ML20077E993

Amends 119 & 101 to Licenses NPF-9 & NPF-17,respectively, Responding to Generic Ltr 89-01 by Relocating Radiological Effluent Tech Specs to Respective Sections of Chapter 16 of FSAR

ML20077E993
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/22/1991
From:	Matthews D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20077E996	List: ML20077E993 ML20077F006
References
GL-89-01, GL-89-1, NUDOCS 9106110336
Download: ML20077E993 (40)

Text

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UNITED STATES E '% c i 'i NUCLE AR REGULATORY COMMISSION

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DUKE POWER COMPAhY DOCKET NO. 50-369 McGUIRE NUCLEAR $TATION, UNIT 1 AMENDMENT TO FACILITY OPERAllNG LICENSE Araer.dment No. 119 License No. NFF-9 1.

The Nuclear Rt.gulatory Commission (the Commission) has found that:

A.

The application for amendment to the McGuire Nuclear Station, Unit 1(thefacility)FacilityOperating)datedFebruary7,1990,as License No, hPF-9 filed by the Duke Power Company (the licensee r

supplemented May 7, 1990, complies with the star.dards and requirements

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of the Atoniic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I;

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B.

The facility will operate in conformity with the application, p'

i the provisions of the Act, and the rules and regulations r -

of the Commission; 77 C.

There is reasonable asserance (1) that the activities authorized by Q

this amendment can be conducted without endangering the health and g

safety of the public, and (ii) that such activities will be conducted in compliance with the Commissian's regulations set forth in 10 C'k F

Chapter I; D.

The issuance of this amendrnent will not be inimical to the common defense and security or to the health and safety of the public; anJ E.

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

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Accordingly, the license is hereby arr,enu(d by page changes to the Technical Specifications as indicated in the 6ttachment to this liter,se amendment, arid Paragraph 2.C.(2) of f acility Operating Licu; e No NPF-9 is hereby amended to read as folicws:

T(chnical Specifications The Techt.ical Specifications ccritained in Appendix A, es revised thrcugh Amendment No.

, are hertby incorporated into the license.

The lictosee shall Operate the f acility in accordar cc with the Techt. ital Specifications and the Environicental Prctection Plan.

3.

Thit license araendment is cf fective as cf its date of issuance and shall be in:pletr,ented within 30 den of issu6nce.

FOR THE liUCLEAR REGULATORY COMMISSION A

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

Attachment:

Techrical Specification Changes Date of issuance:

May 22, 1991

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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE huCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERAllhG LICENSE Araer.dment No.101 License No NPF-17 1.

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

A.

The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No hPT-17 filed by the Duke Power Company (the licensee) dated February 7, 1990, as supplemented May 7, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

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

There is reasonable essurance (1) that the activities authorized by this amendment can bv conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 0.

The issuance of this amendment will not be inimical to the common defense 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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Accordingly, the license is hereby arrenoec b) page changes to the Technical Specifications as indicated in the ettachment to this liccrse amendn.ent, ano Paragraph 2.C.(2) of Facility Operating License lio. NPF-17 is hereby amended te read as tollows:

Technical Specifications The Technical Specificatict.s contained in Appent.i), A, as revised through Arr.endment No.

, are hereby incorpora.ed into the license.

The licensee shall operate the faci!!ty in accordance with the Technical Specificctions and the Envircnnental Protection Plan.

3.

This lico.se arrendment is ef f ectist es of itr. date of issuar.ce and shall be implemented within 30 days of issuance.

FOR THE huCLEAR REGULATORY C0hMISSION 4 David B. Matthews, Directcr Project 01.ectorate 11-3 Division of Reactor Projects-1/II Office cf Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuancc: May 22, 1991 l

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ATTACHMENT TO LICENSE AMENDMENT NO.119 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO.101 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace tre 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.

Remove Pages Insert Pages 11 11 VII VII XIV XIV XV XXil XX11 1-4 1-4 1-6 1-6 3/4 3-42 3/4 3-42 3/4 3-66 3/4 3-66 through 3/4-70 3/4 3-71 3/4 3-71 through 3/4 3-77 through 3-77 3/4 11-1 3/4 11-1 through 3/4 11-6 3/4 11-8 3/4 11-8 through 3/4 11-15 3/4 11-18 3/4 11-18 through 3/4 12-15 B 3/4 3-4 B 3/4 3-4 B 3/4 11-1 B 3/4 11-1 through E, 3/4 11-7 through B 3/4 11-3 B 3/4 11-6 B 3/4 11-7 B 3/4 12-1 B 3/4 12-1 B 3/4 12-2 6-16 6-16 6-16a 6-16b 6-18 6-18 through 6-20 through 6-20 6-23 6-23 through 6-25 through 6-25

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l INDEX DEFINITIONS SECTION PAGE 1.24 PURGE -

PURGING................................................

1-5 1.25 QUADRANT POWER TILT RATI0......................................

1-5 1.26 PATED THERMAL P0WER............................................

1-5 1.27 REACTOR BUILDING INTEGRITY.....................................

1-5 1.28 REACTOR TRIP SYSTEM RESPONSE TIME..............................

1-5 1.29 REPORTABLE EVENT..............................................

1-5 1.30 SHUTDOWN MARGIN................................................

1-6 1.31 SITE 80UNDARY..................................................

1-6 1.32 SLAVE RELAY TEST...............................................

1-6 1.34 SOURCE CHECK...................................................

1-6 1.35 STAGGERED TEST BASIS...........................................

1-6 1.36 THERMAL P0WER..................................................

1-6 1.37 TRIP ACTUATING DEVICE OPERATIONAL TEST.........................

1-7 1.38 UNIDENTIFIED LEAKAGE...........................................

1-7 l

1.39 UNRESTRICTED AREA..............................................

1-7 l

1.40 VENTILATION EXHAUST TREATMENT SYSTEM...........................

1-7 l

1.41 VENTING........................................................

1-7 1.42 WASTE GAS HOLDUP SYSTEM..............

1-7 TABLE 1.1, FREQUENCY N0TATION.......................................

1-8 j

TABLE 1.2, OPERATIONAL M0 DES........................................

1-9 i

McGUIRE - UNITS 1 and 2 II Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2) l

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.s INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................

3/4 3-54 Accident ttoni toring Instrum:nta tion.......................

3/4 3-55 TABLE 3.3-10 ACCIDENT MONITORIN eMFNTATI0N..................

3/4 3-56 TABLE 4.3-7 ACCIDENT MONIT0 Lit.

I' TATION SURVEILLANCE REQu..ahm 3/4 3-57 Explosive Gas Monitoring 1'st,umentation..................

3/4 3-71 TABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION.............

3/4 3-72 TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................

3/4 3-75 Loose-Part Detection Syster...............................

3/4 3-78 3/4.3.4 TURBINE OVERSPEED PROTECTION..............................

3/4 3-79 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power 0peration..............................

3/4 4-1 Hot Standby..............................................

3/4 4-2 Hot Shutdown.............................................

3/4 4-3 Cold Shutdown - Loops Filled.............................

3/4 4-5 l

l McGUIRE - UNITS 1 and 2 VII Amendment No.119 junit 1)

Amendment No.101 Lunit 2)

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I INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.8 RESIDUAL HEAT REMOVAL AND C0OLANT CIRCULATION High Water Level.........................................

3/4 9-10 L ow Wa t e r L e v e 1..........................................

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 SYSTEM.................

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 GROUF HEIGHT, INSERTION, AND POWER O!STRIBUTION LIMITS...

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

3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS...................................

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 Liquid Holdup Tanks.......................................

3/4 11-7 3/4 11.2 GASEOUS EFFLUENTS Explosive Gas Mixture.....................................

3/4 11-16 Gas Storage Tanks.........................................

3/4 11-17 l

l McGUIRE - UNITS 1 and 2 XIV Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2) l l

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. i INDEX ADMINISTRATIVE CO._N.T_.ROLS SECTION PAGE 6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)

Function...........

6-9 Organization..............................................

6-10 Review....................................................

6-11 Audits....................................................

6-11 Authority.................................................

6-12 Records...................................................

6-13

6. 6 REPORTABLE EVENT ACT10N........................................

6-13 6.7 SAFETY LIMIT VIOLATION........................................,

6-13 6.8 PROCEDURES AND PR0 GRAMS........................................

6-14 4

6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REP 0RTS..............................................

6-16b l

Startup Report............................................

6-16 Annual Reports............................................

6-17 Annual Radiological Environmental Operating Report........

6-18 Semiannual Radioactive Ef fluent Release Report............

6-18 Monthly Operating Reports.................................

6-20 Core Operating Limits Report..............................

6-21 McGUIRE - UNITS 1 and 2 XXII Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2)

.- e DEFINITIONS OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.18 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid ef fluents, in the calculation of gaseous and liquid effluent monitor-ing Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Sec-tion 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by FSAR Chapter 16.

OPERABLE - OPERABILITY 1.19 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE 1.20 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

l PHYSICS TESTS l'.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the core and related instrumentation:

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Conmission.

PRESSURE BOUNDARY LEAKAGE 1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

PROCESS CONTROL PROGRAM (PCP) 1.23 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that process-ing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

McGUIRE - UNITS 1 and 2 1-4 Amendment No.119 (Unit 1 (Unit 2))

Amendment No.101 l

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DEFINITIONS i

SHUT 00WN MARGIN 1.30 SHUTDOWN MARGIN shall be the instant <ineous amount of reactivity by which l

the reactor is subcritical or would be subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are i

fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.31 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

SLAVE RELAY TEST 1.32 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay.

The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

SOLIDIFICATION 1.33 Not Used SOURCE CHECK 1.34 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1.35 A STAGGERED TEST BASIS shall consist of:

A test schedule for n systems, subsystems, trains, or other a.

designated components obtained by dividing the specified test interval into n equal subintervals, and b.

The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

l THERMAL F0aER 1.36 THERMAL POWER shall be the total core heat transfer rate to the reactor

coolant, i

l McGUIRE - UNITS 1 and 2 1-6 Ame.1dment No.119 (Unit 2)

Amendment No.101 (Unit 1)

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2 TABLE 3.3-6 (Continued) n RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS A

MINIMUM I

CHANNELS CHANNELS APPLICABLE ALARM / TRIP c$

MONITOR TO TRIP / ALARM OPERABLE MODES SETPOINT ACTION

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6.

Control Room Air 1 per station 2 per All

< 3.4 x 10 27 i

g Intake Radioactivity-station pCi/m1

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,g High (EMF-43a and 43b)

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TABLE NOTATION With fuel in the fuel storage areas or fuel building.

With irradiated fuel in the fuel storage areas or fuel building.

i Must satisfy the requirements of McGuire Selected Licensee Commitment 16.11-6.

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w ACTION STATEMENTS l

l ACTION 26 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge valves are maintained closed.

k ACTION 27 - With the number of operable channels one less than the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolate the Control Room Ventilation System outside air intake which contains the inoperable instrumentation.

ACTION 28 - With less than the Minimum Channels OPERABLE requirement, operation may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm e

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Setpoint is provided in the fuel pool area.

Restore the inoperable monitors to pp OPERABLE status within 30 days or suspend all operations involving fuel movement in j

g the fuel building.

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ACTION 29 - Must satisfy the ACTION requirement for Specification 3.4.6.1.

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ACTION 30 - With less than the minimum channels OPERABLE requirement, operation may continue ww provided the Fuel Handling Ventilation Exhaust System requirements of Specifica-l

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tion 3/4.9.11 are met.

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Pages 3/4 3-66 through 3/4 3-70 deleted.

McGUIRE - UNITS 1 and 2 3/4 3-66 Amendment No.119 (Unit 1) through 3/4 3-70 Amendment No.101 (Unit 2) l

INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The gas monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.

APPLICABILITY:

As shown in Table 3.3-13.

ACTION:

With an explosive gas monitoring instrumentation channel Alarm / Trip a.

Setpoint less conservative than required by the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-13.

b.

With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected within the time specified, c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-9.

MCGUIRE - UNITS 1 and 2 3/4 3-71 Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2)

x TABLE 3.3-13 S

5 EXPLOSIVE GAS MONITORING INSTRUMENTATION l

m l

MINIMUM CHANNELS C

INSTRUMENT OPERABLE APPLICABILITY ACTION 5

d 1.

Not Used l

2.

WASTE GAS HOLDUP SYSTEM Explosive Gas o,

R Monitoring System n

a.

Hydrogen Monitor 1 per station 41 b.

Oxygen Monitors 2 per station 39 3.

Not Used 4.

Not Used i

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l McGUIRE - UNITS 1 and 2 3/4 3-73 Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2) 1 g..,

TABLE 3.3-13 (Continued)

TABLE NOTATION l

During WASTE GAS HOLDUP SYSTEM operation.

ACTION STATEMENTS ACTION 35 -

Not Used ACTION 36 -

Not Used ACTION 37 -

Not Used ACTION 38 -

Not Used ACTION 39 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 14 days.

With two channels inoperable, be in at least HOT STANOBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 40 -

Not Used ACTION 41 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner.

McGUIRE - UNITS 1 and 2 3/4 3-74 Amendment No.119 (Unit 2)

Amendment No.101 (Unit 1)

l TABLE 4.3-9 2

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EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

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ANALOG c-CHANNEL MODES IN WHICH 5

CHANNEL CHANNEL OPEPATIONAL SURVEILLANCE g

INSTRUMENT CHECK CALIBRATION TEST REQUIRED

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Not Used r

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2.

WASTE GAS HOLDUP SYSTEM Explosive m

Gas Monitoring System a.

Hydrogen Monitor D

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Oxygen Monitor D

Q(5)

M c.

Oxygen Monitor (alternate)

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Not Used w

4.

Not Used I

as RR 38 en 9G 22 hh CC

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THIS PAGE INTENTIONALLY LEFT BLANK McGUIRE - UNITS 1 and 2 3/4 3-76 Amendment No. (Unit 2) 119 Amendment No. (Unit 1) 101

TABt.E 4.3-9 (Continued)

TABLE NOTATION l

j During WASTE GAS HOLDUP SYSTEM operation.

(1) Not Used (2) Not Used (3) Not Used (4) The CHANNEL CALIBRATION shall include the use of standard gas samples corresponding to alarm setpoints in accordance with the manufacturer's recommendations.

(5) The CHANNEL CAllBRATION shall include the use of standard gas samples in accordance with the manufacturer's recommendations, in addition, a standard gas sample of nominal 4 volume percent oxygen, balance nitrogen, shall be used in the calibration to check linearity of the oxygen analyzer.

McGUIRE - UNITS 1 and 2 3/4 3-77 Amendment No.119 (Unit 2)

Amendment No.101 (Unit 1)

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l PAGES 3/4 11-1 THROUGH 3/4 11-6 DELETED McGUIRE - UNITS 1 and 2 3/4 11-1 Amendment No. 119 (Unit 1) through 3/4 11-6 Amendment No. 101 (Unit 2)

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I PAGES 3/411-8 THROUGH 3/4 11-15 DELETED McGUIRE - UNITS 1 and 2 3/4 11-8 Amendment No.119 (Unit 1) through 3/4 11-15 Amendment No.101 (Unit 2)

PAGES 3/4 11-18 THROUGH 3/4 12-15 DELETED McGUIRE - UNITS 1 and 2 3/4 11-18 Amendment No.119 (Unit 1) through 3/4 12-15 Amendment No.101 (Unit 2)

BASES 3/4.3.3.7 DELETED 3/4.3.3.8 NOT USED 3/4.3.3.9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The gas instrumentation is.provided for monitoring (and contrc'lling) the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLOUP SYSTEM.

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l McGUIRE - UNITS 1 and 2 B 3/4 3-4 Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2) l

. _ _ _ _. _ _ _.. _ _ _ _. _ _ _ _ _ _ _. _ _ _.. _.... - _ _ _.. _. _ _ _ _.... _ ~ -.

i 3/4.11' RADI0 ACTIVE EFFLUENTS BASES l

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McGUIRE - UNITS 1 and 2 8 3/4 11-1 Amend'.ielt No.119 (Unit 1 Amendmeat No.101 (Unit 2))

a.

RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 NOT USED 3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B. Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

3/4.11.1.5 NOT USED i

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I McGUIRE - UNITS 1. and 2 B 3/4 11-2 Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2)

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RAD 101CTl','E E f rl VENTS BASES l

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Pages B 3/4 11-3 through B 3/4 11-0 deleted R

McGUIRE - UNITS I and 2 B 3/4 11-3 Amendment No. 119 (Unit 1) through B 3/4 11-5 An.endment No. 101 (Unit 2)

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RAD 10AC11VE EFFLUENTS BASES

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i 3/4.11.2.4 NOT USED l

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3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is n.alntained below the flammability limits of hydrogen and oxygen.

Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits.

These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the fiammability limits.

Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.11.2.6 GAS STORAGE TANKS inis specification considers postulated radioactive releases due to a Waste Gas System leak or failure, and limits the quantity of radioactivity contained l

in each pressurized gas storage tank in the WASTE GAS HOLDUP SYSTEM to assure that a release would be substantially below the dose guideline values of 10 CFR Part 100 for a postulated event.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a HEMBER Of THE PUBLIC at the nearest exclusion area beundary will not exceed 0.5 rem.

This is con-sistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5,

" Postulated Radioactive Releases Due to a Waste Gas System Leak or failure,"

in NUREG-0800, July 1981.

1 McGUIRE - UNITS 1 and 2 0 3/4 11-6 Amendment No.119 (Unit 1) l Amendment No. 101 (Unit 2) l m

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RADI0 ACTIVE ErrLUENTS BASES I

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McGUIRE - UNITS 1 and 2 B 3/4 11-7 (Unit 1 Amendment No (Unit 2))

Amendment No 119 101

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l 3/4.12 RADIOLOGICAL ENVIR0fe' ENTAL MONITORING i

BASES i

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McGUIRE - UNITS 1 and 2 B 3/4 12-1 Amendment No.119 1; Unit 1 Amendment No.101 I, Unit 2))

through B 3/4 12-2 I

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 4)

Procedures for the recording and management of data, 5)

Procedures defining corrective actions for all off-control point chemistry conditions, and 6)

A procedure identifying:

(a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action, d.

Backup Method for Determining Subcooling Margin A program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin.

This program shall include the following:

1)

Training of personnel, and 2)

Procedures for monitoring, e.

Post-accident Sampling t

A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines, and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

The program shall include the following:

1)

Training of personnel, 2)

Procedures for sampling and analysis, and 3)

Provisions for maintenance of sampling and analysis equipment, i

f.

Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS Of THE PUBLIC from radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in FSAR Chapter 16, (2) shall be implemented by operating procedures, and (3) shall include remedial act. ions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

1)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the 00CM, 2)

Limitations on the concentrations of radioactive material released in liquid ef fluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B Table II, Column 2, McGUIRE - UNITS 1 and 2 6-16 Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2)

on.

4 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGkAMS (Continued) 3)

Monitoring, sampling, and analysis of radioactive itquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCh, 4

4)

Limitations on the annual and quarterly doses or dose commitment i

to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)

Limitations on the operability and use of the liquid and gasecus effluent treatment systems to ensure that the appropriate por-tions of these systems are used to reduce releases of radio-activity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix ! to 10 CFR Part 50, 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

g.

Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and *adionuclides in the environs of the plant.

The program shall provide i4 represen-tative measurements of radioactivity in the highest potenti.1 exposure i

pathways, and (2) verification of the accuracy of the effluent moni-McGUIRE - UNITS 1 and 2 6-16a Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2)

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ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) toring program and modeling of environmental exposure pathways.

The program shall (1) be contained in FSAR Chapter 16, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCH, 1

2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required i

by the results of this census, and 3)

Participation in an Interlaboratory Comparison Program to i

ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10. Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the NRC Regional Office unless otherwise noted.

STARTUP REPORT

6. 9.1.1 A summary report of plant STARTUP and power escalation testing shall be submitted following:

(1) receipt of an Operating License, (2) amendment to the License involving a planned increase in power level. (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

McGUIRE - UNITS 1 and 2 6-16b Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2)

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ADMINISTRATIVE CONTROLS k

ANNUAL RADIOLOGICAL ENVIRONMENTAt OPERATING REPORT

• 6.9.1.6 Poutine Radiologiesi Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted I

prior to May 1 of each year.

The report shall include summaries, interpreta-tions, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections t

IV.B.2, IV.B.3, and IV.C of Appendix ! to 10 CFR Part 50.

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ***

i 6.9.1.7 The Semiannual Radioactive Ef fluent Release Report covering the operation of the unit during the previous 6 months of operation shall be sub-mitted within 60 days ofter January 1 and July 1 of each year,

,, A single submittal may be made for a multiple unit station.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all enits at the station; however, for units with separate Radwaste Systems, the submittal shall specify the releases of radioactive material from each unit.

i McGUIRE - UNITS 1 and 2 6-18 Amendment No. '19 (Unit 1)

Amendment No. Oi (Unit 2)

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c ADMINISTRATIVE CONTROLS J

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)

The Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

Thematerialprovidedshallbe(1)consistentwiththeobjec-tives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix ! to 10 CFR Part 50.

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l McGUIRE - UNITS 1 and 2 6-19 Amendment No. 119 (Unit 1) l Amendment No.101 (Unit 2)

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f MONTHLY OPERATING REPORTS

6. 9.1. 8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Manage-ment, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the NRC Regional Of fice, no later than the 15th of each month following the calendar month covered by the report.

McGUIRE - UNITS 1 and 2 6-20 Amendment No. 119 (Unit 1)

Amendment No.101 (Unit 2)

ADMINISTRATIVE CONTROLS RE, CORD RETENTION (Continued) g.

Records of training and qualification for current members of the unit staff; h,

Records of inservice inspections performed pursi ant to these Technical Specifications; i.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuaat to 10 CFR 50.59; j.

Records of meetings of the NSRB and reports required by Specification 6.5.1.12; k.

Records of the service lives of all snubbers including the date at which the service life commences and associated installation and maintenance records; 1.

Records of secondary water sampling and water quality; and Records of analyses required by the Radiological Environmental m.

Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date.

This should include procedures effec-tive at specified times and QA records showing that these procedures were followed.

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Records of reviews performed for changes made to the ODCM and the PCP.

l 6.10.3 Records of quality assurance activities required by the QA Manual shall be retained for a period of time required by ANSI N45.2.9-1974.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mrem /hr at 45 CM (18 in.) from the radiation source or from any surf ace which the radiation penetrates shall be barricaded and conspicuously postel as a high radiation area and entrance thereto shall be controlled by requiring issuante of a Radiation Work Permit (RWP).

Individuals qualified in radiation protection proceduros (e.g., Health Physics Technician) or personnel continu-ously escorttd by such individuals may be exempt from the RWP issuance require-ment during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mrem /hr provided they are other-wise following plant radiation protection procedures for entry into high radiation areas.

McGUIRE - UNITS I and 2 6-23 Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2)

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ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area; or b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them; or An individual qualified in radiation protection procedures with a c.

radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Station Health Physicist in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accel-sible to personnel with radiation levels greater than 1000 mrem /hr at 45 CM (18 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorited entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision.

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area, in lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation prntection procedures to provide positive exposure control over the activities being performed within the area.

For individual areas accessible to personnel with radiation levels greater than 1000 mrem /hr* that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, that area shall be bar-ricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee-initiated changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3n.

This documentation shall contain:

A Measurement made at 18 irches from source of radioactivity.

McGUlRE - UNITS 1 and 2 6-24 Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2)

..r ADMINISTRAllVE CONTROLS PROCESS CONTROL PROGRAM (PCP) (Continued) 1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifyir.g the change (s) and 2)

A determination that the change will maintain the overall conformance of the solidified waste product to existing require-ments of federal, State, or other applicable regulations.

b.

Shall become effective upon review and acceptance by the station manager and a qualified individual / organization.

6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee-initiated changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3n.

This documentation shall contain:

1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective upon review and acceptance by the station manager and a qualified individual / organization.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

i McGUIRE - UNITS 1 and 2 6-25 Amendment No.119 (Unit 1)

Amendment No.101 (Unit 2) l

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