ML20246M146

Amends 145,141 & 116 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Making Primary Containment Integrity Definition Operability Requirement & Action Statement More Appropriate & Consistent

ML20246M146
Person / Time
Site:	Browns Ferry
Issue date:	02/29/1988
From:	Zech G NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20246M091	List: ML20246M085 ML20246M146 ML20246M234
References
TAC-R00034, TAC-R00035, TAC-R00036, TAC-R34, TAC-R35, TAC-R36, NUDOCS 8909070107
Download: ML20246M146 (11)

Text

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'o UNITED STATES

.- ! "~ o NUCLEAR REGULATORY COMMISSION

{  ;$ W ASHHJGTON, D. C. 20555

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 145 License No. OPR-33

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

A. The application for amendment by Tennessee Valley Authority (the licensee) dated October 16, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Co imission's rules and regulations set forth in 10 CFR i 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 (1) that the activities authorized by this amendment can be conducteo without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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.

8909070107 880229 PDR ADOCK 05000259 P PDR

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-33 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as l revised through Amendment No.145, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amersdment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Mb cy G. Zech, Ass ant Director for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: February 29, 1988

ATTACHMENT TO LICENSE AMENDMENT NO. 145 FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and'contain marginal lines indicating the area of change. Overleaf page* is provided to maintain document completeness.

REMOVE INSERT 1.0-3 1.0-3*

1.0-4 1.0-4 3.7/4.7-17 3.7/4.7-17 3.7/4.7-18 3.7/4.7-18 l

{

1.0 DEFINITIONS (Cont'd)

H. Reactor power Operation - Reactor power operation is any operation with the mode switch in the "Startup" or "Run" position with the reactor critical and above 1 percent rated power.

I. Hot Standby Condition - Hot standby condition means operation with coolant temperature greater than 212 0F, system pressure less than 1,055 psig, the main steam isolation valves closed and the node switch in the Startup/ Hot Standby position.

J. Cold Condition - Reactor coolant temperature equal to-or less than 2120F.

K. Hot shutdown - The reactor is in the shutdown mode and the reactor coolant temperature greater than 212 0F.

L. Cold Shutdown - The reactor is in the shutdown mode and the reactor coolant temperature equal to or less than 212 0F.

M. Mode of Operation - A reactor mode switch selects the proper interlocks for the operational status of the unit. The fc11owing are the modes and interlocks provided:

1. Startup/ Hot Standby Mode - In this modo the reactor protection scram trips initiated by condenser low vacuum and main steam line isolation valve closure, are bypassed when reactor pressure is less than 1,055 psis, the reactor protection system is energized with IRM neutron monitoring system trip, the ApRM 15 percent high flux trip, and control rod withdrawal interlocks in service. This is of ten referred to as just Startup Mode. This is intended to imply the Startup/ Hot Standby position of the node  ;

switch. ]

2. Run Mode - In this mode the reactor system pressure is at or above 825 psis and the reactor protection system is I energized with ApRM protection (excluding the 15 percent high flux trip.) and the RBM interlocks in service.

)

3. Shutdown Mode - placing the mode switch to the shutdown position initiates a reactor scram and power to the control rod drives is removed. After a short time period (about 10 sec), the scram signal is removed allowing a scram reset and restoring the normal valve lineup in the  ;

control rod drive hydraulic system; also, the main steam line isolation scram and main condenser low vacuum scram are bypassed if reactor vessel pressure is below 1,055 ,

psis.

4. Refuel Mode - With the mode switch in the refuel position, interlocks are established so that one control rod only may be withdrawn when the Source Range Monitor indicates at least 3 cps and the refueling crane is not over the l reactor; also the main steam line isolation scram and main l condenser low vacuum scram are bypassed if the reactor i l

vessel pressure is below 1,055 psig. If the refueling crane is over the reactor, all rods nust be fully inserted and none can be withdrawn.

1.0-3 UEIt 1

1.0 DEFINITIONS (Cent'd)

N. Rated power - Rated power refers to. operation at a reactor power of

• 3,293 MWt; this is also termed 100 percent power and is the maxinum power level authorized by the operating license. Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power. Design power, the power to which the safety analysis applies, corresponds to 3,440 MWt.

O. Primary Containment Intentrity - primary containment integrity means that the drywell and pressure suppression chamber are intact and all of the following conditions are satisfied:

1. All nonautomatic containment isolation valves on lines connected to the reactor coolant systems or containment which are not required to be open during accident conditions are closed.

These valves may be opened to perform necessary operational' activities.

2. At least one door in each airlock is closed and sealed.

3. All automatic containment isolation valves are operable or each line which contains an inoperable isolation valve is isolated as required by specification 3.7.D.2.

4. All blind flanges and manways are closed.

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l BFN 1.0-4 Amendment No. 145 I Unit 1 ,

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3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.C. Secondary containment

4. If refueling zone secondary  ;

containment cannot be maintained the following conditions shall be met:

a. Handling of' spent fuel and  !

all operations over spent fuel pools and open reactor wells containing fuel shall be prohibited,

b. The standby gas treatment system suction to the refueling zone will be blocked except for a controlled leakage area sized to assure the achieving of a vacuum of at least 1/4-inch of water and not over 3 inches of water in all three reactor zones.

D. Primary Containment Isolation Valves D. Primary Containment Isolation Valves

1. When Primary Containment 1. The primary containment Integrity is required, all isolation valves isolation valves listed in surveillance shall be Table 3.7.A and all reactor performed as follows:

coolant system instrument line flow check valves a. At least once per shall be OPERABLE except as operating cycle the specified in 3.7 D.2. OPERABLE isolation valves trat are power operated ond automatically initiated shall be tested for simulated automatic initiation and closure times.

b. At least once per quarter:

(1) All normally open power-operated isolation valves (except for the main steam line power-operated isolation valves) shall be fully closed and reopened.

BFN 3.7/4.7-17 Unit 1 Amendment No. 145

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33,7/4.7- CONTAINMENT SYSTEMS LIMITING CONDITIONS'FOR OPERATION SURVEILLANCE REQUIREMENTS

'3.7.D. Primary Containment Isolation 4.7.D. Primary containment Isolation Valves Valves-4.7.D.1.b (Cont'd)

(2) With the reactor power less than 75%, trip main steam isolation valves individually and verify closure time.

c. At least twice per week the main steam line power-operated isolation valves shall be exercised one at a time by partial closure and subsequent reopening.

d. At least once per operating cycle the operability of the reactor coolant system instrument line flow check valves shall be verified.

-2. In the event any isolation valve 2. Whenever an isolation valve specified in Table 3.7.A becomes listed in Table 3.7.A is INOPERABLE reactor operation INOPERABLE, the position of at may continue provided at least least one other valve in each one valve. in each line having line having an INOPERABLE valve an INOPERABLE valve, is OPERABLE shall be recorded daily, and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

a. The INOPERABLE valve is restored to OPERABLE status, or

b. Each affected line is isolated by use of at least one deactivated containment L isolation valve secured I

in the isolated posltion.

3. If specification 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

BrM 3.7/4.7-18 Amendment No. 145 Unit 1

. . = _ _ _ _ _-____--__-____________-_ - ___ _______ - _ -_______ _ _ --

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9 0 KEco UNITED STATES l>

e y,f 4n NUCLEAR REGULATORY COMMISSION

{  ;$ WASHINGTON, D. C. 20555

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l TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amer.dment No.141 License No. DPR-52

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

A. The application for amendment by Tennessee Valley Authority (the licensee) dated October 16, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations 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 Comission; 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 Comission's regulations; 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 Comission's regulations and all applicable requirements have been satisfied.

I

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-52 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.141, are hereby incorporated in the 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 within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION MN f Gar @. Zech, Ass nt Director f W Projects TVA Projects Division Office of Special Frojects

Attachment:

Changes to the Technical Specifications Date of Issuance: February 29, 1988

________.-.___.-_.-_-_____.-_-----_.__-w

ATTACHMENT TO LICENSE AMENDMENT NO. 141 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf page* is provided to maintain document completeness.

REMOVE INSERT 1.0-3 1.0-3*

1.0-4 1.0-4 3.7/4.7-17 3.7/4.7-17 3.7/4.7-18 3.7/4.7-18 I

d 1.0 DEFINITIONS (C;nt'd)

H. Reactor Power Operation - Reactor power operation is any operation with the mode switch in the "Startup" or "Run" position with the reactor critical and above 1 percent rated power.

I. Hot Standby Condition - Hot Standby condition means operation with coolant temperature greater than 2120F, system pressure less than 1055 psis, the main steam isolation valves closed and the mode switch in the Startup/ Hot Standby position.

J. Cold condition - Reactor coolant temperature equal to or less than 2120F.

K. Hot Shutdown - The reactor is in the shutdown mode and the reactor coolant temperature greater than 212 0F.

L. Cold Shutdown - The reactor is in the shutdown mode and the reactor coolant temperature equal to or less than 212 0F.

M. Aode of Operation - A reactor mode switch selects the proper interlocks for the operational status of the unit. The following are the modes and interlocks provided:

1. Startup/ Hot Standby Mode - In this mode the reactor protection system is energized with IRM neutron monitoring systma trip, the APRM 15 percent high flux trip, and control rod withdrawal interlocks in service. This is often referred to as just Startup Mode. This is intended to imply the Startup/ Hot Standby position of the mode switch.

2. Run Mode - In this mode the reactor system pressure is at or above 825 psig and the reactor protection system is energized with APRM protection (excluding the 15 percent high flux trip) and the RBM interlocks in service.

3. Shutdown Mode - Placing the mode switch to the shutdown position initiates a reactor scram and power to the control rod drives is removed. After a short time period (about 10 seconds), the scram signal is removed allowing a scram reset and restoring the normal valve lineup in the control rod drive hydraulic system.

4. Refuel Mode - With the mode switch in the refuel position, interlocks are established so that one control rod only may be withdrawn when the Source Range Monitor indicates at least three counts per second and the refueling crane is not over the reactor, except as specified by TS 3.10.B.1.b.2. If the refueling crane is over the reactor, all rods nost be fully 5.serted and none can be withdrawn.

BFN 1.0-3 Unit 2

-_____- ______-_-__-- O

1.0 DEFINITIONS (C:nt'd)

N. Rated Power - Rated power refers to operation at a reactor power of 3,293 NWt; this is also termed 100 percent power and is the maximum power level authorized by the operating license. Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power. Design power, the power to which the safety analysis applies, corresponds to 3,440 MWt.

O. Primary Containment Integrity - Primary containment integrity means that the drywell and pressure suppression chamber are intact and all of the following conditions are satisfied:

1. All nonautomatic containment isolation valves on lines connected to the reactor coolant systems or containment which are not required to be open during accident conditions are closed.

These valves may be opened to perform necessary operational activities.

2. At least one door in each airlock is closed and sealed.

3. All automatic containment isolation valves are operable or each line which contains an inoperable isolation valve is isolated as required by specification 3.7.D.2.

4. All blind flanges and manways are closed.

P. Secondary Containment Integrity

1. Secondary containment integrity means that the reactor building is intact and the following conditions are met:

a) At least one door in each access opening to the turbine building, control bay and out-of-doors is closed.

b) The Standby Gas Treatment System is operable and can maintain 0.25 inches of water negative pressure in those areas Where secondary containment integrity is stated to exist.

c) All secondary containment penetrations required to be closed during a:cident conditions are either:

1. Capable of being closed by an operable secondary containment automatic isolation system, or

2. Closed by at least one secondary containment automatic isolation valve deactivated in the isolated position.

2. Reactor zone secondary containment integrity means the unit reactor building is intact and the following conditions are met:

a) At least one door between any opening to the turbine building, control bay and out-of-doors is closed.

BFN 1.0-4 Amendment No. 141

. Unit 2 l

_ _ _ _ . _ _ _ _ _ _ _.m___.. _ _____._____-__m_m.___.__ ____-_______________.-_ _--_-_d

, 3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.C. Secondary containment

4. If refueling zone secondary containment cannot be maintained the following conditions shall be met:

a. Handling of spent fuel and all operations over spent fuel pools and open reactor wells containing fuel shall be prohibited.

b. The standby gas treatment system suction to the refueling zone will be blocked except for a controlled leakage area sized to assure ihe achieving of a vacuum of at least 1/4-inch of water and not over 3 inches of water in all three reactor zones.

D. Primary Containment Isolation Valves D. Primary Containment Isolation Valves

1. When primary Containment 1. The primary containment Integrity is required, all isolation valves isolation valves listed in surveillance shall be Table 3.7.A and all reactor performed as follows:

coolant system instrument line flow check valves a. At least once per shall be OPERABLE except as operating cycle the specified in 3.7.D.2. OPERABLE isolation valves that are power operated and automatically initiated shall be tested for simulated automatic initiation and closure times.

b. At least once per quarter:

(1) All normally open power-operated isolation valves (except for the main steam line power-operated isolation valves) shall be fully closed and reopened.

bbft2 Amendment No. 141 1

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3.7/4.7 CONTAINMENT SYSTEMS ,

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.D. Primary Containment Isolation 4.7.D. Primary Conta.nment Isolation Valves Valves 4.7.D.1.b (Cont'd)

(2) With the reactor power less than 75%, trip main steam isolation valves individually and verify closure time.

c. At least twice per week the main steam line power-operated

. isolation valves shall be exercised one at a time by partial closure and subsequent reopening.

d. At least once per operating cycle the operability of the reactor coolant system instrument line flow check valves shall be verified.

2. In the event any isolation valve 2. Whenever an isolation valve specified in Table 3.7.A becomes listed in Table 3.7.A is INOPERABLE, reactor operation INOPERABLE, the position of at may continue provided at least least one other valve in each one valve, in each line having line having an INOPERABLE valve an INOPERABLE valve, is OPERABLE shall be recorded daily, and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

a. The INOFERABLE valve is restored to OPERABLE status, or

b. Each affected line is i isolated by use of at least one deactivated containment isolation valve secured in the isolated position.

3. If specification 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Bru 3.7/4.7-18 Amendment No. 141 j Unit 2 1

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k UNITED STATES NUCLEAR REGULATORY COMMISSION WAsmNGTON, D. C. 20$55 t ,g

...../

4 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 116 License No. DPR-68

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

A. The application for amendment by Tennessee Valley Authority (the licensee) dated October 16, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations 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; 1

C. There is reasonable assurance (1) 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; 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.

l

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i '2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amenament and paragraph 2.C.(2) of Facility Operating License No. DPR-68 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.116, are hereby incorporated in the 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 within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION M

Ga . Zech, Assis t Director for Projects TVA Project. Division Office of Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: February 29, 1988 1

1 l l

ATTACHMENT TO LICENSE AMENDMENT NO.116 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 4

Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf page* is provided to maintain document completeness.

REMOVE INSERT 1.0-3 1.0-3*

1.0-4 1.0-4 3.7/4.7-17 3.7/4.7-17 3.7/4.7-18 3.7/4.7-18 i i

i

s e, 1.0 DEFINITIONS (C:nt'd)'

H. Reactor Power Operation - Reactor power operation is any operation with the mode switch in the "Startup" or "Run" porition with the reactor critical and above 1-percent rated power.

l'

1. Hot Standby Condition - Hot standby condition means operation with coolant temperature greater than 2120 F, system pressure less than 1,055 psig, the main steam isolation valves closed and the mode switch in the Startup/ Hot Standby position.

J. Cold Condition - Reactor coolant temperature equal to or less than 2120F.

K. Hot Shutdown - The reactor is in the shutdown mode and the reactor coolant temperature greater than 212 0F.

L. Cold Shutdown - The reactor is in the shutdown mode and the reactor coolant temperature equal to or less than 212 0F.

M. Mode of Operation - A reactor mode switch selects the proper interlocks for the operational status of the unit. The following are the modes and interlocks provided:

1. Startup/ Hot Standby Mode - In this mode the reactor protection system is energized with IRN neutron monitoring system trip, the APRM 15 percent high flux trip, and control rod withdrawal interlocks in service. This is of ten referred to as just Startup Mode. This is intended to imply the Startup/ Hot Standby position of the mode switch.

2. Run Mode - In this mode the reactor system pressure is at or above 825 psig and the reactor protection system is energized with APRM protection (excluding the 15 percent high flux trip) and the RBM interlocks in service.

3. Shutdown Mode - Placing the mode switch to the shutdown position initiates a reactor scram and power to the control rod drives is removed. After a short time period (about 10 seconds), the scram signal is removed allowing a scram reset and restoring the normal valve lineup in the control rod drive hydraulic systec.

4. Refuel Mode - With the mode switch in the refuel position, interlocks are established so that one control rod only may be withdrawn when the Source Range Monitor indicates at least 3 cps and the refueling crane is not over the reactor except as specified by TS 3.10.B.1.b.2. If the refueling crane is over the reactor, all rods nust be fully inserted and none can be withdrawn.

BFN-Unit 3 1.0-3

1.0 DEFINITIONS (C:nt'd)

N. Rated Power - Rated power refers to operation at a reactor power of 3,293 NWt; this is also termed 100 percent power and is the maxinum l

power level authorized by the operating license. Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power. Design power, the power to which the safety analysis applies, corresponds to 3,440 MWt.

O. Primary Containment IntetritY - primary containment integrity means that the drywell and pressure suppression chamber are intact and all of the following conditions are satisfied:

1. All nonautomatic containment isolation valves on lines connected to the reactor coolant systemslor containment which are not required to be open during accident conditions are closed.

These valves may be opened to perform necessary operational activities.

2. 'At least one door in each airlock is closed and sealed.

3. All automatic containment isolation valves are operable or each line which contains an inoperable isolation valve is isolated as required by specification 3.7.D.2.

4 All blind flanges and manways are closed.

BrN 1.0-4 Amendment No. 116 Unit 3

[- .

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I' , 3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS j 3.7.C. Secondary containment 4 If refueling zone secondary containment cannot be maintained the following conditions shall be met:

l

a. Handling of spent fuel and all operations over spent fuel pools and open reactor wells containing fuel shall be prohibited.

l

b. The standby gas treatment system suction to the l

refueling zone will be l blocked except for a controlled leakage area sized to assure the achieving of a vacuum of at least 1/A-inch of water and not over 3 inches of water in all three reactor zones.

D. primary containment Isolation Valves D. Primary Containment Isolation Valves l

1. When Primary Containment 1. The primary containment l

Integrity is required, all isolation valves I isolation valves listed in surveillance shall be l Table 3.7.A and all reactor performed as follows:

coolant system instrument l

line flow chec:: valves a. At least once per shall be OPERABLE except as operating cycle the specified in 3.7.D 2. OPERABLE isolation valves that are power operated and automatically initiated shall be tested I for simulated automatic initiation and closure times.

b. At least once per quarter:

(1) All normally open power-operated j isolation valves (except for the main steam line power-operated isolation valves) shall be fully closed and reopened.

Bry 3 7/A 7-17 Unit 3 Amendment No. 116 l.

L o .

3.7/4.7' CONTAINMENT SYSTEMS ..

LIMITING CONDITIONS'FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.D.-primarv Containment Isolation 4.7.D. Primary Containment Isolation-Valves Valves 4.7.D.1.b (Cont'd)

(2) With the reactor power less then.75%. trip pain steam isolation valves individually and verify 1 closure time.

c. At least twice per week the main steam line power-operated isolation valves shall be exercised one at a time by partial closure and subsequent reopening.

d. At least once per operating cycle the operability of the reactor coolant system instrument line flow check ,

valves shall be verified.

2. In the event'any isolation valve 2. Whenever an isolation valve specified in Table 3.7.A becomes listed in Table 3.7.A is INOPERABLE. reactor operation INOPERABLE. the position of at may continue provided at least least one other valve in each one valve,'in each line having line having an INOPERABLE valve an INOPERABLE valve. is OPERABLE shall be recorded daily.

and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

a. The INOPERABLE valve is restored to OPERABLE status, or

b. Each affected line is isolated by use of at least one deactivated containment isolation valve secured in the isolated position.

3. If specification 3.7.D.1 and 3.7.D.2'cannot be met, an crderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

BrW 3.7/4.7-18 Amendment No. 116 Unit 3'

_ _ _ _ _ - . _-____-__- _ ____-_ _ ____ _ _