ML031770135
| ML031770135 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 06/17/2003 |
| From: | Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| DUK031680028 | |
| Download: ML031770135 (17) | |
Text
DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO Normal THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS Date: 06/17/03 PRIORITY OTHERWISE IDENTIFIED BELOW Document Transmittal #: DUK031 680028 1)06593 D E HOLDEN MG03A2
- 2) 09460WC SPENCER MGO1RP Duke Power Company QACONDITION ] Yes
- No
- 3) 09665 ROBERT M.MARTIN, USNRC OTHER ACKNOWLEDGEMENT REQUIRED
- Yes DOCUMENT TRANSMITTAL FORM IF OA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:
REFERENCE MCGUIRE NUCLEAR STATION Duke Power Company SLECTED LICENSEE COMMITMENT P.O. Box 12700 Document Management MGO1 S2 MANUAL (SLC)
Hagers Ferry Road Huntersville, N.C. 28078 Rec'd By Page 3 of 3 Date
- l. , , , , , , , , , , , , , , l l __
DOCUMENT NO QACOND REV #/ DATE DISTR CODE I 2 3 4 5 6 7 8 9 10 11 12 13 14 15 TOTAL I I I I I I SELECTED LICENSEE COMMITMENT MANUAL NA 035 06/11/03 MADM-03A Vi Vi V1 53 MEMORANDUM NA 030 06/12/03 SLC - TABLE OF CONTENTS NA 030 06/12/03 SLC - LIST OF EFFECTIVE PAGES NA 035 06/11/03 SLC 16.9.7 NA 042 06/11/03 SLC 16.6.2 NA DEL 06/11/03 I__ _ _ __ _ _ _ _ _, , ,__ , ,_,_,_, ,_,_,_, ,__
REMARKS: PLEASE UPDATE YOUR MANUAL ACCORDINGLY D M JAMIL VICE PRESIDENT MCGUIRE NUCLEAR STATION
.1
~-(e BY:
BC BEAVER MG01RC BCB/CMK
June 12, 2003 MEMORANDUM To: All McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual Holders
Subject:
McGuire SLC Manual Update Please revise your copy of the manual as follows:
REMOVE INSERT Table of Contents Table of Contents (Rev 30)
List of Effective Sections List of Effective Sections (Rev 35)
SLC 16.6.2 (This SLC has been deleted)
SLC 16.9.7 SLC 16.9.7 (Rev 42)
Revisions may skip numbers due to Regulatory Compliance Filing System.
Please call me if you have questions.
Bonnie Beaver Regulatory Compliance
TABLE OF CONTENTS SECTION TITLE PAGE
16.1 INTRODUCTION
16.1-1 16.2 APPLICABILITY 16.2-1 16.3 DEFINITIONS 16.3-1 16.4 COMMITMENTS RELATED TO REACTOR COMPONENTS 16.5 COMMITMENTS RELATED TO REACTOR COOLANT SYSTEM 16.5.1 Inventory Control - Reduced Inventory Operation 16.5.1-1 16.5.2 Power Systems and Decay Heat Removal - Reduced Inventory Operation 16.5.2-1 16.5.3 Reactivity Control - Reduced Inventory Operation 16.5.3-1 16.5.4 NCS Instrumentation - Reduced Inventory Operation 16.5.4-1 16.5.5 Containment Closure - Reduced Inventory Operation 16.5.5-1 16.5.6 Safety Valves - Shutdown 16.5.6-1 16.5.7 Chemistry 16.5.7-1 16.5.8 Pressurizer 16.5.8-1 16.5.9 Structural Integrity 16.5.9-1 16.5.10 Reactor Vessel Head Vent System 16.5.10-1 16.6 COMMITMENTS RELATED TO ENGINEERED SAFETY FEATURES 16.6.1 Containment Sump 16.6.1-1 16.6.2 DELETED 6/11/03 16.6.3 Inlet Door Position Monitoring System 16.6.3-1 16.6.4 Safety Injection System Nozzles 16.6.4-1 16.7 COMMITMENTS RELATED TO INSTRUMENTATION 16.7.1 ATWS/AMSAC 16.7.1-1 16.7.2 Seismic Instrumentation 16.7.2-1 16.7.3 Meteorological Instrumentation 16.7.3-1 McGuire Units 1 and 2 i Revision 30
TABLE OF CONTENTS SECTION TITLE PAGE 16.7.4 Loose-Part Detection Instrumentation 16.7.4-1 16.7.5 Turbine Overspeed Protection 16.7.5-1 16.7.6 Radiation Monitoring for Plant Operations 16.7.6-1 16.7.7 Movable Incore Detectors 16.7.7-1 16.7.8 Explosive Gas Monitoring Instrumentation 16.7.8-1 16.7.9 Rod Position Indication System - Shutdown 16.7.9-1 16.7.10 Rod Position Indication System -Test Exception 16.7.10-1 16.8 COMMITMENTS RELATED TO ELECTRICAL POWER SYSTEMS 16.8.1 Containment Penetration Overcurrent Protective Devices 16.8.1-1 16.8.2 Switchyard Activities 16.8.2-1 16.8.3 DG Supplemental Testing Requirements 16.8.3-1 16.9 COMMITMENTS RELATED TO AUXILIARY SYSTEMS 16.9.1 Fire Suppression Water System 16.9.1-1 16.9.2 Spray and/or Sprinkler Systems 16.9.2-1 16.9.3 Halon Systems 16.9.3-1 16.9.4 Fire Hose Stations 16.9.4-1 16.9.5 Fire Rated Assemblies 16.9.5-1 16.9.6 Fire Detection Instrumentation 16.9.6-1 16.9.7 Standby Shutdown System 16.9.7-1 16.9.8 Groundwater Level Monitoring System 16.9.8-1 16.9.9 Boration Systems - Flow Path (Operating) 16.9.9-1 16.9.10 Boration Systems - Charging Pumps (Operating) 16.9.10-1 16.9.11 Borated Water Sources (Operating) 16.9.11-1 16.9.12 Boration Systems - Flow Path (Shutdown) 16.9.12-1 16.9.13 Boration Systems - Charging Pumps (Shutdown) 16.9.13-1 McGuire Units 1 and 2 ii Revision 330
TABLE OF CONTENTS SECTION TITLE PAGE 16.9.14 Borated Water Sources (Shutdown) 16.9.14-1 16.9.15 Snubbers 16.9.15-1 16.9.16 Area Temperature Monitoring 16.9.16-1 16.9.17 Refueling Operations - Decay Time 16.9.17-1 16.9.18 Refueling Operations - Communications 16.9.18-1 16.9.19 Refueling Operations - Manipulator Crane 16.9.19-1 16.9.20 Crane Travel - Spent Fuel Pool Storage Building 16.9.20-1 16.9.21 Water Level - Spent Fuel Storage Pool 16.9.21-1 16.9.22 Switchgear Room Ventilation System (SGRVS) 16.9.22-1 16.9.23 Control Room Area Ventilation System (CRAVS) 16.9.23-1 16.9.24 Spent Fuel Pool Storage Rack Poison Material 16.9.24-1 16.10 COMMITMENTS RELATED TO STEAM AND POWER CONVERSION SYSTEMS 16.10.1 Steam Generator Pressure/Temperature Limitation 16.10.1-1 16.11 COMMITMENTS RELATED TO RADIOACTIVE WASTE MANAGEMENT AND RADIOLOGICAL EFFLUENT CONTROL 16.11.1 Liquid Effluents - Concentration 16.11.1-1 16.11.2 Radioactive Liquid Effluent Monitoring Instrumentation 16.11.2-1 16.11.3 Dose - Liquid Effluents 16.11.3-1 16.11.4 Liquid Radwaste Treatment System 16.11.4-1 16.11.5 Chemical Treatment Ponds 16.11.5-1 16.11.6 Dose Rate - Gaseous Effluents 16.11.6-1 16.11.7 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11.7-1 16.11.8 Noble Gases 16.11.8-1 16.11.9 Dose - lodine-1 31 and 133, Tritium and Radioactive Materials in Particulate Form 16.11.9-1 McGuire Units 1 and 2 iii Revision 30
TABLE OF CONTENTS SECTION TITLE PAGE 16.11.10 Gaseous Radwaste Treatment System 16.11.10-1 16.11.11 Solid Radioactive Waste 16.11.11-1 16.11.12 Total Dose 16.11.12-1 16.11.13 Radiological Environmental Monitoring Program 16.11.13-1 16.11.14 Land Use Census 16.11.14-1 16.11.15 Interlaboratory Comparison Program 16.11.15-1 16.11.16 Annual Radiological Environmental Operating Report 16.11.16-1 16.11.17 Radioactive Effluent Release Reports 16.11.17-1 16.11.18 Liquid Holdup Tanks 16.11.18-1 16.11.19 Explosive Gas Mixture 16.11.19-1 16.11.20 Gas Storage Tanks 16.11.20-1 16.12 COMMITMENTS RELATED TO RADIATION PROTECTION 16.12.1 In-Plant Iodine Monitoring 16.12.1-1 16.12.2 Sealed Source Contamination 16.12.2-1 16.13 COMMITMENTS RELATED TO CONDUCT OF OPERATIONS 16.13.1 Fire Brigade 16.13.1 -1 16.13.2 Technical Review and Control 16.13.2-1 16.13.3 Plant Operations Review Committee 16.13.3-1 16.13.4 Minimum Station Staffing Requirements 16.13.4-1 16.14 COMMITMENTS RELATED TO TESTING 16.14.1 Startup Reports 16.14.1 -1 McGuire Units 1 and 2 iv Revision 30
SLC LIST OF EFFECTIVE SECTIONS 1 REVISION NUMBER 1 DATE SECTION l l 16.1 REVISION 32 12/2/02 16.2 REVISION 36 3/17/03 16.3 REVISION 0 12/14/99 16.4 Not Issued 16.5.1 REVISION 0 12/14/99 16.5.2 REVISION 0 12/14/99 16.5.3 REVISION 0 12/14/99 16.5.4 REVISION 7 09/14/00 16.5.5 REVISION 0 12/14199 16.5.6 REVISION 0 12/14/99 16.5.7 REVISION 0 12/14/99 16.5.8 REVISION 0 12/14/99 16.5.9 REVISION 0 12/14/99 16.5.10 REVISION 38 4/9/03 16.6.1 REVISION 0 12/14/99 16.6.2 DELETED 6/11/03 16.6.3 REVISION 17 04/08/02 16.6.4 REVISION 27 06/12/02 16.7.1 REVISION 0 12/14/99 16.7.2 REVISION 24 4/29/02 16.7.3 REVISION 0 12/14/99 16.7.4 REVISION 1 4/11100 16.7.5 REVISION 0 12114199 16.7.6 REVISION 0 12/14/99 16.7.7 REVISION 0 12/14/99 16.7.8 REVISION 39 4/9/03 16.7.9 REVISION 0 12/14/99 16.7.10 REVISION 0 12/14/99 16.8.1 REVISION 2 4111100 16.8.2 REVISION 0 12/14/99 16.8.3 REVISION 26 6/3/02 16.9.1 REVISION 18 12/4/01 16.9.2 REVISION 5 5/24/00 16.9.3 REVISION 31 12/2/02 16.9.4 REVISION 1 03/02/00 16.9.5 REVISION 35 2/26/03 16.9.6 REVISION 0 12/14/99 16.9.7 REVISION 42 6/11/03 16.9.8 REVISION 40 5/1/03 16.9.9 REVISION 34 2/26/03
.16.9.10 REVISION 13 2/26/01 16.9.11 REVISION 22 2/25/02 16.9.12 REVISION 34 2/26/03 16.9.13 REVISION 13 2/26/01 16.9.14 REVISION 22 2/25/02 16.9.15 REVISION 25 5/14/02 McGuire Units 1 and 2 I Revision 35
SLC LIST OF EFFECTIVE SECTIONS SE O REVISION NUMBER DATE SECTiON I _ _ _ __ _ _
16.9.16 REVISION 38 4/9/03 16.9.17 REVISION 0 12/14/99 16.9.18 REVISION 0 12/14/99 16.9.19 REVISION 0 12/14/99 16.9.20 REVISION 8 11/30/00 16.9.21 REVISION 0 12/14/99 16.9.22 REVISION 29 7/10/02 16.9.23 REVISION 29 7/10/02 16.9.24 REVISION 37 4/4/03 16.10.1 REVISION 0 12/14/99 16.11.1 REVISION 9 2/1/01 16.11.2 REVISION 23 4/4/02 16.11.3 REVISION 0 12/14/99 16.11.4 REVISION 0 12/14/99 16.11.5 REVISION 0 12/14/99 16.11.6 REVISION 0 12/14/99 16.11.7 REVISION 12 3/14/01 16.11.8 REVISION 0 12/14/99 16.11.9 REVISION 0 12/14/99 16.11.10 REVISION 0 12/14/99 16.11.11 REVISION 0 12/14/99 16.11.12 REVISION 0 12/14/99 16.11.13 REVISION 0 12/14/99 16.11.14 REVISION 21 1/17/02 16.11.15 REVISION 21 1/17/02 16.11.16 REVISION 1 4/11/00 16.11.17 REVISION 1 4/11/00 16.11.18 REVISION 0 12/14/99 16.11.19 REVISION 0 12/14/99 16.11.20 REVISION 0 12/14/99 16.12.1 REVISION 0 12/14/99 16.12.2 REVISION 0 12/14/99 16.13.1 REVISION 0 12/14/99 16.13.2 REVISION 24 4/29/02 16.13.3 REVISION 24 4/29/02 16.13.4 REVISION 30 8/29/02 16.14.1 REVISION 0 12/14/99 McGuire Units 1 and 2 2 Revision 35
Standby Shutdown System 16.9.7 16.9 AUXILIARY SYSTEMS - FIRE PROTECTION SYSTEMS 16.9.7 Standby Shutdown System COMMITMENT The Standby Shutdown System (SSS) shall be operable.
APPLICABILITY MODES 1, 2, and 3.
REMEDIAL ACTIONS
.' ^rvr
- - -- - - - - - - --- --- -Nr - -- - -----------------------
- 1. The SRO should ensure that security is notified 10 minutes prior to declaring the SSS inoperable. Immediately upon discovery of the SSS inoperability, Security must be notified to implement compensatory measures within 10 minutes of the discovery.
- 2. If inoperable SSS component is located inside containment, repairs shall be made at the first outage which permits containment access.
CONDITION REQUIRED ACTION COMPLETION TIME
NOTE--------------- A.1 Verify the OPERABILITY of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Not applicable to the SSS fire detection and Diesel Generator or 24 V suppression systems in the Battery Bank and Charger. associated areas identified
- ----------- in Tablel 6.9.7-1.
A. One or more required AND SSS components identified in Table A.2 Restore the component to 7 days 16.9.7-1 inoperable. OPERABLE status.
B. SSS Diesel Generator or B.1 Verify the OPERABILITY of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 24 V Battery Bank and fire detection and Charger inoperable. suppression systems in the associated areas identified in Tablel 6.9.7-1.
AND (continued)
McGuire Units 1 and 2 16.9.7-1 Revision 42
Standby Shutdown System 16.9.7 REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. (continued). B.2 Verify offsite power and 1hour one emergency diesel generator OPERABLE.
AND B.3 Restore the component to 60 days OPERABLE status.
C. Total Unidentified C.1 Declare the standby Immediately LEAKAGE, Identified makeup pump and SSS LEAKAGE, and reactor inoperable.
coolant pump seal leakoff > 20 gpm.
D. Required Action and D.1 Prepare and submit a 30 days associated Completion Special Report to the NRC Time of Condition A or C outlining the cause of the not met. inoperability, corrective actions taken, and plans for restoring the SSS to OPERABLE status.
E. Required Action and E.1 Prepare and submit a 14 days associated Completion Special Report to the NRC Time of Condition B not outlining the extent of met. repairs required, schedule for completing repairs, and basis for continued operation.
McGuire Units 1 and 2 16.9.7-2 Revision 42
Standby Shutdown System 16.9.7 TESTING REQUIREMENTS TEST FREQUENCY TR 16.9.7.1 Verify total Identified LEAKAGE, Unidentified LEAKAGE, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and reactor coolant pump seal leakoff are < 20 gpm.
TR 16.9.7.2 Verify the requirements for spent fuel water level in 7 days Surveillance Requirement 3.7.13.1 are met and the boron concentration in the spent fuel storage pool is within the limits specified in the COLR.
OR Verify the refueling water storage tank is capable of being aligned to the SSS standby makeup pump.
TR 16.9.7.3 Verify fuel oil level in the SSS diesel generator fuel 31 days storage tank is > 4.0 ft.
TR 16.9.7.4 Verify the SSS diesel generator starts from ambient 31 days conditions and operates for > 30 minutes at > 700 kW.
TR 16.9.7.5 Verify fuel oil properties of new fuel oil for the SSS diesel In accordance with generator are tested in accordance with the Diesel Fuel the Diesel Fuel Oil Oil Testing Program. Testing Program TR 16.9.7.6 Verify the SSS diesel generator 24 V battery voltage is > 31 days 24 volts.
TR 16.9.7.7 Perform a CHANNEL CHECK of the SSS Instrumentation 31 days as required by Table 16.9.7-2.
TR 16.9.7.8 Verify the electrolyte level of each SSS 250/125 V battery 31 days bank is above the plates.
(continued)
McGuire Units 1 and 2 16.9.7-3 Revision 42
Standby Shutdown System 16.9.7 TESTING REQUIREMENTS (continued)
TEST FREQUENCY TR 16.9.7.9 Verify the total battery terminal voltage of each SSS 31 days 250/125 V battery bank is > 258/129 V on float charge.
TR 16.9.7.10 Verify the average specific gravity of each SSS 250/125 92 days V battery bank is > 1.200.
TR 16.9.7.11 Verify the standby makeup pump's developed head and 92 days capacity is greater than or equal to that required by the Inservice Testing Program.
TR 16.9.7.12 Verify the SSS diesel generator 24 V batteries and 18 months battery racks show no visual indication of physical damage or abnormal deterioration.
TR 16.9.7.13 Verify SSS diesel generator 24 V battery to battery and 18 months terminal connections are clean, tight, and free of corrosion.
TR 16.9.7.14 Perform a CHANNEL CALIBRATION of the SSS 18 months Instrumentation as required by Table 16.9.7-2.
TR 16.9.7.15 Perform inspection of SSS diesel generator in 18 months accordance with procedures prepared in conjunction with manufacturer's recommendations for class of service.
TR 16.9.7.16 Verify the SSS 250/125 V batteries, cell plates, and 18 months battery racks show no visual indication of physical damage or abnormal deterioration.
TR 16.9.7.17 Verify the SSS 250/125 V battery to battery and terminal 18 months connections are clean, tight, free of corrosion, and coated with anti-corrosion material.
TR 16.9.7.18 Verify the "C" solenoid to valve SA48ABC can be 18 months deenergized to provide steam supply to the turbine driven auxiliary feedwater pump.
McGuire Units 1 and 2 16.9.7-4 Revision 42
C ( (
Standby Shutdown System 16.9.7 TABLE 16.9.7-1 STANDBY SHUTDOWN SYSTEM FIRE DETECTION & SUPPRESSION SYSTEMS VERIFICATION( 1 )
INOPERABLE SSS FIRE DETECTION & SUPPRESSION SYSTEMS LOCATION COMPONENT EL 716 EL 733 EL 750 Control Battery Cable Turbine Driven Motor Driven Containment EE-KK EE-KK EE-KK Room Room Rooms AFW Pump AFW Pump SSS Diesel Generator 3 ) X X X X X X X X Note 2 SSS DG Starting 24 V Battery X X X X X X X X Note 2 Bank and Charger(3)
Standby Makeup Pump and X X X Water Supply SSS 250/1 25V Battery and X X X Note 2 Charger(3)
Turbine Driven AFW Pump _ X I Turbine Driven AFW Pump X Solenoid "C" . -
Groundwater Drainage Sump X Pump A, Sump A AND Groundwater Drainage Sump Pump A, Sump B INSTRUMENTATION:
- 1. RCS Pressure X X X Note 2
- 2. Pressurizer Level X X X Note 2
- 3. SG Level X X X Note 2
- 4. Incore Temperature X X X Note 2
- 5. NC Wide Range Cold Leg X X X Note 2 Temperature NOTES:
- 1. If fire detection and/or suppression systems are inoperable, then the ACTION statement(s) of the applicable fire detection and/or suppression SLC shall be complied with.
- 2. Monitor containment air temperature at least once per hour at the locations specified in Technical Specification Surveillance Requirement 3.6.5.1 or 3.6.5.2, in lieu of verification of operability of systems inside containment
- 3. With this component inoperable, then denoted areas of both units are affected.
McGuire Units 1 and 2 16.9.7-5 Revision 42
Standby Shutdown System 16.9.7 TABLE 16.9.7-2 STANDBY SHUTDOWN SYSTEM INSTRUMENTATION TESTING REQUIREMENTS REQUIRED TESTING READOUT INSTRI JMENT CHANNELS REQUIREMENTS .
LOCATION
- 1. Reactor Coolant Pressure 1 TR 16.9.7.7 SSF Control TR 16.9.7.14 Panel
- 5. Standby MakeuF Pump Flow 1 TR 16.9.7.14 SSF Control Panel
- 6. NC Wide Range Cold Leg 1 per 2 Cold TR 16.9.7.7 SSF Control Temperature Legs TR 16.9.7.14 Panel McGuire Units 1 and 2 16.9.7-6 Revision 42
Standby Shutdown System 16.9.7 BASES The Standby Shutdown System (SSS) is designed to mitigate the consequences of certain postulated fire incidents, sabotage, or station blackout events by providing capability to maintain HOT STANDBY conditions and by controlling and monitoring vital systems from locations external to the main control room. This capability is consistent with the requirements of 10 CFR Part 50, Appendix R and 10 CFR 50.63.
By design, the SSS is intended to respond to those low-probability events which render both l the control room and automatic safety systems inoperable. Because of the low probability of occurrence of these events, the remedial actions rely on compensatory action, timely repair or return to operability and, if necessary, a justification for continued operation.
Because the SSS performs a redundant fire protection function, compensatory action during periods when the SSS is inoperable relies largely on assurance of the operability of fire detection and suppression systems. Table 16.9.7-1 establishes requirements for operability of fire detection and suppression systems.
Both A&D NC Cold Leg Wide Range Temperatures are required for SSS operability. This conclusion is based on NRC Correspondence during issuance of the original operating license.
The Source Range Wide Range Neutron Flux Instrumentation was installed at the SSS Control Panel as part of NRC review of this system in the early 1980s. The indication is not required for SSS operability, based on the NRCs response to Duke dated July 12, 1983.
Controls and power to the pressurizer heater banks are included for SSF events; however, they are not required for SSS operability. NRC Generic Letter 86-10 provides that conclusion.
The Testing Requirements ensure that the SSS systems and components are capable of performing their intended functions. The testing requirements were based largely on SSS Technical Specifications for the Catawba Nuclear Station, which was approved prior to the issuance of the fuel load license for Unit 1 of that plant. Also considered in the formulation of the testing requirements were existing McGuire Technical Specifications, such as those for the 1E Diesel Generators, Refueling Water Storage Tank, Fire Protection & Detection Systems, and other Tech Specs which are related to the safe operation and/or shutdown of the plant.
The required level in the SSS diesel generator fuel storage tank ensures sufficient fuel for 3 1,h days of uninterrupted operation. Per Appendix R requirements, the unit must be in cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of going to the SSF. The 3 H day supply of fuel oil assures this capability.
McGuire Units 1 and 2 16.9.7-7 Revision 42
Standby Shutdown System 16.9.7 BASES (continued)
New fuel oil is sampled in accordance with ASTM D4057-81 prior to addition to the storage tanks. In accordance with the tests specified in ASTM D975-81, the sample is verified to have:
- 1. an API Gravity of within 0.3 degrees at 60°F or a specific gravity of within 0.0016 at 60/600F, when compared to the supplier's certificate, or an absolute specific gravity at 60/60°F of greater than or equal to 0.83 but less than or equal to 0.89, or an API gravity at 60°F of greater than or equal to 27 degrees but less than or equal to 39 degrees,
- 2. a kinematic viscosity at 40 0C of greater than or equal to 1.9 centistokes but less than or equal to 4.1 centistokes (or a Saybolt Universal Viscosity at 100°F of greater than or equal to 32.6 SUS but less than or equal to 40.1 SUS),
- 3. a flash point equal to or greater than 125 0F, and
- 4. a clear and bright appearance with proper color when tested in accordance with ASTM D4176-82.
Within 31 days of obtaining the new fuel sample, the other properties specified in Table 1 of ASTM D975-81 are verified to be met when tested in accordance with ASTM D975-81, except that the analysis for sulfur may be performed in accordance with ASTM Dl 552-90 or ASTM D2622-82.
Although the Standby Makeup Pump is not nuclear safety-related and was not designed according to ASME code requirements, it is tested quarterly to ensure-its OPERABILITY.
The Standby Makeup Pump (SMP) functions as part of the SSF to provide makeup capacity to the reactor coolant system and cooling flow to the reactor coolant pump seals. The reactor coolant pump seal leak-off flow is temperature dependent (i.e., the higher the temperature the higher the leak-off flow). During normal operation the NCP seals are supplied from the Centrifugal Charging Pump (CCP) drawing from the Volume Control Tank (VCT). During the SSF event, the SMP draws from the Spent Fuel Pool (SFP). During the SSF event there is no SFP cooling, so water injected into the NCP seals will have a higher temperature than during normal operation. The SMP is capable of providing a makeup capacity of at 26 gpm. The revised SLC limit of 20 gpm total accumulative leakage is based on a calculation that was performed by Westinghouse, indicating increased seal leak-off at higher seal water temperatures, to relate the SSF event leakage of 26 gpm at elevated NCP seal temperatures. This more conservative limit will ensure that the SMP will be capable of providing makeup and seal cooling flow equal to or greater than total leakage during the SSF event, increased seal leak-off flow due to heat-up of the SFP, and still provide a margin of safety. As a conservative measure, during normal power operation the total accumulative system leakage (unidentified + identified + seal leak-off flows) shall be limited to 20 gpm.
The Testing Requirement concerning the Standby Makeup Pump water supply ensures that an adequate water volume is available to supply the pump continuously for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The Groundwater Drainage Sump Pump A, in the A (Unit 1) and B (Unit 2) sumps, can be controlled and powered from the SSF. These Sump Pumps remove accumulation of groundwater, Turbine driven AFW Pump drains, and other miscellaneous sources. For the SSS to be OPERABLE, a minimum of one of these pumps must be OPERABLE. Credit is taken for the groundwater underdrain system to transport water from one sump to the other.
McGuire Units 1 and 2 16.9.7-8 Revision 42
Standby Shutdown System 16.9.7 The turbine driven AFW pump can be controlled from the SSF and is utilized during an SSS event to maintain adequate secondary side heat removal. For the SSS to be OPERABLE, the turbine driven AFW pump must be OPERABLE.
While the SSS 24 VDC battery charger is isolated for batery surveillance testing, the SSS Diesel Generator remains operable as long as the battery voltage is > 24 volts.
BASES (continued)
The SSS 125V batteries and battery chargers consist of three pairs SDSP1, SDSP2 and SDSS. Each pair consists of a battery and associated battery charger. Pair SDSS can be used to substitute for either pair SDSP1 or SDSP2. Only two of these pairs are required operable since pair SDSS is spare.
This selected licensee commitment is part of the McGuire Fire Protection Program and therefore subject to the provisions of McGuire Facility Operating License Conditions C.4 (Unit 1) and C.7 (Unit 2).
REFERENCES
- 1. McGuire Nuclear Station UFSAR, Chapter 9.5.1
- 2. McGuire Nuclear Station SER Supplement 2, Chapter 9.5.1 and Appendix D
- 3. McGuire Nuclear Station SER Supplement 5, Chapter 9.5.1 and Appendix B
- 4. McGuire Nuclear Station SER Supplement 6, Chapter 9.5.1 and Appendix C
- 5. McGuire Fire Protection Review, as revised
- 6. McGuire Fire Protection Safe Shutdown Review
- 7. IEEE 308-1974, Class 1E Power Systems
- 8. IEEE 450-1975, Maintenance Testing & Replacement of Large Lead Storage Bateries
- 9. OP/O/B/6350104, Standby Shutdown Facility Diesel Operation
- 10. McGuire Nuclear Station Facility Operating Licenses, Unit 1 License Condition C.(4) and Unit 2 License Condition C.(7)
- 11. PIP 0-M-99-03926
- 12. PIP-M-01-3466
- 13. 10 CFR 50.63, Loss of All Alternating Current
- 14. Letter from H.B. Tucker to NRC, dated April 4, 1990, Requirements for Station Blackout.
McGuire Units 1 and 2 16.9.7-9 Revision 42