Text

Supplemental Information to License Amendment Request, Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System Instrumentation Test Times
	ML14234A097
Person / Time
Site:	Millstone
Issue date:	08/14/2014
From:	Mark D. Sartain; Dominion, Dominion Nuclear Connecticut
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	14-107A, WCAP-14333, WCAP-15376 WCAP-14333, Rev. 1, WCAP-15376, Rev. 1
	Download: ML14234A097 (28)
	v • d • e

Dominion Nuclear Connecticut, Inc.

Rope Ferry Rd., Waterford, CT 06385 Domilinion Mailing Address: P.O. Box 128 Waterford, CT 06385 donicoi AUG 14 20414 U.S. Nuclear Regulatory Commission Serial No.

14-107A Attention: Document Control Desk NSSL/MAE RO Washington, DC 20555 Docket No.

50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 SUPPLEMENTAL INFORMATION TO LICENSE AMENDMENT REQUEST, IMPLEMENTATION OF WCAP-14333 AND WCAP-15376, REACTOR TRIP SYSTEM INSTRUMENTATION AND ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TEST TIMES AND COMPLETION TIMES By letter dated May 8, 2014, Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for Millstone Power Station Unit 3 (MPS3).

The proposed amendment would revise Technical Specifications (TS) 3/4.3.1, "Reactor Trip System Instrumentation," and TS 3/4.3.2, "Engineered Safety Feature Actuation System Instrumentation." These changes are based on Westinghouse Electric Company LLC topical reports WCAP-14333-P-A, Revision 1, "Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times," and WCAP-15376-P-A, Revision 1, "Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times." DNC requested approval of the LAR by April 30, 2015 with implementation within 90 days of issuance.

In a conference call on July 28, 2014 with the Nuclear Regulatory Commission (NRC) staff, it was identified that due to the nature of MPS3 custom technical specifications, some of the proposed changes are not supported by the scope of WCAP-14333-P-A, Revision 1. Accordingly, DNC is revising the LAR to reflect deletion of the identified unsupported changes to the TS. Attachment 1 provides a discussion of the proposed changes. Attachment 2 provides the revised marked-up TS pages.

No revisions are being made to the proposed changes to surveillance test intervals as addressed in Technical Specification Task Force (TSTF) Travelers TSTF-41 1, Revision 1, "Surveillance Test Interval Extension for Components of the Reactor Protection System (WCAP-15376-P)."

These proposed changes remain consistent with the NRC-approved TSTF-41 1, Revision 1 and TSTF-418, Revision 2, "RPS and ESFAS Test Times and Completion Times (WCAP-14333)."

Additionally, the proposed changes do not impact the conclusions of the no significant hazards considerations in Section 5.1 of the LAR.

Serial No. 14-107A Docket No. 50-423 Page 2 of 3 If you have any questions regarding this submittal, please contact Wanda Craft at (804) 273-4687.

Sincerely, LWAt(

-~

Mark D. Sartain Vice President - Nuclear Engineering STATE OF CONNECTICUT COUNTY OF NEW LONDON The foregoing document was acknowledged before me, in and for the County and State aforesaid, today by Mark D. Sartain, who is Vice President - Nuclear Engineering of Dominion Nuclear Connecticut, Inc.

He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.

4 Acknowledged before me this/V day ofV69V 2014.

My Commission Expires: /f7'3e.

2P ZCo)

Notary Public Commitments made in this letter: None THOMAS CLEARY NOTARY PUBLIC MY COMMISSION EXPIRES FEBRUARY 28,2016 Attachments:

1. Discussion of Proposed Changes

2. Revised Marked-up Pages of the Proposed Changes to the Technical Specifications

Serial No. 14-107A Docket No. 50-423 Page 3 of 3 cc:

U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 Mohan C. Thadani Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 B1 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127

Serial No. 14-107A Docket No. 50-423 Discussion of Proposed Changes DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

Serial No. 14-107A Docket No. 50-423 Supplement to Implementation of WCAP-1 4333 and WCAP-1 5376, Page 1 of 3 By letter dated May 8, 2014, Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for Millstone Power Station Unit 3 (MPS3).

The proposed amendment would revise Technical Specifications (TS) 3/4.3.1, "Reactor Trip System Instrumentation," and TS 3/4.3.2, "Engineered Safety Feature Actuation System Instrumentation." These changes are based on Westinghouse Electric Company LLC topical reports WCAP-14333-P-A, Revision 1, "Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times," and WCAP-1 5376-P-A, Revision 1, "Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times." DNC requested approval of the LAR by April 30, 2015 with implementation within 90 days of issuance.

In a conference call on July 28, 2014 with the Nuclear Regulatory Commission (NRC) staff, it was identified that due to the nature of MPS3 custom technical specifications, some of the proposed changes are not supported by the scope of WCAP-14333-P-A, Revision 1.

The following are the identified unsupported changes:

1. Two functional units which are subject to the proposed ACTION 6:

" Reactor Coolant Flow-Low, Single Loop (Above P-8) {RTS functional unit 12.a};

Reactor Coolant Flow-Low, Two Loops (Above P-7 and below P-8) {RTS functional unit 12.b}.

2. One functional unit which is subject to the proposed ACTION 14:

Control Building Isolation, Automatic Actuation Logic and Actuation Relays

{ESFAS functional unit 7.c}.

3. Two functional units which are subject to the proposed ACTION 20:

Turbine Trip and Feedwater Isolation, Tave Low Coincident with P-4 {ESFAS functional unit 5.d};

Cold Leg Injection Permissive, P-19 {ESFAS functional unit 11}.

Accordingly, DNC is revising the proposed LAR to reflect deletion of the identified unsupported changes to the Technical Specifications. provides the revised marked-up pages which incorporate the following changes:

1. Revise TS Table 3.3-1 by adding ACTION 6A. The new ACTION 6A is similar to ACTION 6 but extends the completion time (CT) in ACTION 6A.a from 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and extends bypass testing time in ACTION 6A.b from 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The following functional units are affected by the new ACTION 6A:

Serial No. 14-107A Docket No. 50-423 Supplement to Implementation of WCAP-14333 and WCAP-1 5376, Page 2 of 3

" Overtemperature AT {RTS functional unit 7};

" Overpower AT {RTS functional unit 8};

" Pressurizer Pressure -Low {RTS functional unit 9};

" Pressurizer Pressure -High {RTS functional unit 10};

" Pressurizer Water Level - High {RTS functional unit 11};

Steam Generator Water Level--Low-Low {RTS functional unit 13};

Low Shaft Speed--Reactor Coolant Pumps {RTS functional unit 14};

Turbine Trip, Turbine Stop Valve Closure {RTS functional unit 15.b}.

The following functional units will continue to be subject to the existing ACTION 6:

" Reactor Coolant Flow-Low, Single Loop (Above P-8) {RTS functional unit 12.a};

Reactor Coolant Flow-Low, Two Loops (Above P-7 and below P-8) {RTS functional unit 12.b};

2. Revise Table 3.3-3 by adding ACTION 14A. The new ACTION 14A is similar to ACTION 14 but extends the CT from 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The following functional units are affected by the new ACTION 14A:

Safety Injection (Reactor Trip, Feedwater Isolation, Control Building Isolation (Manual Initiation Only), Start Diesel Generators, and Service Water), Automatic Actuation Logic and Actuation Relays {ESFAS functional unit l.b};

Containment Spray (CDA), Automatic Actuation Logic and Actuation Relays

{ESFAS functional unit 2.b};

" Containment Isolation, Phase "A" Isolation, Automatic Actuation Logic and Actuation Relays {ESFAS functional unit 3.a.2};

Containment Isolation, Phase "B" Isolation, Automatic Actuation Logic and Actuation Relays {ESFAS functional unit 3.b.2};

The following functional unit will continue to be subject to the existing ACTION 14:

Control Building Isolation, Automatic Actuation Logic and Actuation Relays

{ESFAS functional unit 7.c}.

3. Revise TS Table 3.3-3 by adding ACTION 20A. The new ACTION 20A is similar to ACTION 20 but extends the CT in ACTION 20A.a from 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and extend bypass testing time in ACTION 20A.b from 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The following functional units are affected by the new ACTION 20A:

Safety Injection (Reactor Trip, Feedwater Isolation, Control Building Isolation (Manual Initiation Only), Start Diesel Generators, and Service Water),

Containment Pressure--High-1 {ESFAS functional unit 1.c};

Serial No. 14-107A Docket No. 50-423 Supplement to Implementation of WCAP-14333 and WCAP-1 5376, Page 3 of 3 Safety Injection (Reactor Trip, Feedwater Isolation, Control Building Isolation (Manual Initiation Only), Start Diesel Generators, and Service Water),

Pressurizer Pressure--Low {ESFAS functional unit 1.d};

Safety Injection (Reactor Trip, Feedwater Isolation, Control Building Isolation (Manual Initiation Only), Start Diesel Generators, and Service Water), Steam Line Pressure-- Low {ESFAS functional unit l.e};

" Steam Line Isolation, Containment Pressure-- High-2 {ESFAS functional unit 4.c);

Steam Line Isolation, Steam Line Pressure-- Low {ESFAS functional unit 4.d};

" Steam Line Isolation, Steam Line Pressure - Negative Rate--High {ESFAS functional unit 4.e};

" Turbine Trip and Feedwater Isolation, Steam Generator Water Level-- High-High (P-14) {ESFAS functional unit 5.b};

Auxiliary Feedwater, Steam. Gen. Water Level-- Low-Low, Start Motor-Driven Pumps {ESFAS functional unit 6.c.1};

Auxiliary Feedwater, Steam. Gen. Water Level-- Low-Low, Start Turbine-Driven Pump {ESFAS functional unit 6.c.2};

The following functional units will continue to be subject to the existing ACTION 20:

" Turbine Trip and Feedwater Isolation, Tave Low Coincident with P-4 {ESFAS functional unit 5.d};

" Cold Leg Injection Permissive, P-19 {ESFAS functional unit 11}.

No revisions are being made to the proposed changes to surveillance test intervals as addressed in TSTF-41 1, Revision 1, "Surveillance Test Interval Extension for Components of the Reactor Protection System (WCAP-1 5376-P)."

These proposed changes remain consistent with the NRC-approved Technical Specification Task Force (TSTF) Travelers TSTF-41 1, Revision I and TSTF-418, Revision 2, "RPS and ESFAS Test Times and Completion Times (WCAP-14333)."

Additionally, the proposed changes do not impact the conclusions of the no significant hazards considerations in Section 5.1 of the LAR.

Revised Marked-up Pages of the Proposed Changes to the Technical Specifications DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

Serial No. 14-107A Docket No. 50-423, Page 1 of 20 November 3, 2000 3/4.3 INSTRUMENTATION IFor Information Only, No Change 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.

APPLICABILITY:

As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1.

4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be verified to be within its limit at least once per 18 months. Neutron detectors and speed sensors are exempt from response time verification. Each verification shall include at least one train such that both trains are verified at least once per 36 months and one channel (to include input relays to both trains) per function such that all channels are verified at least once every N times 18 months where N is the total number of redundant channels in a specific Reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1.

AMILLSTONE - UNIT 3 3/4 3-1 Amendment No. 4-, 49, 94-, 409, 187

Serial No. 14-107A Docket No. 50-423, Page 2 of 20 Z

z.

TABLE 3.3-1 REACTIOR TRIP SYSTEM INSTRUMENTATION FU fNCTIONAL UNIT I. Manual Reactor Trip TOTAL NO.

OF CHANNELS 2

CHANNELS T17RIP MINIMUM CHANNELS 2

APPLICABLE 1,2 AC`flQN 2

C-zC

2. Power Range. Neutron Flux

a. High Selpoint

b. Low Setpoint

3. Power Range, Neutron Flux IHigh Positive Rate

4. Deleted

5. Intermediate Range, Neutron Flux

6. Source Range, Neutron Flux

a. STARTUP

b. Shutdown

7. Overtemperature AT

8. Overpower AT

9. Pressurizer Pressure--Low

10. Pressurizer Pressure--High I1. Pressurizer Water lIevel--High 4

4 2

2 2

2 3*, 4*" 5*

3 1.2 3

144..2 3

1,2 2

1,10. 2 2

29#

2 2

2 3

4 2

2 4

4 4

4 3

2 2

2 3*,4*, 5*

I1 3

1.,2 3

1.2 3

1,2 (1) 2 I**

4-

Serial No. 14-107A Docket No. 50-423, Page 3 of 20 T-ABLEF 3.3-1 (Comtonued'i REAC'rOR '1111' SVSTEN'I ]Ir'STRIuT~lNTIATION FIUNCTIONAL TNIT

12.

Reactor Coolant Flow--Low

a.

Single Loop (Above P-8)

b.

Two Loops (Above P-7 and below P-8)

13.

Steam Generator Water Lcvel--Low-l.ow

14.

Low Shaft Speed--Reactor Coolant Pumps

15.

Turbine Trip

a.

Low Fluid Oil Pressure

b.

Turbine Stop Valve Closure

16.

Deleted

17.

Reactor Trip System Interlocks

a.

Intennediale Range Neutron Flux. P-6

b.

low Power Reacdor Trips Block. P'-7 Power Range Neutron F'lux*

P-10 Input or Turbine Impulse Chamber Pressure. P-13 Input TlOTAL NO.

OF

..nNI-;

MINIMUM CHANNELS CHANNELS iTO M OPERABLP APPLICABLE MIOD)ES ACTION' 3/loop 2/loop 3/loop 2/loop in two operating loops 4'strn. gen.

2/stm. gen.

2/loop 2Tloop II 6

6 4-1/pump 2

2 4

3/sttit.gen.

1.2 C,(1) 3 1**

/4 2

12 I

.4 l.*

4; 3

4 2

4 24#

8 2

2 22

Serial No. 14-107A Docket No. 50-423, Page 4 of 20 z

z TABLE 3.3-1 (Continued)

RI:.A(-rOR TRIP SYSTFNI INSTlIUNIENT&'rION TOTAL NO.

CIIANNEILS OF CIIANNEIJ MINIMIUM CI IANNELS OPERAlIEF APPLICABLE FUNCTIONAL. UNIT

17.

ReactorTrip System Interlocks (Continued)

c.

Power Range Neutron Flux, P-8

d.

Power Range Netron Flux P-9

c.

Power Range Neutron Flux, P-10

18.

Reactor Trip Breakers (2)

19.

Automatic Trip and Interlock Logic

20.

DELETED

21.

DELETED ACTlION 4

4 4

2 2

2 3

3 3

2 2

I 8

m, 0

a.

0a 1.2 8

1.2 3*, 4*. 5*

1,2 3*. 4*. 5*

10, 13 I1 13A 11 7-.z C

C C

Serial No. 14-107A Docket No. 50-423, Page 5 of 20 peeeffiber 10, 2002 TABLE 3.3-1 (Continued)

TABLE NOTATIONS When the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.

Above the P-7 (At Power) Setpoint.

Above the P-9 (Reactor Trip/Turbine Trip Interlock) Setpoint.

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

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

(1)

The applicable MODES and ACTION statements for these channels noted in Table 3.3-3 are more restrictive and, therefore, applicable.

(2)

Including any reactor trip bypass breakers that are racked in and closed for bypassing a reactor trip breaker.

ACTION STATEMENTS ACTION 1 -

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

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

a.

The inoperable channel is placed in the tripped condition within

hours,

b.

The Minimum Channels OPERABLE requirenrit is met; however, the inoperable channel may be bypassed for up to-4-hours for surveillance testing of other channels per Specification 4.3.1.1, and

c.

Either, THERMAL POWER is restricted to less than or equal to 75%

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

A"

-I" MILLSTONE - UNIT 3 3/4 3-5 Amendment No. 5-7, 6G, 9-3, 4.64, 24-7.

Serial No. 14-107A Docket No. 50-423, Page 6 of 20 TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

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

a.

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

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

b.

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

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

ACTION 4 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity additions.*

ACTION 5 - (Not used)

ACTION 6 -

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

a.

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

b.

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

ACTION 7-(Not used)

ACTION 8 -

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

Limited plant cooldown or boron dilution is allowed provided the change is accounted for in the calculated SDM.

4 MILLSTONE - UNIT 3 3/4 3-6 Amendment No. -5, 69,4-3-1-, J64, 2434.

Serial No. 14-107A Docket No. 50-423, Page 7 of 20 Insert A - Page 3/4 3-6 ACTION 6A - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable 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 of other channels per Specification 4.3.1.1

Serial No. 14-107A Docket No. 50-423, Page 8 of 20 TABLE 3.3-1 (Conthnned)

ACTION STATEM[ENTS (Lotiued)a

[restore the inoperable channel to ACTION 9-(Not used)

JOPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or ACTION 10-With the number of OPERABLE cha K one less than the Minimum Channels OPERABLE requirement, e in at least HOT STANDBY within the next

-> 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to-2-hours for surveillance testing per Specification 4.3.1.1, provided the kher channel is OPERABLE.

i ACTION 11-With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor Trip System breakers within the next hour.

ACTION 12-With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

F2]

a.

The inoperable channel is placed in the tripped condition withi hours, and a]

b.

When the Minimum Channels OPERABLE req~ment is met, the inoperable channel may be bypassed for up to-4-hours for surveillance testing of the Turbine Control Valves.

ACTION 13-With one of the diverse trip features (undervoltage or shunt trip attachments) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 10. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

ACTION 13A-With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable Channel to OPERABLE status within-hours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, 4[e channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Speification 4.3.1.1, provided the other charmel is OPERABLE.

L4 MILLSTONE - UNIT 3 3/4 3-7 Amendment No. 4G, 49, 229,

Serial No. 14-107A Docket No. 50-423, Page 9 of 20 5/26/98 INSTRUMENTATION For Information Only, No Change 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Nominal Trip Setpoint column of Table 3.3-4.

APPLICABILITY:

As shown in Table 3.3-3.

AC TI ON:

a.

With an ESFAS Instrumentation Channel or Interlock Channel Nominal Trip Setpoint inconsistent with the value shown in the Nominal Trip Setpoint column of Table 3.3-4, adjust the Setpoint consistent with the Nominal Trip Setpoint value.

b.

With an ESFAS Instrumentation Channel or Interlock Channel found to be inoperable, declare the channel inoperable and apply the applicable ACTION statement requirements of Table 3.3-3 until the channel is restored to OPERABLE status.

MILLSTONE - UNIT 3 3/4 3-15 Amendment No. 9+,159

Serial No. 14-107A Docket No. 50-423, Page 10 of 20 November 3, 2000 INSTRUMENTATION IFor Information Only, No Change I SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2.

4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME* of each ESFAS function shall be verified to be within the limit at least once per 18 months. Each verification shall include at least one train such that both trains are verified at least once per 36 months and one channel (to include input relays to both trains) per function such that all channels are verified at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS fuinction as shown in the "Total No. of Channels" column of Table 3.3-3.

The provisions of Specification 4.0.4 are not applicable for response time verification of steam line isolation for entry into MODE 4 and MODE 3 and turbine driven auxiliary feedwater pump for entry into MODE 3.

MILLSTONE - UNIT 3 3/4 3-16 Amendment No. 4-5, 7-9, 96, 400, 187

Serial No. 14-107A Docket No. 50-423, Page 11 of 20 2z Cz TABLE 3.3-ENGIlNEERED) SAFEYFEIN'P-ltrRE.S AILC'lI'I ON SYSTEM INSTRUM~ENVTA'ION MINI MUM TOTAL NO.

CHANNELS CHANNELS OFCIIANNEIS TOTRIP OPERABLE APPLICABLE MODES F1NCTIONAL I,NIT I. Safety Injection (Reactor Irip, Feedwater Isolation.

Control Building Isolation (Manual Initiation Only),

Start Diesel Generator,.

mid Service Water).

a.

Manual Initiation

b. Automatic Actuation Logic and Actuation Relays

e. Containment Pressure--High-I

d.

Pressurizer Pressure--Low

e.

Steam Line Pressure--

Low

2.

Containment Spray (CDA)

a. Manual Initiation ACTION 2

2 I

1 2

2 1,2,3.

19 1,2.324

-1,4 C-z C

3 4

3/steam line in each operating loop 2

2 2/steant line in any operating loop 2

1,2.3 20 3

1, 2.3#L Z H

-o 2/steam line in 1, 2, 3#

-_v each operating loop V 2

1 with 2 coincident switches 2

1,2.3.4 19

Serial No. 14-107A Docket No. 50-423, Page 12 of 20 0

cz Sc TABLE~r 3.3-3 (Continued)t ENGIlNEERED) SAEE1V IiN"A'It[lIES AC 'ii~'rION SY'STEMl INSTRUiIIMEN~r.,%:oN TOTAL NO-FUNCTIONAL I IN IT OF CHANNEI.S

2. Containment Spray (CDA) (Continued)

b. Automatic Actuation 2

Logic and Actuation Relays

c. Containnlont Pressure--

4 High-3

3. Containment Isolation

a.

'hase "A" Isolation I) Manual Initiation 2

MINIMUM CHANNELS CHANNELS TO TRIP OPERABL.E, I

2 2

3 APPLICABLE 1.MODES 1.2.3,4 ACTION 144 1,2.3.4 2

1.2.3.4 2

1,2,3.4 17 19

2)

AutomalicActuation Logic and Actuation Relays

3)

Salety Injection

b. Phase "B" Isolation I) Manual Initiation

2)

Automatic Actuation Logic mid Actuation Relays 2

I See Item 1. above Ibr all Safety Injection 2

I with

2 2 coincident switches 2

1 2

I-I I. 2. 3,4 zb 1,2.3,4

Serial No. 14-107A Docket No. 50-423, Page 13 of 20 TrABIE. 33-3 (R"ontinueTFdr E,:N(INEERED S;AFETY ItEA'I'RES ACITATIrON SYS TEM INS 1'R111MIENT:VrlON FI1NCTIONAIIJNIT

5. Turbine Trip and Feedwater Isolation TOIAL NO.

CHANNELS OF CIIANNI'].S TO TRIP MINIMUM CHANNELS OPERAB1L.

APPLICABLE MODES AC-nON

a.

Automatic Actuation Logic and Actuaion Relays

1.

Stean Generator Water Level--

High-High (P-14)

c.

Safety Injection Actuation Logic

d.

Ta,, Low Coincident with P-4 1.2 25 1,2.3 4.. 21 4/siem. gen.

in each operating loop 2/stin. gen.

in any operating loop I

3istm. gen.

in each operating loop 2

1,2 22 20 I Taw/loop I 1.

in any two ITa., in any loops three loops 1.2 Z

1-I

Serial No. 14-107A Docket No. 50-423, Page 14 of 20 z

z I:NGINIFERED SAFETV IFEA'I'IIRES.AC.'IUtA'IION SYSTEM I NKs-lRUMENTh'rION TO*AL NO.

CHANNELS OF CHANNEIS TOTRIP MINIMUM CHANNELS OPERAB31E APPLICABLE MODES F1NCTIONAI. I JNIT

6. Atlsiliary Feedwater

a.

Manual Initiation K. Automatic Actuation Logic anid Actuation Relays

c. Sin. Gen. Water Level--

Low-Low I) Start Motor-Driven Pumps

2) Stant Turbine-Driven Pump

d.

Safely Injection Start Motor-Driven Pumps

e.

Loss-ofIOlTsite Power Start Motor-Driven Pumps ACTION 23 22 2

2 I

2 1.2,3 2

1.2.3 4/stm. gen.

2/sttn. gen. in any operating stm.

gen.

31stm. gen. in each operating stilt. gen.

I, 2.3 1.2,3 Mý -

I, I-4,Stil. gen.

2,sitn. gen. in any 3/asini. gen. iii 2 operating still.

each operating gen.

stil. gen.

See Item I. above f1r all Safety Injection initiating functions and requirements.

F.

z 0

4Z 2

1.2,3 19

Serial No. 14-107A Docket No. 50-423, Page 15 of 20 Cz 13111 I 3.3-3 (Co.nfinued)

ENGINEIERED SAFET'I'F FAXtTURES AUF IT[,r [ON' SYSITE I NSTRUtINENn, TlON 1K n-INCTIONAI UNIT OF

6.

Auxiliary Feedvater (Continued) 1.. Containmcnt Dcpres-surizalion Actuation (CDA) Stan Motor-Driven l'.nsps

7.

Control Building Isolation

a. Manual Actuation

b. Manual Sal'ety Injection Actuation

c.

Automatic Actuation Logic and Actuationt Relavs

)TAL NO.

CHANNELS CIIANNEI.S TOTRIP MINIMUM CHANNELS OPERABILE APPLICABLE MODES ACil1ON See Item 2. above for all CDA fwictions and requirements.

0 0

z0 0

=r 2

2 1

I 2

2 1,2.3,4 1.2.3.4 d, Containuniel E.

High-I

v. Control Bui

z Ventilation I

8. Los lof Power 4 kV Bus U voltage-los S

b. 4kV' BusU Grid Degrac It Pressurc--

Iding Inlct Radiation ndcr-s of Voltage ndervoltage-led Voltage 1, 2.3 19 19 14 16 18 27 27 2/intake 4..hits 4/bus 2/intake r-.

2/huts 2/bus 3/bus 31bus 1.2.3.4 1,2,3,4

Serial No. 14-107A Docket No. 50-423, Page 16 of 20 0

z z

ENG INEERED SAFETV I'EA'I'UHS ACrrIIATlON SYSTEMI INSTRUMIENTATION

1.

1`1NCTIONAI, I JNIT 0

9.

Engineering Safety Features Actuation System Interlocks

a.

Pressurizer Pressure.

13_11

b.

Low-Low Trnv, P-12

c.

Reacior Trip, P-4

10.

Emergency Generator Load Sequencer II.

Cold Leg Injection Permissive, P-19 "OTAL NO.

CHANNELS F CIIANNIELS TO TRIP M IN IMIU.NI CHANNELS OPERABLfE APPLICABLE

.IODES 3

4 2

2 4

2 2

2 1

I1 2,3 ACTION 21 21 23 15 20 0

0 z

0 0

3 2

2 L,2.3 1.2,3 1r 2.3,4 I, 2.3 I

z C

4,-

C C

0 0

Serial No. 14-107A Docket No. 50-423, Page 17 of 20

,.epternbe. 1:8, 2008 TABLE 3.3-3 (Continued)

TABLE NOTATIONS The Steamline Isolation Logic and Safety Injection Logic for this trip function may be blocked in this MODE below the P-Il (Pressurizer Pressure Interlock) Setpoint.

MODES 1.2. 3, and4.#

During movement of recently irradiated fuel assemblies.

Trip function automatically blocked above P-Il and may be blocked below P-Il when Safety Injection on low steam line pressure is not blocked.

ACTION STATEMENTS ACTION 14 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months s-however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance Insert B - Page 3/4 3-24 ing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 16-ACTION 17-ACTION 18 -

ACTION 19-MILLSTONE - U]

With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

/

~I With the number of O ERABLE channels one less than the Total Number of Channels, operation mrr, proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to-4-hours for surveillance testing per Specification 4.3.2. 1.

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 7 days.

After 7 days, or if no channels are OPERABLE, immediately suspend movement of recently irradiated fuel assemblies, if applicable, and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

NIT 3 3/4 3-24 Amendment No. -5 4, 9, 4-29, 2*03, 9+-9, 2-2+2-2,*

24,

Serial No. 14-107A Docket No. 50-423, Page 18 of 20 Insert B - Page 3/4 3-24 ACTION 14A - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

Serial No. 14-107A Docket No. 50-423, Page 19 of 20

-March 17, 2004 TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACTION 20 -

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

a.

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

b.

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

Inset C - Page 3/432 ACTION 21 -

With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

24 ACTION 22 -

With the number of OPERABLPaels one less than the Minimum Channels OPERABLE requ;,'ment, restore the inoperable channel to OPERABLE status within-6-hours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 23 -

ACTION 24 -

ACTION 25 -

ACTION 26 -

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

With the number of OPERABLE*annels one less than the Minimum Channels OPERABLE requ~ient, restore the inoperable channel to OPERABLE status within-6-hours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

DELETED MILLSTONE - UNIT 3 3/4 3-25 Amendment No. 44, -29, Q+9-,

Serial No. 14-107A Docket No. 50-423, Page 20 of 20 Insert C - Page 3/4 3-25 ACTION 20A - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and

b. the Minimum Channels OPERABLE requirement is met; however, the inoperable 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 of other channels per Specification 4.3.2.1.

v t e Letter Sequence Supplement
TAC:MF4131, RPS and ESFAS Test Times and Completion Times - WCAP-14333, TSTF-41 (Open)
Initiation Request, Request, Request Acceptance... Supplement Administration Questions 17 March 2015 Answers Results Approval... Other:
MONTHYEAR2015-03-17 [Table View]

ML14234A097

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