ML16139A461

NOTES---------------------------.,------

1.

Neutron detectors are excluded from CHANNEL CALIBRATION.

2.

Power Range Neutron Flux high voltage detector saturation curve verification is not required to be performed prior to entry into MODE 1 or 2.

Perform CHANNEL CALIBRATION.

SR 3.3.1.12 Perform CHANNEL CALIBRATION.

RTS Instrumentation 3.3.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

McGuire Units 1 and 2 3.3.1-12 Amendment Nos. 283/262

SURVEILLANCE SR 3.3.1.13 Perform COT.

SR 3.3.1.14 ------------------------------NOTES-----------------------------

Verification of setpoint is not required.

Perform TADOT.

SR 3.3.1.15 -----------------------------NOTES----------------------------------

Verification of setpoint is not required.

Perform TADOT.

SR 3.3.1.16 -----------------------------NOTES-----------------------------

Neutron detectors are excluded from response time testing.

Verify RTS RESPONSE TIME is within limits.

SR 3.3.1.17 Verify RTS RESPONSE TIME for RTDs is within limits.

RTS Instrumentation 3.3.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance

Frequency Control Program

---:---NOTE-------

Only required when not performed within previous 31 days Prior to reactor startup In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program McGuire Units 1 and 2 3.3.1-13 Amendment Nos. 261/241

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of7)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

1.

Manual Reactor Trip 1,2 2

B SR 3.3.1.14 NA NA 3(a), 4(a), 5(a) 2 c

SR 3.3.1.14 NA NA

2.

Power Range Neutron Flux

a.

High 1,2 4

D SR 3.3.1.1

.:=_ 110% RTP 109% RTP SR 3.3.1.2 SR3.3.1.7 SR 3.3.1.11 SR 3.3.1.16

b.

Low 1(b),2 4

E SR 3.3.1.1

.:=_26% RTP 25% RTP SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16

3.

Power Range Neutron Flux Rate High Positive Rate 1,2 4

D SR 3.3.1.7

.:=_5.5% RTP 5% RTP SR 3.3.1.11 with time with time constant constant

~2 sec

4.

Intermediate Range 1(b), 2(c) 2 F,G SR 3.3.1.1

_::38% RTP 25% RTP Neutron Flux SR 3.3.1.aUJ(k)

SR 3.3.1.11 U)(k) 2(d) 2 H

_::38% RTP 25% RTP SR 3.3.1.aUJ(k)

SR 3.3.1.11 U)(k)

(continued)

(a)

With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

(b)

Below the P-1 O (Power Range Neutron Flux) interlocks.

(c)

Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(d)

Below the P-6 (Intermediate Range Neutron Flux) interlocks.

U)

If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(k)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and the as-left tolerances are specified in the UFSAR.

McGuire Units 1 and 2 3.3.1-14 Amendment Nos. 283/262

APPLICABLE MODES OR OTHER SPECIFIED FUNCTION CONDITIONS

5.

Source Range 2(d)

Neutron Flux 3(a), 4(a), 5(a)

Table 3.3.1-1 (page 2 of7)

Reactor Trip System Instrumentation REQUIRED CHANNELS CONDITIONS 2

l,J 2

J,K L

SURVEILLANCE REQUIREMENTS SR3.3.1.1 SR 3.3.1.80)(k)

SR 3.3.1.11 O)(k)

SR 3.3.1.1 SR 3.3.1.70)(k)

SR 3.3.1.11 O)(k)

SR 3.3.1.1 SR 3.3.1.1.1 RTS Instrumentation 3.3.1 ALLOWABLE VALUE

~ 1.44 E5 cps

~ 1.44 E5 cps NIA NOMINAL TRIP SETPOINT 1.0 E5 cps 1.0 E5 cps N/A

6.

Overtemperature 1ff 1,2 4

E SR3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.12 SR3.3.1.16 SR 3.3.1.17 Refer to Note 1 (Page 3.3.1-18)

Refer to Note 1 (Page 3.3.1-18)

7.

Overpower Ll. T 1,2 4

E SR 3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR3.3.1.12 SR3.3.1.16 SR3.3.1.17 Refer to Note 2 (Page 3.3.1-19)

Refer to Note 2 (Page 3.3.1-19)

8.

Pressurizer Pressure (a)

(d)

(e)

(f)

0)

(k)

a.

Low 4

b.

High 1,2 4

M E

SR 3.3.1.1 SR 3.3.1.7 SR3.3.1.10 SR 3.3.1.16 SR 3.3.1.1 SR 3.3.1.7 SR3.3.1.10 SR 3.3.1.16 With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

Below the P-6 (Intermediate Range Neutron Flux) interlocks.

.:: 1935 psig

~2395 psig With the RTBs open. In this condition, source range Function does not provide reactor trip but does provide indication.

Above the P-7 (Low Power Reactor Trips Block) interlock.

1945 psig 2385 psig (continued)

If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and the as-left tolerances are specified in the UFSAR.

McGuire Units 1 and 2 3.3.1-15 Amendment Nos. 283/262

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of7)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

9.

Pressurizer Water 1 (f) 3 M

~93%

92%

Level-High SR 3.3.1.7 SR 3.3.1.10

10. Reactor Coolant Flow-Low

a.

Single Loop 1(g) 3 per loop N

~87%

88%

SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16

b.

Two Loops 1(h) 3 per loop M

~87%

88%

SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16

11. Undervoltage RCPs 1 (f) 1 per bus M

~ 5016 v 5082 v SR 3.3.1.10 SR 3.3.1.16

12. Underfrequency 1 (f) 1 per bus M

~ 55.9 Hz 56.4 Hz RCPs SR 3.3.1.10 SR 3.3.1.16

13. Steam Generator 1,2 4 perSG E

SR3.3.1.1

~ 15%

16.7%

(SG) Water Level -

SR 3.3.1.7 Low Low SR3.3.1.10 SR3.3.1.16

14. Turbine Trip

a.

Low Fluid Oil 1(g) 3 0

~42 psig 45 psig Pressure SR 3.3.1.15

b.

Turbine Stop 1(g) 4 p

~ 1% open

~ 1% open Valve Closure SR 3.3.1.15

15. Safety Injection (SI) 1,2 2 trains Q

SR 3.3.1.5 NA NA Input from SR3.3.1.14 Engineered Safety Feature Actuation System (ESFAS)

(continued)

(f)

Above the P-7 (Low Power Reactor Trips Block) interlock.

(g)

Above the P-8 (Power Range Neutron Flux) interlock.

(h)

Above the P-7 (Low Power Reactor Trips Block) interlock and below the P-8 (Power Range Neutron Flux) interlock.

McGuire Units 1 and 2 3.3.1-16 Amendment Nos. 257/237

RTS Instrumentation 3.3.1 Table 3.3.1-1(page4 of7)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

16. Reactor Trip System Interlocks

a.

Intermediate 2(d) 2 s

~ 6.6E-6% RTP 1E-5% RTP Range Neutron SR3.3.1.13 Flux, P-6

b.

Low Power 1 per train T

SR 3.3.1.5 NA NA Reactor Trips Block, P-7

c.

Power Range 4

T SR 3.3.1.11

~49% RTP 48% RTP Neutron Flux, SR 3.3.1.13 P-8

d.

Power Range 1,2 4

s SR 3.3.1.11

~ 7% RTP and 10% RTP Neutron Flux, SR 3.3.1.13

~ 11% RTP P-10

e.

Turbine Inlet 2

T SR 3.3.1.12

~ 11 % turbine 10% turbine Pressure, P-13 SR 3.3.1.13 inlet pressure inlet pressure equivalent equivalent

17. Reactor T.riP 1,2 2 trains R,V SR 3.3.1.4 NA NA Breakers (i) 3(a), 4(a), 5(a) 2 trains c

SR 3.3.1.4 NA NA

18. Reactor Trip Breaker 1,2 1 each per u

SR 3.3.1.4 NA NA Undervoltage and RTB Shunt Trip 3(a), 4(a), 5(a)

Mechanisms 1 each per c

SR 3.3.1.4 NA NA RTB

19. Automatic Trip Logic 1,2 2 trains Q,V SR 3.3.1.5 NA NA 3(a), 4(a), 5(a) 2 trains c

SR 3.3.1.5 NA NA (a)

With RTBs closed and Rod Control System capable of rod withdrawal.

(d)

Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(i)

Including any reactor trip bypass breakers that are racked in and closed for bypassing on RTP.

McGuire Units 1 and 2 3.3.1-17 Amendment Nos. 283/262

Table 3.3.1-1 (page 5 of 7)

Reactor Trip System Instrumentation RTS Instrumentation 3.3.1 Note 1: Overtemperature L\\ T The Overtemperature L\\T Function Allowable Value shall not exceed the following NOMINAL TRIP SETPOINT by more than 4.3 % of RTP.

e,. T (1 + r1s) (-1-) < e,. T. {K - K (1 + r 4 s) [r.

1

- r] + K (P - P') - f (M)}

. (1+T2S) 1+T3S -

0 1

2 (1+Ts s)

(1+Ts s) 3 1

Where:

L\\ T is measured RCS L\\ T by loop narrow range RTDs, °F.

L\\To is the indicated L\\T at RTP, °F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, °F.

T' is the nominal Tavg at RTP, ~the value specified in the COLR.

P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, = the value specified i!l the COLR.

K1

=

K2

=

K3

=

't1,'t2 =

't3

=

't4, 'ts

'ts

=

f 1(L\\I) =

Overtemperature L\\ T reactor NOMINAL TRIP SETPOINT, as presented in the COLR, Overtemperature L\\ T reactor trip heatup setpoint penalty coefficient, as presented in the COLR, Overtemperature L\\ T reactor trip depressurization setpoint penalty coefficient, as presented in the COLR, Time constants utilized in the lead:-lag controller for L\\ T, as presented in the

COLR, Time constants utilized in the lag compensator for L\\ T, as presented in the

COLR, Time constants utilized in the lead-lag controller for T avg. as presented in the

COLR, Time constants utilized in the measured T avg lag compensator, as presented in the COLR, and, a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gain$ to be selected based on measured instrument response during plant startup tests such that:

(i) for qt - qb between the "positive" and "negative" f1(L\\I) breakpoints as presented in the COLR; f1(L\\I) = 0, where qt and qb are percent RA TED THERMAL POWER in the top and bottom halves of the core respectively, and qt+ qb is total THERMAL POWER in percent of RATED THERMAL POWER; (continued)

McGuire Units 1 and 2 3.3.1-18 Amendment Nos. 2191201

Table 3.3.1-1 (page 6 of 7)

Reactor Trip System Instrumentation RTS Instrumentation 3.3.1 (ii) for each percent imbalance that the magnitude of qt - qb is more negative than the f1 (~1) "negative" breakpoint presented in the COLR, the ~ T Trip Setpoint shall be automatically reduced by the f1 (~1) "negative" slope presented in the COLR; and (iii) for each percent imbalance that the magnitude of qt - qb is more positive than the f1(~I) "positive" breakpoint presented in the COLR, the ~ T Trip Setpoint shall be automatically reduced by the f 1(~1)

"positive" slope presented in the COLR.

Note 2: Overpower ~ T The Overpower ~T Function Allowable Value shall not exceed the following NOMINAL TRIP SETPOINT by more than 2.6% of RTP.

ti T <1 + T1 s) (

1

) :::; ti To {K4 - Ks T7 s (

1

) T - Ka [r 1

- r*]- f2 (ti/)}

(1 + Tz s 1 + T3 s 1 + T7 s 1 +Ta s 1 +Ta s Where:

~Tis measured RCS ~T by loop narrow range RTDs, °F.

~To is the indicated ~Tat RTP, °F.

s is the Laplace transform operator, sec*1.

Tis the measured RCS average temperature, °F.

T" is the nominal Tavg at RTP, ~the value specified in the COLR.

~

=

Ks

=

Ks

=

't1, 't2 =

't3

=

'ts

=

't7

=

f2(~1) =

Overpower ~T reactor NOMINAL TRIP SETPOINT as presented in the

COLR, The value specified in the COLR for increasing average temperature and the value specified in the COLR for decreasing average temperature, Overpower~ T reactor trip heatup setpoint penalty coefficient as presented in the COLR for T > T" and Ks= the value specified in the COLR for T ~ T",

Time constants utilized in the lead-lag controller for ~ T, as presented in the

COLR, Time constants utilized in the lag compensator for~ T, as presented in the

COLR, Time constants utilized in the measured Tavg lag compensator, as presented in the COLR, Time constant utilized in the rate-lag controller for T avg, as presented in the COLR, and a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(continued)

McGuire Units 1 and 2 3.3.1-19 Amendment Nos. 219 / 201

Table 3.3.1-1(page7of7)

Reactor Trip System Instrumentation RTS Instrumentation 3,3.1 (i) for qt - qb between the "positive" and "negative" f 2(~1) breakpoints as presented in the COLR; M~I) = 0, where qt and qb are percent RA TED THERMAL POWER in the top and bottom halves of the core respectively, and%+ qb is total THERMAL POWER in percent of RATED THERMAL POWER; (ii) for each percent imbalance that the magnitude of qt - qb is more negative than the f 2(~1) "negative" breakpoint presented in the COLR, the ~ T Trip Setpoint shall be automatically reduced by the f 2(~1) "negative" slope presented in the COLR; and (iii) for each percent imbalance that the magnitude of qt - qb is more positive than the f 2(~1) "positive" breakpo_int presented in the COLR, the ~ T Trip Setpoint shall be automatically reduced by the f 2(~1) "positive" slope presented in the COLR.

McGuire Units 1 and 2 3.3.1..:20 Amendment Nos. 184/166

McGuire Nuclear Station Technical Specification Bases LOES TS Bases are revised by section Page Number Revision Revision Date BASES (Revised per section)

Revision 87 8/15/07 ii Revision 87 8/15/07 iii Revision 87 8/15/07 B 2.1.1 Revision 51 01/14/04 B 2.1.2 Revision 109 9/20/10 B 3.0 Revision 81 3/29/07 B 3.1.1 Revision 115 3/29/11 B 3.1.2 Revision 115 3/29/11 B 3.1.3 Revision 136 5/14/15 B 3.1.4 Revision 115 3/29/11 B 3.1.5 Revision 115 3/29/11 B 3.1.6 Revision 115 3/29/11 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 115 3/29/11 B 3.2.1 Revision 115 3/29/11 B 3.2.2 Revision 115 3/29/11 B 3.2.3 Revision 115 3/29/11 B 3.2.4 Revision 115 3/29/11 B 3.3.1 Revision 141 4/8/16 B 3.3.2 Revision 138 12/9/15 B 3.3.3 Revision 122 10/25/12 B 3.3.4 Revision 115 3/29/11 B 3.3.5 Revision 115 3/29/11 B 3.3.6 Not Used - Revision 87 6/29/06 B 3.4.1 Revision 115 3/29/11 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 115 3/29/11 B 3.4.4 Revision 115 3/29/11 B 3.4.5 Revision 115 3/29/11 McGuire Units 1 and 2 Page 1 Revision 128

Page Number Amendment Revision Date B 3.4.6 Revision 115 3/29/11 B 3.4.7 Revision 115 3/29/11 B 3.4.8 Revision 115 3/29/11 B 3.4.9 Revision 115 3/29/11 B 3.4.10 Revision 102 8/17/09 B 3.4.11 Revision 115 3/29/11 B 3.4.12 Revision 134 1/8/15 B 3.4.13 Revision 126 5/1/13 83.4.14 Revision 115 3/29/11 B 3.4.15 Revision 115 3/29/11 B 3.4.16 Revision 121 8/5/09 B 3.4.17 Revision 115 3/29/11 B 3.4.18 Revision 86 6/25/07 B 3.5.1 Revision 115 3/29/11 B 3.5.2 Revision 139 2/3/16 B 3.5.3 Revision 57 4/29/04 B 3.5.4 Revision 122 10/25/12 B 3.5.5 Revision 115 3/29/11 B 3.6.1 Revision 53 2/17/04 B 3.6.2 Revision 115 3/29/11 B 3.6.3 Revision 115 3/29/11 B 3.6.4 Revision 115 3/29/11 B 3.6.5 Revision 115 3/29/11 B 3.6.6 Revision 138 12/9/15 B 3.6.7.

Not Used - Revision 63 4/4/05 B 3.6.8 Revision 115 3/29/11 B 3.6.9 Revision 131 4/14/14 B 3.6.10 Revision 120 4/26/12 B 3.6.11 Revision 138 12/9/15 B 3.6.12 Revision 138 12/9/15 B 3.6.13 Revision 138 12/9/15 B 3.6.14 Revision 138 12/9/15 B 3.6.15 Revision 125 10/19/12 B 3.6.16 Revision 130 4/7/14 McGuire Units 1 and 2 Page2 Revision 128

Page Number Amendment Revision Date 8 3.7.1 Revision 129 10/24/13 8 3.7.2 Revision 105 2/22/10 8 3.7.3 Revision 102 8/17/09 8 3.7.4 Revision 115 3/29/11 8 3.7.5 Revision 115 3/29/11 8 3.7.6 Revision 127 8/2/13 8 3.7.7 Revision 136 3/16/16 8 3.7.8 Revision 128 10/2/13 8 3.7.9 Revision 120 4/26/12 8 3.7.10 Revision 115 3/29/11 8 3.7.11 Revision 115 3/29/11 83.7.12 Revision 115 3/29/11 8 3.7.13 Revision 115 3/29/11 8 3.7.14 Revision 115 3/29/11 83.7.15 Revision 66 6/30/05 8 3.7.16 Revision 115 3/29/11 8 3.8.1 Revision 115 3/29/11 8 3.8.2 Revision 92 1/28/08 8 3.8.3 Revision 123 9/29/12 8 3.8.4 Revision 137 8/26/15 8 3.8.5 Revision 41 7/29/03 8 3.8.6 Revision 115 3/29/11 8 3.8.7 Revision 115 3/29/11 8 3.8.8 Revision 115 3/29/11 8 3.8.9 Revision 115 3/29/11 8 3.8.10.

Revision 115 3/29/11 8 3.9.1 Revision 115 3/29/11 8 3.9.2 Revision 115 3/29/11 8 3.9.3 Revision 142 4/8/16 8 3.9.4 Revision 115 3/29/11 8 3.9.5 Revision 115 3/29/11 8 3.9.6 Revision 115 3/29/11 8 3.9.7 Revision 115 3/29/11 McGuire Units 1 and 2 Page3 Revision 128

Duke Energy Date: 5l1Ql2QUi Distribution:

Document Transmittal #: JR-NUC-MC-QQ3Q43

1. Gardner, Troy R DOCUMENTTRANSMITTALFORM

Purpose:

lall

2. Mc Ginnis, Vickie L

3.

Mccree, Victor M Released By:

4.

OPS HUMAN PERFORMANCE -

Facility: MCGUIRE NUCLEAR STATIQN Puke Emmix

5. OPS TRNG MGR.

SUBJECT 13225 l::!i!9!:!'.i E!:n:y RQi!d

6. QATS-TECH SPEC ~.~,1 REV, OQ1 AMENDMENT 28~£2§2 DQ,Um!:nt Mi!ni!g!:m!:ot

7. RESIDENT NRC INSPECT MGQ2PM

8. SERV BLDG FILE ROOM -

l::luot!:CiXill!:, NC 28QZ8

9.

U S NUC REG WASHINGTON, DC MNSPCRM@duk!:-H!:cgx,,s;im

10. USNRC

11. WESTINGHOUSE ELECTRIC CO LLC Page 1of1 Document ID 1

2 3

4 5

6 7

8 9

10 11 LICN - MC - MNS-TS-3.3.1 - 001 - ISSUED FYIIE FYIIE FYIIE FYIIE R&AIE FYIIE R&AILP FYIIE R&AIE R&AIE R&AIE Remarks:

3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation RTS Instrumentation 3.3.1 LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1-1.

ACTIONS

~---------~~~~-----~-~~----~~~---~--~NOTE--------------~-------~~--------~~~---------~--~--

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Functions A.1 Entedhe Condition Immediately with one or more referenced in Table 3.3.1-1 required channels for the channel(s).

inoperable.

B.

One Manual Reactor B.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Trip channel inoperable.

OPERABLE status.

OR B.2 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months C.

One channel or train C.1 Restore channel or train to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable.

OPERABLE status.

OR C.2 Open reactor trip breakers 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months (RTBs).

(continued)

McGuire Units 1 and 2 3.3.1-1 Amendment Nos. 184/166

ACTIONS (continued)

CONDITION REQUIRED ACTION D.

One channel inoperable.

NOTE-----------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing and setpoint adjustment.

D.1.1

NOTE---------------

Only required to be performed when the Power Range Neutron Flux input to QPTR is inoperable Perform SR 3.2.4.2 D.1.2 Place channel in trip.

D.2 Be in MODE 3, RTS Instrumentation 3.3.1 COMPLETION TIME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from discovery of THERMAL POWER

> 75% RTP Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 78 hours (continued)

McGuire Units 1 and 2 3.3.1-2 Amendment Nos. 248/228 I

ACTIONS (continued)

CONDITION E.

One channel inoperable.

F.

THERMAL POWER

> P-6 and< P-10, one Intermediate Range Neutron Flux channel inoperable.

G.

THERMAL POWER

> P-6 and< P-10, two Intermediate Range Neutron Flux channels inoperable.

H.

THERMAL POWER

< P-6, one or two Intermediate Range Neutron Flux channels inoperable.

McGuire Units 1 and 2 REQUIRED ACTION

NOTE-----------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

E.1 Place channel in trip.

OR E.2 Be in MODE 3.

F.1 Reduce THERMAL POWER to < P-6.

OR F.2 Increase THERMAL POWER to> P-10.

.:--------NOTE--------------

Limited boron concentration changes associated with RCS inventory control or limited plant temperature changes are allowed.

G.1 Suspend operations involving positive reactivity additions.

AND G.2 Reduce THERMAL POWER to < P-6.

H.1 Restore channel(s) to OPERABLE status.

RTS Instrumentation 3.3.1 COMPLETION TIME 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 78 hours 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 hours Immediately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Prior to increasing THERMAL POWER to> P-6 (continued) 3.3.1-3 Amendment Nos. 248/228

ACTIONS (continued)

CONDITION I.

One Source Range Neutron Flux channel inoperable.

J.

Two Source Range Neutron Flux channels inoperable.

K.

One Source Range Neutron Flux channel inoperable.

L.

Required Source Range Neutron Flux channel inoperable.

McGuire Units 1 and 2 REQUIRED ACTION

NOTE--------:----

Limited boron concentration changes associated with RCS inventory control or limited plant temperature changes are allowed.

1.1 Suspend operations involving positive reactivity additions.

J.1 Open RTBs.

K.1 Restore channel to OPERABLE status.

OR K.2 Open RTBs.

NOTE---------------

Plant temperature chan.ges are allowed provided that SOM is maintained and Keff remains*<

0.9.9.

L.1 Suspend operations involving positive reactivity

additions~

AND L.2 Close unborated water source isolation valves.

AND L.3 Perform SR 3.1.1.1.

RTS Instrumentation 3.3.1 COMPLETION TIME Immediately Immediately 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 49 hours Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter (continued) 3.3.1-4 Amendm~nt Nos. 216/197

ACTIONS (continued)

CONDITION M.

One channel inoperable.

N.

One Reactor Coolant Flow - Low (Single Loop) channel inoperable.

McGuire Units 1 and 2 REQUIRED ACTION

NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

M.1 Place channel in trip.

OR M.2 Reduce THERMAL POWER to< P-7.

NOTE--------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

N.1 Place channel in trip.

OR N.2 Reduce THERMAL POWER to < P-8.

RTS Instrumentation 3.3.1 COMPLETION TIME 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 78 hours 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 76 hours (continued) 3.3.1-5 Amendment Nos. 250/230

ACTIONS (continued)

CONDITION

0.

One Turbine Trip - Low Fluid Oil Pressure channel inoperable.

P.

One or more Turbine Trip - Turbine Stop Valve Closure channels inoperable.

Q.

One train inoperable.

McGuire Units 1 and 2 REQUIRED ACTION

NOTE------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

0.1 Place channel in trip.

OR 0.2 Reduce THERMAL POWER to < P-8.

P.1 Place channel(s) in trip.

OR P.2 Reduce THERMAL POWER to < P-8.

N 0 TE-------------------

One train 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 provided the other train is OPERABLE.

Q.1 Restore train to OPERABLE status.

OR Q.2 Be in MODE 3.

RTS Instrumentation 3.3.1 COMPLETION TIME 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 76 hours 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 76 hours 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 30 hours (continued) 3.3.1-6 Amendment Nos. 248/228

ACTIONS (continued)

CONDITION R.

One RTB train inoperable.

S.

One or more channel(s) inoperable.

McGuire Units 1 and 2 REQUIRED ACTION

NOTE----------------

One train 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, provided the other train is OPERABLE.

R.1 Restore train to OPERABLE status.

OR R.2 Be in MODE3.

S.1 Verify interlock is in required state for existing unit conditions.

OR S.2 Be in MODE 3.

RTS Instrumentation 3.3.1 COMPLETION TIME 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 30 hours 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 7 hours (continued) 3.3.1-7 Amendment Nos. 248/228

ACTIONS (continued)

CONDITION T.

One or more channel(s)

T.1 inoperable.

OR T.2 U.

One trip mechanism U.1 inoperable for one RTB.

OR U.2 V.

Two RTS trains V.1 inoperable.

McGuire Units 1 and 2 REQUIRED ACTION Verify interlock is in required state for existing unit conditions.

Be in MODE 2.

Restore inoperable trip mechanism to OPERABLE status.

Be in MODE 3.

Enter LCO 3.0.3.

RTS Instrumentation 3.3.1 COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 7 hours 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 54 hours Immediately 3.3.1-8 Amendment Nos. 184/166

SURVEILLANCE REQUIREMENTS RTS Instrumentation 3.3.1

NOTE------------------------------------------------------

Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE SR 3.3.1.1 Perform CHANNEL CHECK.

SR 3.3.1.2

NOTES------------------------------

1.

Adjust NIS channel if absolute difference is > 2%

RTP.

2.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is~ 15% RTP.

Compare results of calorimetric heat balance calculation to Nuclear Instrumentation System (NIS) channel output.

s R 3. 3. 1. 3

NOTES-------------M--------------------

1.

Adjust NIS channel if absolute difference is~ 3%

AFD.

2.

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is~ 15% RTP.

Compare results of the incore detector measurem ents to NIS AFD.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control.

Proa ram In accordance with the Surveillance Frequency Control Program (continued)

McGuire Units 1 and 2 3.3.1-9 Amendment Nos. 261/241

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.1.4

NOTES-------------------------

This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in.

service.

Perform TADOT.

SR 3.3.1.5 Perform ACTUATION LOGIC TEST.

SR 3. 3. 1. 6

NOTES--------------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is~ 75% RTP.

Calibrate excore channels to agree with incore detector measurements.

SR 3.3.1. 7

NOTES----------------------------------

Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entry into MODE 3.

Perform COT.

RTS Instrumentation 3.3.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

McGuire Units 1 and 2 3.3.1-10 Amendment Nos. 261/241

SURVEILLANCE REQUIREMENTS continued SURVEILLANCE SR 3.3.1.8

NOTES-------------------------------

This Surveillance shall include verification that interlocks P-6 (for the Intermediate Range channels) and P-10 (for the Power Range channels) are in their required state for existing unit conditions.

Perform COT.

RTS Instrumentation 3.3.1 FREQUENCY

NOTE------

Only required when not performed within the Frequency specified in the Surveillance Frequency Control Program or previous 184 days

Prior to reactor startup AND Four hours after reducing power below P-1 0 for power and intermediate range instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND In accordance with the Surveillance Frequency Control Pro ram (continued)

McGuire Units 1 and 2 3.3.1-11 Amendment Nos. 261/241

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3. 3. 1. 9

NOTES----------------------------------

Verification of setpoint is not required.

Perform TADOT.

SR 3.3.1.10 ------:---------------------NOTES---------------------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

Perform CHANNEL CALIBRATION.

NOTES---------------------------.,------

1.

Neutron detectors are excluded from CHANNEL CALIBRATION.

2.

Power Range Neutron Flux high voltage detector saturation curve verification is not required to be performed prior to entry into MODE 1 or 2.

Perform CHANNEL CALIBRATION.

SR 3.3.1.12 Perform CHANNEL CALIBRATION.

RTS Instrumentation 3.3.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

McGuire Units 1 and 2 3.3.1-12 Amendment Nos. 283/262

SURVEILLANCE SR 3.3.1.13 Perform COT.

SR 3.3.1.14 ------------------------------NOTES-----------------------------

Verification of setpoint is not required.

Perform TADOT.

SR 3.3.1.15 -----------------------------NOTES----------------------------------

Verification of setpoint is not required.

Perform TADOT.

SR 3.3.1.16 -----------------------------NOTES-----------------------------

Neutron detectors are excluded from response time testing.

Verify RTS RESPONSE TIME is within limits.

SR 3.3.1.17 Verify RTS RESPONSE TIME for RTDs is within limits.

RTS Instrumentation 3.3.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance

Frequency Control Program

---:---NOTE-------

Only required when not performed within previous 31 days Prior to reactor startup In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program McGuire Units 1 and 2 3.3.1-13 Amendment Nos. 261/241

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of7)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

1.

Manual Reactor Trip 1,2 2

B SR 3.3.1.14 NA NA 3(a), 4(a), 5(a) 2 c

SR 3.3.1.14 NA NA

2.

Power Range Neutron Flux

a.

High 1,2 4

D SR 3.3.1.1

.:=_ 110% RTP 109% RTP SR 3.3.1.2 SR3.3.1.7 SR 3.3.1.11 SR 3.3.1.16

b.

Low 1(b),2 4

E SR 3.3.1.1

.:=_26% RTP 25% RTP SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16

3.

Power Range Neutron Flux Rate High Positive Rate 1,2 4

D SR 3.3.1.7

.:=_5.5% RTP 5% RTP SR 3.3.1.11 with time with time constant constant

~2 sec

4.

Intermediate Range 1(b), 2(c) 2 F,G SR 3.3.1.1

_::38% RTP 25% RTP Neutron Flux SR 3.3.1.aUJ(k)

SR 3.3.1.11 U)(k) 2(d) 2 H

_::38% RTP 25% RTP SR 3.3.1.aUJ(k)

SR 3.3.1.11 U)(k)

(continued)

(a)

With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

(b)

Below the P-1 O (Power Range Neutron Flux) interlocks.

(c)

Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(d)

Below the P-6 (Intermediate Range Neutron Flux) interlocks.

U)

If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(k)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and the as-left tolerances are specified in the UFSAR.

McGuire Units 1 and 2 3.3.1-14 Amendment Nos. 283/262

APPLICABLE MODES OR OTHER SPECIFIED FUNCTION CONDITIONS

5.

Source Range 2(d)

Neutron Flux 3(a), 4(a), 5(a)

Table 3.3.1-1 (page 2 of7)

Reactor Trip System Instrumentation REQUIRED CHANNELS CONDITIONS 2

l,J 2

J,K L

SURVEILLANCE REQUIREMENTS SR3.3.1.1 SR 3.3.1.80)(k)

SR 3.3.1.11 O)(k)

SR 3.3.1.1 SR 3.3.1.70)(k)

SR 3.3.1.11 O)(k)

SR 3.3.1.1 SR 3.3.1.1.1 RTS Instrumentation 3.3.1 ALLOWABLE VALUE

~ 1.44 E5 cps

~ 1.44 E5 cps NIA NOMINAL TRIP SETPOINT 1.0 E5 cps 1.0 E5 cps N/A

6.

Overtemperature 1ff 1,2 4

E SR3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.12 SR3.3.1.16 SR 3.3.1.17 Refer to Note 1 (Page 3.3.1-18)

Refer to Note 1 (Page 3.3.1-18)

7.

Overpower Ll. T 1,2 4

E SR 3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR3.3.1.12 SR3.3.1.16 SR3.3.1.17 Refer to Note 2 (Page 3.3.1-19)

Refer to Note 2 (Page 3.3.1-19)

8.

Pressurizer Pressure (a)

(d)

(e)

(f)

0)

(k)

a.

Low 4

b.

High 1,2 4

M E

SR 3.3.1.1 SR 3.3.1.7 SR3.3.1.10 SR 3.3.1.16 SR 3.3.1.1 SR 3.3.1.7 SR3.3.1.10 SR 3.3.1.16 With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

Below the P-6 (Intermediate Range Neutron Flux) interlocks.

.:: 1935 psig

~2395 psig With the RTBs open. In this condition, source range Function does not provide reactor trip but does provide indication.

Above the P-7 (Low Power Reactor Trips Block) interlock.

1945 psig 2385 psig (continued)

If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and the as-left tolerances are specified in the UFSAR.

McGuire Units 1 and 2 3.3.1-15 Amendment Nos. 283/262

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of7)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

9.

Pressurizer Water 1 (f) 3 M

~93%

92%

Level-High SR 3.3.1.7 SR 3.3.1.10

10. Reactor Coolant Flow-Low

a.

Single Loop 1(g) 3 per loop N

~87%

88%

SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16

b.

Two Loops 1(h) 3 per loop M

~87%

88%

SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16

11. Undervoltage RCPs 1 (f) 1 per bus M

~ 5016 v 5082 v SR 3.3.1.10 SR 3.3.1.16

12. Underfrequency 1 (f) 1 per bus M

~ 55.9 Hz 56.4 Hz RCPs SR 3.3.1.10 SR 3.3.1.16

13. Steam Generator 1,2 4 perSG E

SR3.3.1.1

~ 15%

16.7%

(SG) Water Level -

SR 3.3.1.7 Low Low SR3.3.1.10 SR3.3.1.16

14. Turbine Trip

a.

Low Fluid Oil 1(g) 3 0

~42 psig 45 psig Pressure SR 3.3.1.15

b.

Turbine Stop 1(g) 4 p

~ 1% open

~ 1% open Valve Closure SR 3.3.1.15

15. Safety Injection (SI) 1,2 2 trains Q

SR 3.3.1.5 NA NA Input from SR3.3.1.14 Engineered Safety Feature Actuation System (ESFAS)

(continued)

(f)

Above the P-7 (Low Power Reactor Trips Block) interlock.

(g)

Above the P-8 (Power Range Neutron Flux) interlock.

(h)

Above the P-7 (Low Power Reactor Trips Block) interlock and below the P-8 (Power Range Neutron Flux) interlock.

McGuire Units 1 and 2 3.3.1-16 Amendment Nos. 257/237

RTS Instrumentation 3.3.1 Table 3.3.1-1(page4 of7)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

16. Reactor Trip System Interlocks

a.

Intermediate 2(d) 2 s