Text

Amends 128 & 110 to Licenses NPF-09 & NPF-17,respectively, Revising TS to Reflect Reloading of Unit 1 Cycle 8 W/B&W Fuel
	ML20086S926
Person / Time
Site:	McGuire, Mcguire
Issue date:	12/17/1991
From:	; Office of Nuclear Reactor Regulation
To:	;
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ML20086S928	List: ML20086S926;
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	NUDOCS 9201060069
	Download: ML20086S926 (41)
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..'.a n dRE Amendment Nos. 128 A 110 McGuire Units 1 & 2 Remove Pages insert Pages 1

II IV XVil XVIII XIV XX XXI XXII XX111 111 til VII Vil Vill Vill IX IX X

X XI XI X111 X111 XIV XIV XV XV 2-A10 2-A10 2-A11 2-A11 3/4 A2-14 3/4 A2-14 3/4 A2-14a 3/4 A2-14a 3/4 A2-15 3/4 A2-15 3/4 A2-15a 3/4 A2-15a 3/4 3-1 3/4 A3-1 3/4 3-3 3/4 A3-3 3/4 3-4 3/4 A3-4 3/4 3-5 3/4 A3-5 3/4 3-6 3/4 A3-6 3/4 3-7 3/4 A3-7

-3/4'3-8 _

3/4 A3-8 3/4 3-10 3/4 A3-10 3/4 3-12 3/4 A3-12 3/4 3-13 3/4 A3-13 3/4 3-14 3/4 A3-14 3/4 3-Ida 3/4 A3-14a 3/4 3-33 3/4 A3-33 3/4 B3-1 3/4 B3-3 3/4 83-4 3/4 B3-5 3/4 B3-6 3/4 B3-7 3/4 B3-8 3/4 B3-10 3/4 B3-12 3/4 B3-13 3/4 B3-14 9201060069 911217 3/4 B3-14a gDR ADOCK0500g9 3/4 B3-33

i INDEX l

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS

.SECTION PAGE

)

12;1-brETY LIMITS (UNIT 1) l 2.1.I' REACTOR C0RE.................................,...............

2-Al 2 1. 2 - REACTOR CCOLANT SYSTEM PRESSURE.,............................

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

2-A2 FIGURE 2.1-2_-

(BLANK)...............................................

2-3 2.1 SAFETY LIMITS (UNIT 2) l 2.1.1 REACTOR C0RE......................................

2-B1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE..............................

t-B1 FIGURE 2.1-Ib: UNITS I and-2 REACTOR CORE SAFETY LIMIT - FOUR LOOPS

.IN-0PERATION..,......................................

2-B2a FIGURE 2.1-2 (BLANK).....................................,........

2-3 2.2. LIMITING SAFETY SYSTEM SETTINGS (UNIT 1) l 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS..............-. A4 TABLE 2.2-la REACTOR TRIP-SYSTEM INSTRUMENTATION TRIP SETPOINTS....

2-A5 2.2 iLIMITING SAFETY SYSTEM SETTINGS (UNIT _2) l 2.2.1--REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS...............

2-B4 TABLE 2.2-Ib REACTOR TPIP SYSTEM INSTRUMENTATION TRIP SETPOINTS...,

2-05 BASES-SECTION-PAGE J2.1 SAFETY-LIMITS 2, l'.1 REACTOR COREL(UNIT-1)..-......................................

B A2-1 12.' 1.1-REACTOR CORE'(UNIT 2)........................................

B B2-1 2.1.2 REACTOR COOLANT 5YSTEM PRESSURE..............................

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

B 2-3 l

McGUIRE - UNITS 1 and 2 III Amendment No.128 (Unit 1) l Amendment No.110 (Unit 2)

_m.__

INDEX LIMITINGCONDITIONSFOROPERATIONAN{SURVEILLANCEREQUIREMENTS I

SECTION PAGE

-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 VII Amendment No.128(Unit 1)

Amendment No.110(Unit 2)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION P6G{

TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................

3/4 3-64 Accident Monitoring Instrumentation.........,.............

3/4 3-55 TABLE.3.3-10 ACCIDENT MONITORING INSTRUMENTATION..................

3/4 3-56 TABLE 4.3-7 ACCIDENT-MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................

3/4 3-57 Explosive Gas Monitoring Instrumentation..................

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 Detect on Ejstem..............................

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 Operation....................

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

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

3/4 4-3 Col d Shutdown - Loop s Fi ll ed.............................

3/4 4-5

!p f

l l-McGUIRE - UNITS 1-and 2 VIII Amendment Nc 128 Unit 1) l Amendment No.110 Unit 2)

- -. ~. -

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE Cold Shutdown - Loops Not Filled...........................

3/4 4-6 3/4.4.2 SAFETY VALVES Shutdown....

3/4 4-7 Operating.

3/4 4-8 3/4.4.3 PRESSURIZER.................

3/4 4-9 3/4.4.4.

RELIEF VALVES...

3/4 4-10 3/4.4.5 STEAM GENERATORS....,......................

3/4 4-11 TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION............

3/4 4-16 TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION..

3/4 4-17 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.

3/4 4-18 Operational Leakage.

3/4 4-19 TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES....

3/4 4-21 3/4,4.7 CHEMISTRY...........

3/4 4-22 TABLE 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS.,..........

3/4 4-23 TABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS.........................

3/4 4-24 3/4.4.8 SPECIFIC ACTIVITY..........................................

3/4 4-25 FIGURE 3.4-1 DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY

> 1 pCi/ gram DOSE EQUIVALENT I-131................

3/4 4-27

~

TABLE 4.4-4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM........................................

3/4 4-28 l

ll.

l McGUIRE UNITS I and 2 IX Amendment No.128 (Unit 1) l Amendment No.110 (Unit 2)

o INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System....................................

3/4 4-30 FIGURE 3.4-2a UNIT 1 REACTOR COOLANT SYSTEM HEATOP LIMITATIONS - APPLICABLE UP TO 10 EFPY...................

3/4 4-31 FIGURE 3.4-2b UNIT 2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS-APPLICABLE UP TO 10 EFPY.....................

3/4 4-32 FIGURE 3.4-3a UNIT 1 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS - APPLICABLE UP TO 10 EPFY............................

3/4 4-33 FIGURE 3.4-3b UNIT 2 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS-APPLICABLE UP TO 10 EPFY.........................,

3/4 4-34 TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM -

WITHDRAWAL SCHEDULE..............................

3/4 4-35 Pressurizer...............................................

3/4 4-36 Overpressure Protection Systems..........

3/4 4-37 3/4.4.10 STRUCTURAL INTEGRITY.................

3/4 4-39 3/4.4.11 REACTOR VESSEL HEAD VENT SYSTEM............

3/4 4-40 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS E

Cold Leg Injection................................,.......

3/4 5-1

[ Deleted].................................................

3/4 5 '

3/4.5.2 ECCS SUBSYSTEMS - T

> 350 F.............................

3/4 5-5 avg 3/4.5.3 ECCS SUBSYSTEM 5 - T,yg < 350 F.................

3/4 5-9 3/4.5.4

[0eleted].................................

3/4 5-11 L

3/4.5.5. REFUELING. WATER STORAGE TANK............

3/4 5-12 McGUIRE - UNITS 1 and 2 X

Amendment No.128 (Unit 1) l Amendment No.110 (Unit 2)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity.....................................

3/4 6-1 Containment Leakage.......................................

3/4 6-2 Containment Air Locks.....................................

3/4 6-10 Internal Pressure...................................

3/4 6-12 Air Temperature....................

3/4 6-13 i

Containment Vessel Structural Integrity...................

3/4 6-14 Reactor Building Structural Integrity....................

3/4 6-15 Annulus Ventilation System................................

3/4 6 Containment Ventilation System.................

3/4 6-18 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System...............

3/4 6-20 3/4.6.3 CONTAINMENT ISOLATION VALVES..............................

3/4 6-22 3/4.6.4 COMBUSTIBLE' GAS CONTROL Hydrogen Monitors.........................................

3/4 6-31 Electric Hydrogen Recombiners.............................

3/4 6-32 Hydrogen Control Distributed Ignition System..............

3/4 6-33 3/4.6.5 ICE CONDENSER Ice Bed.......................................

3/4 6-34 McGUIRE - UNITS 1 and 2 XI Amendment No.128 (Unit 1) l Amendment No.110 (Unit 2)

e 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 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL...................

3/4 7-18 4

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- Deleted 3/4.7.11 Deleted 3/4/7.12 AREA-TEMPERATURE M0NITCRING...............

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 AUXILIARY BUILDING GROUNDWATER LEVEL MONITORS..........

3/4 7-45 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating................................................

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

3/4 8-8 i -

McGUIRE - UNITS 1 and 2 XIII Amendment No.128 (Unit 1) l Amendment No.110 (Unit 2)

i e

INDEX LIMITINGCONDITICNSFOROPERATIONANDSURVEILL,AEEREQUIREMENTS SECTION PAGE TABLE 4.8-2 LOAD SEQUENCING TIMES.........

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

3/4 8-10 3/4.8.2 D.C. SOURCES Operating....................

3/4 8-11 TABLE 4.6-3 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 3/A.9 REFUELING OPERATIONS 3/4.9.1 BORON C0NCENTRATICN......................................

3/4 9-1 L

3/4.9.2 INSTRUMENTATION..........................................

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

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

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

3/4 9-6 3/4.9.6 MANIPULATOR CRANE........................................

3/4 9-7 l

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

3/4 9-8 L

FIGURE 3.9-1 REQUIRED PATH FOR MOVEMENT OF TRUCK CASKS............

3/4 9-9 i

McGUIRE - UNITS 1 and 2 XIV Amendment No.128 Unit 1 l

Amendment No.110 Unit 2

_m..

i i

i INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9,8 RESIOUAL 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 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 SHUTOOWN MARGIN..........................................

3/4 10-1

. 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION 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 GASE0US EFFLUENTS Explosive Gas Mixture.............................,......

3/4 11-16 i

Gas Storage Tanks.........

3/4 11-17 l.

l McGUIRE -' UNITS 1 and 2 XV Amendment No.128 Unit 1) l Amendment No.110 Unit 2)

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-TABLE 2.'2-la (Continued)

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,c REACTOR' TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS

[

NOTATION (Continued) ~

5-

-4

[

T

=

As defined in Note 1,

[

T"

,= < 588.2 F Reference T at RATED THERMAL PCWER, avg

' As' defined:.in Note 1,.and 5.

~

=

f (AI) is a function of the indicated difference between top and bottom detectors 2

of the powor-range nuclear ion chambers'; with gains to be selected based on measured instrument. response during plant startup tests such that:

(i) for q q between -35% and +35% AI; f (aI) = 0, where q and q are percent 2

r RATEDTHERbLPbWERinthetopandbottom.halvesofthecorerbspectihely,and 7

qt

9b is total. THERMAL POWER in percent of RATED THERMAL POWER; 3

-(ii) for each percent imbalance that the magnitude cf q q is more negative than

-35%AI,theATTripSetpoint'shallbeautomaticallyredbcedby7.0%ofATo; and (iii) for each percent imbalance that the magnitude of q q is more-positive than

+35% AI, the AT. Trip Setpoint shall be automatically redbced by 7.0% of ATo.

Note 3:

The channel's. maximum Trip Setpoint shall not exceed its computed Trip Setpoint L/ more tcan yh 3.6% of Rated Thermal Power.

\\

es c>

55 Note 4:

The channel's maximum Trip Setru.it shall not exceed its computed Trip Setpaint by more than 4.2%

gg of Rated Thermal Power.

^2 c15 i-

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..- - ~ ~. - -.~

_e i

-POWER DISTRIBUTION LIMITS UNIT 1 3/4.2.31 NUCLEAR ENTHALPY-RISE HOT CHANNEL-FACTOR - F3g(X,Y)

LIMITING CONDITION FOR OPERATION 3.2.3 F3g(X,Y) shall be limited by imposing the following relationship:

3 N

F3g(X,Y) ] [FAH(X,Y)]LC0 M

where:

Fag (X,Y) - the measured radial peak,

[F3g(X,Y)]LC0 - the maximum allowable radial peak as-defined in Core Operating Limits Report (COLR).

APPLICABILITY:

MODE 1.

(UNIT _1)-

i

-ACTION:

-With-F3g(X,Y) exceeding its limit:

a.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , reduce the allowable THERMAL POWER from RATED THERMAL-POWER at-least RRH%( ) for each 1% that F3H(X,Y) exceeds the limit, and-M b.

Within 6. hours either:

-1.

_ Restore F H(X,Y) to within the limit of Specification 3.2.3 for RATED THERMAL POWER, or-2.

Reduce the Power Range Neutron Flux-High Trip Setpoint_ in Table N

2.2-la at least RRH% for each 1% that F3g(X,Y) exceeds that-limit, and c.

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of initially being outside the--limit of Specification 3.2.'3; either:

Restore F"g(X,Y) to_within_the limit-._of Specification 3.2.3'for oli

-RATED THERMAL POWER,-or 2.

Perform the-following actions:

() - RRH is the amount of THERMAL POWER reduction required to compensate for'-

each'1% that F g(X,Y): exceeds the limit of Specification 3.2.3, provided in the COLR-per Specification-6.9.1.9.

McGUIRE - UNITS 1 AND 2 3/4 A2-14 Amendment No.128 (Unit 1)

Amendment No.110 (Unit 2)

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

POWER DISTRIBUTION LIMITS UNIT I L 3/4 '. 2. 3 : NUCLEAR ENTHALPY-RISE' HOT CHANNEL FACTOR - F3g(X,Y)

- LIMITING CONDITION FOR OPERATION

)

ACTION:

(a) Reduce'the OTAT K term in Table 2.2-la by at least 1RH ')

I i

for each 1% that FN (X,Y) exceeds the limit, and g

_ b) VerifythroughincoremappingthatF$g(X,Y)isrestoredto

(

within the limit for the reduced THERMAL POWER allowed by ACTION a, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

f) _TRH is the amount of OTAT Ki setpoint reduction requirea to cc apensate for each 1% that F H(X,Y) exceeds the limit of Specification 3.2.3, provided in the COLR per Specification 6.9.1.9.

McGUIRE - UNITS 1 AND 2 3/4 A2-14a Amendment No.128 (Unit 1)

Amenoment No 110 (Unit 2)

.a

i POWER DISTRIBUTION LIMITS UNIT 1 l

LIMITING CONDITION FOR OPERATION

=

ACTION:

(Continued)-

l d.

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit i;

required by ACTION a. and/or c.2 above; subsequent POWER OPERATION M

may proceed provided that F3H(X,Y) is demonstrated, through incore flux mapping, to be within the Limit specified in the COLR prior to exceeding the following THERMAL POWER levels:

1.

50% of RATED THERMAL POWER, 2.

75% _f RATED THERMAL POWER, and l

3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of-attaining greater. than or equal to 95% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

M 4.2.3.2 F3g(X,Y) shall be evaluated to determine whether F3g(X,Y) is within its limit by:

a.

Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

b.

Measuring FM (X,Y) according to the following schedule:

g 1.

Upon reaching equilibrium conditions after exceeding 10%

or more of RATED THERMAL POWER, the THERMAL POWER at which g(X,Y_) was-last determined ('), or F

2.

At_least once per 31 Effective Full. Power Days, or 3.

At each time _the QUADRANT POWER TILT RATIO indicated by the excore detectors is normalized using incore detector measurements.

c.

Performing the following calculations:

1.

For each location, calculate the % margin to the maximum allowable design as follows:

( ) During power escalation at the beginning of each cycle, THERMAL POWER may i

be increased until a power level for extended operation has been achieved l,

and a power distribution map obtained.

McGUIRE - UNITS-1 AND 2 3/4 A2-15 Amendment No.128 (Unit 1)

Amendment No.110 (Unit 2).

POWER DISTRIBUTION-LIMITS UNIT 1 SURVEll!ANCE REQUIREMENTS

%F Margin = (1 -

) x 100%

g9

[FAH(X,Y)] sun M

No additional uncertainties are required for F3g(X,Y),because

[Ffg(X,Y)]suryincludesuncertainties.

2.

Find the minimum margin of all locations examined in 4.2.3.2.c.1 above.

If any margin is less than zero, comply with the ACTION requirementsofSpecification3.2.3asif[Ffg(X,Y))surv is the same as [FAH(X,Y)] LCO d.

ExtrapolatingU ) at least two measurements to 31 Effective Full Power Days beyond the most recent measurement and if:

FN (X,Y) (extrapolated) > [Ffg(X,Y)] sun (extrapolated) and g

F g(X,Y)

(extrapolated)

F g(X,Y)

[FAH(X,Y))S"" (extrapolated)

[FAH(X,Y)] "

either of the following actions shall be taken:

M 1,

F3H(X,Y) shall be increased by 2 percent over that specified in 4.2.3.2.a. and the calculations of 4.2.3.2.c repeated, or 2.

A movable incore detector power distribution map shall be obtained, and the calculations of 4.2.3.2.c shall be performed no later than the time at which the margin in 4.2.3.2.c is extrapolated to be equal to zero.

)

Extrapolation of F f r the initial flux map taken after reaching equili-H brium conditions is not required since the initial flux map establishes the baseline measurement for future trending.

McGUIRE - UNITS 1 AND 2 3/4 A2-15a Amendment No.128 (Unit 1)

Amendment No.110 (Unit 2)

.. ~..

3/4.3 INSTRUMENTATION UNIT 1 l

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System In3trumentation channels and interlocks of Table 3.3-la (Unit 1) shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2a.

APPLICABILITY:

As shown in Table 3.3-la (Unit 1).

l ACTION:

As shown in Table 3.3-la.

-SURVEILLANCE REQUIREMENTS 4.3.1.1 Each Reactor Trip System Instrumentation channel and interlor:k shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-la.

l

4. 3.1. 2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific Reactor trip function as shown in the-

" Total No..of Channels" column of Table 3.3-la.

l 4.3.1.3 The response time of RTDs associated with the Reactor Trip System shall be demonstrated to be within their limits (see note 2 to Table 3.3-2a) l at least once per 18 months.

1 McGUIRE - UNITS 1 and 2 3/4 A3-1 Amendment No.128 (Unit 1) l Amendment No.110 (Unit 2)

.ur

' TABLE 3;3-la (Co'ntinued)

' UNIT'1; l

REACTOR TRIP SYSTEM' INSTRUMENTATION w

MINIMUM-TOTAL NO.

CHANNELS CHANNELS' APPLICABLE E

FUNCTIONAL UNIT-

0F CHANNELS

.TO TRIP OPERABLE MODES

' ACTION:

7 d

i-7.

Overpower WT-

' (

Four Loop Operation 4

2 3

1, 2 6

Three Loop ~ Operation

(**)

(**)'

(**)

y 8.

Pressurizer' Pressttre-Low ~

4 2.

3 1

6 l

(***).

9.

Pressurizer Pressure--High 4

2 3

1, 2 6

l

(***)

{

10.

Pressurizer Water Level--High 3

2 2

1 6

i j

J B

11.

Low Reactor Coolant Flow l

E a.

-Single Leop-(Above P-8) 3/ loop 2/ loop in 2/ loop in 1

6 i

any oper-each.oper-i ating 1.00,3 ating loop i

b.

Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop 1

6 below P-8) two oper-each oper-ating loops ating loop

'I

.i EE 12.

Steam Generator Water 4/stm. gen.

2/stm. gen.

3/stm. gen.

1, 2 6-l 5A Level--Low-Low in any oper-each oper-(***)

i gg ating stm.

ating stm.

{

gen.

- ru O CD

^^pg

3 1

vv Li i

t

U

]

TABLE 3.3-la (Continued)

UNIT 1..

..] '-

2 E

'l 5

REACTOR TRIP SYSTEM INSTRUMENTATION J

A MINIMUM'

-J TOTAL NO.

CHANNELS CHANNELS APPLICABLE I

~

.5 FUNCTIONAL UNIT OF CHANNELS TO TRIP-OPERABLE MODES

' ACTION f

c-I s 13..Undervoltage-Reactor Coolant Pumps (above P-7)

'4-1/ bus '

2 3

1>

6.

l'

. o, 5

14.

Underfrequency-Reactor Coolant Pumps (above D-7)

.4-1/ bus 2

3 1

6

-l m

15.

Turbine Trip a.

Low Fluid Oil Pressure 3

2 2

1 6-l-

b.

-Turbine Stop Valve Closure 4

4-

'l 1

11 16.

Safety Injection Input

)

.from ESF 2-

.1

'2

1. 2 9'

1 w

T 17.

Reactor Trip System Interlocks l

a.

Intermediate Range gg Neutron Flux, P-6 2

1-2 2

8 b.

Low Power Reactor Trips" Block,.P-7 FF P-10 Input 4

2 3

1 8

or P-13 Input 2

1 2

1 8

c.

Power Range Neutron l

gg Flux, P-8 4

2 3

1 8,

i IC d.

Low Setpoint Power Range Neutron Flux, P-10 4

2 3

1, 2 8

i 22

5. 3.

e.

Turbine Irapulse ' Chamber Fressure, P-13 2

1.

2 8

M l

.l l

i L

w I

~

s 2

j l; TA8LE 3.3-la (Continued)

UNIT 1 2

. REACTOR ' TRIP SYSTEM INSTRUMENTATION.

MINIMUM-TOTAL NOI CHANNELS CHANNELS APPLICABLE

[

FUNCTIONAL UNIT

-0F CHANNELS

.TO TRIP OPERABLE MODES ACTION 3

M

18. ' Reactor Trip Creakers 2

1:

2 1, 2

. 9,.12.

=l' 2

1-2:

3*,.4*, 5*

10-y

[

19.

Automatic Trip and Interlock 2-1

'2-1, 2 9

-l Logic 2

1 2

3*,

4*, ?

10~

a N

a 03 g

J.

ER l

aa ai i

an e

t'*

.F F O co bC 55 SC s

1

-l J

-'i t

n-TABLE 3.3-la(Continued),

UNIT 1 l

TABLE NOTATION With fthe Reactor Trip System breakers -in the closed position, the Centrol Rod Drive-System capable of rod withdrawal.

Values left blank pending NRC approval of three loop operation.

AtComply with the provisions of Specification 3.3.2 for any portion of the channel required-to be 0PERABLE by Specification 3.3.2.

1. elow the1P-G (Intermediate Range Neutro'. Flux Interlock) Setpoint.

~

B

1. 1. elow the P-10 '(Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

B ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore-the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 - With the number of OPERABLE channels one less than the-Total Number of Channels, STARTUP and/or P0"ER OPERATION may proceed provided the-following conditions are-satisffed:

a.

The: inoperable channel is placed in the tripped condition

.within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,.

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up-to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveiliance testing of other channels per Specification

~

4.3.1.1, and c.

Either, THERMAL POWER is restricted to-less than or eqaal to 75% of RATED THERMAL POWER and the Power Range Neutron.

Flux Trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT-

.F0WER TILT RATIO is monitored at11 east once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

. per-Specification 4.2.4.2.

i i

l l

McGUIRE - UNITS 1 & 2 3/4 A3-6 Amendment No.128 (Unit 1) l Amendment No. 110 (Unit 2) i

. ~

m. _......

m TAbtE 3.3-la (Cont;inued)

UNIT 1 l

-ACTION __ STATEMENTS (Continued)

(

.)

A.fl0N 3-- With the mumber of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

2

a. = Below the P-6 (Intermediate Range Neutron Fluk Intarlock)

Setpoint, restore the inoparable channel to OPERABLE status prior 19 increasing THERMAL POWER above the P-6 Setpoint, and

'b. 'Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the 11103 era' ole enannel to OPERABLE status prior to increasing THE 41AL POWER above 10% of RATD THERMAL POWER.

ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels.0PERABLE requirement suspend all operations involving positive reactivity changes.

ACTION 5 --With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, verify compliance' with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once por

.22' hours thereafter.

O ACTION 6 - With the number of OPERABLE channels one less than the Total

)-

Number of Channels, STARTUP and/or POWER OPERATION may proceed 1

provided tho'following conditions'are' satisfied:

a 'The inoperable channel is placed in the tripped condition within 6: hours, and..

. b,.

The Minimum Channels OPERABLE requirement is. met; howevere the-inoperable channel may be-bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.L1 e.1 Specification 4,3.2.1.

1 ACTION 7-'

Delete ACTION R-With.-less-than the Minimum Number of Channels OPERABLE, within

1. hour determine by observation of th' associated pertnissive annunciator. window (s) that the interlac is.in its requ' ired state for the existing plant condition, or apply Specification 3.0.3.

4 J

McGUIRE - UNITS i & 2 3/4 A3-7 Amendent No.128 (Unit 1) l Amendnent No.110 (Unit 2) l a

____...____._q i

'o TABLE 3.3 la (Continued)

UNIT 1 l

ACTION STA1(MENTS (Continued)

ACTION 9 -

With the number of C.' RABLE chcnnels one less than the Miri aum c

Channels OPERABLE requiretent, be in ht least H0f STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; Lowever, one channel may be bypassad for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, i

provided the other channel is OhERABLE, i

AC110N

- With the number of-OPERABLE channels one less than the Minimum Chant.els OPERABLE r.?quirement, restore the inoterable channel i

to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor trip i

breakers within the next hour.

ACTION 11 With the number of OPLPABLE channels less than the Total Number of. Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 12 With one of the diverse trip features (Undervoltage or shunt trip attachment)_ inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply Atl10N 9.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenan;e to restore the breaker to f

OPERABLE status.

~

a 2

b i

?

McGUIRE - UNITS 1 and 2 3/4 A3-8 Acaendment No.128 (Unit 1) l-Amendment No.110 (Unit.2)

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I-i-

i..

TABLE 4.3-la (Continued)

UNIT 1 l

x.

.E j

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS c.

i A

TRIP ANALOG ACTUATING MODES FOR c5 CHANNEL DEVICE WHICH g

CHANNEL CHANNEL OPERATIONAL.

OPERATIONAL ACTUATION SURVEILLAVCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST-LOGIC TEST 15 REOUIRED y

o, j

g d.

Low Setpoint Power Range i

'y Neutron Flux, P-10 N.A.

R(4)

M (8)

M.A.

N.A.

1, 2 i

i e.

T::rbii e Iepuise chaciber' s

Pressure, P-13 N.A.

R M (8)-

M.A.

N.A.

I 18.-

Reactor Trip Breaker..

N.A.

M (7, 12)

N.A.

1, 2, 3*, 4*, 5* lI 19.

Automatic Trip and j:

g Interlock Logic N.A.

N.A.

M (7) 1, 2, 3*, 4*, 5*

[;

l' h

20.

Reactor" Trip Bypass

[

g Breakers-N.A.

N.A.

M (13), R (14)

N.A.

1, 2, 3*, 4*, 5* l, i

?.

FF as

'83 nn N

o co

^^

L l

~~

mm I

i

TABLE 4.3-la (Continued)

UNIT 1 l

TABl.E 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 gaine consistent with 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 ext.luded from CHANNEL CAllBRATION.

(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-than or equal to five times background.

(10) -

Setpoint verification is not required.

McGUIRE - UNITS 1 and 2 3/4 A3-14 Amendment No.128 (Unit 1)

Amendment No.110 (Unit 2)

j TABtE 4.3-la (Continued)

UNIT 1 l

TABLE NOTATION (11) -

The -TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of-the undervoltage and shunt trip circuits for the Manual Reactor Trip function.

(12) -

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip breakers.

(13)-

Prior to placing breaker in servict, a local manual shunt trip shall be performed.

(14) - '

The automative undervoltage trip carability shall be verified j

operable.

l 1

f b

1 i

)

h b

McGUIRE. UNITS 1 and 2 3/4 A3-14a Amendment No.128 (Unit 1)

Amendment No.110 (Unit-2)

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

UNIT 1 l

1ABLE 3.3-$a (Continued)

TABLE NOTATION (1) Diesel generator starting and sequence loading delays included.

Response

time limit includes opening of valves to establish Safety Injection path j

and attainment of discharge pressure for centrifugal charging pumps.

Safety injection and RHR pumps.

)

(2) Valves 1KC30$8 and 1EC315B for Unit I and Valves 2KC305B and 2KC315B for Unit 2 are exceptions to the response times listed in the table.

The following response times in seconds are the required values for these valves for the initiating signal and function indicated:

i

<30f3)/40(4)

)

2. d 7 30

3. d

4. d

-[30(3)/40I4)

(3) Diesel generator starting and sequence loading delays not included.

Offsite power available.

Response time limit includes cpening of valves i

to establish Safety injection path and attainment of discharge pressure for centrifugal charging pumps and Safety Injection pumps.

1 (4) Diesel generator starting and sequence loading delays included.

Response

-time limit includes opening of valves to establish Safety Injection path and attainment of discharge pressure for centrifugal charging pumps and SafetyInjectionpumps.

($)- Response time for motor-driven auxiliary feedwater pumps on all Safety i

Injection signal shall be less than or equal to 60 seconds.

Response time limit includes opening of valves to establish Safety Injection path and attainment of discharge pressure for auxiliary feedwater pumps.

(6) The turbine driven pump does not start on a blackoat signal coincident with a safe #y injection signal.

McGUIRE - UNITS 1 and 2 3/4 A3-33 Amendment No.128 (Unit 1) l Amendment No.110 (Unit 2)

i 4

3/4._3__INSTRUM[NTATION UN11 2 l

3/4.3.1 REAC10R 1 RIP SYST[M INSTRUMENTA110N tlMITING CONDITION FOR OPCRA110N r

3.3.1 As a minimum, the Reactor Trip System Instrumentation channels and interlotts of Table 3.3-1b (Unit 2) shall be OPERABLE with RESPONSE TIMES as l

l shown in Table 3.3-2b.

l l

i E

APPLICABILIT,Y:

As shown in Table 3.1-lb (Unit 2).

l 8

ACTION:

i t

As shown in Table 3.3-lb.

l SURVEILLANCE RtQUIREMENTS 4.3.1.1 Each Reactor Trip System Instrumentation channel and interlock shall

- be demonstrated OPERABLE by the performance of the Reactor Trip System j

instrumentation Surveillance Requirements specified in Table 4.3-Ib.

l

4. 3.-l. 2 The REACTOR TRIP SYST[M RESPONSE TIME of each Reactor trip function t

shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at lea $t one train such that both trains are testl*d at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific Reactor trip function as shown in the

" Total No, of Channels" column of lable 3.3-Ib.

l

4. 3.1. 3 The response time of RTDs associated with the Reactor Trip System shall be demonstrated to be within their limits (see note 2 to Table 3.3-2b) at.

l least once per 18 months, l

McGUIRE - UNITS I and 2 3/4 83-1 Amendment No.128 (Unit 1) l Amendment No.110 (Unit 2)_

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l TABLE 3.3-Ib (Continued)

UNIT 2 l

TABLE NOTATION 1

A With the Reactor Trip System breakers in the closed position, the Control Rod Drive System capable of rod withdrawal.

u Values left blank pending NRC approvtl of three loop operation.

Corr, ply with the provisions of Specification 3.3.2 for any portion of the channel required to be OPERABLE by Specification 3.3.2.

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

i

1. 1. elow the P 10_(Low Setpoint Power Range Neutron flux Interlock) Setpoint.

0 ACTION STATEMENTS ACTION 1 - With the number of 0PERABLE channels one less than the Minimum

-Channels OPERABLE requirement, restore the inoperable channel-to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or ba in H01 STANDBY within l

the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 - With the r. umber of OPERABLE channels one less than the Total Number of Channels, STARTUP-and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

- The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1, and c.

Either, THERMAL POWER is restrictid to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

McGUIRE - UNITS 1 & 2 3/4 B3-6 Amendment No.128 (Unit 1) l Amendment No.110 (Unit 2)

.___;,_-a..-_._._-

TABLE 3.3-lb (Continued)

UNIT 2 l

ACTION STATEMENTS (Continued)

ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint, and b.

Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.

ACTION 4 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.

--ACTION 5 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUF and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in'the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1-and Specification 4.3.2.1.

ACTION 7-Delete ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition,-or apply Specification 3.0.3.

P McGUIRE - UNITS 1-& 2 3/4 B3-7 Amendment No.128 (Unit 1) l Amendment No.110 (Unit 2)

- l bgh

_____________m_

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m.___.___,

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ma

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t TABLE 3.3-lb (Continued)

UNIT 2 l

ACTION STATEMENTS (Continued) i ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

ACTION 10 - With the number of OPERABLE channels one less than tne Minimum Channels OPERABLE requirement, restore the inoperable channel i

to OPERABLE-status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor trip breakers within the next-hour.

ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the-inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 12 - With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERAB.E status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 9.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker-to OPERABLE-status.

4 E

McGUIRE

. UNITS-1 and 2 3/4 B3-8 Amendment No.128 (Unit 1) l Amendment No.110 (Unit 2) mse?-WE+-rxr 5*W r vuEWS-9-%T9^w>

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TABLE 3.3-2b (Con +.inued)

UNIT 2 l

3 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES A

.[ FUNCTIONAL UNIT RESPONSE TIME 5g 12.

Low Reactor Coolant Flow

[

a.

Single Loop (Above P-8)'

$1.0 second g.

b.

Two Loops (Above P-7 and below P-8) 51.0 second 13.

Steam Generator Water Level--Low-Low

$2.0 (Unit 1), 3.5 (Unit 2) seconds 14.

Undervoltage-Reactor Coolant Pumps

<l.5. seconds 15.

Underfrequency-Reactor Coolant Pumps

<0.6 second 16.

Turbine Trip w^

a.-

Low Fluid Oil Pressure N.A.

y b.

Turbine Stop Valve Closure N.A.

17.

Safety Injection Input from ESF N.A.

18.

Reactor Trip System Interlocks N.A.

p g 19.

Reactor Trip Breakers N.A.

aa R $

20.

Automatic Trip and Interlock logic N. A.

ee 32 hh.

e=

s iw 44yr-s

+e e

y-

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ye.

.4,s-i-1e-

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.-..s

.-iu-4-.m, r

S z

TABLE 4.3-1b (Continued)

UNIT 2 l

E-S REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS y

TRIP ANALOG ACTUATING MODES FOR c-5

. CHANNEL DEVICE WHICH d

CHANNEL CHANNEL

- OPERATIONAL

~ 0PERATIONAL

' ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION-TEST TEST LOGIC TEST IS REQUIRED g

k 13.

Steam Generator Water level--

S R

M.

N.A.

1, 2 Low-Low m

14..Undervoltage - Reactor: Coolant N.A.

R N.A..

M N.A.

1 Pumps

15..Underfrequency - Reactor N.A.

R

.N.A.

M N.A.

1 Coolant Pumps w}

16.

Turbine Trip 5

a.

Low Fluid Oil Pressure N.A.

R N.A.

S/U(1, 10)

N.A.

I h

b.

Turbine Stop Valve Closure N.A.

R N.A.

S/U(1, 10)

N.A.

I 17.

Safety Injection Input from N.A N.A.

N. A.

R N.A.

1. 2 ESF p p 18.

Reactor. Trip System Interlocks kk a.

Intermediate Range gg Neutron Flux, P-6 N.A.

R(4)

M N.A.

N.A.

2,,

S5 b.

Low Power Reactor

. Trips Block, P-7 N.A.

R(4)

M (8)

N.A..

N.A.

1

_7, c.

Power Range Neutron om Flux, P-8 N.A.

R(4)

M (8)

N. A.

N.A.

1 29 W$

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c l

TABLE 4.3-Ib (Continued)

UNIT E

{

REACTOR TRIP SYSTEM INSTRtMENTATION SURVEILLANCE REQUIREMENTS LA:

TRIP ANALOG ACTUATING ADDES FOR z

.c 4

z CHANNEL DEVICE WHICH i-U CHANNEL CHANNEL OPERATIONAL

' OPERATIONAL ACTUATION SURVEILLANCE

[,FUNCTIONALUNIT CHECK CALIBRATION TEST TEST LOGIC TEST' IS REQUIRED g

d.

. Low Setpoint Power Range Neutrco Flux, P-10 N.A.

R(4)

M (8)

N.A.

1, 2 y

i.

e.

Turbine Impulse Chamber l

Pressure P-13-.

N.A.

R M (8)

N.A.

I 1

19.

Reactor Trip Breaker N.A.

N.A.

M (7, 12)

N.A.

1, 2', 3*, 4*, 5*

o 20.

Automatic Trip and Interlock Logic N.A.

N.A.

M (7)

I, 2, 3*,

4*, 5*

l y

21.

Reactor Trip Bypass g

Breakers N.A.

N.A.

M (13), R (14)

N.A.

1, 2, 3*, 4 *, 5*

t

=

ea ae 1

aa zz-oo 22 Ah

==

p 1

k

).

e **,

TABLE 4.3-lb (Continued)

UNIT 2 l

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

Below P-6 (Intermediate Range Neetron 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 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.

1 (3)

Single point comparison of incore to excore axial flux difference above 1$% 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 provit;

, of Specification 4.0.4 are not applicable for entry into H0DE-2 or 1.

(7)

Each-train 'shall oe tested at least every 62 days on a S1AGGERED TEST BASIS.

(8)

With power greater than or equal to the interlock Setpoint the required operational test sha11' 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 existibg plant conditions by observation of the permis-sive annunciator wincow.

Monthly surveillance shall-include verification of the'High Flux at Shutdown Alarm Setpoint of less than or equal to five times background.

(10) -

Setpoint verification is not required.

McGulRE -UN115 1 and 2 3/4 B3-14 Amendment No.128 (Unit 1) l Amendment No,110 (Unit 2)

4 TABLE 4.3-1b (Continued)

UNil 2 l

TABLE NOTATION (11) -

The TRIP ACTUATING DEVICE OPERATIONAL TLST saall independently verify the OPERABILITY of the undervoltage and shu t trip circuits for the Manual Reactor Trip function.

(12) -

The TRIP ACTUATING DEVICE OPERATIONAL If5T iball independently verify the OPERABILITY of the undervoltage and sh.nt trip attachments of the Reactor Trip Breakers.

i (13) -

Prior to placing breM,er in service, a,ocal manual shunt trip shall be performed.

(14) -

lhe automative undervoltage trip capability shall be verified

operable, i

i F

McGUIRE - UNITS 1 and 2 3/4 B3-14a Amendment No.128 (Unit 1)

Amendment No.110 (Unit 2)

c ',o a

TABLE 3.3 5b (Continued)

UNIT 2

, TABLE NOTATION A

(1) Diesel generator start.ing and sequence loading delays included.

Response

tirne limit includes opening of valves to establish Safety injection path and attainment of discharge pressure for centrifugal charging pumps, Safety injection and RHR pumps.

(2) Valves 1KC305B and 1KC31$B for Unit 1 and Valves 2KC30$D and 2KC31SB for Unit 2 are exceptions to the response times listed in the table.

The following response times in seconds are the required values for these valves for the initiating signal and function indicated:

< 30(3)

I4) 2d

~ 30((3)/40

3. d 4.d 530 3)/40(4)

(3) Diesel generator starting and sequence leading delays not included.

Offsite power available.

Response time limit includes iipening of valves

~

to establish Safety injection path and attainment of discharge pressure for centrifugal charging pumps and Safety injection pumps.

(4) Diesel generator starting and sequence loading delays included.

Response

time limit includes opening of valves to establish $nfety injection path and attainment of discharge pressure for centrifegfl charging pumps and SafetyInjectionpumps.

(b) Response time for motor-driven auxiliary feedwater pumps on all Safety Injection signal shall be less than or equal to 60 seconda, Response time limit includes opening of valves to establish Safety injection path and attainment of discharge pressure for auxiliary f eedwater pumps.

(6) The turbine driven pump does not start on a blackout signal coincident withasafetyinjectionsignal.

F

- (

McGUIRE - UNITS 1 and 2-3/4 B3-33 Amendment No.128 (Unit 1) l Amendment No,110 (Unit 2)

...

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