ML16139A461

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Technical Specification 3.3.1, Rev. 001, Amendments 283 and 262
ML16139A461
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 05/10/2016
From:
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TR-NUC-MC-003043
Download: ML16139A461 (24)
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Text

Distribution:

1. Gardner, Troy R
2. Mc Ginnis, Vickie L Duke Energy DOCUMENTTRANSMITTALFORM Date: 5l1Ql2QUi Document Transmittal #: JR-NUC-MC-QQ3Q43

Purpose:

lall Released By:

3. Mccree, Victor M Facility: MCGUIRE NUCLEAR STATIQN Puke Emmix
4. OPS HUMAN PERFORMANCE -

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

5. OPS TRNG MGR.

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

6. QATS-MGQ2PM
7. RESIDENT NRC INSPECT
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:

RTS Instrumentation

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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Trip channel inoperable. OPERABLE status.

OR B.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> C. One channel or train C.1 Restore channel or train to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable. OPERABLE status.

OR C.2 Open reactor trip breakers 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />

' (RTBs).

(continued)

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

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 3.3.1 D. One channel inoperable. ----------------NOTE-----------------

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from discovery of THERMAL POWER

> 75% RTP

  • Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter D.1.2 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> D.2 Be in MODE 3, 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> I (continued)
  • McGuire Units 1 and 2 3.3.1-2 Amendment Nos. 248/228

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 3.3.1 E. One channel inoperable. ---------------NOTE-----------------

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

E.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR E.2 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> F. THERMAL POWER F.1 Reduce THERMAL 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

> P-6 and< P-10, one POWER to < P-6.

Intermediate Range Neutron Flux channel OR inoperable.

F.2 Increase THERMAL 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> POWER to> P-10.

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

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

G. THERMAL POWER G.1 Suspend operations Immediately

> P-6 and< P-10, two involving positive reactivity Intermediate Range additions.

Neutron Flux channels inoperable. AND G.2 Reduce THERMAL 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> POWER to < P-6.

H. THERMAL POWER H.1 Restore channel(s) to Prior to increasing

< P-6, one or two OPERABLE status. THERMAL POWER Intermediate Range to> P-6 Neutron Flux channels inoperable .

  • McGuire Units 1 and 2 3.3.1-3 (continued)

Amendment Nos. 248/228

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION

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

COMPLETION TIME 3.3.1 Limited boron concentration changes associated with RCS inventory control or limited plant temperature changes are allowed.

I. One Source Range 1.1 Suspend operations Immediately Neutron Flux channel involving positive reactivity inoperable. additions.

J. Two Source Range J.1 Open RTBs. Immediately Neutron Flux channels inoperable.

K. One Source Range K.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Neutron Flux channel OPERABLE status.

inoperable.

OR K.2 Open RTBs. 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />

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

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

0.9.9.

L. Required Source Range L.1 Suspend operations Immediately Neutron Flux channel involving positive reactivity inoperable.

  • additions~

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

AND L.3 Perform SR 3.1.1.1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter (continued)

McGuire Units 1 and 2 3.3.1-4 Amendm~nt Nos. 216/197

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 3.3.1 M. One channel inoperable. ------------------NOTE-------------------

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

M.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR M.2 Reduce THERMAL 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> POWER to< P-7.

N. One Reactor Coolant -----------------NOTE--------------------

Flow - Low (Single One channel may be bypassed for Loop) channel up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance inoperable. testing.

  • N.1 OR N.2 Place channel in trip.

Reduce THERMAL 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 76 hours POWER to < P-8.

(continued)

  • McGuire Units 1 and 2 3.3.1-5 Amendment Nos. 250/230

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 3.3.1

0. One Turbine Trip - Low -----------------NOTE------------------

Fluid Oil Pressure One channel may be bypassed for channel inoperable. up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

0.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR 0.2 Reduce THERMAL 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> POWER to < P-8.

P. One or more Turbine P.1 Place channel(s) in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Trip - Turbine Stop Valve Closure channels OR inoperable.

P.2 Reduce THERMAL 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> POWER to < P-8.

Q. One train inoperable. ------------------N 0 TE-------------------

  • One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing provided the other train is OPERABLE.

Q.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

OR Q.2 Be in MODE 3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> (continued)

  • McGuire Units 1 and 2 3.3.1-6 Amendment Nos. 248/228

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 3.3.1 R. One RTB train ----------------NOTE----------------

inoperable. One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing, provided the other train is OPERABLE.

R.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

OR R.2 Be in MODE3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />

S.1 Verify interlock is in required state for existing 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unit conditions.

OR S.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (continued)

  • McGuire Units 1 and 2 3.3.1-7 Amendment Nos. 248/228

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION 3.3.1 COMPLETION TIME T. One or more channel(s) T.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. required state for existing unit conditions.

OR T.2 Be in MODE 2. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> U. One trip mechanism U.1 Restore inoperable trip 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable for one RTB. mechanism to OPERABLE status.

OR U.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> V. Two RTS trains V.1 Enter LCO 3.0.3. Immediately inoperable .

  • McGuire Units 1 and 2 3.3.1-8 Amendment Nos. 184/166

RTS Instrumentation

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

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

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER is~ 15% RTP.

Compare results of calorimetric heat balance calculation In accordance with

  • sR 3. 3. 1. 3 to Nuclear Instrumentation System (NIS) channel output.

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

1. Adjust NIS channel if absolute difference is~ 3%

the Surveillance Frequency Control .

Proa ram AFD.

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

Compare results of the incore detector measurem In accordance with ents to NIS AFD. the Surveillance Frequency Control Program (continued)

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

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 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. In accordance with the Surveillance Frequency Control Program SR 3.3.1.5 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3. 3. 1.6 ------------------------------NOTES--------------------------------

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

Calibrate excore channels to agree with incore detector In accordance with measurements. the Surveillance Frequency Control Program 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into MODE 3.

Perform COT. In accordance with the Surveillance Frequency Control Program (continued)

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

RTS Instrumentation

  • SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY 3.3.1 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. ---------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

RTS Instrumentation

  • SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 3.3.1 SR 3. 3. 1.9 ---------------------------NOTES----------------------------------

Verification of setpoint is not required.

Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.10 ------:---------------------NOTES---------------------------------

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

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program

  • SR 3.3.1.11 ----------------------------NOTES---------------------------.,------

1.

2.

Neutron detectors are excluded from CHANNEL CALIBRATION.

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. In accordance with the Surveillance Frequency Control Program SR 3.3.1.12 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program (continued)

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

RTS Instrumentation

SURVEILLANCE FREQUENCY 3.3.1 In accordance with the Surveillance Frequency Control Program SR 3.3.1.14 ------------------------------NOTES-----------------------------

Verification of setpoint is not required.

Perform TADOT. In accordance with the Surveillance

  • Frequency Control Program SR 3.3.1.15 -----------------------------NOTES---------------------------------- ---:---NOTE-------

Verification of setpoint is not required. Only required when not performed within previous 31 days

  • Perform TADOT.

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

Neutron detectors are excluded from response time Prior to reactor startup testing.

Verify RTS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SR 3.3.1.17 Verify RTS RESPONSE TIME for RTDs is within limits. In accordance with the Surveillance Frequency Control Program

  • McGuire Units 1 and 2 3.3.1-13 Amendment Nos. 261/241

RTS Instrumentation

  • APPLICABLE Table 3.3.1-1 (page 1 of7)

Reactor Trip System Instrumentation 3.3.1 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 ~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 SR 3.3.1.1 _::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

RTS Instrumentation

  • APPLICABLE MODES OR OTHER Table 3.3.1-1 (page 2 of7)

Reactor Trip System Instrumentation 3.3.1 NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

5. Source Range 2(d) 2 l,J SR3.3.1.1 1.0 E5 cps

~ 1.44 E5 cps Neutron Flux SR 3.3.1.80)(k)

SR 3.3.1.11 O)(k) 3(a), 4(a), 5(a) 2 J,K SR 3.3.1.1 ~ 1.44 E5 cps 1.0 E5 cps SR 3.3.1.70)(k)

SR 3.3.1.11 O)(k)

L SR 3.3.1.1 NIA N/A SR 3.3.1.1.1

6. Overtemperature 1ff 1,2 4 E SR3.3.1.1 Refer to Note 1 Refer to SR 3.3.1.3 (Page Note 1 (Page SR 3.3.1.6 3.3.1-18) 3.3.1-18)

SR 3.3.1.7 SR 3.3.1.12 SR3.3.1.16 SR 3.3.1.17

7. Overpower Ll.T 1,2 4 E SR 3.3.1.1 Refer to Note 2 Refer to SR 3.3.1.3 (Page Note 2 (Page SR 3.3.1.6 3.3.1-19) 3.3.1-19)

SR 3.3.1.7 SR3.3.1.12 SR3.3.1.16 SR3.3.1.17

8. Pressurizer Pressure
a. Low 4 M SR 3.3.1.1 .:: 1935 psig 1945 psig SR 3.3.1.7 SR3.3.1.10 SR 3.3.1.16
b. High 1,2 4 E SR 3.3.1.1 ~2395 psig 2385 psig SR 3.3.1.7 SR3.3.1.10 SR 3.3.1.16 (continued)

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

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

(e) With the RTBs open. In this condition, source range Function does not provide reactor trip but does provide indication.

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

0) 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 3.3.1-15 Amendment Nos. 283/262

RTS Instrumentation

  • APPLICABLE MODES OR OTHER Table 3.3.1-1 (page 3 of7)

Reactor Trip System Instrumentation 3.3.1 NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

9. Pressurizer Water 1 (f) 3 M SR 3.3.1.1 ~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 SR 3.3.1.1 ~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 SR 3.3.1.1 ~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 SR 3.3.1.9 ~ 5016 v 5082 v SR 3.3.1.10 SR 3.3.1.16
12. Underfrequency 1 (f) 1 per bus M SR 3.3.1.9 ~ 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 SR 3.3.1.10 ~42 psig 45 psig Pressure SR 3.3.1.15
b. Turbine Stop 1(g) 4 p SR 3.3.1.10 ~ 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

  • APPLICABLE MODES OR OTHER Table 3.3.1-1(page4 of7)

Reactor Trip System Instrumentation 3.3.1 NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

16. Reactor Trip System Interlocks
a. Intermediate 2(d) 2 s SR 3.3.1.11 ~ 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 Mechanisms 3(a), 4(a), 5(a) 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

RTS Instrumentation

  • Note 1: Overtemperature L\T Table 3.3.1-1 (page 5 of 7)

Reactor Trip System Instrumentation 3.3.1 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.0 {K1 - K2 (1 + r 4 s)

. (1+T2S) 1+T3S - (1+Ts s)

[r . r]1 (1+Ts s)

- + K3 (P - P') - f1 (M)}

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 = Overtemperature L\T reactor NOMINAL TRIP SETPOINT, as presented in the COLR, K2 = Overtemperature L\T reactor trip heatup setpoint penalty coefficient, as presented in the COLR, K3 = Overtemperature L\T reactor trip depressurization setpoint penalty coefficient, as presented in the COLR,

't1,'t2 = Time constants utilized in the lead:-lag controller for L\T, as presented in the COLR,

't3 = Time constants utilized in the lag compensator for L\T, as presented in the COLR,

't4, 'ts Time constants utilized in the lead-lag controller for T avg. as presented in the COLR,

'ts = Time constants utilized in the measured T avg lag compensator, as presented in the COLR, and, f 1(L\I) = 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" f 1(L\I) breakpoints as

=

presented in the COLR; f1(L\I) 0, where qt and qb are percent RATED 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

RTS Instrumentation

  • (ii)

Table 3.3.1-1 (page 6 of 7)

Reactor Trip System Instrumentation for each percent imbalance that the magnitude of qt - qb is more 3.3.1 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.

1 ti T < + T 1 s) (

1 (1 + Tz s 1 + T3 s

) :::; ti To {K4 - Ks 1 + T7s s ( 1 +Ta1 s ) T - Ka T

7

[r 1 1 +Ta s

- r*]- f2 (ti/)}

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.

~ = Overpower ~T reactor NOMINAL TRIP SETPOINT as presented in the COLR, Ks = The value specified in the COLR for increasing average temperature and the value specified in the COLR for decreasing average temperature, Ks = 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",

't1, 't2 = Time constants utilized in the lead-lag controller for ~T, as presented in the COLR,

't3 = Time constants utilized in the lag compensator for~T, as presented in the COLR,

'ts = Time constants utilized in the measured Tavg lag compensator, as presented in the COLR,

't7 = Time constant utilized in the rate-lag controller for T avg, as presented in the COLR, and f2(~1) = 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:

  • McGuire Units 1 and 2 3.3.1-19 (continued)

Amendment Nos. 219 / 201

RTS Instrumentation 3,3.1 Table 3.3.1-1(page7of7)

Reactor Trip System Instrumentation (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 RATED 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 f2(~1) "negative" breakpoint presented in the COLR, the ~T Trip Setpoint shall be automatically reduced by the f2(~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 B 3.1.7 B 3.1.8 B 3.2.1 Revision 115 Revision 58 Revision 115 Revision 115 3/29/11 06/23/04 3/29/11 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 B 3.4.4 B 3.4.5 Revision 115 Revision 115 Revision 115 3/29/11 3/29/11 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 B 3.4.8 B 3.4.9 B 3.4.10 Revision 115 Revision 115 Revision 115 Revision 102 3/29/11 3/29/11 3/29/11 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 B 3.5.5 B 3.6.1 B 3.6.2 Revision 122 Revision 115 Revision 53 Revision 115 10/25/12 3/29/11 2/17/04 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 B 3.6.15 B 3.6.16 Revision 138 Revision 125 Revision 130 12/9/15 10/19/12 4/7/14 McGuire Units 1 and 2 Page2 Revision 128

Page Number Amendment Revision Date Revision 129 10/24/13 8 3.7.1 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 8 3.8.2 8 3.8.3 8 3.8.4 Revision 115 Revision 92 Revision 123 Revision 137 3/29/11 1/28/08 9/29/12 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

Distribution:

1. Gardner, Troy R
2. Mc Ginnis, Vickie L Duke Energy DOCUMENTTRANSMITTALFORM Date: 5l1Ql2QUi Document Transmittal #: JR-NUC-MC-QQ3Q43

Purpose:

lall Released By:

3. Mccree, Victor M Facility: MCGUIRE NUCLEAR STATIQN Puke Emmix
4. OPS HUMAN PERFORMANCE -

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

5. OPS TRNG MGR.

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

6. QATS-MGQ2PM
7. RESIDENT NRC INSPECT
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:

RTS Instrumentation

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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Trip channel inoperable. OPERABLE status.

OR B.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> C. One channel or train C.1 Restore channel or train to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable. OPERABLE status.

OR C.2 Open reactor trip breakers 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />

' (RTBs).

(continued)

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

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 3.3.1 D. One channel inoperable. ----------------NOTE-----------------

One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from discovery of THERMAL POWER

> 75% RTP

  • Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter D.1.2 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> D.2 Be in MODE 3, 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> I (continued)
  • McGuire Units 1 and 2 3.3.1-2 Amendment Nos. 248/228

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 3.3.1 E. One channel inoperable. ---------------NOTE-----------------

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

E.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR E.2 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> F. THERMAL POWER F.1 Reduce THERMAL 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

> P-6 and< P-10, one POWER to < P-6.

Intermediate Range Neutron Flux channel OR inoperable.

F.2 Increase THERMAL 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> POWER to> P-10.

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

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

G. THERMAL POWER G.1 Suspend operations Immediately

> P-6 and< P-10, two involving positive reactivity Intermediate Range additions.

Neutron Flux channels inoperable. AND G.2 Reduce THERMAL 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> POWER to < P-6.

H. THERMAL POWER H.1 Restore channel(s) to Prior to increasing

< P-6, one or two OPERABLE status. THERMAL POWER Intermediate Range to> P-6 Neutron Flux channels inoperable .

  • McGuire Units 1 and 2 3.3.1-3 (continued)

Amendment Nos. 248/228

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION

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

COMPLETION TIME 3.3.1 Limited boron concentration changes associated with RCS inventory control or limited plant temperature changes are allowed.

I. One Source Range 1.1 Suspend operations Immediately Neutron Flux channel involving positive reactivity inoperable. additions.

J. Two Source Range J.1 Open RTBs. Immediately Neutron Flux channels inoperable.

K. One Source Range K.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Neutron Flux channel OPERABLE status.

inoperable.

OR K.2 Open RTBs. 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />

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

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

0.9.9.

L. Required Source Range L.1 Suspend operations Immediately Neutron Flux channel involving positive reactivity inoperable.

  • additions~

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

AND L.3 Perform SR 3.1.1.1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter (continued)

McGuire Units 1 and 2 3.3.1-4 Amendm~nt Nos. 216/197

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 3.3.1 M. One channel inoperable. ------------------NOTE-------------------

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

M.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR M.2 Reduce THERMAL 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> POWER to< P-7.

N. One Reactor Coolant -----------------NOTE--------------------

Flow - Low (Single One channel may be bypassed for Loop) channel up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance inoperable. testing.

  • N.1 OR N.2 Place channel in trip.

Reduce THERMAL 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 76 hours POWER to < P-8.

(continued)

  • McGuire Units 1 and 2 3.3.1-5 Amendment Nos. 250/230

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 3.3.1

0. One Turbine Trip - Low -----------------NOTE------------------

Fluid Oil Pressure One channel may be bypassed for channel inoperable. up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.

0.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR 0.2 Reduce THERMAL 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> POWER to < P-8.

P. One or more Turbine P.1 Place channel(s) in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Trip - Turbine Stop Valve Closure channels OR inoperable.

P.2 Reduce THERMAL 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> POWER to < P-8.

Q. One train inoperable. ------------------N 0 TE-------------------

  • One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing provided the other train is OPERABLE.

Q.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

OR Q.2 Be in MODE 3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> (continued)

  • McGuire Units 1 and 2 3.3.1-6 Amendment Nos. 248/228

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 3.3.1 R. One RTB train ----------------NOTE----------------

inoperable. One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing, provided the other train is OPERABLE.

R.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

OR R.2 Be in MODE3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />

S.1 Verify interlock is in required state for existing 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unit conditions.

OR S.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (continued)

  • McGuire Units 1 and 2 3.3.1-7 Amendment Nos. 248/228

RTS Instrumentation

  • ACTIONS (continued)

CONDITION REQUIRED ACTION 3.3.1 COMPLETION TIME T. One or more channel(s) T.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. required state for existing unit conditions.

OR T.2 Be in MODE 2. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> U. One trip mechanism U.1 Restore inoperable trip 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable for one RTB. mechanism to OPERABLE status.

OR U.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> V. Two RTS trains V.1 Enter LCO 3.0.3. Immediately inoperable .

  • McGuire Units 1 and 2 3.3.1-8 Amendment Nos. 184/166

RTS Instrumentation

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

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

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER is~ 15% RTP.

Compare results of calorimetric heat balance calculation In accordance with

  • sR 3. 3. 1. 3 to Nuclear Instrumentation System (NIS) channel output.

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

1. Adjust NIS channel if absolute difference is~ 3%

the Surveillance Frequency Control .

Proa ram AFD.

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

Compare results of the incore detector measurem In accordance with ents to NIS AFD. the Surveillance Frequency Control Program (continued)

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

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 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. In accordance with the Surveillance Frequency Control Program SR 3.3.1.5 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3. 3. 1.6 ------------------------------NOTES--------------------------------

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

Calibrate excore channels to agree with incore detector In accordance with measurements. the Surveillance Frequency Control Program 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into MODE 3.

Perform COT. In accordance with the Surveillance Frequency Control Program (continued)

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

RTS Instrumentation

  • SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY 3.3.1 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. ---------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

RTS Instrumentation

  • SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 3.3.1 SR 3. 3. 1.9 ---------------------------NOTES----------------------------------

Verification of setpoint is not required.

Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.10 ------:---------------------NOTES---------------------------------

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

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program

  • SR 3.3.1.11 ----------------------------NOTES---------------------------.,------

1.

2.

Neutron detectors are excluded from CHANNEL CALIBRATION.

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. In accordance with the Surveillance Frequency Control Program SR 3.3.1.12 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program (continued)

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

RTS Instrumentation

SURVEILLANCE FREQUENCY 3.3.1 In accordance with the Surveillance Frequency Control Program SR 3.3.1.14 ------------------------------NOTES-----------------------------

Verification of setpoint is not required.

Perform TADOT. In accordance with the Surveillance

  • Frequency Control Program SR 3.3.1.15 -----------------------------NOTES---------------------------------- ---:---NOTE-------

Verification of setpoint is not required. Only required when not performed within previous 31 days

  • Perform TADOT.

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

Neutron detectors are excluded from response time Prior to reactor startup testing.

Verify RTS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SR 3.3.1.17 Verify RTS RESPONSE TIME for RTDs is within limits. In accordance with the Surveillance Frequency Control Program

  • McGuire Units 1 and 2 3.3.1-13 Amendment Nos. 261/241

RTS Instrumentation

  • APPLICABLE Table 3.3.1-1 (page 1 of7)

Reactor Trip System Instrumentation 3.3.1 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 ~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 SR 3.3.1.1 _::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

RTS Instrumentation

  • APPLICABLE MODES OR OTHER Table 3.3.1-1 (page 2 of7)

Reactor Trip System Instrumentation 3.3.1 NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

5. Source Range 2(d) 2 l,J SR3.3.1.1 1.0 E5 cps

~ 1.44 E5 cps Neutron Flux SR 3.3.1.80)(k)

SR 3.3.1.11 O)(k) 3(a), 4(a), 5(a) 2 J,K SR 3.3.1.1 ~ 1.44 E5 cps 1.0 E5 cps SR 3.3.1.70)(k)

SR 3.3.1.11 O)(k)

L SR 3.3.1.1 NIA N/A SR 3.3.1.1.1

6. Overtemperature 1ff 1,2 4 E SR3.3.1.1 Refer to Note 1 Refer to SR 3.3.1.3 (Page Note 1 (Page SR 3.3.1.6 3.3.1-18) 3.3.1-18)

SR 3.3.1.7 SR 3.3.1.12 SR3.3.1.16 SR 3.3.1.17

7. Overpower Ll.T 1,2 4 E SR 3.3.1.1 Refer to Note 2 Refer to SR 3.3.1.3 (Page Note 2 (Page SR 3.3.1.6 3.3.1-19) 3.3.1-19)

SR 3.3.1.7 SR3.3.1.12 SR3.3.1.16 SR3.3.1.17

8. Pressurizer Pressure
a. Low 4 M SR 3.3.1.1 .:: 1935 psig 1945 psig SR 3.3.1.7 SR3.3.1.10 SR 3.3.1.16
b. High 1,2 4 E SR 3.3.1.1 ~2395 psig 2385 psig SR 3.3.1.7 SR3.3.1.10 SR 3.3.1.16 (continued)

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

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

(e) With the RTBs open. In this condition, source range Function does not provide reactor trip but does provide indication.

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

0) 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 3.3.1-15 Amendment Nos. 283/262

RTS Instrumentation

  • APPLICABLE MODES OR OTHER Table 3.3.1-1 (page 3 of7)

Reactor Trip System Instrumentation 3.3.1 NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

9. Pressurizer Water 1 (f) 3 M SR 3.3.1.1 ~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 SR 3.3.1.1 ~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 SR 3.3.1.1 ~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 SR 3.3.1.9 ~ 5016 v 5082 v SR 3.3.1.10 SR 3.3.1.16
12. Underfrequency 1 (f) 1 per bus M SR 3.3.1.9 ~ 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 SR 3.3.1.10 ~42 psig 45 psig Pressure SR 3.3.1.15
b. Turbine Stop 1(g) 4 p SR 3.3.1.10 ~ 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

  • APPLICABLE MODES OR OTHER Table 3.3.1-1(page4 of7)

Reactor Trip System Instrumentation 3.3.1 NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

16. Reactor Trip System Interlocks
a. Intermediate 2(d) 2 s SR 3.3.1.11 ~ 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 Mechanisms 3(a), 4(a), 5(a) 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

RTS Instrumentation

  • Note 1: Overtemperature L\T Table 3.3.1-1 (page 5 of 7)

Reactor Trip System Instrumentation 3.3.1 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.0 {K1 - K2 (1 + r 4 s)

. (1+T2S) 1+T3S - (1+Ts s)

[r . r]1 (1+Ts s)

- + K3 (P - P') - f1 (M)}

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 = Overtemperature L\T reactor NOMINAL TRIP SETPOINT, as presented in the COLR, K2 = Overtemperature L\T reactor trip heatup setpoint penalty coefficient, as presented in the COLR, K3 = Overtemperature L\T reactor trip depressurization setpoint penalty coefficient, as presented in the COLR,

't1,'t2 = Time constants utilized in the lead:-lag controller for L\T, as presented in the COLR,

't3 = Time constants utilized in the lag compensator for L\T, as presented in the COLR,

't4, 'ts Time constants utilized in the lead-lag controller for T avg. as presented in the COLR,

'ts = Time constants utilized in the measured T avg lag compensator, as presented in the COLR, and, f 1(L\I) = 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" f 1(L\I) breakpoints as

=

presented in the COLR; f1(L\I) 0, where qt and qb are percent RATED 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

RTS Instrumentation

  • (ii)

Table 3.3.1-1 (page 6 of 7)

Reactor Trip System Instrumentation for each percent imbalance that the magnitude of qt - qb is more 3.3.1 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.

1 ti T < + T 1 s) (

1 (1 + Tz s 1 + T3 s

) :::; ti To {K4 - Ks 1 + T7s s ( 1 +Ta1 s ) T - Ka T

7

[r 1 1 +Ta s

- r*]- f2 (ti/)}

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.

~ = Overpower ~T reactor NOMINAL TRIP SETPOINT as presented in the COLR, Ks = The value specified in the COLR for increasing average temperature and the value specified in the COLR for decreasing average temperature, Ks = 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",

't1, 't2 = Time constants utilized in the lead-lag controller for ~T, as presented in the COLR,

't3 = Time constants utilized in the lag compensator for~T, as presented in the COLR,

'ts = Time constants utilized in the measured Tavg lag compensator, as presented in the COLR,

't7 = Time constant utilized in the rate-lag controller for T avg, as presented in the COLR, and f2(~1) = 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:

  • McGuire Units 1 and 2 3.3.1-19 (continued)

Amendment Nos. 219 / 201

RTS Instrumentation 3,3.1 Table 3.3.1-1(page7of7)

Reactor Trip System Instrumentation (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 RATED 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 f2(~1) "negative" breakpoint presented in the COLR, the ~T Trip Setpoint shall be automatically reduced by the f2(~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 B 3.1.7 B 3.1.8 B 3.2.1 Revision 115 Revision 58 Revision 115 Revision 115 3/29/11 06/23/04 3/29/11 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 B 3.4.4 B 3.4.5 Revision 115 Revision 115 Revision 115 3/29/11 3/29/11 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 B 3.4.8 B 3.4.9 B 3.4.10 Revision 115 Revision 115 Revision 115 Revision 102 3/29/11 3/29/11 3/29/11 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 B 3.5.5 B 3.6.1 B 3.6.2 Revision 122 Revision 115 Revision 53 Revision 115 10/25/12 3/29/11 2/17/04 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 B 3.6.15 B 3.6.16 Revision 138 Revision 125 Revision 130 12/9/15 10/19/12 4/7/14 McGuire Units 1 and 2 Page2 Revision 128

Page Number Amendment Revision Date Revision 129 10/24/13 8 3.7.1 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 8 3.8.2 8 3.8.3 8 3.8.4 Revision 115 Revision 92 Revision 123 Revision 137 3/29/11 1/28/08 9/29/12 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
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