ML15314A029

Transmittal of Manual MNS-SLC-16.7.14 - McGuire Nuclear Station

ML15314A029
Person / Time
Site:	Mcguire, McGuire
Issue date:	10/29/2015
From:	Duke Energy Corp
To:	Office of Nuclear Reactor Regulation
References
TR-NUC-MC-000817 MNS-SLC-16.7.14
Download: ML15314A029 (9)

Text

Date: 1012912015 Distribution: Duke Energy Document Transmittal #: TR-NUC-MC-000817

1. Beaver, Bonnie C

2. Carroll, Michael E DOCUMENT TRANSMI1TAL FORM

Purpose:

Issue

3. Dacus, Casey Michelle Released By:

Facility: MCGUIRE NUCLEAR STATION Duke Energy

4. Gardner, Troy R

5. Helton, Daniel E SUBJECT 13225 Haaers Ferry Road

6. Mc Ginnis, Vickie L (At Mcguire) MNS-SLC-16.7.14 Document Manacement

7. McCree, Victor M MGO2M

8. MCG DOC CNTRL MISC MAN Huntersville, NC 28078

9. MCG OPS PROCEDURE GP MNSDCRMt~duke-enernv.com

10. MCG OPS STAFF MGR

11. MCG PLANT ENG. LIBR.

12. Miller, Don

13. Montgomery, Gary L

14. OPS HUMAN PERFORMANCE -

15. OPS TRNG MGR.

16. RESIDENT NRC INSPECT

17. SERV BLDG FILE ROOM -

18. Spencer, William C

19. U S NUC REG WASHINGTON, DC

20. USNRC Page 1 of 1 LICNI -MC -MSSC1..4-12ISE YI FYIIE FYIIE FYIIE FYIIE FfIIE FYIIE FYIIE R&AII R&AI IFYIIE FYIIE FYIIE FYIIE R&AI IFRINfII E FYIIE R&AI iR&AI Remarks: New SIC to distribute to manual holders V:

TABLE OF CONTENTS SECTION TITLE PAGE 16.1 I NTRODUCTION 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 DELETED Revision 120 12/30/10 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 Revision 43 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 2Reion4 Revision 41

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 16.7.11 Hydrogen Monitors 16.7.11-1 16.7.12 Leading Edge Flow Meter (LEFM) System 16.7.12-1 16.7.13 Water Level - Spent Fuel Storage Pool 16.7.13-1 16.7.14 Source Range HF@SD Alarm 16.7.14-1 16.8 COMMITMENTS RELATED TO ELECTRICAL POWER SYSTEMS 16.8.1 Containment Penetration Overcurrent Protective Devices 16.8.1-1 16.8.2 Switchyard Activiti es 16.8.2-1 16.8.3 DG Supplemental Testing Requirements 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 McGuire Urnits 1 and 2 Revision 41 ii

TABLE OF CONTENTS SECTION TITLE PAGE 16.9.10 DELETED Revision 13 2/26/01 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 DELETED Revision 13 2/26/01 16.9.13-1 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 DELETED Revision 74 6/27/05 16.9.25 Refueling Operations - Containment Equip Hatch 16.9.25-1 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 McGuire Units 1 and 2 iReson4 iii Revision 41

TABLE OF CONTENTS SECTION TITLE PAGE 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 -Ilodine-131 and 133, Tritium and Radioactive Materials in Particulate Form 16.11.9-1 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 DELETED Revision 75 7/20/05 16.13.3 DELETED Revision 75 7/20/05 16.13.4 Minimum Station Staffing Requirements 16.13.4-1 McGuire Units 1 and 2 iv i Revision eiin4 41

TABLE OF CONTENTS SECTION TITLE PAGE 16.14 COMMITMENTS RELATED TO TESTING 16.14.1 Startup Reports 16.14.1-1 16.14.2 Reactor Trip Breaker and Solid State Protection 16.14.2-1 System (SSPS) Logic Train Out of Service Commitments McGuire Units 1 and 2VReion4 Revision 41

Source Range HF@SD Alarm 16.7.14 16.7 INSTRUMENTATION 16.7.14 Source Range High Flux at Shutdown (HF@SD) Alarm COMMITMENT At least one channel of source range shall be FUNCTIONAL with:

a. HF@SD alarm set < 2.12 times background,

b. Visual and audible alarm.

APPLICABILITY MODES 3, 4 and 5.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

---

NOTE- ----

A. No functional source Plant temperature changes are range HF@SD alarm allowed provided that SDM is maintained and Keff remains <

0.99.

A.1 Suspend operations Immediately involving positive reactivity additions.

AND A.2 Close unborated water 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> source isolation valves.

AND A.3 Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limit specified in the COLR AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND A.4 Initiate action to restore Immediately one source range HF@SD alarm.

McGuire Units 1 and 2 1..41Rvso 16.7.14-1 5 Revision 152

Source Range HF@SD Alarm 16.7.14 TESTING REQUIREMENTS TEST FREQUENCY TR 16.7.14.1 Perform CHANNEL CHECK 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> TR 16.7.14.2----------NOTE-----------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months BASES The source range neutron flux monitors are used during shutdown modes of operation to monitor the core reactivity condition. The installed source range neutron flux monitors are available from the Nuclear Instrumentation System (NIS) or from the Wide Range Neutron Flux Monitoring System (Gamma-Metrics). Source range indication is provided via the NIS source range channels and the Gamma-Metrics shutdown monitors using detectors located external to the reactor vessel. These detectors monitor neutrons leaking from the core.

Neutron flux indication for these monitors are provided in counts per second (CPS). The NIS source range channels and the Gamma-Metrics shutdown monitors provide continuous visible count rate indication in the Control Room and a high flux control room alarm to alert operators to any unexpected positive reactivity additions.

The FUNCTIONALITY of the source range (SR) high flux at shutdown (HF@SD) alarm is for detection of an inadvertent boron dilution event. The source range monitor may consist of any channel of an NIS monitor or a wide range neutron flux (WRNF) monitor. The NIS SR HF@SD alarm provides a visual alarm indication on the respective NIS SR drawer, visual and audible alarm notification from AD2-D3, "SIR HI FLUX AT SHUTDOWN", visual and audible alarm notification from the Operator Aid Computer (OAC) and audible alarm from the containment evacuation alarm inside containment. The WRNF SR HF@SD alarm provides visual alarm indication on main control board MC2 and visual and audible alarm from AD2-D3, "SIR HI FLUX AT SHUTDOWN". NIS audible alarm requires the respective source range drawer high flux at shutdown switch in NORMAL. WRNF audible alarm requires the respective SHUTDOWN MONITOR ANNUNCIATOR BYPASS switch in NORMAL.

FUNCTIONALITY requires at least one channel with its detector monitoring neutron leakage from the core with visual and audible alarm notification from the HF@SD alarm configured at

< 2.12 times background. Audible alarm notification may consist of either the plant annunciator system or OAC. Alarm setpoint shall be <*2.12 (alarm ratio of 2.0) times background. Background is the average CPS neutron level reading (the average CPS reading is the most consistent value between highest and lowest CPS neutron level reading). The source range shutdown margin monitor (SDMM) measures the source range count-rate and identifies any statistically significant increase in counts that could suggest a loss of reactor shutdown margin.

McGuire Units 1 and 2 1..42Rvso 16.7.14-2 5 Revision 152

Source Range HF@SD Alarm 16.7.14 Selection of HF@SD alarm setpoint of 2.12 is based upon industry operating experience that determined source range (SR) Nuclear Instrumentation response lagged the reactivity change experienced by the core which occurred at substantially subcritical, rodded conditions. This is due to low-leakage core loading patterns with high-burnup fuel on the core periphery (and without secondary sources) that affect SR response in a manner that departs from traditional subcritical multiplication theory. The maximum setpoint calculated by the SDMM is 2.12 with an alarm ratio multiplier selection of 2.0. Analysis has shown that*

a HF@SD alarm setpoint of 2.12 is sufficient to compensate for the lagged detector response under these conditions and provide ample time for Operators to terminate a dilution event once the HF@SD alarm activates.

Condition A applies when the required number of FUNCTIONAL source range HF@SD alarms are not met in MODES 3, 4, or 5. With the unit in this condition, the source range HF@SD alarm performs a monitoring function. With less than the required number of source range HF@SD alarms FUNCTIONAL, operations involving positive reactivity additions shall be suspended immediately. In addition to suspension of positive reactivity additions, all valves that could add unborated water to the reactor coolant system (RCS) must be closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The isolation of unborated water sources will preclude a boron dilution accident.

Also, the shutdown margin (SDM) must be verified within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter as per TS SR 3.1.1.1, SDM verification. With no source range HF@SD alarm FUNCTIONAL, core monitoring is severely reduced. Verifying the SDM within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> allows sufficient time to perform the calculations and determine that the SDM requirements are met. The SDM must also be verified once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter to ensure that the core reactivity has not changed. Required Action A.1 precludes any positive reactivity additions; therefore, core reactivity should not be increasing, and a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is adequate.

The Completion Times of within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> are based on operating experience in performing the Required Actions and the knowledge that unit conditions will change slowly. Required Action A.1 is modified by a note which permits plant temperature changes provided the temperature change is accounted for in the calculated SDM and that Keff remains < 0.99. Introduction of temperature changes, including temperature increases when a positive moderator temperature coefficient (MTC) exists, must be evaluated to ensure they do not result in a loss of required SDM or adequate margin to criticality.

REFERENCES

1. SER Supplement 1 Section 15.2.1

2. UFSAR Sections 7.7.1.3.1 and 15.4.6

3. Commitment Change 2010-M-002, PIP M-10-00463

4. Commitment Change 2014-M-001, PIP M-13-09052

5. Commitment Change 2015-M-002

6. NRC Generic Letter 85-05, "Inadvertent Boron Dilution Events" dated January 31, 1985

7. MCC-1 552.08-00-0136 Rev. 08, "Generic FSAR Boron Dilution Accident Analysis" McGuire Units 1 and 2 1..43Rvso 16.7.14-3 Revision 152 5