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| {{#Wiki_filter:PRIORITY NormalDISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TOTHE TRANSMITTAL SIGNATURE UNLESS RECIPIENT ISOTHERWISE IDENTIFIED BELOWDate: 03/10115Document Transmittal | | {{#Wiki_filter:PRIORITY Normal DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW Date: 03/10115 Document Transmittal |
| #:DUK150690031 | | #: DUK150690031 |
| : 1) 01820 J R ELKINS- EC0812) 02361 QATS-MG01MM | | : 1) 01820 J R ELKINS- EC081 2) 02361 QATS-MG01MM |
| : 3) 02388 BOB SCHOMAKER | | : 3) 02388 BOB SCHOMAKER LYNCHBG, VA 4) 02532 RESIDENT NRC INSPECT MG01 NRC 5) 03044 MCG DOC CNTRL MISC MAN MG05DM 6) 03614 MCG OPS PROCEDURE GP MG01OP 7) 03744 OPS TRNG MGR. MG030T 8) 03759 U S NUC REG WASHINGTON, DC 9) 03796 SCIENTECH CLEARWTR, FL 10) 04809 MCG PLANT ENG. LIBR. MG05SE 11) 05262 J L FREEZE MG01IE 12) 05606 J C MORTON MG01EP 13) 08103 WESTINGHOUSE ELECTRIC CO LLC 14) 09665 JON H THOMPSON, USNRC Duke Energy DOCUMENT TRANSMITTAL FORM REFERENCE MCGUIRE NUCLEAR STATION TECHNICAL SPECIFICATIONS (TS)TECHNICAL SPECIFICATIONS BASES (TSB)RECORD RETENTION |
| : LYNCHBG, VA4) 02532 RESIDENT NRC INSPECT MG01 NRC5) 03044 MCG DOC CNTRL MISC MAN MG05DM6) 03614 MCG OPS PROCEDURE GP MG01OP7) 03744 OPS TRNG MGR. MG030T8) 03759 U S NUC REG WASHINGTON, DC9) 03796 SCIENTECH
| | #421734 Page 2 of 2 QA CONDITION |
| : CLEARWTR, FL10) 04809 MCG PLANT ENG. LIBR. MG05SE11) 05262 J L FREEZE MG01IE12) 05606 J C MORTON MG01EP13) 08103 WESTINGHOUSE ELECTRIC CO LLC14) 09665 JON H THOMPSON, USNRCDuke EnergyDOCUMENT TRANSMITTAL FORMREFERENCE MCGUIRE NUCLEAR STATIONTECHNICAL SPECIFICATIONS (TS)TECHNICAL SPECIFICATIONS BASES(TSB)RECORD RETENTION
| | [] Yes 0 No OTHER ACKNOWLEDGEMENT REQUIRED 0 Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO: Duke Energy McGuire DCRM MGO2DM 13225 Hagers Ferry Road Huntersville, N.C. 28078 Rec'd By Date DOCUMENT NO QACOND REV #/ DATE DISTR CODE 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 TOTAL MNS TSB 3.7.7 N/A 135 03/10/15 MADM-04B V1 V1 V1 x V3 V1 V1 V1 V1 vi V1 29 REMARKS: PLEASE UPDATE ACCORDINGLY. |
| #421734Page 2 of 2QA CONDITION | | TECHNICAL SPECIFICATION BASES LOES REVISION 122 DATED 02/25/15 S D CAPPS VICE PRESIDENT MCGUIRE NUCLEAR STATION BY: B C BEAVER MG01RC BCB/BRG-~ |
| [] Yes 0 NoOTHER ACKNOWLEDGEMENT REQUIRED 0 YesIF QA OR OTHER ACKNOWLEDGEMENT | | February 25, 2015 MEMORANDUM |
| : REQUIRED, PLEASEACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:Duke EnergyMcGuireDCRM MGO2DM13225 Hagers Ferry RoadHuntersville, N.C. 28078Rec'd ByDateDOCUMENT NOQACONDREV #/ DATEDISTR CODE123456789101112131415TOTALMNS TSB 3.7.7N/A135 03/10/15MADM-04BV1V1V1xV3V1V1V1V1viV129REMARKS:PLEASE UPDATE ACCORDINGLY.
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| TECHNICAL SPECIFICATION BASESLOES REVISION 122 DATED 02/25/15S D CAPPSVICE PRESIDENT MCGUIRE NUCLEAR STATIONBY:B C BEAVER MG01RC BCB/BRG-~ | |
| February 25, 2015MEMORANDUM | |
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| ==Subject:== | | ==Subject:== |
| | | McGuire TS Bases Updates REMOVE INSERT TSB List of Effected Sections Rev 121 TSB List of Effected Sections Rev 122 TSB 3.7.7 Rev. 115 TSB 3.7.7 Rev 135 Due to the revision process used for TS and Bases, revision numbers may be skipped.Please call me if you have questions. |
| McGuire TS Bases UpdatesREMOVE INSERTTSB List of Effected Sections Rev 121 TSB List of Effected Sections Rev 122TSB 3.7.7 Rev. 115 TSB 3.7.7 Rev 135Due to the revision process used for TS and Bases, revision numbers may be skipped.Please call me if you have questions. | | Bonnie Beaver Regulatory Compliance 875-4180 McGuire Nuclear Station Technical Specification Bases LOES TS Bases are revised by section Page Number Revision Revision Date O BASES (Revised per section)i Revision 87 8/15/07 ii Revision 87 8/15/07 iii Revision 87 8/15/07 B 2.1.1 Revision 51 01/14/04 B 2.1.2 Revision 109 9/20/10 B 3.0 Revision 81 3/29/07 B 3.1.1 Revision 115 3/29/11 B 3.1.2 Revision 115 3/29/11 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 115 3/29/11 B 3.1.5 Revision 115 3/29/11 B 3.1.6 Revision 115 3/29/11 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 115 3/29/11 B 3.2.1 Revision 115 3/29/11 B 3.2.2 Revision 115 3/29/11 B 3.2.3 Revision 115 3/29/11 B 3.2.4 Revision 115 3/29/11 B 3.3.1 Revision 124 10/1/12 B 3.3.2 Revision 132 8/27/14 B 3.3.3 Revision 122 10/25/12 B 3.3.4 Revision 115 3/29/11 B 3.3.5 Revision 115 3/29/11 B 3.3.6 Not Used -Revision 87 6129/06 B 3.4.1 Revision 115 3/29/11 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 115 3/29/11 B 3.4.4 Revision 115 3/29/11 B 3.4.5 Revision 115 3/29/11 McGuire Units 1 and 2 Page I Revision 122 Page Number Amendment Revision Date B 3.4.6 Revision 115 3/29/11 B 3.4.7 Revision 115 3/29/11 B 3.4.8 Revision 115 3/29/11 B 3.4.9 Revision 115 3/29/11 B 3.4.10 Revision 102 8/17/09 B 3.4.11 Revision 115 3/29/11 B 3.4.12 Revision 134 1/8/15 B 3.4.13 Revision 126 5/1/13 B 3.4.14 Revision 115 3/29/11 B 3.4.15 Revision 115 3/29/11 B 3.4.16 Revision 121 8/5/09 B 3.4.17 Revision 115 3/29/11 B 3.4.18 Revision 86 6/25/07 B 3.5.1 Revision 115 3/29/11 B 3.5.2 Revision 116 8/18/11 B 3.5.3 Revision 57 4/29/04 B 3.5.4 Revision 122 10/25/12 B 3.5.5 Revision 115 3/29/11 B 3.6.1 Revision 53 2/17/04 B 3.6.2 Revision 115 3/29/11 B 3.6.3 Revision 115 3/29/11 B 3.6.4 Revision 115 3/29/11 B 3.6.5 Revision 115 3/29/11 B 3.6.6 Revision 122 10/25/12 B 3.6.7 Not Used -Revision 63 4/4/05 B 3.6.8 Revision 115 3/29/11 B 3.6.9 Revision 131 4/14/14 B 3.6.10 Revision 120 4/26/12 B 3.6.11 Revision 122 10/25/12 B 3.6.12 Revision 115 3/29/11 B 3.6.13 Revision 115 3/29/11 B 3.6.14 Revision 115 3/29/11 B 3.6.15 Revision 125 10/19/12 B 3.6.16 Revision 130 4/7/14 McGuire Units 1 and 2 Page 2 Revision 122 Page Number Amendment Revision Date B 3.7.1 Revision 129 10/24/13 B 3.7.2 Revision 105 2/22/10 B 3.7.3 Revision 102 8/17/09 B 3.7.4 Revision 115 3/29/11 B 3.7.5 Revision 115 3/29/11 B 3.7.6 Revision 127 8/2/13 B 3.7.7 Revision 135 2/11/15 B 3.7.8 Revision 128 10/2/13 B 3.7.9 Revision 120 4/26/12 B 3.7.10 Revision 115 3/29/11 B 3.7.11 Revision 115 3/29/11 B 3.7.12 Revision 115 3/29/11 B 3.7.13 Revision 115 3/29/11 B 3.7.14 Revision 115 3/29/11 B 3.7.15 Revision 66 6/30/05 B 3.7.16 Revision 115 3/29/11 B 3.8.1 Revision 115 3/29/11 B 3.8.2 Revision 92 1/28/08 B 3.8.3 Revision 123 9/29/12 B 3.8.4 Revision 133 9/10/14 B 3.8.5 Revision 41 7/29/03 B 3.8.6 Revision 115 3/29/11 B 3.8.7 Revision 115 3/29/11 B 3.8.8 Revision 115 3/29/11 B 3.8.9 Revision 115 3/29/11 B 3.8.10 Revision 115 3/29/11 B 3.9.1 Revision 115 3/29/11 B 3.9.2 Revision 115 3/29/11 B 3.9.3 Revision 115 3/29/11 B 3.9.4 Revision 115 3/29/11 B 3.9.5 Revision 115 3/29/11 B 3.9.6 Revision 115 3/29/11 B 3.9.7 Revision 115 3/29/11 McGuire Units 1 and 2 Page 3 Revision 122 NSWS B 3.7.7 B 3.7 PLANT SYSTEMS B 3.7.7 Nuclear Service Water System (NSWS)BASES BACKGROUND The NSWS provides a transfer mechanism for the removal of process and operating heat from safety related components during a Design Basis Accident (DBA) or transient. |
| Bonnie BeaverRegulatory Compliance 875-4180 McGuire Nuclear Station Technical Specification BasesLOESTS Bases are revised by sectionPage Number Revision Revision DateO BASES(Revised per section)i Revision 87 8/15/07ii Revision 87 8/15/07iii Revision 87 8/15/07B 2.1.1 Revision 51 01/14/04B 2.1.2 Revision 109 9/20/10B 3.0 Revision 81 3/29/07B 3.1.1 Revision 115 3/29/11B 3.1.2 Revision 115 3/29/11B 3.1.3 Revision 10 9/22/00B 3.1.4 Revision 115 3/29/11B 3.1.5 Revision 115 3/29/11B 3.1.6 Revision 115 3/29/11B 3.1.7 Revision 58 06/23/04B 3.1.8 Revision 115 3/29/11B 3.2.1 Revision 115 3/29/11B 3.2.2 Revision 115 3/29/11B 3.2.3 Revision 115 3/29/11B 3.2.4 Revision 115 3/29/11B 3.3.1 Revision 124 10/1/12B 3.3.2 Revision 132 8/27/14B 3.3.3 Revision 122 10/25/12B 3.3.4 Revision 115 3/29/11B 3.3.5 Revision 115 3/29/11B 3.3.6 Not Used -Revision 87 6129/06B 3.4.1 Revision 115 3/29/11B 3.4.2 Revision 0 9/30/98B 3.4.3 Revision 115 3/29/11B 3.4.4 Revision 115 3/29/11B 3.4.5 Revision 115 3/29/11McGuire Units 1 and 2Page IRevision 122 Page NumberAmendment Revision DateB 3.4.6 Revision 115 3/29/11B 3.4.7 Revision 115 3/29/11B 3.4.8 Revision 115 3/29/11B 3.4.9 Revision 115 3/29/11B 3.4.10 Revision 102 8/17/09B 3.4.11 Revision 115 3/29/11B 3.4.12 Revision 134 1/8/15B 3.4.13 Revision 126 5/1/13B 3.4.14 Revision 115 3/29/11B 3.4.15 Revision 115 3/29/11B 3.4.16 Revision 121 8/5/09B 3.4.17 Revision 115 3/29/11B 3.4.18 Revision 86 6/25/07B 3.5.1 Revision 115 3/29/11B 3.5.2 Revision 116 8/18/11B 3.5.3 Revision 57 4/29/04B 3.5.4 Revision 122 10/25/12B 3.5.5 Revision 115 3/29/11B 3.6.1 Revision 53 2/17/04B 3.6.2 Revision 115 3/29/11B 3.6.3 Revision 115 3/29/11B 3.6.4 Revision 115 3/29/11B 3.6.5 Revision 115 3/29/11B 3.6.6 Revision 122 10/25/12B 3.6.7 Not Used -Revision 63 4/4/05B 3.6.8 Revision 115 3/29/11B 3.6.9 Revision 131 4/14/14B 3.6.10 Revision 120 4/26/12B 3.6.11 Revision 122 10/25/12B 3.6.12 Revision 115 3/29/11B 3.6.13 Revision 115 3/29/11B 3.6.14 Revision 115 3/29/11B 3.6.15 Revision 125 10/19/12B 3.6.16 Revision 130 4/7/14McGuire Units 1 and 2Page 2Revision 122 Page NumberAmendment Revision DateB 3.7.1 Revision 129 10/24/13B 3.7.2 Revision 105 2/22/10B 3.7.3 Revision 102 8/17/09B 3.7.4 Revision 115 3/29/11B 3.7.5 Revision 115 3/29/11B 3.7.6 Revision 127 8/2/13B 3.7.7 Revision 135 2/11/15B 3.7.8 Revision 128 10/2/13B 3.7.9 Revision 120 4/26/12B 3.7.10 Revision 115 3/29/11B 3.7.11 Revision 115 3/29/11B 3.7.12 Revision 115 3/29/11B 3.7.13 Revision 115 3/29/11B 3.7.14 Revision 115 3/29/11B 3.7.15 Revision 66 6/30/05B 3.7.16 Revision 115 3/29/11B 3.8.1 Revision 115 3/29/11B 3.8.2 Revision 92 1/28/08B 3.8.3 Revision 123 9/29/12B 3.8.4 Revision 133 9/10/14B 3.8.5 Revision 41 7/29/03B 3.8.6 Revision 115 3/29/11B 3.8.7 Revision 115 3/29/11B 3.8.8 Revision 115 3/29/11B 3.8.9 Revision 115 3/29/11B 3.8.10 Revision 115 3/29/11B 3.9.1 Revision 115 3/29/11B 3.9.2 Revision 115 3/29/11B 3.9.3 Revision 115 3/29/11B 3.9.4 Revision 115 3/29/11B 3.9.5 Revision 115 3/29/11B 3.9.6 Revision 115 3/29/11B 3.9.7 Revision 115 3/29/11McGuire Units 1 and 2Page 3Revision 122 NSWSB 3.7.7B 3.7 PLANT SYSTEMSB 3.7.7 Nuclear Service Water System (NSWS)BASESBACKGROUND The NSWS provides a transfer mechanism for the removal of processand operating heat from safety related components during a Design BasisAccident (DBA) or transient. | | During normal operation, and a normal shutdown, the NSWS also provides this function for various safety related and nonsafety related components. |
| During normal operation, and a normalshutdown, the NSWS also provides this function for various safety relatedand nonsafety related components. | | The safety related function is covered by this LCO.The NSWS is normally supplied from Lake Norman as a non-seismic source, through a single supply line as shown in Figure B 3.7.7-1. An additional safety-related and seismic supply of water to the NSWS, in the event of a loss of Lake Norman, is the Standby Nuclear Service Water Pond (SNSWP). The supply line from Lake Norman separates into two supply headers, each header is capable of being isolated by two, independently powered, motor operated valves. The two supply headers feed into two separate supply trains. The "A" train supplies water to the"A" pump on each unit and the "B" train to the "B" pump on each unit.During normal operation, only one pump, per unit, is in operation to supply NSWS flow to the essential and non-essential headers for each unit. The "B" train supply is automatically realigned to the SNSWP and supplies the "B" header on an SI signal from either unit. The "A" train supply is automatically realigned to the low-level supply from Lake Norman and supplies the "A" header on an SI signal from either unit.Essential headers provide flow to the following safety related components and systems: 1. Component Cooling (CCW) Heat Exchangers and Pump Motor Coolers, 2. Containment Spray Heat Exchangers and Pump Motor Coolers, 3. Control Room Area Chiller Condensers, 4. Diesel Generator Heat Exchangers, 5. Centrifugal Charging Pump Motor, Bearing Oil and Gear Oil Coolers, 6. Nuclear Service Water Pump Motor Coolers, 7. Auxiliary Feedwa-ter Pump Motor Coolers, 8. Safety Injection Pump Motor and Bearing Oil Coolers, 9. Residual Heat Removal Pump Motor Coolers, 10. Fuel Pool Pump Motor Coolers, 11. Assured Auxiliary Feedwater Supply, 12. Assured Component Cooling System Makeup, 13. Assured Fuel Pool Cooling System makeup, and 14. Assured Diesel Generator Engine Cooling System makeup.McGuire Units 1 and 2 B 3.7.7-1 Revision No. 135 NSWS B 3.7.7 BASES BACKGROUND (continued) |
| The safety related function iscovered by this LCO.The NSWS is normally supplied from Lake Norman as a non-seismic source, through a single supply line as shown in Figure B 3.7.7-1. | | The non-essential channel supply comes from the "A" and "B" train crossover piping and isolates on an SI or Blackout signal.The Reactor Coolant Pump Motor Air Coolers are not essential for safe shutdown, but are set up to receive cooling flow until the Containment, High-High signal is received. |
| Anadditional safety-related and seismic supply of water to the NSWS, in theevent of a loss of Lake Norman, is the Standby Nuclear Service WaterPond (SNSWP).
| | The pumps and valves are remote and manually aligned, except in the unlikely event of a loss of coolant accident (LOCA). The pumps aligned to the critical loops are automatically started upon receipt of a safety injection or Station Blackout signal, and all essential valves are aligned to their post accident positions. |
| The supply line from Lake Norman separates into twosupply headers, each header is capable of being isolated by two,independently | | Additional information about the design and operation of the NSWS, along with a list of the components served, is presented in the UFSAR, Section 9.2 (Ref. 1). The principal safety related function of the NSWS is the removal of decay heat from the reactor via the CCW System.APPLICABLE The design basis of the NSWS is for one NSWS train, in conjunction with SAFETY ANALYSES the CCW System and the Containment Spray system, to remove core decay heat following a design basis LOCA as discussed in the UFSAR, Section 6.2 (Ref. 2). This prevents the containment sump fluid from increasing in temperature during the recirculation phase following a LOCA and provides for a gradual reduction in the temperature of this fluid as it is supplied to the Reactor Coolant System by the ECCS pumps. The NSWS is designed to perform its function with a single failure of any active component, assuming the loss of offsite power.The NSWS, in conjunction with the CCW System, also removes heat from the residual heat removal (RHR) system, as discussed in the UFSAR, Section 5.4 (Ref. 3), from RHR entry conditions to MODE 5 during normal and post accident operations. |
| : powered, motor operated valves. The two supply headersfeed into two separate supply trains. The "A" train supplies water to the"A" pump on each unit and the "B" train to the "B" pump on each unit.During normal operation, only one pump, per unit, is in operation tosupply NSWS flow to the essential and non-essential headers for eachunit. The "B" train supply is automatically realigned to the SNSWP andsupplies the "B" header on an SI signal from either unit. The "A" trainsupply is automatically realigned to the low-level supply from LakeNorman and supplies the "A" header on an SI signal from either unit.Essential headers provide flow to the following safety related components and systems:1. Component Cooling (CCW) Heat Exchangers and Pump Motor Coolers,2. Containment Spray Heat Exchangers and Pump Motor Coolers,3. Control Room Area Chiller Condensers,
| | The time required for this evolution is a function of the number of CCW and RHR System trains that are operating. |
| : 4. Diesel Generator Heat Exchangers,
| | One NSWS train is sufficient to remove decay heat during subsequent operations in MODES 5 and 6. This assumes a maximum NSWS inlet temperature of 102 0 F is not exceeded.The NSWS satisfies Criterion 3 of 10 CFR 50.36 (Ref. 4).LCO Two NSWS trains are required to be OPERABLE to provide the required redundancy to ensure that the system functions to remove post accident McGuire Units 1 and 2 B 3.7.7-2 Revision No. 135 NSWS B 3.7.7 BASES LCO (continued) heat loads, assuming that the worst case single active failure occurs coincident with the loss of offsite power.An NSWS train is considered OPERABLE during MODES 1, 2, 3, and 4 when: a. The associated unit's pump is OPERABLE; and b. The associated piping, valves, and instrumentation and controls required to perform the safety related function are OPERABLE.Portions of the NSWS system are shared between the two units (Figure B 3.7.7-1). |
| : 5. Centrifugal Charging Pump Motor, Bearing Oil and Gear Oil Coolers,6. Nuclear Service Water Pump Motor Coolers,7. Auxiliary Feedwa-ter Pump Motor Coolers,8. Safety Injection Pump Motor and Bearing Oil Coolers,9. Residual Heat Removal Pump Motor Coolers,10. Fuel Pool Pump Motor Coolers,11. Assured Auxiliary Feedwater Supply,12. Assured Component Cooling System Makeup,13. Assured Fuel Pool Cooling System makeup, and14. Assured Diesel Generator Engine Cooling System makeup.McGuire Units 1 and 2B 3.7.7-1Revision No. 135 NSWSB 3.7.7BASESBACKGROUND (continued)
| | The shared portions of the system must be OPERABLE for each unit when that unit is in the MODE of Applicability. |
| The non-essential channel supply comes from the "A" and "B" traincrossover piping and isolates on an SI or Blackout signal.The Reactor Coolant Pump Motor Air Coolers are not essential for safeshutdown, but are set up to receive cooling flow until the Containment, High-High signal is received. | | Additionally, both normal and emergency power for shared components must also be OPERABLE. |
| The pumps and valves are remote andmanually | | If a shared NSWS component becomes inoperable, or normal or emergency power to shared components becomes inoperable, then the Required Actions of this LCO must be entered independently for each unit that is in the MODE of applicability of the LCO.APPLICABILITY In MODES 1, 2, 3, and 4, the NSWS is a normally operating system that is required to support the OPERABILITY of the equipment serviced by the NSWS and required to be OPERABLE in these MODES.In MODES 5 and 6, the requirements of the NSWS are determined by the systems it supports.ACTIONS A._1 If one NSWS train is inoperable, action must be taken to restore OPERABLE status within 72 hours. In this Condition, the remaining OPERABLE NSWS train is adequate to perform the heat removal function. |
| : aligned, except in the unlikely event of a loss of coolantaccident (LOCA). The pumps aligned to the critical loops areautomatically started upon receipt of a safety injection or StationBlackout signal, and all essential valves are aligned to their post accidentpositions.
| | However, the overall reliability is reduced because a single failure in the OPERABLE NSWS train could result in loss of NSWS function. |
| Additional information about the design and operation of the NSWS,along with a list of the components served, is presented in the UFSAR,Section 9.2 (Ref. 1). The principal safety related function of the NSWS isthe removal of decay heat from the reactor via the CCW System.APPLICABLE The design basis of the NSWS is for one NSWS train, in conjunction withSAFETY ANALYSES the CCW System and the Containment Spray system, to remove coredecay heat following a design basis LOCA as discussed in the UFSAR,Section 6.2 (Ref. 2). This prevents the containment sump fluid fromincreasing in temperature during the recirculation phase following aLOCA and provides for a gradual reduction in the temperature of thisfluid as it is supplied to the Reactor Coolant System by the ECCSpumps. The NSWS is designed to perform its function with a singlefailure of any active component, assuming the loss of offsite power.The NSWS, in conjunction with the CCW System, also removes heatfrom the residual heat removal (RHR) system, as discussed in theUFSAR, Section 5.4 (Ref. 3), from RHR entry conditions to MODE 5during normal and post accident operations. | | Required Action A. 1 is modified by two Notes. The first Note indicates that the applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources-Operating," should be entered if an inoperable NSWS train results in an inoperable emergency diesel generator. |
| The time required for thisevolution is a function of the number of CCW and RHR System trainsthat are operating. | | The second Note indicates that the applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4," should be entered if an inoperable NSWS train results in an inoperable decay heat removal train.McGuire Units 1 and 2 B 3.7.7-3 Revision No. 135 NSWS B 3.7.7 BASES ACTIONS (continued) |
| One NSWS train is sufficient to remove decay heatduring subsequent operations in MODES 5 and 6. This assumes amaximum NSWS inlet temperature of 1020F is not exceeded. | | This is an exception to LCO 3.0.6 and ensures the proper actions are taken for these components. |
| The NSWS satisfies Criterion 3 of 10 CFR 50.36 (Ref. 4).LCOTwo NSWS trains are required to be OPERABLE to provide the requiredredundancy to ensure that the system functions to remove post accidentMcGuire Units 1 and 2B 3.7.7-2Revision No. 135 NSWSB 3.7.7BASESLCO (continued) heat loads, assuming that the worst case single active failure occurscoincident with the loss of offsite power.An NSWS train is considered OPERABLE during MODES 1, 2, 3, and 4when:a. The associated unit's pump is OPERABLE; andb. The associated piping, valves, and instrumentation and controlsrequired to perform the safety related function are OPERABLE. | | The 72 hour Completion Time is based on the redundant capabilities afforded by the OPERABLE train, and the low probability of a DBA occurring during this time period.B.1 and B.2 If the NSWS train cannot be restored to OPERABLE status within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours and in MODE 5 within 36 hours.The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.SURVEILLANCE SR 3.7.7.1 REQUIREMENTS This SR is modified by a Note indicating that the isolation of the NSWS components or systems may render those components inoperable, but does not affect the OPERABILITY of the NSWS.Verifying the correct alignment for manual, power operated, and automatic valves in the NSWS flow path provides assurance that the proper flow paths exist for NSWS operation. |
| Portions of the NSWS system are shared between the two units (FigureB 3.7.7-1). | | This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since they are verified to be in the correct position prior to being locked, sealed, or secured. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position. |
| The shared portions of the system must be OPERABLE foreach unit when that unit is in the MODE of Applicability. | | This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves.The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.McGuire Units 1 and 2 B 3.7.7-4 Revision No. 135 NSWS B 3.7.7 BASES SURVEILLANCE REQUIREMENTS (continued) |
| Additionally, both normal and emergency power for shared components must also beOPERABLE. | | SR 3.7.7.2 This SR verifies proper automatic operation of the NSWS valves on an actual or simulated actuation safety injection signal. The NSWS is a normally operating system that cannot be fully actuated as part of normal testing. This Surveillance is not required for valves that are locked, sealed, or otherwise secured in the required position under administrative controls. |
| If a shared NSWS component becomes inoperable, ornormal or emergency power to shared components becomes inoperable, then the Required Actions of this LCO must be entered independently foreach unit that is in the MODE of applicability of the LCO.APPLICABILITY In MODES 1, 2, 3, and 4, the NSWS is a normally operating system thatis required to support the OPERABILITY of the equipment serviced by theNSWS and required to be OPERABLE in these MODES.In MODES 5 and 6, the requirements of the NSWS are determined by thesystems it supports. | | The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.SR 3.7.7.3 This SR verifies proper automatic operation of the NSWS pumps on an actual or simulated actuation signal. The NSWS is a normally operating system that cannot be fully actuated as part of normal testing during normal operation. |
| ACTIONS A._1If one NSWS train is inoperable, action must be taken to restoreOPERABLE status within 72 hours. In this Condition, the remaining OPERABLE NSWS train is adequate to perform the heat removalfunction. | | The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.REFERENCES |
| : However, the overall reliability is reduced because a singlefailure in the OPERABLE NSWS train could result in loss of NSWSfunction.
| |
| Required Action A. 1 is modified by two Notes. The first Noteindicates that the applicable Conditions and Required Actions ofLCO 3.8.1, "AC Sources-Operating," | |
| should be entered if an inoperable NSWS train results in an inoperable emergency diesel generator. | |
| Thesecond Note indicates that the applicable Conditions and RequiredActions of LCO 3.4.6, "RCS Loops-MODE 4," should be entered if aninoperable NSWS train results in an inoperable decay heat removal train.McGuire Units 1 and 2B 3.7.7-3Revision No. 135 NSWSB 3.7.7BASESACTIONS (continued)
| |
| This is an exception to LCO 3.0.6 and ensures the proper actions aretaken for these components. | |
| The 72 hour Completion Time is based onthe redundant capabilities afforded by the OPERABLE train, and the lowprobability of a DBA occurring during this time period.B.1 and B.2If the NSWS train cannot be restored to OPERABLE status within theassociated Completion Time, the unit must be placed in a MODE inwhich the LCO does not apply. To achieve this status, the unit must beplaced in at least MODE 3 within 6 hours and in MODE 5 within36 hours.The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full powerconditions in an orderly manner and without challenging unit systems.SURVEILLANCE SR 3.7.7.1REQUIREMENTS This SR is modified by a Note indicating that the isolation of the NSWScomponents or systems may render those components inoperable, butdoes not affect the OPERABILITY of the NSWS.Verifying the correct alignment for manual, power operated, andautomatic valves in the NSWS flow path provides assurance that theproper flow paths exist for NSWS operation. | |
| This SR does not apply tovalves that are locked, sealed, or otherwise secured in position, sincethey are verified to be in the correct position prior to being locked, sealed,or secured. | |
| This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of beingmispositioned are in the correct position. | |
| This SR does not apply tovalves that cannot be inadvertently misaligned, such as check valves.The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under theSurveillance Frequency Control Program.McGuire Units 1 and 2B 3.7.7-4Revision No. 135 NSWSB 3.7.7BASESSURVEILLANCE REQUIREMENTS (continued) | |
| SR 3.7.7.2This SR verifies proper automatic operation of the NSWS valves on anactual or simulated actuation safety injection signal. The NSWS is anormally operating system that cannot be fully actuated as part of normaltesting. | |
| This Surveillance is not required for valves that are locked,sealed, or otherwise secured in the required position underadministrative controls. | |
| The Surveillance Frequency is based onoperating experience, equipment reliability, and plant risk and iscontrolled under the Surveillance Frequency Control Program.SR 3.7.7.3This SR verifies proper automatic operation of the NSWS pumps on anactual or simulated actuation signal. The NSWS is a normally operating system that cannot be fully actuated as part of normal testing duringnormal operation. | |
| The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled underthe Surveillance Frequency Control Program.REFERENCES | |
| : 1. UFSAR, Section 9.2.2. UFSAR, Section 6.2.3. UFSAR, Section 5.4.4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii). | | : 1. UFSAR, Section 9.2.2. UFSAR, Section 6.2.3. UFSAR, Section 5.4.4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii). |
| : 5. 10 CFR 50, Appendix A, GDC 5, "Sharing of Structures, | | : 5. 10 CFR 50, Appendix A, GDC 5, "Sharing of Structures, Systems, and Components". |
| : Systems, and Components".
| | McGuire Units 1 and 2 B 3.7.7-5 Revision No. 135 NSWS B 3.7.7 BASES FIGURE B 3.7.7-1 NUCLEAR SERVICE WATER SYSTEM (, C3 w zX McGuire Units 1 and 2 B 3.7.7-6 Revision No. 135}} |
| McGuire Units 1 and 2B 3.7.7-5Revision No. 135 NSWSB 3.7.7BASESFIGURE B 3.7.7-1 NUCLEAR SERVICE WATER SYSTEM(, C3w zXMcGuire Units 1 and 2B 3.7.7-6Revision No. 135}} | |
|
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Category:Memoranda
MONTHYEARML23118A2852023-05-0202 May 2023 Public Meeting Summary - 2022 Annual Assessment Meeting Regarding Catawba Nuclear Station, McGuire Nuclear and Oconee Nuclear Station ML22299A1052023-01-11011 January 2023 Memo to File - McGuire Final EA 2017+19+21 ML21056A5502021-04-22022 April 2021 Memo to File - Ea/Fonsi for McGuire DFP ML21099A0932021-04-0909 April 2021 Public Meeting Summary - 2020 Annual Assessment Meeting Regarding Catawba, McGuire, and Oconee Nuclear Stations ML20141L4172020-05-20020 May 2020 EOC Public Meeting Summary ML19088A1362019-03-29029 March 2019 Public Meeting Summary ML20052D9362018-07-0303 July 2018 Response to Nrg Request for Additional Information (RAI) Regarding NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density ML18089A0532018-03-30030 March 2018 Summary of Public Meeting with McGuire Nuclear Station ML17151A3372017-06-0202 June 2017 Recommendation for Non-Acceptance with Opportunity to Supplement of McGuire Nuclear Station Units 1 and 2 Technical Specifications Completion Time Extension Request for Failure to Supply Information (CACs MF9673, MF9674) ML17110A1862017-04-20020 April 2017 Summary of Public Meeting - McGuire, Units 1 and 2 to Discuss Concerning Annual Assessment ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16082A0682016-03-21021 March 2016 Summary of Meeting with the Public Concerning the Annual Assessment of McGuire Nuclear Station, Units 1 and 2 ML15138A3392015-06-0101 June 2015 Summary of Public Teleconference Regarding Potential Submission of a License Amendment Request for a One-Time Extension of Completion Time for Nuclear Service Water System ML15106A0222015-04-15015 April 2015 Summary of Meeting with Public to Discuss Annual Assessment of McGuire Nuclear Station, Units 1 and 2, in Huntersville, North Carolina ML15119A2182015-04-0707 April 2015 Technical Specification (TS) and Tech Spec Bases (Tsb) Manual ML15083A0832015-03-10010 March 2015 TS Bases Updates ML14136A1302014-05-15015 May 2014 End of Cycle Meeting Summary Memo ML14142A0112014-05-0505 May 2014 Technical Specification & Technical Specification Bases ML13295A3062013-10-22022 October 2013 Meeting Notice with Duke Energy Carolinas, LLC Discuss the Planned Modifications Related to the Fukushima Flood Hazard Reevaluations for the Sites Operated by Duke Energy Carolinas, LLC ML13198A1732013-07-17017 July 2013 Notice of Forthcoming Pre-Application Teleconference with Duke Energy Carolinas, LLC, McGuire Units 1 and 2 ML13191A9592013-07-15015 July 2013 Notice of Pre-Application Meeting with Duke Energy Carolinas, LLC, McGuire Units 1 & 2, to Discuss with Licensee Its Proposed License Amendment Request to Technical Specification 3.8.4 Condition a to Allow Replacement of Existing Shared ... ML13204A1162013-06-26026 June 2013 SLC Manual Update ML13135A5962013-05-16016 May 2013 Cancelled 05/23/2013 Notice of Forthcoming Pre-Application Meeting with Duke Energy Carolinas, Llc. to Discuss a Proposed License Amendment Request Concerning Methodology Report DPC-NE-3001-P for Catawba and McGuire Nuclear Stations ML13127A4352013-05-0909 May 2013 Notice of Forthcoming Pre-Application Meeting with Duke Energy Carolinas, Llc. to Discuss a Proposed License Amendment Request Concerning Methodology Report DPC-NE-3001-P for Catawba and McGuire Nuclear Stations ML13072B2022013-03-19019 March 2013 Meeting Notice with Duke Energy Concerning NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants License Amendment Request for Catawba, McGuire, and H. B. Robinson ML12340A5182012-11-26026 November 2012 Submittal of Technical Specification (TS) and Technical Specification Bases (Tsb) Manual ML12300A4032012-10-26026 October 2012 11/8/2012 Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-design-Basis External Events ML12284A4612012-10-12012 October 2012 Forthcoming Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-Design-Basis External Events ML1218006502012-07-0303 July 2012 Mcguire Nuclear Station, Units 1 and 2 - Fire Protection Fire Protection Safety Evaluation Input Regarding License Amendment Request Measurement Uncertainty Recapture Power Uprate ML11257A0382011-09-0101 September 2011 Technical Specification Bases Updates ML1106603302011-03-0707 March 2011 Notice of Meeting with Duke Energy to Present Status of Licensing Submittals Regarding Implementation of National Fire Protection Association Standard 805, Requirements at Catawba Nuclear Station, Units 1 and 2 and McGuire Nuclear Station ML1104900602011-03-0404 March 2011 Final McGuire Task Interface Agreement (TIA) - McGuire Service Water System Unit Crossties Relative to Sharing/Donating in Abnormal Procedures (TIA 2009-011) ML1029306502010-10-20020 October 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC Regarding McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2, ML1027001972010-09-14014 September 2010 Revisions to Technical Specifications Bases ML1025203282010-09-13013 September 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC (Duke), to Discuss Duke'S Potential Submittal of an Amendment to McGuire 1 and 2 Licenses Regarding Implementation of an Alternate Source Term ML1015804072010-06-0808 June 2010 the Nuclear Regulatory Commission Staff Spot-Check Review of Duke Energy'S Ownership Interest of Catawba, Units 1 and 2, McGuire, Units 1 and 2, and Oconee, Units 1, 2 and 3 on May 20, 2010 - Finding of No Potential Issues in Bank Statement ML1012604632010-05-0707 May 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC (Duke) to Discuss Duke'S Responses to Generic Letter 2004-02 at Catawba 1 and 2 and McGuire 1 and 2 ML1007503442010-03-10010 March 2010 Submittal of Technical Specification Bases Updates ML0926700202009-10-0707 October 2009 Summary of Conference Call with Duke Regarding Responses to Generic Letter (GL) 2004-02 ML0922908922009-08-18018 August 2009 Notice of Conference Call with Duke Energy Carolinas, LLC (Duke), Regarding Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2) and McGuire Nuclear Station Units 1 and 2 ML0908202662009-03-16016 March 2009 Submittal of Facility Operating License Revision ML0831009482008-11-10010 November 2008 Notice of Meeting with Duke Energy Carolinas, LLC, (Duke), Catawba, Units 1 and 2, and McGuire, Units 1 and 2 ML0831107952008-11-0606 November 2008 Cancellation of Meeting with Duke Energy Carolinas, LLC, to Discuss the Request for Additional Information Generic Letter 2004-04, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents. ML0829701832008-10-30030 October 2008 Notice of Meeting with Duke Energy Carolinas, LLC, to Discuss the Request for Additional Information Generic Letter 2004-04, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents ... ML0818301542008-07-0101 July 2008 Notice of Meeting with Duke Energy Carolinas, LLC to Discuss Transition to ASME NQA-1-1994 ML0809200162008-04-0101 April 2008 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.2.06 Regarding Protection Against High-Pressure Feedwater Heater ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0805704982008-02-27027 February 2008 Memo to Wong Re Request for Exemption - Duke Power Company'S December 3, 2007, Request for Exemption from 10 CFR 74.19(C) Requirements Regarding Physical Inventory ML0805602452008-02-14014 February 2008 Document Transmittal Form for Technical Specifications and Technical Specification Bases 2023-05-02
[Table view] Category:Technical Specification
MONTHYEARRA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power RA-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-16016 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020 Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS2019-02-0505 February 2019 Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS RA-18-0166, Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-09-13013 September 2018 Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs ML18191A5452018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-18-001, Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages2018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. ML17237A0492017-08-17017 August 2017 Technical Specification Bases - List of Effected Sheets ML17237A0482017-08-17017 August 2017 Technical Specification Bases (Rev. 150) ML17237A0462017-08-17017 August 2017 Document Transmittal Form Regarding Technical Specification Changes - Amendment Nos. 296/275 ML17186A0682017-06-26026 June 2017 Tech Spec Bases - List of Affected Sections ML17186A0672017-06-26026 June 2017 Revision 151 to Tech Spec Bases - B 3.6.13 and B 3.6.14 ML17186A0662017-06-26026 June 2017 TS 3.6.13 Amendment 292/271 and TS 3.6.14 Amendment 294/273 ML17186A0692017-06-26026 June 2017 Issue Tech Spec - List of Affected Pages ML17136A2792017-05-0303 May 2017 Technical Specification Leep, Rev. 109 ML17136A2782017-05-0303 May 2017 Technical Specification Bases - Loes, Rev. 133 ML17136A3612017-05-0303 May 2017 Technical Specification Bases, Revision 149 ML17136A3602017-05-0303 May 2017 Technical Specification Amendment Nos. 285/264 ML17124A3682017-04-19019 April 2017 Tech Spec Bases List of Effected Pages ML17124A3712017-04-19019 April 2017 Bases B 3.5.1 - Accumulators ML17094A6722017-03-29029 March 2017 Issue Selected License Commitment Cslcl 16.7.14 Revision ML17094A6732017-03-29029 March 2017 Issue SLC List of Effected Pages ML17090A4522017-03-23023 March 2017 Revision to Technical Specification 3.3.2 - Amendment 293/272 ML17090A4512017-03-23023 March 2017 Revision to Technical Specification 3.8.1 - Amendment 293/272 ML17090A4352017-03-22022 March 2017 Technical Specification Bases ML17090A4502017-03-22022 March 2017 Revision to Technical Specification Bases - B 3.6.15 ML17094A6702017-03-15015 March 2017 Issue MNS-SLC-16.9.15. Snubbers MNS-16-092, License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-12-19019 December 2016 License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16305A1442016-10-20020 October 2016 Issue MNS Technical Specification 5.5 RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process ML16265A5312016-08-30030 August 2016 Issue MNS Tech Spec Bases List of Effective Sections ML16265A5322016-08-30030 August 2016 Technical Specification Bases 3.6.14 Revisions, List of Revisions and Dates ML16250A0142016-08-29029 August 2016 Amendment 287 ML16243A3492016-08-23023 August 2016 Mccguire, Units 1 and 2, Revision 143 to Issue MNS Technical Specification Bases 3.3.1 ML16243A3482016-08-23023 August 2016 Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation. ML16243A3512016-08-23023 August 2016 Revision 105 to Technical Specifications List of Effective Pages ML16243A3502016-08-23023 August 2016 Revision 129 to Technical Specification Bases ML16243A3572016-08-18018 August 2016 Technical Specification Bases Revision 001, List of Revised Sections 2023-02-16
[Table view] Category:Bases Change
MONTHYEARRA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS2019-02-0505 February 2019 Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS RA-18-0166, Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-09-13013 September 2018 Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs ML18191A5452018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-18-001, Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages2018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. ML17237A0462017-08-17017 August 2017 Document Transmittal Form Regarding Technical Specification Changes - Amendment Nos. 296/275 ML17237A0482017-08-17017 August 2017 Technical Specification Bases (Rev. 150) ML17237A0492017-08-17017 August 2017 Technical Specification Bases - List of Effected Sheets ML17186A0662017-06-26026 June 2017 TS 3.6.13 Amendment 292/271 and TS 3.6.14 Amendment 294/273 ML17186A0672017-06-26026 June 2017 Revision 151 to Tech Spec Bases - B 3.6.13 and B 3.6.14 ML17186A0682017-06-26026 June 2017 Tech Spec Bases - List of Affected Sections ML17186A0692017-06-26026 June 2017 Issue Tech Spec - List of Affected Pages ML17136A3612017-05-0303 May 2017 Technical Specification Bases, Revision 149 ML17136A3602017-05-0303 May 2017 Technical Specification Amendment Nos. 285/264 ML17136A2792017-05-0303 May 2017 Technical Specification Leep, Rev. 109 ML17136A2782017-05-0303 May 2017 Technical Specification Bases - Loes, Rev. 133 ML17124A3682017-04-19019 April 2017 Tech Spec Bases List of Effected Pages ML17124A3712017-04-19019 April 2017 Bases B 3.5.1 - Accumulators ML17094A6722017-03-29029 March 2017 Issue Selected License Commitment Cslcl 16.7.14 Revision ML17094A6732017-03-29029 March 2017 Issue SLC List of Effected Pages ML17090A4522017-03-23023 March 2017 Revision to Technical Specification 3.3.2 - Amendment 293/272 ML17090A4512017-03-23023 March 2017 Revision to Technical Specification 3.8.1 - Amendment 293/272 ML17090A4352017-03-22022 March 2017 Technical Specification Bases ML17090A4502017-03-22022 March 2017 Revision to Technical Specification Bases - B 3.6.15 ML17094A6702017-03-15015 March 2017 Issue MNS-SLC-16.9.15. Snubbers RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process ML16265A5312016-08-30030 August 2016 Issue MNS Tech Spec Bases List of Effective Sections ML16265A5322016-08-30030 August 2016 Technical Specification Bases 3.6.14 Revisions, List of Revisions and Dates ML16250A0142016-08-29029 August 2016 Amendment 287 ML16243A3482016-08-23023 August 2016 Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation. ML16243A3502016-08-23023 August 2016 Revision 129 to Technical Specification Bases ML16243A3512016-08-23023 August 2016 Revision 105 to Technical Specifications List of Effective Pages ML16243A3492016-08-23023 August 2016 Mccguire, Units 1 and 2, Revision 143 to Issue MNS Technical Specification Bases 3.3.1 ML16243A3572016-08-18018 August 2016 Technical Specification Bases Revision 001, List of Revised Sections ML16243A3552016-08-17017 August 2016 Renewed Facility Operating License, Amendment 284 ML16243A3522016-08-17017 August 2016 Technical Specification 3.4.18, Amendment Nos. 284/263, Steam Generator (SG) Tube Integrity. ML16243A3542016-08-17017 August 2016 Technical Specification Bases 3.4.18, Revision 144, Steam Generator (SG) Tube Integrity RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process ML16139A5572016-05-10010 May 2016 Technical Specification Bases 3.3.1 Rev. 001, Revision 141 ML16139A5552016-05-10010 May 2016 Technical Specification Bases 3.9.3, Revision 001, Revision 142 MNS-16-020, License Amendment Request Removal of Superseded Technical Specification Requirements2016-05-0505 May 2016 License Amendment Request Removal of Superseded Technical Specification Requirements MNS-16-015, License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval2016-02-18018 February 2016 License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval ML16056A2432016-02-18018 February 2016 Emergency Action Level Technical Bases Document Redline MNS-16-016, Emergency Action Level Technical Bases, Revision 1 Redline. Part 1 of 22016-02-18018 February 2016 Emergency Action Level Technical Bases, Revision 1 Redline. Part 1 of 2 ML16056A2452016-02-18018 February 2016 Emergency Action Level Technical Bases, Revision 1 Redline. Part 2 of 2 2023-02-16
[Table view] |
Text
PRIORITY Normal DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW Date: 03/10115 Document Transmittal
- DUK150690031
- 1) 01820 J R ELKINS- EC081 2) 02361 QATS-MG01MM
- 3) 02388 BOB SCHOMAKER LYNCHBG, VA 4) 02532 RESIDENT NRC INSPECT MG01 NRC 5) 03044 MCG DOC CNTRL MISC MAN MG05DM 6) 03614 MCG OPS PROCEDURE GP MG01OP 7) 03744 OPS TRNG MGR. MG030T 8) 03759 U S NUC REG WASHINGTON, DC 9) 03796 SCIENTECH CLEARWTR, FL 10) 04809 MCG PLANT ENG. LIBR. MG05SE 11) 05262 J L FREEZE MG01IE 12) 05606 J C MORTON MG01EP 13) 08103 WESTINGHOUSE ELECTRIC CO LLC 14) 09665 JON H THOMPSON, USNRC Duke Energy DOCUMENT TRANSMITTAL FORM REFERENCE MCGUIRE NUCLEAR STATION TECHNICAL SPECIFICATIONS (TS)TECHNICAL SPECIFICATIONS BASES (TSB)RECORD RETENTION
- 421734 Page 2 of 2 QA CONDITION
[] Yes 0 No OTHER ACKNOWLEDGEMENT REQUIRED 0 Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO: Duke Energy McGuire DCRM MGO2DM 13225 Hagers Ferry Road Huntersville, N.C. 28078 Rec'd By Date DOCUMENT NO QACOND REV #/ DATE DISTR CODE 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 TOTAL MNS TSB 3.7.7 N/A 135 03/10/15 MADM-04B V1 V1 V1 x V3 V1 V1 V1 V1 vi V1 29 REMARKS: PLEASE UPDATE ACCORDINGLY.
TECHNICAL SPECIFICATION BASES LOES REVISION 122 DATED 02/25/15 S D CAPPS VICE PRESIDENT MCGUIRE NUCLEAR STATION BY: B C BEAVER MG01RC BCB/BRG-~
February 25, 2015 MEMORANDUM
Subject:
McGuire TS Bases Updates REMOVE INSERT TSB List of Effected Sections Rev 121 TSB List of Effected Sections Rev 122 TSB 3.7.7 Rev. 115 TSB 3.7.7 Rev 135 Due to the revision process used for TS and Bases, revision numbers may be skipped.Please call me if you have questions.
Bonnie Beaver Regulatory Compliance 875-4180 McGuire Nuclear Station Technical Specification Bases LOES TS Bases are revised by section Page Number Revision Revision Date O BASES (Revised per section)i Revision 87 8/15/07 ii Revision 87 8/15/07 iii Revision 87 8/15/07 B 2.1.1 Revision 51 01/14/04 B 2.1.2 Revision 109 9/20/10 B 3.0 Revision 81 3/29/07 B 3.1.1 Revision 115 3/29/11 B 3.1.2 Revision 115 3/29/11 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 115 3/29/11 B 3.1.5 Revision 115 3/29/11 B 3.1.6 Revision 115 3/29/11 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 115 3/29/11 B 3.2.1 Revision 115 3/29/11 B 3.2.2 Revision 115 3/29/11 B 3.2.3 Revision 115 3/29/11 B 3.2.4 Revision 115 3/29/11 B 3.3.1 Revision 124 10/1/12 B 3.3.2 Revision 132 8/27/14 B 3.3.3 Revision 122 10/25/12 B 3.3.4 Revision 115 3/29/11 B 3.3.5 Revision 115 3/29/11 B 3.3.6 Not Used -Revision 87 6129/06 B 3.4.1 Revision 115 3/29/11 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 115 3/29/11 B 3.4.4 Revision 115 3/29/11 B 3.4.5 Revision 115 3/29/11 McGuire Units 1 and 2 Page I Revision 122 Page Number Amendment Revision Date B 3.4.6 Revision 115 3/29/11 B 3.4.7 Revision 115 3/29/11 B 3.4.8 Revision 115 3/29/11 B 3.4.9 Revision 115 3/29/11 B 3.4.10 Revision 102 8/17/09 B 3.4.11 Revision 115 3/29/11 B 3.4.12 Revision 134 1/8/15 B 3.4.13 Revision 126 5/1/13 B 3.4.14 Revision 115 3/29/11 B 3.4.15 Revision 115 3/29/11 B 3.4.16 Revision 121 8/5/09 B 3.4.17 Revision 115 3/29/11 B 3.4.18 Revision 86 6/25/07 B 3.5.1 Revision 115 3/29/11 B 3.5.2 Revision 116 8/18/11 B 3.5.3 Revision 57 4/29/04 B 3.5.4 Revision 122 10/25/12 B 3.5.5 Revision 115 3/29/11 B 3.6.1 Revision 53 2/17/04 B 3.6.2 Revision 115 3/29/11 B 3.6.3 Revision 115 3/29/11 B 3.6.4 Revision 115 3/29/11 B 3.6.5 Revision 115 3/29/11 B 3.6.6 Revision 122 10/25/12 B 3.6.7 Not Used -Revision 63 4/4/05 B 3.6.8 Revision 115 3/29/11 B 3.6.9 Revision 131 4/14/14 B 3.6.10 Revision 120 4/26/12 B 3.6.11 Revision 122 10/25/12 B 3.6.12 Revision 115 3/29/11 B 3.6.13 Revision 115 3/29/11 B 3.6.14 Revision 115 3/29/11 B 3.6.15 Revision 125 10/19/12 B 3.6.16 Revision 130 4/7/14 McGuire Units 1 and 2 Page 2 Revision 122 Page Number Amendment Revision Date B 3.7.1 Revision 129 10/24/13 B 3.7.2 Revision 105 2/22/10 B 3.7.3 Revision 102 8/17/09 B 3.7.4 Revision 115 3/29/11 B 3.7.5 Revision 115 3/29/11 B 3.7.6 Revision 127 8/2/13 B 3.7.7 Revision 135 2/11/15 B 3.7.8 Revision 128 10/2/13 B 3.7.9 Revision 120 4/26/12 B 3.7.10 Revision 115 3/29/11 B 3.7.11 Revision 115 3/29/11 B 3.7.12 Revision 115 3/29/11 B 3.7.13 Revision 115 3/29/11 B 3.7.14 Revision 115 3/29/11 B 3.7.15 Revision 66 6/30/05 B 3.7.16 Revision 115 3/29/11 B 3.8.1 Revision 115 3/29/11 B 3.8.2 Revision 92 1/28/08 B 3.8.3 Revision 123 9/29/12 B 3.8.4 Revision 133 9/10/14 B 3.8.5 Revision 41 7/29/03 B 3.8.6 Revision 115 3/29/11 B 3.8.7 Revision 115 3/29/11 B 3.8.8 Revision 115 3/29/11 B 3.8.9 Revision 115 3/29/11 B 3.8.10 Revision 115 3/29/11 B 3.9.1 Revision 115 3/29/11 B 3.9.2 Revision 115 3/29/11 B 3.9.3 Revision 115 3/29/11 B 3.9.4 Revision 115 3/29/11 B 3.9.5 Revision 115 3/29/11 B 3.9.6 Revision 115 3/29/11 B 3.9.7 Revision 115 3/29/11 McGuire Units 1 and 2 Page 3 Revision 122 NSWS B 3.7.7 B 3.7 PLANT SYSTEMS B 3.7.7 Nuclear Service Water System (NSWS)BASES BACKGROUND The NSWS provides a transfer mechanism for the removal of process and operating heat from safety related components during a Design Basis Accident (DBA) or transient.
During normal operation, and a normal shutdown, the NSWS also provides this function for various safety related and nonsafety related components.
The safety related function is covered by this LCO.The NSWS is normally supplied from Lake Norman as a non-seismic source, through a single supply line as shown in Figure B 3.7.7-1. An additional safety-related and seismic supply of water to the NSWS, in the event of a loss of Lake Norman, is the Standby Nuclear Service Water Pond (SNSWP). The supply line from Lake Norman separates into two supply headers, each header is capable of being isolated by two, independently powered, motor operated valves. The two supply headers feed into two separate supply trains. The "A" train supplies water to the"A" pump on each unit and the "B" train to the "B" pump on each unit.During normal operation, only one pump, per unit, is in operation to supply NSWS flow to the essential and non-essential headers for each unit. The "B" train supply is automatically realigned to the SNSWP and supplies the "B" header on an SI signal from either unit. The "A" train supply is automatically realigned to the low-level supply from Lake Norman and supplies the "A" header on an SI signal from either unit.Essential headers provide flow to the following safety related components and systems: 1. Component Cooling (CCW) Heat Exchangers and Pump Motor Coolers, 2. Containment Spray Heat Exchangers and Pump Motor Coolers, 3. Control Room Area Chiller Condensers, 4. Diesel Generator Heat Exchangers, 5. Centrifugal Charging Pump Motor, Bearing Oil and Gear Oil Coolers, 6. Nuclear Service Water Pump Motor Coolers, 7. Auxiliary Feedwa-ter Pump Motor Coolers, 8. Safety Injection Pump Motor and Bearing Oil Coolers, 9. Residual Heat Removal Pump Motor Coolers, 10. Fuel Pool Pump Motor Coolers, 11. Assured Auxiliary Feedwater Supply, 12. Assured Component Cooling System Makeup, 13. Assured Fuel Pool Cooling System makeup, and 14. Assured Diesel Generator Engine Cooling System makeup.McGuire Units 1 and 2 B 3.7.7-1 Revision No. 135 NSWS B 3.7.7 BASES BACKGROUND (continued)
The non-essential channel supply comes from the "A" and "B" train crossover piping and isolates on an SI or Blackout signal.The Reactor Coolant Pump Motor Air Coolers are not essential for safe shutdown, but are set up to receive cooling flow until the Containment, High-High signal is received.
The pumps and valves are remote and manually aligned, except in the unlikely event of a loss of coolant accident (LOCA). The pumps aligned to the critical loops are automatically started upon receipt of a safety injection or Station Blackout signal, and all essential valves are aligned to their post accident positions.
Additional information about the design and operation of the NSWS, along with a list of the components served, is presented in the UFSAR, Section 9.2 (Ref. 1). The principal safety related function of the NSWS is the removal of decay heat from the reactor via the CCW System.APPLICABLE The design basis of the NSWS is for one NSWS train, in conjunction with SAFETY ANALYSES the CCW System and the Containment Spray system, to remove core decay heat following a design basis LOCA as discussed in the UFSAR, Section 6.2 (Ref. 2). This prevents the containment sump fluid from increasing in temperature during the recirculation phase following a LOCA and provides for a gradual reduction in the temperature of this fluid as it is supplied to the Reactor Coolant System by the ECCS pumps. The NSWS is designed to perform its function with a single failure of any active component, assuming the loss of offsite power.The NSWS, in conjunction with the CCW System, also removes heat from the residual heat removal (RHR) system, as discussed in the UFSAR, Section 5.4 (Ref. 3), from RHR entry conditions to MODE 5 during normal and post accident operations.
The time required for this evolution is a function of the number of CCW and RHR System trains that are operating.
One NSWS train is sufficient to remove decay heat during subsequent operations in MODES 5 and 6. This assumes a maximum NSWS inlet temperature of 102 0 F is not exceeded.The NSWS satisfies Criterion 3 of 10 CFR 50.36 (Ref. 4).LCO Two NSWS trains are required to be OPERABLE to provide the required redundancy to ensure that the system functions to remove post accident McGuire Units 1 and 2 B 3.7.7-2 Revision No. 135 NSWS B 3.7.7 BASES LCO (continued) heat loads, assuming that the worst case single active failure occurs coincident with the loss of offsite power.An NSWS train is considered OPERABLE during MODES 1, 2, 3, and 4 when: a. The associated unit's pump is OPERABLE; and b. The associated piping, valves, and instrumentation and controls required to perform the safety related function are OPERABLE.Portions of the NSWS system are shared between the two units (Figure B 3.7.7-1).
The shared portions of the system must be OPERABLE for each unit when that unit is in the MODE of Applicability.
Additionally, both normal and emergency power for shared components must also be OPERABLE.
If a shared NSWS component becomes inoperable, or normal or emergency power to shared components becomes inoperable, then the Required Actions of this LCO must be entered independently for each unit that is in the MODE of applicability of the LCO.APPLICABILITY In MODES 1, 2, 3, and 4, the NSWS is a normally operating system that is required to support the OPERABILITY of the equipment serviced by the NSWS and required to be OPERABLE in these MODES.In MODES 5 and 6, the requirements of the NSWS are determined by the systems it supports.ACTIONS A._1 If one NSWS train is inoperable, action must be taken to restore OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. In this Condition, the remaining OPERABLE NSWS train is adequate to perform the heat removal function.
However, the overall reliability is reduced because a single failure in the OPERABLE NSWS train could result in loss of NSWS function.
Required Action A. 1 is modified by two Notes. The first Note indicates that the applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources-Operating," should be entered if an inoperable NSWS train results in an inoperable emergency diesel generator.
The second Note indicates that the applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4," should be entered if an inoperable NSWS train results in an inoperable decay heat removal train.McGuire Units 1 and 2 B 3.7.7-3 Revision No. 135 NSWS B 3.7.7 BASES ACTIONS (continued)
This is an exception to LCO 3.0.6 and ensures the proper actions are taken for these components.
The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is based on the redundant capabilities afforded by the OPERABLE train, and the low probability of a DBA occurring during this time period.B.1 and B.2 If the NSWS train cannot be restored to OPERABLE status within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.SURVEILLANCE SR 3.7.7.1 REQUIREMENTS This SR is modified by a Note indicating that the isolation of the NSWS components or systems may render those components inoperable, but does not affect the OPERABILITY of the NSWS.Verifying the correct alignment for manual, power operated, and automatic valves in the NSWS flow path provides assurance that the proper flow paths exist for NSWS operation.
This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since they are verified to be in the correct position prior to being locked, sealed, or secured. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position.
This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves.The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.McGuire Units 1 and 2 B 3.7.7-4 Revision No. 135 NSWS B 3.7.7 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.7.7.2 This SR verifies proper automatic operation of the NSWS valves on an actual or simulated actuation safety injection signal. The NSWS is a normally operating system that cannot be fully actuated as part of normal testing. This Surveillance is not required for valves that are locked, sealed, or otherwise secured in the required position under administrative controls.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.SR 3.7.7.3 This SR verifies proper automatic operation of the NSWS pumps on an actual or simulated actuation signal. The NSWS is a normally operating system that cannot be fully actuated as part of normal testing during normal operation.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.REFERENCES
- 1. UFSAR, Section 9.2.2. UFSAR, Section 6.2.3. UFSAR, Section 5.4.4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
- 5. 10 CFR 50, Appendix A, GDC 5, "Sharing of Structures, Systems, and Components".
McGuire Units 1 and 2 B 3.7.7-5 Revision No. 135 NSWS B 3.7.7 BASES FIGURE B 3.7.7-1 NUCLEAR SERVICE WATER SYSTEM (, C3 w zX McGuire Units 1 and 2 B 3.7.7-6 Revision No. 135