Text

Amends 88 & 69 to Licenses NPF-9 & NPF-17,respectively, Revising Tech Specs by Updating Index & Making Other Purely Administrative Changes
	ML20150D008
Person / Time
Site:	McGuire, Mcguire
Issue date:	07/05/1988
From:	Matthews D; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20150D011	List: ML20150D008; ML20150D013; ML20150D021;
References
	NUDOCS 8807130255
	Download: ML20150D008 (25)
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UNITED STATES

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DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. NPF-9 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated February 17, 1987, as revised June 3, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act).

l and the Comission's rules and regulations as set forth in 10 CFR I

Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon defensa and security or to the health and safety of the public; and E. ' The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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Accordirigly, the license is hereby amended by page changes to-the Technical Specifications as indicated in the attachments to this license amandment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby ainended. to read as follows:

(2) Technical Specifi, cations

'The Technical Specifications contained in Appendix A, as revised through Amendment flo.

88, are hereby incorporated into the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

Inis license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY C011HISSION Original signed by:

David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II

Attachment:

Technical Specification Changes Date of Issuance:

July 5, 1988 P

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DUKE POWER COMPANY 00CXET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. NPF-17 1.

The Nuclear Regulatory Connission (the Comission) has found that:

A.

The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated February 17, 1987, as revised June 3, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; ar.d E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Cumission's regulations and all applicable requirements have been satisfied.

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Accordingly, ~ the license is :hereby amended by page changes. to' the Technical Specifications as indicated in.the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:

'(2) Technical Specifications The Technical Specifications contained in Appendix A,.6s revised through Amendment No.

69, are hereby incorporated into the license.

-The licensee.shall operate the facility in.accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Original signed by:

David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II

Attachment:

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Technical Spec fication Changes Date of Issuance: July 5, 1988 OFFICIAL RECORD COPY

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.~G ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. NPF-9 DOCKET N0.~50-369 AND TO LICENSE AMENDMENT N0.

FACILITY OPERATING LICENSE N0. NPF-17 DOCKET NO. 50-370

-Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding over-leaf pages are also provided to maintain document completeness.

Amended Page Overleaf Page III V

VI XI XII XIV XIII XVI XVIII XIX XX 3/4 1-21 3/4 3-14 3/4 3-21 3/4 3-22 3/4 3-38 3/4 3-56 3/4 3-57 3/4 6-24 3/4~6-25 y

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INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR-C0RE.................................................

2-1 2.1.2 REACTOR C0O LANT - SYSTEM PRESSURE..............................

2-1 FIGURE 2.1-1 UNITS.1 and 2 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN 0PERATION...........................................

2-2a FIGURE 2.1-2

( B LA N K )...............................................

2-3 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS...............

2-4 TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS.....

2-5 BASES SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR C0RE.................................................

B 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE..............................

B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETP0lNTS................

B 2-3 McGUIRE - UNITS 1 and 2 III Amendment No. 88 (Unit 1)

Amendment No. 69 (Unit 2)

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE Control Rod Insertion Limi ts..............................

3/4 1-21 FIGURE 3.1-1 R0D BANK INSERTION LIMITS VERSUS RELATIVE POWER.......

3.4 1-22 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE..............

3/4 2-1 FIGURE 3.2-1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL P0WER...................................

3/4 2-3 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F (Z)......................

3/4 2-6 9

K(Z) - NORMALIZED F FIGURE 3.2-2 HEIGHT............ 9.(.Z) AS A FUNCTION OF CORE 3/4 2-12 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R.................................

3/4 2-14 FIGURE 3.2-3 RCS FLOW RATE VERSUS R - FOUR LOOPS IN OPERATION....

3/4 2-17 1

3/4.2.4 QUADRANT POWER TILT RATI0.........................

3/4 2-19 3/4.2.5 DNB PAR /. METERS............................................

3/4 2-22 TABLE 3.2-1 DNB PARAMETERS.......................................

3/4 2-23 3/4.3 INSTRlWENTATION 3/4.3.1 PEACTOR TRIP SYSTEM INSTRUMENTATION.......................

3/4 3-1 McGUIRE - UNITS 1 and 2 V

Amendment No. 88 (Unit 1)

Amendment No. 69 (Unit 2)

7 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION..................

3/4 3-2 TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES...

3/4 3-9 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......................................

3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.........................................

3/4 3-15 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION....................................

3/4 3-16 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM l

INSTRUMENTATION TRIP SETP0INTS.....................

3/4 3-25 TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES............

3/4 3-30 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........

3/4 3-34 3/4.3.3 ROSITORING INSTRUMENTATION RADIATION MONITORING FOR P LANT 0 P E RAT I O N S........................................

3/4 3-40 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT 0PERATIONS.........................................

3/4 3-41 TABLE 4.3.3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS...............

3/4 3-43 Movable Incore Detectors..................................

3/4 3-45 Seismic Instrumentation...................................

3/4 3-46 TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION...................

3/4 3-47 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......................................

3/4 3-48 Meteorological Instrumentation............................

3/4 3-49 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION............

3/4 3-50 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................

3/4 3-51 Remote Shutdown Instrumentation...........................

3/4 3-52 TABLE 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION...........

3/4 3-53 McGUIRE - UNITS 1 and 2 VI Amendment No. 88 (Unit 1)

Amendment No. 69 (Unit 2)

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE Ice Bed Temperature Monitoring System.....................

3/4 6-36 Ice Condenser 0oors.......................................

3/4 6-37 Inlet Door Position Monitoring System.....................

3/4 6-39 Divider Barrier Personnel Access Doors and Equipment Hatches.......................................

3/4 6-40 Containment Air Return and Hydrogen Skimmer System........

3/4 6-41 Floor Drains..............................................

3/4 6-42 Refueling Canal 0 rains....................................

3/4 6-43 Divider Barrier Sea 1......................................

3/4 6-44 TABLE 3.6-3 DIVIDER BARRIER SEAL ACCEPTABLE PHYSICAL PROPERTIES....

3/4 6-45 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Va1ves............................................

3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH IN0PERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERAT10N........................

3/4 7-2 TABLE 3.7-2 (BLANK).............................................

3/4 7-2 TABLE 3.7-3 STEAM LINE SAFETY VALVES PER L00P...................

3/4 7-3 Auxiliary Feedwater System...............................

3/4 7-4 Specific Activity........................................

3/4 7-6 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM..............................

3/4 7-7 Main Steam Line Isolation Va1ves.........................

3/4 7-8 3/4.7.2 STEAM GENERATOR PRESSURS/ TEMPERATURE LIMITATION..........

3/4 7-9 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................

3/4 7-10 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM.............................

3/4 7-11 FIGURE 3/4 7-1 NUCLEAR SERVICE WATER SYSTEM..................

3/4 7-11a McGUIRE - UNITS 1 and 2 XI Amendment No. 88(Unit 1)

Amendment No. 69(Unit 2)

3 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.5 STANDBY NUCLEAR SERVICE WATER P0ND.......................

3/4 7-12 3/4.7.6 CONTROL AREA VENTILATION SYSTEM..........................

3/4 7-13 3/4.7.7 AUXILIARY BUILDING FILTERED VENTILATION EXHAUST SYSTEM...

3/4 7-16 3/4.7.8 SNUBBERS.................................................

3/4 7-18 TABLE 3.7-4a SAFETY-RELATED HYDRAULIC SNUBBERS (UNITS 1 AND 2)....

3/4 7-23 TABLE 3.7-4b SAFETY-RELATED MECHANICAL SNUBBERS (UNITS 1 AND 2)...

3/4 7-26 FIGURE 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST...........

3/4 7-29 3/4.7.9 SEALED SOURCE CONTAMINATION..............................

3/4 7-30 3/4.7.10 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System............................

3/4 7-32 Sp ray a nd/o r Sp ri n kl e r Sys tems............................

3/4 7-34 Halon Systems.............................................

3/4 7-36 Fire Hose Stations........................................

3/4 7-37 TABLE 3.7-5 FIRE HOSE STATIONS.....................................

3/4 7-38 3/4.7.11 FIRE BARRIER PENETRATIONS.................

3/4 7-40 3/4/7.12 AREA TEMPERATURE MONITORING...............................

3/4 7-42 TABLE 3.7-6 AREA TEMPERATURE MONITORING............................

3/4 7-43 3/4.7.13 GROUNDWATER LEVEL.........................................

3/4 7-44 TABLE 3.7-7 GROUNDWATER LEVEL MONITORING STATIONS..................

3/4 7-46 3/4.8 ELECTRICAL POWER TYSTEMS 3/4.8.1 A.C. SOURCES 0perating................................................

3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE......................

3/4 8-8 XII McGUIRE - UNITS 1 and 2

e INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 4.8-2 LOAD SEQUENCING TIMES...............................

3/4 8-9 Shutdown.................................................

3/4 8-10 3/4.8.2 0.C. SOURCES 0perating................................................

3/4 8-11 TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS...................

3/4 8-14 Shutdown (Units 1 and 2).................................

3/4 8-15 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS 0perating................................................

3/4 8-16 Shutdown.................................................

3/4 8-17 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices......................................

3/4 8-18 TABLE 3.8-la UNIT 1 CONTAINNENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES.............

3/4 8-20 TABLE 3.8.lb UNIT 2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROJECTIVE DEVICES.............

3/4 8-59 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION......................................

3/4 9-1 3/4.9.2 INSTRUNENTATION..........................................

3/4 9-2 3/4.9.3 DECAY TIME...............................................

3/4 9-3 l

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................

3/4 9-4

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3/4.9.5 COMMUNICATIONS...........................................

3/4 9-6 3/4.9.6 MAN I P U LATO R C RAN E........................................

3/4 9-7 l

l 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING..........

3/4 9-8 FIGURE 3.9-1 REQUIRED PATH FOR MOVEMENT OF TRUCK CASKS............

3/4 9-9 i

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XIII l

McGUIRE - UNITS 1 and 2

ny INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Leve1.........................................

3/4 9-10 Low Water Level..........................................

3/4 9-11 3/4.9.9 WATER LEVEL - REACTOR VESSEL.............................

3/4 9-12 3/4.9.10 WATER LEVEL - STORAGE P00L...............................

3/4 9-13 3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEH.................

3/4 9-14 3/4.9.12 FUEL STORAGE - SPENT FUEL P00L...........................

3/4 9-16 TABLE 3.9-1 MINIMUM BURNUP vs. INITIAL ENRICHMENT FOR REGION 2 ST0 RAGE.............................................

3/4 9-17 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..........................................

3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS...

3/4 10-2 3/4.10.3 PHYSICo TESTS............................................

3/4 10-3 3/4.10.4 RE ACTO R COO LANT LOO PS...................................

3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN....................

3/4 10-5 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4 11.1 LIQUID EFFLUENTS Concentration.............................................

3/4 11-1 TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PR0 GRAM...................................

3/4 11-2 Dose......................................................

3/4 11-5 Liquid Radwaste Treatment System..........................

3/4 11-6 Liquid Holdup Tanks.......................................

3/4 11-7 Chemical Treatment Ponds..................................

3/4 11-8 l

3/4.11.2 GASEOUS EFFLUENTS Dose Rate.................................................

3/4 11-9 McGUIRE - UNITS 1 and 2 XIV Amendment No. 88 (Unit 1)

Amendment No. 69 (Unit 2)

4 INDEX BASES SECTION-PAGE 3/4.0 APPLICABILITY................................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTR0L..........................................

B 3/4 1-1 3/4.1.2 B0 RATION SYSTEMS..........................................

B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES................................

B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE.....................................

B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR.......

B 3/4 2-2 3/4.2.4 QUADRANT POWER TI LT RATI0.................................

B 3/4 2-5 3/4.2.5 DNB PARAMETERS............................................

B 3/4 2-5 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION........................

B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................

B 3/4 3-2 3/4.3.4 TURBINE OVERSPEED PROTECTION..............................

B 3/4 3-5 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.............

B 3/4 4-1 3/4.4.2 SAFETY VALVES.............................................

B 3/4 4-2 3/4.4.3 PRESSURIZER...............................................

B 3/4 4-2 i

I 3/4.4.4 RELIEF VALVES.............................................

B 3/4 4-3 1

3/4.4.5 STEAM GENERATORS..........................................

B 3/4 4-3 l

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McGUIRE - UNITS 1 and 2 XVI Amendment No. 88 (Unit 1)

Amendment No. 69 (Unit 2)

-3 INDEX BASES

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SECTION P3GE 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........

B 3/4 7-3 l

3/4.7.3 COMP 0NENT COOLING WATER SYSTEM............................

B 3/4 7-3 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM..............................

B 3/4 7-3 3/4.7.5 STANDBY NUCLEAR SERVICE WATER P0ND........................

B 3/4 7-3a TABLE B 3/4 7-1 NUCLEAR SERVICE WATER SYSTEM SHARED VALVES.........

B 3/4 7-3b

-3/4.7.6 CONTROL AREA VENTILATION SYSTEM...........................

B 3/4 7-4 3/4.7.7 AUXILIARY BUILDING FILTERED VENTILATION EXHAUST SYSTEM....

B 3/4 7-4 3/4.7.8 SNUBBERS..........................

B 3/4 7-5 3/4.7.9 SEALED SOURCE CONTAMINATION...............................

B 3/4 7-6 3/4.7.10 FIRE SUPPRESSION SYSTEMS..................................

B 3/4 7-6 3/4.7.11 FIRE BARRIER PENETRATIONS.................................

B 3/4 7-7 3/4.7.12 AREA TEMPERATURE MONITORING...............................

B 3/4 7-7 3/4.7.13 GROUNDWATER LEVEL.........................................

B 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/8N$IfE pgggf4 $$}RIAU910RoWYSfinS9:9:.!?YF9??.Af9........

B 3/4 8-1 a

0 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...................

B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.......................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION...........................................

B 3/4 9-1 3/4.9.3 DECAY TIME................................................

B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.........................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS............................................

B 3/4 9-2 3/4.9.6 MAN I P U LATO R C R AN E.........................................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P0OL BUILDING...........

B 3/4 9-2 McGUIRE - UNITS 1 and 2 XVIII Amendment No. 88 (Unit 1)

Amendment No. 69 (Unit 2)

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INDEX BASES SECTION PAGE 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.............

B 3/4 9-2 3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL and STORAGE P00L............................................

B 3/4 9-3 3/4.9.11 FUEL HANDLING VENTI LATION EXHAUST SYSTEM..................

B 3/4 9-3 3/4.9.12 FUEL STORAGE - SPENT FUEL STORAGE P00L....................

b 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................................

B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTIO.1 LIMITS....

B 3/4 10-1 3/4.10.3 PHYSICS TESTS.............................................

B 3/4 10-1 3/4.10.4 REACTOR COOLANT L00PS.....................................

B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM -

SHUTD0WN.....................

B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.........................................

B 3/4 11-1 3/4.11.2 GASE0US EFFLUENTS........................................

B 3/4 11-3 3/4.11.3 SOLID RADI0 ACTIVE WASTE..................................

B 3/4 11-7 3/4.11.4 TOTAL 00SE...............................................

B 3/4 11-7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM.......................................

B 3/4 12-1 3/4.12.2 LAND USE CENSUS..........................................

B 3/4 12-2 3/4.12.3 INTERLABORATORY COMPARIS0N PR0 GRAM.......................

B 3/4 12-2 McGUIRE - UNITS 1 and 2 XIX Amendment No. 88(Unit 1)

Amendment No. 69(Unit 2)

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INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE

- 5.1.1 EXCLUSION AREA...............................................

5-1 5.1. 2 LOW PO P U LAT I O N Z0 N E..........................................

5-1

- 5.1. 3 MAP DEFINING UNRESTRICTED AREAS FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS...............................

5-1 FIGURE 5.1-1 EXCLUSION AREA.......................................

5-2 FIGURE 5.1-?

LOW PO P U LAT I O N Z 0 N E..................................

5-3 FIGURE 5.1-3 SITE BOUNDARY FOR GASE0US EFFLUENTS..................

5-4 FIGURE 5.1-4 SITE BOUNDARY FOR I.IQUID EFFLUENTS...................

5-5 5.2 CONTAINMENT 5.2.1 CO N F I G U RAT I O N................................................

5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE..............................

5-6 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES..............................

5-6 5.3.2 CONTROL R0D ASSEMBLIES.......................................

5-6 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE..............................

5-7 5.4.2 V0LUME.......................................................

5-7 5.5 METEOROLOGICAL TOWER LOCATION..................................

5-7 5.6 FUEL STORAGE 5.6.1 CRITICALITY..................................................

5-7 5.6.2 0RAINAGE.....................................................

5-7 1

5.6.3 CAPACITY.....................................................

5-7 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT............................

5-7a TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS...................

5-8 t

t McGUIRE - UNITS 1 and 2 XX Amendment No.88 (Unit 1)

Amendment No.69 (Unit 2)

1, 4

REACTIVITY CONTROL SYSTEMS CONTROLRODINSERTIONLIMQS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as shown in Figure 3.1-1.

l APPLICABILITY:

MODES 18 and 2*#.

,ACTIOl;:

With the control banh inserted beyond the above inset tion limits, except for surveillance testing' pursuant to Specification 4.1.3.1.2:

a.

Restore the control banks to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or b.

Reduce THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank position using the above figures, or c.

Be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be detetuined to be within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

See Special Test Exceptions 3.10.2 and 3.10.3.

With A,7f greater than or equal to 1.0.

McGUIRE - UNITS 1 and 2 3/4 1-21 Amendment No. 88 (Unit 1)

Amendment No. 69 (Unit 2)

jc TABLE 4.3-1 (Continued)

TABLE NOTATION With the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal.

Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1)

If not performed in previous 7 days.

(2)

Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore channel gains consistent with l

calorimetric power if absolute difference is greater than 2%.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(3)

Single point comparison of incore to excore axial flux difference above 15% of RATED THERMAL POWER.

Recalibrate if the absolute difference is greater than or equal to 3%.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(4)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5)

Detector plateau curves shall be obtained, evaluated, and compared to manufacturer's data.

For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(6)

Incore - Excore Calibration, above 75% of RATED THERMAL POWER.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(7)

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8)

With power greater than or equal to the interlock Setpoint the required operational test shall consist of verifying that the interlock is in the required state by observing the permissive annunciator window.

(9)

Monthly surveillance in MODES 3*, 4* and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permis-sive annunciator window.

Monthly surveillance shall include verification of the High Flux at Shutdown Alarm Setpoint of less l

than or equal to five times background.

(10) -

Setpoint verification is not required.

McGUIRE - UNITS 1 and 2 3/4 3-14 Amv.ndment No. 88 (Unit 1)

Amendment No. 69 (Unit 2)

?.

TABLE 3.3-3 (Continued) 2 S5 ENGINEERED SAFETY FEATURES ACTUATION SYSTFT. INSTRUMENTATION M

3 h

MINIMUM

~

T0fAL NO.

CHANNELS CHANNELS APPLICABLE g FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE M0CES ACTION w 7.

Auxiliary Feedwater o

Manual Initiation 2

1 2

1,2,3 22 u

b.

Automatic Actuation Logic 2

1 2

1,2,3 21 and Actuation Relays c.

Stm. Gen. Water Level-Low-Low R

1) Start Motor-Y Driven Pumps 4/sta. gen.

2/sta. gen.

3/sta. gen.

1,2,3 19 in any opera-in each N

ting sta gen, operating sta. gen.

2) Start Turbine-Driven Pump 4/sta. gen.

2/sta. gen.

3/sta. gen 1, 2, 3 19 gg in any in each gg 2 operating operating gg sta. gen.

sta. gen S

d.

Auxiliary Feedwater gg Suction Pressure - Low 2/ pump 2/ pump 2/ pump 1,2,3 24~

(Suction Supply Automatic Realignment) e.

Safety Injection Start Motor-Driven Pumps me See Item 1. above for all Safety Injection initiating functions and requirements vv

. El

=--

TABLE 3.3-3 (Continued)

N ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION E

m MINIMUM g

TOTAL NO.

CHANNELS C51ANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP DPERABLE MODES ACTION g

~

7.

Auxiliary feedwater (continued) f.

Station Blackout N

Start Motor-Driven Pumps and Turbine-Driven Pump 6-3/ Bus 2/ Bus 2/ Bus 1, 2, 3 19" Either Bus g.

Trip of All Main Feedwater Pumps Start Motor-Driven Pumps 2/ pump 1/ pump 1/ pump 1, 2, 14 wk 8.

Automatic Switchover to m

4 Recirculation RWST Level 3

2 2

1,2,3 IS*

9.

Loss of Power 4 kV Emergency Bus 3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 IS*

Undervoltage-Grid Degraded Voltage 10.

Engineered Safety Features Actuation System Interlocks a.

Pressurizer Pressure, 3

2 2

1. 2, 3 20 P-11 b.

Low-Low T,y, P-12 4

2 3

1, 2, 3 20 c.

Reactor Trip, P-4 2

2 2

1,2,3 22 d.

Steam Generator 3/sta gen.

2/sta gen.

1,2,3 20 Level,'P-14 in any in each operating operating sta gen.

sta gen.

2

o TABLE 4.3-2 (Continue <1J 2

E5 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION g

SURVEILLANCE REQUIREMENTS TRIP g

ANALOG ACTUATING MODES q

CHANNEL DEVICE MASTER SLAVE FOR WHICH m

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

- FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC lES1 TEST TEST IS REQUIRED

$ 10.

Engineered Safety Features Actuation m

System Interlocks a.

Pressurizer N.A.

R M

N.A.

1,2,3 Pressure, P-11 b.

Low, Low T,y, P-12 N.A.

N.A.

R N.A.

N.A.

1,2,3 A

c.

Reactor Trip, P-4 H.A.

R M

N.A.

1, 2, 3

<a O

d.

Steam Generator Level, P-14 S

R M

N.A.

M(1)

Q 1,2,3 l

l si in

.F F.

22

3. 3.

er

~l

TABLE 3.3-10

{

ACCIDENT MONITORIt.3 INSTRUMENTATION 5

REQUIRED MINIMUM

=

NO. OF CHANNELS

[

INSTRUMENT CHANNELS OPERABLE

~

3 1.

Containment Pressure 2

1 d

2.

Reactor Coolant Temperature - T and T 3.

ReactorCoolantPressure-Wide $Inge COW (Wide Range) 2 1

2 1

2, 4.

Pressurizer Water Level 2

1 5

5.

Steam Line Pressure 2/ steam generator 1/ steam generator to 6.

Steam Generator Water Level - Narrow Range 2/ steam generator 1/ steam cenerator 7.

Refueling Water Storage Tank Water Level 2

1 8.

Auxiliary Feedater Flow Rate 2/ steam generator 1/ steam generator 9.

Reactor Coolant System Subcooling Margin Monitor 2***

1 10.

PORV Position Indicator

2/ valve 1/ valve 11.

PORV Block Valve Position Indicator **

1/ valve 1/ valve w

12.

Safety Valve Position Indicator 2/ valve 1/ valve 1

13. Containment Water Level (Wide Range) 2 1

w 14.

In Core Thermocouples 4/ core quadrant 2/ core quadrant a

15.

Unit Vent - High Range Noble Gas Monitor 1

1 (High-High Range - EMF-36) 16.

Steam Relief - High Range Monitor 1/ steam line 1/ steam line (Unit 1 - EMF-24, 25, 26, 27)

(Unit 2 - EMF-10, 11, 12, 13) 17.

Containment Atmosphere - High Range Monitor 1

1 (11 F-51a or 51b) 18.

Reactor Vessel Level Instrumentation ****

g$&

a.

Dynamic Head (D/P) Range 2

1 b.

Lower Range 2

1 g

EE

Not applicable if the associated block valve is in the closed position.

- Not applicable if the associated block valve is in the closed position and power is removed.

- - 0nly one channel per unit is requirea until the end of the first refueling outage following 1/86 for each unit.

EJ

- - - Not applicable until the beginning of Cycle 4 for Unit 1 and Cycle 3 for Unit 2.

en

w TABLE 4.3-7 f

ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS a

S CHANNEL CHANNEL 5 INSTRUMENT CHECK CALIBRATION

)

[

1.

Containment Pressure M

R z

]

2.

Reactor Coolant Temperature - T and TCOLD (Wide Range)

M R

H0T 3.

Reactor Coolant Pressure - Wide Range M

R g

4.

Pressurizer Water Level M

R m

5.

Steam Line Pressure M

R 6.

Steam Generator Water Level - Narrow Range M

R 7.

Refueling Water Storage Tank Water Level M

R 8.

Auxiliary Feedwater Flow Rate M

R 9.

Reactor Coolant System Subcooling Margin Monitor M

R 1 10.

PORV Position Indicator M

R Y 11.

PORV Block Valve Position Indicator M

R 12.

Safety Valve Position Indicator M

R 13.

Containment Water Level (Wide Range)

M R

14.

In Core Thermocouples M

R 15.

Unit Vent - High Range Noble Gas Monitor M

R

??

(High-High Range - EMF-36)

[ E 16.

Steam Relief - High Range Monitor M

R

. P.

(Unit 1 - EMF-24, 25, 26, 27) a5 (Unit 2 - EMF-10, 11, 12, 13)

E E 17.

Containment Atmosphere - High Range Monitor M

R (EMF-Sla or 51b)

$$ 18.

Reactor Vessel Level Instrumentation 22 a.

Dynamic Head (D/P) Range M

R

3. 3.

b.

Lower Range M

R er

TABLE 3.6-2 N

O CONTAINMENT ISOLATION VALVES m

MAXINUM ISOLATION

^

E VALVE NUMBER FUNCTION TIME (SEC)

[1.

Phase "A" Isolation E

B8-18#

Steam Generator A Blowdown Containment Outside Isolation

<10 BB-2B#

Steam Generator B Blowdown Containment Outside Isolation 210 BB-3B#

Steam Generator C Blowdown Containment Outside Isolation 710 BB-4B#

Steam Generator D Blowdown Containment Outside Isolation 710 BB-5A#

Steam Generator A Blowdown Containment Inside Isolation 710 BB-6A#

Steam Generator B Blowdown Containment Inside Isolation 710 BB-7Af Steam Generator C Blowdown Containment Inside Isolation 710 BB-8A#

Steam Generator D Blowdown Containment Inside Isolation 310 CF-26AB#

Steam Generator D Feedwater Containment Isolation

<5 m

CF-28AB#

Steam Generator C Feedwater Containment Isolation 75 4

CF-30AB#

Steam Generatcr B Feedwater Containment Isolation 75 CF-35AB#

Steam Generator A Feedwater Containment Isolation 55 CF-1268 Steam Generator A Main Feedwater to Auxiliary Feedwater

$10 Nozzle Isolation CF-127B Steam Generator B Main Feedwater to Auxiliary Feedwater

$10 Nozzle Isolation CF-128B gg Steam Generator C Main Feedwater to Auxiliary Feedwater

$10 a.c Nozzle Isolation yy CF-129B Steam Generator D Main Feedwater to Auxiliary Feedwater

$10 Nozzle Isolation 55 CF-134A Steam Generator A Feedwater Containment Isolation Bypass

$10 zz CF-135A Steam Generator B Feedwater Containment Isolation Bypass

<10 l

PP CF-136A Steam Generator C Feedwater Containment Isolation Bypass 310 gg CF-137A St. cam Generator D Feedwater Containment Isolation Bypass

$10 CF-151B Auxiliary Nozzle Temper SG A

$10 22N 00

w 24 m,

3 TABLE 3.6-2 (Continued)

~

l CONTAlletENT ISOLATION VALVES m

7 MAXIMLM ISOLATION c

z VALVE NUpBER FUNCTION TIME (SEC) w

[ 1.

Phase "A" Isolation (continued)

CF-153B Auxiliary Nozzle Temper SG B

$10 l

l CF-155B Auxiliary Nozzle Temper SG C

'$10 l

CF-1578 Auxiliary Nozzle Temper SG D

$10

}

KC-3058#

Exc ss Letdown Hx Supply Pent. Isolation Outside

$30 l

KC-313Bf Excess Letdown Hx Ret. Hdr. Pent. Isolation Outside

<30 KC-320A NCDT Hx Supply Hdr. Pent. Isolation Outside 315 4

i KC-332B NCDT Hx Supply Hdr. Pent. Isolation Inside

$15 w

KC-333A NCDT Hx Return Hdr. Pent. Isolation Outside

<15 1

KC-429B RB Drain Header Inside Containment Isolation 715 KC-430A RB Drain Header Outside Containment Isolation.

315 NB-2608 Reactor Makeup Water Tank to NV System

$15 NC-538 Nitrogen to Pressurizer Relief Tank Containment

$10 Isolation Outside NC-54A Nitrogen to Pressurizer Relief Tank Containment

$10-rg Isolation Inside 3e NC-568 PRT Makeup

<10 yy NC-1958 NC Pump Motor Oil Containment Isolation Outside 315 ee NC-1%A NC Pump Motor Oil Containment Isolation Inside

$15 ee

-gg NF-228A Air Handling Units Glycol Supply Containment

$15 Isolation Outside gg NF-2338 Air Handling Units Glycol Supply Containment

$15 Isolation Inside 22 NF-234A Air Handling Units Glycol Supply Containment

-<15 Isolation Outside 00 NI-47A Accumulator Nitrogen Supply Outside Containment

$15 Isolation NI-95A Test HDR Inside Containment Isolation

$10

.:n

ML20150D008

Text

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