non-functional. | ~chr Regulatory Affairs Manager Attachment | ||
OR A.1.2 Align affected RN loop(s) Immediately discharge(s) to Standby Nuclear Service Water Pond (SNSWP). AND A.2 Restore non-functional 72 hours instrument loop(s) and/or annunciator(s) to FUNCTIONAL status. B. Required Action and B.1 Contact Station Immediately associated Completion Management for additional Time for Condition A not guidance. | |||
met. TESTING REQUIREMENTS TEST FREQUENCY TR 16.7-6-1 Perform CHANNEL CALIBRATION. | LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE TABLE OF CONTENTS 15 05/10/16 16.1 1 08/27/08 16.2 2 08/21/09 16.3 1 08/21/09 16.5-1 3 08/19/15 16.5-2 Deleted 16.5-3 1 02/20/04 16.5-4 0 10/09/02 16.5-5 1 01/28/10 16.5-6 1 08/21/09 16.5-7 2 02/06/15 16.5-8 2 12/22/08 16.5-9 1 02/20/12 16.5-10 Deleted 16.6-1 0 10/09/02 16.6-2 Deleted 16.6-3 1 08/21/09 16.6-4 1 08/21/09 16.6-5 2 01/09/13 16.7-1 1 08/21/09 16.7-2 4 02/03/11 16.7-3 4 07/27/13 16.7-4 2 08/21/09 16.7-5 2 08/21/09 Catawba Units 1 and 2 Page 1 | ||
18 months BASES The basis for this SLC is stated in Reference 1, page 11, "Part of the licensing bases of the RN system included the ability for operators to manually change the discharge path for the RN system from the safety related Lake Wylie to the safety related SNSWP." This SLC was developed to address the NRC concerns about actions to be taken in the event instrumentation/alarms were out of service which would impair the ability of operators to recognize loss of the non-safety discharge. | |||
This SLC shall ensure the proper actions are taken based on plant equipment conditions. | LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.7-6 3 06/10/16 16.7-7 1 08/21/09 16.7-8 2 08/21/09 16.7-9 9 06/06/13 16.7-10 7 03/28/16 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 1 08/21/09 16.7-16 0 06/08/09 16.7-17 0 02/10/15 16.7-18 0 05/10/16 16.8-1 6 12/10/15 16.8-2 2 02/20/12 16.8-3 1 10/24/06 16.8-4 2 11/05/07 16.8-5 3 08/21/09 16.9-1 7 10/24/11 16.9-2 5 10/24/11 16.9-3 3 02/03/11 16.9-4 3 08/21/09 16.9-5 6 06/23/10 16.9-6 10 02/10/15 | ||
Catawba Units 1 and 2 16.7-6-2 Revision 3 | \ *. ,; . '''--=~r~Gatawba Units 1 and 2 ** .. ~:._, .. , Page 2 | ||
Catawba Units 1 and 2 16.7-6-3 Revision 3 AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 16.7 INSTRUMENTATION 16.7-13 Auxiliary Feedwater (AFW) Pump Turbine Steam Supply Piping Monitoring System COMMITMENT | 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 3 08/21/09 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 0 10/09/02 | ||
'16.9-19 3 02/20/12 16.9-20 0 10/09/02 16.9-21 0 10/09/02 16.9-22 1 08/21/09 16.9-23 4 10/24/11 16.9-24 2 10/24/06 16.9-25 2 08/21/09 16.9-26 0 03/05/12 16.10-1 1 08/21/09 16.10-2 1 10/24/06 16.10-3 1 08/21/09 16.11-1 1 07/27/13 | |||
MODES 1, 2, and 3. REMEDIAL ACTIONS A. | |||
Catawba Units 1 and 2 | LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.11-2 4 02/10/15 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 9 02/10/15 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 16.11-19 0 10/09/02 16.11-20 2 ' 03/28/16 16.11-21 o* 10/09/02 16.12-1 0 10/09/02 16.13-1 0 10/09/02 16.13-2 Deleted 16.13-3 Deleted | ||
16.7-13-1 | |||
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Initiate action*to obtain Immediately associated Completion steam supply piping Time for Condition A not temperature using met. alternate means. AND 8.2 Monitor steam supply ----------NOTE--------- | LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.13-4 0 10/09/02 | ||
piping temperature using The provisions of alternate means to ensure SLC 16.2.6 are not it is within established applicable. | |||
limits. --------------------------- | RN Discharge Instrumentation 16.7-6 16.7 INSTRUMENTATION 16.7-6 RN Discharge Instrumentation COMMITMENT The following shall be FUNCTIONAL: | ||
' Once per 15 C. All steam supply piping C.1 Declare the turbine driven Immediately temperature monitoring AFW pump inoperable. | Instrument Components: | ||
capability lost. AND C.2 Enter applicable Conditions Immediately and Required Actions of Technical Specification 3.7.5, AFW System, for the inoperable turbine driven AFW pump. AND C.3 Isolate steam supply to 15 minutes I turbine driven AFW pump. AND C.4 De-energize turbine driven 15 minutes. I AFW pump steam supply piping heat trace. (continued) | Loops: | ||
Catawba Units 1 and 2 16.7-13-2 Revision 3 AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 REMEDIAL ACTIONS (continued) | 1RNFE7520 RN Pump A Discharge Flow Annubar 1RNLP7520 1RNFT7520 RN Pump A Discharge Flow 1RNP7520 RN Pump A Discharge Flow (Control Room Indication) 1RNFE7510 RN Pump B Discharge Flow Annubar 1RNLP7510 1RNFT7510 RN Pump B Discharge Flow 1RNP7510 RN Pump B Discharge Flow (Control Room Indication) 2RNFE7520 RN Pump A Discharge Flow Annubar 2RNLP7520 2RNFT7520 RN Pump A Discharge Flow 2RNP7520 RN Pump A Discharge Flow (Control Room Indication) 2RNFE7510 RN Pump B Discharge Flow Annubar 2RNLP7510 2RNFT7510 RN Pump B Discharge Flow 2RNP7510 RN Pump B Discharge Flow (Control Room Indication) | ||
D. | Annunicators: | ||
1AD12-A/1 RN Pump A Flow Hi/Low 1AD12-A/4 RN Pump B Flow Hi/Low 2AD12-A/1 RN Pump A Flow Hi/Low 2AD12-A/4 RN Pump B Flow Hi/Low APPLICABILITY: Whenever the associated unit's RN train is required to be OPERABLE. | |||
D.2 Verify that backup control room steam supply temperature monitoring capability is available. | Catawba Units 1 and 2 16.7-6-1 Revision 3 | ||
TESTING REQUIREMENTS TEST TR 16. 7-13-1 ----------------------------------NOTE---- | |||
.. ----------------------------. Instrument calibration includes verification of OAC output and OAC alarm setpoints. | RN Discharge Instrumentation 16.7-6 REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more instrument A.1.1 Ensure associated RN Immediately loop(s) and/or pump(s) are not in service. | ||
Perform calibration of applicable instrumentation and heat trace controllers. | annunciator(s) non-functional. OR A.1.2 Align affected RN loop(s) Immediately discharge(s) to Standby Nuclear Service Water Pond (SNSWP). | ||
TR 16. 7-13-2 Perform a visual and thermography inspection of the steam supply piping heat trace circuitry. | AND A.2 Restore non-functional 72 hours instrument loop(s) and/or annunciator(s) to FUNCTIONAL status. | ||
TR 16. 7-13-3 Perform a visual inspection of selected portions* | B. Required Action and B.1 Contact Station Immediately associated Completion Management for additional Time for Condition A not guidance. | ||
of the turbine driven AFW pump steam supply piping for high temperature damage. | met. | ||
The heat trace control system is designed to maintain the piping temperature within a narrow operating band. The heat trace is energized and deenergized to maintain the piping temperature within the band. Catawba Units 1 and 2 16.7-13-3 Revision 3 AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16. 7-13 BASES (continued) | TESTING REQUIREMENTS TEST FREQUENCY TR 16.7-6-1 Perform CHANNEL CALIBRATION. 18 months BASES The basis for this SLC is stated in Reference 1, page 11, "Part of the licensing bases of the RN system included the ability for operators to manually change the discharge path for the RN system from the non-safety related Lake Wylie to the safety related SNSWP." | ||
This SLC was developed to address the NRC concerns about actions to be taken in the event instrumentation/alarms were out of service which would impair the ability of operators to recognize loss of the non-safety discharge. This SLC shall ensure the proper actions are taken based on plant equipment conditions. | |||
Backup control room temperature monitoring capability is provided via a control room annunciator. | Catawba Units 1 and 2 16.7-6-2 Revision 3 | ||
The annunciator is fed via a reflash panel, from the same local chart recorder as the OAC. Alternate means of monitoring turbine driven AFW pump steam supply piping temperature include: the chart recorder local temperature display, the heat trace controller local temperature display, or calibrated, hand-held temperature measuring instruments. | |||
It is only when all steam supply piping temperature monitoring capability (including any alternate means) is lost that Condition C is required to be entered. This indicates a condition where the actual temperature of the piping is unknown. Failure of the heat trace to deenergize could result in the design temperature for the steam supply piping being exceeded. | RN Discharge Instrumentation 16.7-6 REFERENCES 1. NRC Inspection Report, 50-413, 414/94-17, September 9, 1994. | ||
The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System ensures the OPERABILITY of the turbine driven AFW pump by providing control room indication of high steam supply piping temperatures. | : 2. Catawba Nuclear Station PIP O-C94-1555. | ||
The OAC high temperature alarm setpoint is established to ensure that the design temperature of the steam supply piping of 600°F is not exceeded. | Catawba Units 1 and 2 16.7-6-3 Revision 3 | ||
Upon receipt of the OAC alarm due to high temperature on the steam supply piping, personnel are required to open the heat trace supply breaker for the appropriate high temperature section of piping within 15 minutes. The time limit prevents the possibility of the actual piping temperature reaching the piping design temperature of 600°F. Low steam supply piping temperatures result in increased condensate formation during turbine driven AFW pump startup. A large volume of condensate in the steam supply piping could result in turbine damage, water hammer, or turbine overspeed trips. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System further ensures the OPERABILITY of the turbine driven AFW pump by providing control room indication of low steam supply piping temperatures. | |||
The OAC low average temperature alarm setpoints are set such that a low average system temperature condition is identified prior to the piping system reaching the minimum average temperature required for turbine driven AFW pump OPERABILITY (375°F). The OAC low temperature alarm setpoints for individual piping sections are set such that a low temperature condition is identified prior to the piping reaching the minimum temperature required for turbine driven AFW pump OPERABILITY (225°F). The 225°F limit is provided to prevent the accumulation of condensate in the piping during periods of standby readiness. | AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 16.7 INSTRUMENTATION 16.7-13 Auxiliary Feedwater (AFW) Pump Turbine Steam Supply Piping Temperat~~/ | ||
1 .. Problem Investigation Process (PIPs) C-97-0616 and C | Monitoring System ~ | ||
: 2. CNC-1223.43-02-0012, Calculation of Maximum Operator Response Time for SA System Heat Trace Failure to energize Scenario. | COMMITMENT a. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System, which is comprised of an Operator Aid Computer (OAC) temperature display graphic, shall be FUNCTIONAL, and | ||
: b. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System high temperature alarm setpoints shall be set to ensure that the design temperature of the steam supply piping (600°F) is not exceeded, and | |||
: c. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System low average temperature alarm setpoint shall be set such that a low temperature condition is identified prior to the piping system reaching the minimum average temperature required for turbine driven AFW pump OPERABILITY (375°F), and | |||
: d. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System low temperature alarm setpoints shall be set such that a low temperature condition is identified prior to an individual piping section reaching the minimum temperature required for turbine driven AFW pump OPERABILITY (225°F). | |||
APPLICABILITY: MODES 1, 2, and 3. | |||
REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. OAC steam supply A.1 Verify that backup control Immediately piping temperature room steam supply piping monitoring function non- temperature monitoring functional. capability is available. | |||
(continued) | |||
Catawba Units 1 and 2 16.7-13-1 . Revision 3 | |||
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 REMEDIAL ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Initiate action*to obtain Immediately associated Completion steam supply piping Time for Condition A not temperature using met. alternate means. | |||
AND 8.2 Monitor steam supply ----------NOTE--------- | |||
piping temperature using The provisions of alternate means to ensure SLC 16.2.6 are not it is within established applicable. | |||
limits. --------------------------- | |||
' Once per 15 minute~ | |||
C. All steam supply piping C.1 Declare the turbine driven Immediately temperature monitoring AFW pump inoperable. | |||
capability lost. | |||
AND C.2 Enter applicable Conditions Immediately and Required Actions of Technical Specification 3.7.5, AFW System, for the inoperable turbine driven AFW pump. | |||
AND C.3 Isolate steam supply to 15 minutes I turbine driven AFW pump. | |||
AND C.4 De-energize turbine driven 15 minutes. I AFW pump steam supply piping heat trace. | |||
(continued) | |||
Catawba Units 1 and 2 16.7-13-2 Revision 3 | |||
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 REMEDIAL ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME D. OAC steam supply D.1 Initiate action to restore Immediately piping temperature . OAC steam supply piping monitoring function temperature monitoring alarm setpoints not set function alarm setpoints per COMMITMENT. per COMMITMENT. | |||
D.2 Verify that backup control Immediately room steam supply temperature monitoring capability is available. | |||
TESTING REQUIREMENTS TEST FREQUENCY TR 16. 7-13-1 ----------------------------------NOTE----..---------------------------- | |||
. Instrument calibration includes verification of OAC output and OAC alarm setpoints. | |||
Perform calibration of applicable instrumentation and 18 months heat trace controllers. | |||
TR 16. 7-13-2 Perform a visual and thermography inspection of the 18 months steam supply piping heat trace circuitry. | |||
TR 16. 7-13-3 Perform a visual inspection of selected portions* of the Each refueling turbine driven AFW pump steam supply piping for high outage temperature damage. | |||
BASES The turbine driven AFW pump steam supply piping is equipped with heat trace to minimize condensate generation during turbine startup operations. | |||
The heat trace control system is designed to maintain the piping temperature within a narrow operating band. The heat trace is energized and deenergized to maintain the piping temperature within the band. | |||
Catawba Units 1 and 2 16.7-13-3 Revision 3 | |||
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System | |||
: 16. 7-13 BASES (continued) | |||
The primary means of monitoring turbine driven AFW pump steam supply piping temperature is the OAC. The OAC data is obtained via piping thermocouples and a local chart recorder (EHCR002). Backup control room temperature monitoring capability is provided via a control room annunciator. | |||
The annunciator is fed via a reflash panel, from the same local chart recorder as the OAC. Alternate means of monitoring turbine driven AFW pump steam supply piping temperature include: the chart recorder local temperature display, the heat trace controller local temperature display, or calibrated, hand-held temperature measuring instruments. It is only when all steam supply piping temperature monitoring capability (including any alternate means) is lost that Condition C is required to be entered. This indicates a condition where the actual temperature of the piping is unknown. | |||
Failure of the heat trace to deenergize could result in the design temperature for the steam supply piping being exceeded. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System ensures the OPERABILITY of the turbine driven AFW pump by providing control room indication of high steam supply piping temperatures. The OAC high temperature alarm setpoint is established to ensure that the design temperature of the steam supply piping of 600°F is not exceeded. Upon receipt of the OAC alarm due to high temperature on the steam supply piping, personnel are required to open the heat trace supply breaker for the appropriate high temperature section of piping within 15 minutes. The time limit prevents the possibility of the actual piping temperature reaching the piping design temperature of 600°F. | |||
Low steam supply piping temperatures result in increased condensate formation during turbine driven AFW pump startup. A large volume of condensate in the steam supply piping could result in turbine damage, water hammer, or turbine overspeed trips. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System further ensures the OPERABILITY of the turbine driven AFW pump by providing control room indication of low steam supply piping temperatures. The OAC low average temperature alarm setpoints are set such that a low average system temperature condition is identified prior to the piping system reaching the minimum average temperature required for turbine driven AFW pump OPERABILITY (375°F). The OAC low temperature alarm setpoints for individual piping sections are set such that a low temperature condition is identified prior to the piping reaching the minimum temperature required for turbine driven AFW pump OPERABILITY (225°F). The 225°F limit is provided to prevent the accumulation of condensate in the piping during periods of standby readiness. | |||
REFERENCES 1.. Problem Investigation Process (PIPs) C-97-0616 and C 1431. | |||
Catawba Units 1 and 2 16.7-13-4 Revision 3 | |||
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 REFERENCES (continued) | |||
: 2. CNC-1223.43-02-0012, Calculation of Maximum Operator Response Time for SA System Heat Trace Failure to De-energize Scenario. | |||
: 3. CNC-1223.43-02-0009, SA System TDAFWP Steam Supply Pipe Heat Tracing Operability Determination. | : 3. CNC-1223.43-02-0009, SA System TDAFWP Steam Supply Pipe Heat Tracing Operability Determination. | ||
Catawba Units 1 and 2 16.7-13-5 Revision 3}} | Catawba Units 1 and 2 16.7-13-5 Revision 3}} |
Latest revision as of 17:55, 10 November 2019
ML16196A075 | |
Person / Time | |
---|---|
Site: | Catawba |
Issue date: | 07/12/2016 |
From: | Henderson K Duke Energy Carolinas |
To: | Office of Nuclear Reactor Regulation |
References | |
CNS-16-050 | |
Download: ML16196A075 (16) | |
Text
I ~-
Kelvin Henderson
((_-..DUKE Vice President
~JENERGYm Catawba Nuclear Station Duke Energy CN01VP 14800 Concord Road York, SC 29745 o: 803.701.4251 f: 803.701.3221 CNS-16-050
July 12, 2016 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC Catawba Nuclear Station, Unit 1 and Unit 2 Docket Nos. 50-413 and 50-414 UFSAR/Selected Licensee Commitment Changes Pursuant to 10CFR 50. 71 (e), please find attached changes to the Catawba Nuclear Station Selected Licensee Commitments Manual. This document constitutes Chapter 16 of the Updated Final Safety Analysis Report (UFSAR).
Any questions regarding this information should be directed to Tolani Owusu, Regulatory Affairs, at (803) 701-5385.
I certify that I am a duly authorized officer of Duke Energy Carolinas, LLC, and that the information contained herein accurately represents changes made to Chapter 16 of the UFSAR sinceJ previous submittal.
Kelvin Henderson Vice President, Catawba Nuclear Station Attachment
U.S. Nuclear Regulatory Commission July 12, 2016 Page 2 xc: Catherine Haney, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Michael Orenak NRC Project Manager (CNS)
U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 0-8G9A 11555 Rockville Pike Rockville, MD 20852 J.D. Austin, Senior Resident Inspector Catawba Nuclear Station
Duke Energy
~~DUKE CN01VP I 4800 Concord Road
~ ENERGY~ York, SC 29745 July 12, 2016 Re: Catawba Nuclear Station Selected Licensee Commitments Manual Revision Date: 06/10/2016 Attached are revisions to the Catawba Nuclear Station Selected Licensee Commitments Manual. Please remove and replace the following pages:
REMOVE THESE PAGES INSERT THESE PAGES LIST OF EFFECTIVE SECTIONS Pages 1 through 5 Pages 1 through 5 Revision 64 Revision 65 TAB 16.7-6 16.7-6-1 through 16.7-6-3 16.7-6-1through16.7-6-3 Revision 2 Revision 3
- TAB 16.7-13
- 16. 7-13-1 through 16. 7-13-5 16.7-13-1through167-13-5 Revision 2 Revision 3 If you have any questions concerning the contents of this package update, contact Toni Lowery at (803)701-5 ~
~chr Regulatory Affairs Manager Attachment
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE TABLE OF CONTENTS 15 05/10/16 16.1 1 08/27/08 16.2 2 08/21/09 16.3 1 08/21/09 16.5-1 3 08/19/15 16.5-2 Deleted 16.5-3 1 02/20/04 16.5-4 0 10/09/02 16.5-5 1 01/28/10 16.5-6 1 08/21/09 16.5-7 2 02/06/15 16.5-8 2 12/22/08 16.5-9 1 02/20/12 16.5-10 Deleted 16.6-1 0 10/09/02 16.6-2 Deleted 16.6-3 1 08/21/09 16.6-4 1 08/21/09 16.6-5 2 01/09/13 16.7-1 1 08/21/09 16.7-2 4 02/03/11 16.7-3 4 07/27/13 16.7-4 2 08/21/09 16.7-5 2 08/21/09 Catawba Units 1 and 2 Page 1
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.7-6 3 06/10/16 16.7-7 1 08/21/09 16.7-8 2 08/21/09 16.7-9 9 06/06/13 16.7-10 7 03/28/16 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 1 08/21/09 16.7-16 0 06/08/09 16.7-17 0 02/10/15 16.7-18 0 05/10/16 16.8-1 6 12/10/15 16.8-2 2 02/20/12 16.8-3 1 10/24/06 16.8-4 2 11/05/07 16.8-5 3 08/21/09 16.9-1 7 10/24/11 16.9-2 5 10/24/11 16.9-3 3 02/03/11 16.9-4 3 08/21/09 16.9-5 6 06/23/10 16.9-6 10 02/10/15
\ *. ,; . --=~r~Gatawba Units 1 and 2 ** .. ~:._, .. , Page 2
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 3 08/21/09 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 0 10/09/02
'16.9-19 3 02/20/12 16.9-20 0 10/09/02 16.9-21 0 10/09/02 16.9-22 1 08/21/09 16.9-23 4 10/24/11 16.9-24 2 10/24/06 16.9-25 2 08/21/09 16.9-26 0 03/05/12 16.10-1 1 08/21/09 16.10-2 1 10/24/06 16.10-3 1 08/21/09 16.11-1 1 07/27/13
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.11-2 4 02/10/15 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 9 02/10/15 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 16.11-19 0 10/09/02 16.11-20 2 ' 03/28/16 16.11-21 o* 10/09/02 16.12-1 0 10/09/02 16.13-1 0 10/09/02 16.13-2 Deleted 16.13-3 Deleted
LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.13-4 0 10/09/02
RN Discharge Instrumentation 16.7-6 16.7 INSTRUMENTATION 16.7-6 RN Discharge Instrumentation COMMITMENT The following shall be FUNCTIONAL:
Instrument Components:
Loops:
1RNFE7520 RN Pump A Discharge Flow Annubar 1RNLP7520 1RNFT7520 RN Pump A Discharge Flow 1RNP7520 RN Pump A Discharge Flow (Control Room Indication) 1RNFE7510 RN Pump B Discharge Flow Annubar 1RNLP7510 1RNFT7510 RN Pump B Discharge Flow 1RNP7510 RN Pump B Discharge Flow (Control Room Indication) 2RNFE7520 RN Pump A Discharge Flow Annubar 2RNLP7520 2RNFT7520 RN Pump A Discharge Flow 2RNP7520 RN Pump A Discharge Flow (Control Room Indication) 2RNFE7510 RN Pump B Discharge Flow Annubar 2RNLP7510 2RNFT7510 RN Pump B Discharge Flow 2RNP7510 RN Pump B Discharge Flow (Control Room Indication)
Annunicators:
1AD12-A/1 RN Pump A Flow Hi/Low 1AD12-A/4 RN Pump B Flow Hi/Low 2AD12-A/1 RN Pump A Flow Hi/Low 2AD12-A/4 RN Pump B Flow Hi/Low APPLICABILITY: Whenever the associated unit's RN train is required to be OPERABLE.
Catawba Units 1 and 2 16.7-6-1 Revision 3
RN Discharge Instrumentation 16.7-6 REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more instrument A.1.1 Ensure associated RN Immediately loop(s) and/or pump(s) are not in service.
annunciator(s) non-functional. OR A.1.2 Align affected RN loop(s) Immediately discharge(s) to Standby Nuclear Service Water Pond (SNSWP).
AND A.2 Restore non-functional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> instrument loop(s) and/or annunciator(s) to FUNCTIONAL status.
B. Required Action and B.1 Contact Station Immediately associated Completion Management for additional Time for Condition A not guidance.
met.
TESTING REQUIREMENTS TEST FREQUENCY TR 16.7-6-1 Perform CHANNEL CALIBRATION. 18 months BASES The basis for this SLC is stated in Reference 1, page 11, "Part of the licensing bases of the RN system included the ability for operators to manually change the discharge path for the RN system from the non-safety related Lake Wylie to the safety related SNSWP."
This SLC was developed to address the NRC concerns about actions to be taken in the event instrumentation/alarms were out of service which would impair the ability of operators to recognize loss of the non-safety discharge. This SLC shall ensure the proper actions are taken based on plant equipment conditions.
Catawba Units 1 and 2 16.7-6-2 Revision 3
RN Discharge Instrumentation 16.7-6 REFERENCES 1. NRC Inspection Report, 50-413, 414/94-17, September 9, 1994.
- 2. Catawba Nuclear Station PIP O-C94-1555.
Catawba Units 1 and 2 16.7-6-3 Revision 3
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 16.7 INSTRUMENTATION 16.7-13 Auxiliary Feedwater (AFW) Pump Turbine Steam Supply Piping Temperat~~/
Monitoring System ~
COMMITMENT a. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System, which is comprised of an Operator Aid Computer (OAC) temperature display graphic, shall be FUNCTIONAL, and
- b. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System high temperature alarm setpoints shall be set to ensure that the design temperature of the steam supply piping (600°F) is not exceeded, and
- c. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System low average temperature alarm setpoint shall be set such that a low temperature condition is identified prior to the piping system reaching the minimum average temperature required for turbine driven AFW pump OPERABILITY (375°F), and
- d. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System low temperature alarm setpoints shall be set such that a low temperature condition is identified prior to an individual piping section reaching the minimum temperature required for turbine driven AFW pump OPERABILITY (225°F).
APPLICABILITY: MODES 1, 2, and 3.
REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. OAC steam supply A.1 Verify that backup control Immediately piping temperature room steam supply piping monitoring function non- temperature monitoring functional. capability is available.
(continued)
Catawba Units 1 and 2 16.7-13-1 . Revision 3
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Initiate action*to obtain Immediately associated Completion steam supply piping Time for Condition A not temperature using met. alternate means.
AND 8.2 Monitor steam supply ----------NOTE---------
piping temperature using The provisions of alternate means to ensure SLC 16.2.6 are not it is within established applicable.
limits. ---------------------------
' Once per 15 minute~
C. All steam supply piping C.1 Declare the turbine driven Immediately temperature monitoring AFW pump inoperable.
capability lost.
AND C.2 Enter applicable Conditions Immediately and Required Actions of Technical Specification 3.7.5, AFW System, for the inoperable turbine driven AFW pump.
AND C.3 Isolate steam supply to 15 minutes I turbine driven AFW pump.
AND C.4 De-energize turbine driven 15 minutes. I AFW pump steam supply piping heat trace.
(continued)
Catawba Units 1 and 2 16.7-13-2 Revision 3
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. OAC steam supply D.1 Initiate action to restore Immediately piping temperature . OAC steam supply piping monitoring function temperature monitoring alarm setpoints not set function alarm setpoints per COMMITMENT. per COMMITMENT.
D.2 Verify that backup control Immediately room steam supply temperature monitoring capability is available.
TESTING REQUIREMENTS TEST FREQUENCY TR 16. 7-13-1 ----------------------------------NOTE----..----------------------------
. Instrument calibration includes verification of OAC output and OAC alarm setpoints.
Perform calibration of applicable instrumentation and 18 months heat trace controllers.
TR 16. 7-13-2 Perform a visual and thermography inspection of the 18 months steam supply piping heat trace circuitry.
TR 16. 7-13-3 Perform a visual inspection of selected portions* of the Each refueling turbine driven AFW pump steam supply piping for high outage temperature damage.
BASES The turbine driven AFW pump steam supply piping is equipped with heat trace to minimize condensate generation during turbine startup operations.
The heat trace control system is designed to maintain the piping temperature within a narrow operating band. The heat trace is energized and deenergized to maintain the piping temperature within the band.
Catawba Units 1 and 2 16.7-13-3 Revision 3
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System
- 16. 7-13 BASES (continued)
The primary means of monitoring turbine driven AFW pump steam supply piping temperature is the OAC. The OAC data is obtained via piping thermocouples and a local chart recorder (EHCR002). Backup control room temperature monitoring capability is provided via a control room annunciator.
The annunciator is fed via a reflash panel, from the same local chart recorder as the OAC. Alternate means of monitoring turbine driven AFW pump steam supply piping temperature include: the chart recorder local temperature display, the heat trace controller local temperature display, or calibrated, hand-held temperature measuring instruments. It is only when all steam supply piping temperature monitoring capability (including any alternate means) is lost that Condition C is required to be entered. This indicates a condition where the actual temperature of the piping is unknown.
Failure of the heat trace to deenergize could result in the design temperature for the steam supply piping being exceeded. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System ensures the OPERABILITY of the turbine driven AFW pump by providing control room indication of high steam supply piping temperatures. The OAC high temperature alarm setpoint is established to ensure that the design temperature of the steam supply piping of 600°F is not exceeded. Upon receipt of the OAC alarm due to high temperature on the steam supply piping, personnel are required to open the heat trace supply breaker for the appropriate high temperature section of piping within 15 minutes. The time limit prevents the possibility of the actual piping temperature reaching the piping design temperature of 600°F.
Low steam supply piping temperatures result in increased condensate formation during turbine driven AFW pump startup. A large volume of condensate in the steam supply piping could result in turbine damage, water hammer, or turbine overspeed trips. The AFW Pump Turbine Steam Supply Piping Temperature Monitoring System further ensures the OPERABILITY of the turbine driven AFW pump by providing control room indication of low steam supply piping temperatures. The OAC low average temperature alarm setpoints are set such that a low average system temperature condition is identified prior to the piping system reaching the minimum average temperature required for turbine driven AFW pump OPERABILITY (375°F). The OAC low temperature alarm setpoints for individual piping sections are set such that a low temperature condition is identified prior to the piping reaching the minimum temperature required for turbine driven AFW pump OPERABILITY (225°F). The 225°F limit is provided to prevent the accumulation of condensate in the piping during periods of standby readiness.
REFERENCES 1.. Problem Investigation Process (PIPs) C-97-0616 and C 1431.
Catawba Units 1 and 2 16.7-13-4 Revision 3
AFW Pump Turbine Steam Supply Piping Temperature Monitoring System 16.7-13 REFERENCES (continued)
- 2. CNC-1223.43-02-0012, Calculation of Maximum Operator Response Time for SA System Heat Trace Failure to De-energize Scenario.
- 3. CNC-1223.43-02-0009, SA System TDAFWP Steam Supply Pipe Heat Tracing Operability Determination.
Catawba Units 1 and 2 16.7-13-5 Revision 3