Text

Amends 182 & 164 to Licenses NPF-9 & NPF-17,respectively, Deleting All References to Steamline Low Pressure Safety Injection Function
	ML20153F631
Person / Time
Site:	McGuire, Mcguire
Issue date:	09/22/1998
From:	Berkow H; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20153F634	List: ML20153F631; ML20153F640;
References
	NUDOCS 9809290184
	Download: ML20153F631 (18)
	v • d • e

_... _...._. _. _ _ _. _. _ _ _ _ _ _ _ _ _ _.. _ _ _ _ _

neouq y

UNITED STATES j

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 49.....,o DUKE ENERGY CORPORATION DOCKET NO. 50-369 McGUIRE NUCLEAR STATION. UNIT 1 4

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.182 License No. NPF-9

1. The Nuclear Regulatory Commission (the Commission) has found that:

A - The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility),

Facility Operating License No. NPF-9 filed by the Duke Energy Corporation (licensee) dated October 6,1997, as supplemented by letter dated August 24,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i

C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

5 m

9809290184 9809 PDR ADOCK 0500 69 P

PDR

, 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and

(

Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby smended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.182, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented in the refueling outage associated with the plant's hardware modifications.

FOR THE NUCLEAR REGULATORY COMMISSION e

/W Herbert N. Berkow, Directo Project Directorate 11-2 Division of Reactor Projects -l/II Office of Nuclear Reactor Regu!ation

Attachment:

Technical Specification Changes Date of Issuance: September 22, 1998

l t

-,~

v.--r

~

~..-

ATTACHMENTTO LICENSE AMENDMENT NO.182 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-389.

Replace the followin0 pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain verticallines indicating the areas of change.

Remove IDRE1 3/4 3-17 3/4 3-17 3/4 3-24 3/4 3-24 3/4 3-27 3/4 3-27 3/4 3-33 3/4 3-33 3/4 3-37 3/4 3-37 B 3/4 3-2 8 3/4 3-2

TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT

'0F CHANNELS TO TRIP OPERABLE MODES ACTION 1.

Safety Injection, Reactor-Trip, Feedwater Isolation.

Component Cooling Water, Start Diesel Generators, and Nuclear Service Water a.

Manual Initiation 2

1 2

1,2,3,4 18 b.

Automatic Actuation 2

1 2

1,2,3,4 14 Logic and Actuation Relays c.

Containment 3

2 2

1,2,3 15 Pressure-High d.

Pressurizer 4

2 3

1, 2, 3#

19 Pressure - Low-Low I

McGUIRE - UNIT 1 3/4 3-17 Amendment No.'182

- - - - - -..-.. -. - -. --... - -.. -. - -. ~

TABLE 3.3-3 (Continued)

TABLE NOTATION Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.

Trip function automatically blocked above P-11 and may be blocked below P-11 when Main Steam Isolation on low steam pressure is not blocked.

l These values left blank pending NRC approval of three loop operation.

Note 1:

Turbine driven auxiliary feedwater pump will not start on a blackout signal coincident with a safety injection signal.

ACTION STATEMENTS ACTION 14 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-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 15 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required OPERATIONAL TEST provided 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 .

l ACTION 15a With the number of OPERABLE channels less than the Total Number of Channels, operation may proceed until performance of the next required OPERATIONAL TEST provided 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 .

With more than one channel inoperable, enter Specification 3.8.1.1.

ACTION 15b With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required 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 .

ACTION 16 With the number of OPERABLE channels one less than the Total Number of Channels, operation may 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.

ACTION 17 With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.

McGUIRE - UNIT 1 3/43-24 Amendment No. 182

+

TABLE 3 3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES-t 1.-

Safety Injection, Reactor Trip, Feedwater Isolation, Component Cooling 1

Water, Start Diesel Generators, and

' Nuclear Service Water.

a.

Manual Initiation N.A.

N.A.

i b.

Automatic Actuation Logic.

N.A.

j and Actuation Relays j

c.

Cor.tainment Pressure--High s 1.1 psig s 1.2 psig '

d.

Pressurizer Pressure--Low-Low 2 1845 psig 2 1835 psig 1

i 2.

Containment Spray a.

Manual Initiation N.A.

N.A.

b.

Automatic Actuation Logic N.A.

N.A.

t and Actuation Relays c.

Containment Pressure--High-High s 2.9 psig s 3.0 psig l

f I

l i

McGUIRE - UNIT 1-3/43-27 Amendment No. 182 i

i

TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3.

Pressurizer Pressure-Low-Low a.

Safety Injection (ECCS) s 27(II/12(3) b.

Reactor Trip (from SI) s2 c.

Feedwater Isolation-s 12 d.

Containment Isolation-Phase "A.(2) s 18(3)/28(4) e.

Containment Purge and Exhaust Isolation' s4 f.

Auxiliary Feedwater(s)

N.A.

g.

Nuclear Service Water System s 76(1)/65(3) h.

Component Cooling Water s 76(1)/65(3) 1.

Start Diesel Generators s 11 4.

Steam Line Pressure-Low Steam Line Isolation s 10 i

McGUIRE UNIT 1 3/43-33 Amendment No.182

TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUENTATION SURVEILLANCE REQUIREENTS-

~

TRIP ANALOG ACTUATING-MODES CHANNEL DEVICE MASTER SLAVE ~ FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY-RELAY SURVEILLANCE

]

FUNCTIONAL UNIT-CHECK CALIBRATION' TEST TEST LOGIC TEST: TEST TEST' IS REQUIRED

1. Safety Injection, Reactor Trip, Feedwater Isolation, Component Cooling Water, 3

Start Diesel Generators, and Nuclear Service Water a.

Manual Initiation N. A.-

N.A.

M.A.

R N.A, N.A.

N.A.

1, 2, 3, 4 -

I b.

Automatic Actuation N.A.

N.A N.A N.A.

M(1)

Q 1, 2, 3, 4 Logic and Actuation Relays c.

Containment Pressure-S R

Q N.A..

M.A.

N.A.

1, 2, 3 High d.

Pressurizer Pressure-S R

Q N.A.

N.A.

1, 2, 3 Low-Low I

2. Containment Spray a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4 b.

Automatic Actuation N.A.

N.A.

M(1)

Q 1, 2, 3, 4 Logic and Actuation Relays c.

Containment Pressure-- S R

Q N.A.

M.A.

N.A.

1, 2, 3 High-High McGUIRE - UNIT 1 3/43-37 Amendment No.182 o

INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued) may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a steam line break or loss-of-coolant accident: (1) Safety Injection pumps start and automatic valves position, (2) Reactor trip, (3 feedwater isolation, (4) startup of the emergency diesel generators. (5) )

containment spray pumps start and automatic valves position, (6) containment isolation, (7) steam line isolation, (8) Turbine tri pumps start and automatic valves position, and (10) p, (9) auxiliary feedwater nuclear service water pumps start and automatic valves position.

Technical Specifications for the Reactor Trip Breakers and the Reactor Trip Bypass Breakers are based upon NRC Generic Letter 85-09 " Technical Specifications for Generic Letter 83-28. Item 4.3," dated May 23, 1985.

The Engineered Safety Features Actuation System interlocks perform the following functions:

P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves on T

below Setpoint, prevents the opening of the main feedwater valves wEi'ch were closed by a Safety Injection or High Steam Generator Water Level signal, allows Safety Injection block so that components can be reset or tripped.

Reactor not tripped - prevents manual block of Safety Injection.

P-11 Defeats the manual block of Safety Injection actuation on low pressurizer pressure and defeats steamline isolation on negative steamline pressure

[

rate. Defeats the manual block of the motor-driven auxiliary feedwater pumps on t;ip of main feedwater pumps and low-low steam generator water level.

' P-12 On increasing reactor coolant loop temperature, P-12 automatically provides an arming signal to the steam dump system. On decreasing reactor coolant loop temperature -P-12 automatically removes the arming signal from the steam dump system.

P-14 On. increasing steam generator level, P-14 automatically trips all feed-water isolation valves and inhibits feedwater control valve modulation.

d McGUIRE - UNIT 1 B 3/4 3-2 Amendment No. 182

,p nouq p

k UNITED STATES g

j NUCLEAR REGULATORY. COMMISSION o,

,g WASHINGTON, D.C. 2066tL4001 g, *****y DUKE ENERGY CORPORATION DOCKET NO. 50-370 McGUIRE NUCLEAR STATION. UMT_2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.164 License No. NPF-17

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility),

Facility Operating License No. NPF-17 filed by the Duke Energy Corporation (licensee) dated October 6,1997, as supplemented by letter dated August 24,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized t,y this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

. 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows; l'

(2) TechnicalSoecifications The Technical Specifications contained in Appendix A, as revised through i

Amv.Jinent No.164, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be impkmented in i

the refuelirig outage associated with the plant's hardware modifications.

I FOR THE NUCLEAR GULATORY COMMISSION W

I Herbert N. Berkow, Director Project Ditoctorate ll-2 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation

Attachment:

Technical, Specification Changes l

Date of issuance:

September 22, 1998 i

4 4

l ATTACHMENT TO LICENSE AMENDMENT NO.164 i

FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain verticallines indicating the areas of change.

Remove Insert 3/4 3-17 ^

3/4 3-17 3/4 3-24 3/4 3-24 3/4 3 3/4 3-27 3/4 3-33 3/4 3-33 3/4 3-37 3/4 3-37 B 3/4 3-2 B 3/4 3-2

TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS

. APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE

' MODES ACTION L

1.-

Safety Injection, Reactor Trip, Feedwater Isolation, Component Cooling Water, Start Diesel Generators, and Nuclear Service Water a.

Manual Initiation 2

1 2

1,2,3,4 18 b.

Automatic Actuation 2

1 2

1,2,3,4 14 Logic and Actuation Relays c.

Containment 3

2-2 1,2,3 15 Pressure-High d.

Pressurizer 4

2 3

1, 2, 3#

19 Pressure - Low-Low i

McGUIRE - UNIT 2 3/43-17 Amendthent No. 164

TABLE 3.3-3 (Continued)

TABLE NOTATION Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.

Trip function automatically blocked above P-11 and may be blocked below P-11 when Main Steam Isolation on low steam pressure is not blocked.

I These values left blank pending NRC approval of three loop ' operation.

Note 1:

Turbine driven auxiliary feedwater pump will not start on a blackout signal coincident with a safety injection signal.

ACTION STATEMENTS ACTION 14 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-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 15 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance cf the next required OPERATIONAL TEST provided 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 .

ACTION 15a With the number of OPERABLE channels less than the Total Number of Channels, operation may proceed until performance of the next required OPERATIONAL TEST provided 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 . With more than one channel inoperable, enter Specification 3.8.1.1.

ACTION 15b With the number of OPERABLE channels one.less than the Total Number of Channels, operation may proceed until performance of the next required 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 .

ACTION 16 With the number of OPERABLE channels one less than the Total Number of Channels, operation may 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.

ACTION-17 With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge suppv and exhaust valves are maintained closed.

McGUIRE - UNIT 2 3/43-24 Amendment ilo. 164 l

TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES.

1.

Safety Injection, Reactor Trip, Feedwater Isolation Component Cooling Water, Start Diesel Generators, and Nuclear Service Water.

a.

Manual Initiation N.A.

N.A.

b.

Automatic Actuation Logic N.A.

N.A.

and Actuation Relays c.

Containment Pressure--High s 1.1 psig s l.2 psig L

I d.

Pressurizer Pressure--Low-Low 2 1845 psig 2 1835 psig I

i 2.

Centainment Spray I

a.

Manual Initiation N.A.

N.A.

b.

Automatic Actuation Logic N.A.

N.A.

and Actuation Relays c.

Containment Pressure--High-High s 2.9 psig s 3.0 psig McGUIRE - UNIT 2 3/43-27 Amendment No.- 164

P TABLE 3.3-5 (Continued) i ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3.

Pressurizer Pressure-Low-Low a.

Safety Injection (ECCS) s 27(1)/12(3) i

)

b.

Reactor Trip (from SI) s2 c.

Feedwater Isolation s 12 d.

Containment Isolation-Phase "A.(2) s 18(3)/28(4) i e.

Containment Purge and Exhaust Isolation s4 f.

Auxiliary FeedwaterIS)

N.A.

g.

Nuclear Service Water System s 76(1)/65(3) h.

Component Cooling Water s 76(1)/65(3) 1.

Start Diesel Generators s 11 4.

Steam Line Pressure-Low Steam Line Isolation s 10 l

l l.

I i.

a 4

McGUIRE - UNIT 2 3/43-33 Amendment No.164

..e

,, -, - ~. -.

n

TABLE 4.3-2' ENGINEERED SAFETY FEATURES ACTUATION SYSTEM'INSTRUENTATION_

SURVEILLANCE REQUIREMENTS TRIP

[

ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL -OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST-TEST LOGIC TEST TEST TEST-IS REQUIRED

1. Safety Injection. Reactor Trip, Feedwater Isolation, Component Cooling Water.

Start. Diesel Generators, and Nuclear Service Water a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4 b.

Automatic Actuation N.A.

N.A N.A N.A.

M(1)

Q 1,2,3,4 Logic and Actuation Relays j

c.

Containment Pressure-S R

Q-N.A.

N.A.

1, 2, 3 High d.

Pressurtzer Pressure-S R

Q N.A.

N.A.

1, 2, 3 i

Low-Low

2. Containment Spray I

a.

Manual Initiation M.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4 b.

Automatic Actuation N.A.

N.A.

M(1)

Q 1, 2, 3, 4 Logic and Actuation Relays c.

Containment Pressure-- S R

Q N.A.

N.A.

1, 2, 3 i

High-High i

+

McGUIRE - UNIT 2 3/43-37 Amendment No.164 t

L l

INSTRUMENTATION BASES 3/4.3.1and3/4.3.2REACTORTRIPANDENGINEEREDSAFETYFEATURESACTUATION SYSTEM INSTRUMENTATION (Continued) may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a steam line break or loss-of-coolant accident: (1) Safety Injection pumps' start and automatic valves position, (2) Reactor trip (3 feedwater isolation, (4) startup of the emergency diesel generators, (5) )

containment spray pumps start and automatic valves position, (6) containment

. isolation, (7) steam line isolation, (8) Turbine trip, (9) auxiliary feedwater pumps start and automatic valves position, and (10) nuclear service water pumps start and automatic valves position.

Technical Specifications for the Reactor Trip Breakers and the Reactor Trip Bypass Breakers are based upon NRC Generic Letter 85-09 "Te,hnical Specifications for Generic Letter 83-28 Item 4.3," dated May 23, 1985.

The Engineered Safety Features Actuation System interlocks perform the following functions:

P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves on T

below Setpoint, prevents the opening of the main feedwater valves wEi'chwereclosedbyaSafetyInjectionorHighSteamGeneratorWater Level signal, allows Safety Injection block so that components can be reset or tripped.

Reactor not tripped - prevents manual block of Safety Injection.

P-11 Defeats the manual block of Safety Injection actuation on low pressurizer pressure and defeats steamline isolation on negative steamline pressure l

rate. Defeats the manual block of the motor-driven auxiliary feedwater pumps on trip of main feedwater pumps and low-low steam generator water level.

l P-12 On increasing reactor coolant loop temperature, P-12 automatically provides an arming signal to the steam dump system. On decreasing reactor coolant loop temperature, P-12 automatically removes the arming signal from the steam dump system.

P 14 On increasing steam generator level, P-14 automatically trips all feed-water isolation valves and inhibits feedwater control valve modulation.

l

~

McGUIRE - UNIT 2 83/43-2 Amendment No. 164 i

y m--

--.r- - -.

--g-t w

sa-.

- -+.,,.

e

,s.-m-gr+

no.,---

y--

t.

~-e n

ML20153F631

Text

Attachment:

Attachment:

Navigation menu

Search