Text

Amends 148 & 178 to Licenses DPR-71 & DPR-62,respectively, Revising Tech Specs Re Isolation Actuation Instrumentation
	ML20058D227
Person / Time
Site:	Brunswick
Issue date:	10/25/1990
From:	Adensam E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20058D230	List: ML20058D227; ML20058D233;
References
	NUDOCS 9011050413
	Download: ML20058D227 (10)
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I CAROLINA POWER & LIGHT _ COMPANY. et al.

L DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 148 License No. DPR-71 1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendment filed by Carolina Power & Light Company (the licensee), dated February 15,1989. as supplemented February 23 and October 23, 1990, complies with the standards and requirements of theAtomicEnergyActof1954,asamended(theAct),andthe 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: (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 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; j

and paragraph 2.C.(2) of Facility Operating License No. OPR-71 is hereby amended to read as follows:

9011050413 901025 DR ADOCK 050 4

2-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.148, are hereby incorporated in the license.

Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:

Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: October 25, 1990 I

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ATTACHMENT TO LICENSE AMENDMENT NO,148 FACILITY OPERATING LICENSE NO, DPR-71 DOCKET NO, 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Remove Pages Insert Pages 3/4 3-17 3/4 3-17 3/4 3-17a F

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E TABLE 3.3.2-1 (Continued )

ISOLATION ACTUATION I NSTR UM ENTATI ON ACTIONS ACTION 20 - Be in at least HOT SHUTDOWN within 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 .

ACTION 21 - Be in at least STARTUP with the main steam line isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 22 - Be in at least STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ACTION 23 - In OPERATIONAL CONDITIONS 1, 2, or 3, establish SECONDARY CONTAINMENT INTECRITY with the standby gas treatment system operating within one hour.

In OPERATIONAL CONDITION 5 cr when handling irradiated fuel in the secondary containment:

1)

Establish SECONDARY CONTAINMENT INTECRITY with the standby gas treatment system operating within one hourt 2)

Otherwise, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS, or activities that could reduce the SHUTDOWN MARCIN.

ACTION.24 - Isolate the reactor water cleanup system.

ACTION 25 --Close the affected system isolation valves and declare the af f ected system inoperable.

ACTION 26 - Verify power availability to the bus at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

. ACTION 27 - Deactivate the. shutdown cooling supply and reactor vessel head-spray isolation valves in the closed position until the reactor steam dome pressure is within the specified limits.

ACTION 28 - Close the af fected isolation valves within 14 days or be in HOT' SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i BRUNSWICK - UNIT 1 3/4 3-17 Amendment No. 60,122, 132, 148

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TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION NOTES When handling irradiated f uel in the secondary containment.

(a )

See Specificat ion 3.6.3.1, Table 3.6.3.1-1 f or valves in each valve group.

(b)

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that pa ra me t e r.

(c)

With only one channel pe'r trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.

In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

(d)

A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE.

-(e )

With reactor steam pressure > 500 psig.

(f)

. Closes only RWCU outlet isolation valve.

(g)

Alarm only.

(h)

Isolates containment purge and vent valves.

s BRUNSWICK - UNIT 1 3/4 3-17a Amendment No. 148

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CAROLINA POWER & LIGHT COMPANYi et al.

DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE 4

Ainendment No.178 License No. DPR-62 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The apnlication for amendment filed by Carolina Power & Light Company (the licensee), dated February 15, 1989, as supplemented February 23. -

and October 23, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the

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Comission's rules and regulations set forth in 10 CFR Chapter I; 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 conducted without endangering the health and safety of the public, and'(ii) that such activities will be conducted in comp 11ence with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon i

defense and security or to the health and safety of'the public; and t

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.

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. OPR-62 is hereby amended to read as follows:

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2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.178, are hereby incorporated in the license.

Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

3.

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

1 FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:

Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

L Changes to the. Technical Specifications Date of Issuance: October-25,1990

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ATTACHMENT TO LICENSE AMEN 0 MENT NO.178 FACILITY OPERATING LICENSE NO OPR-62 DOCKET NO. 50-324

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Replace the following paces of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Pages insert Pages 3/4 3-17 3/4 3-17 3/4 3-17a

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TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTIONS ACTION 20 - Be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWH within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 21.-

Be in at least STARTUP with the main steam line isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 22 - Be in at least STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ACTION 23 - In OPERATIONAL CONDITIONS 1, 2, or 3, establish SECONDARY CONTAINMENT INTECRITY with the standby gas treatment system operating within one hour.

In OPERATIONAL CONDITION $ or when handling irradiated fuel in the secondary containment

[.

1)

Establish SECONDARY CONTAINHENT INTECRITY with the standby gas treatment system operating witnin one houri 2)

Otherwise, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS, or activities that could reduce the SHUTDOWN MARCIN.

ACTION 24 -

Isolate the reactor water cleanup system.

ACTION 25 - Close the affected system ' isolation valves and declare the affected system inoperable..

ACTION 26 Verif y power availability to the bus at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 27 - Deactivate the shutdown cooling supply and reactor vessel head spray isolation valves in the closed position until the reactor steam dome pressure is within the specified limits.

ACTION 28 - Close the affected isolation valves within 14 days or be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

s BRUNSWICK - UNIT 2 3/4 3-17 Amendment No. $$, 78, f

97, 137, 146, 162, 178

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TABLE 3.3.2-1 (Continued )

l ISOLATION ACTUATION INSTRUMENTATION I

j NOTES ji When handling irradiated fuel in the secondary containment.

i (a) See Specification 3.6.3.1. Table 3.6.3.1-1 f or val ves in each valve group -

(b) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for l

required surveillance without placing the trip system in the tripped I

condition provided at least one other OPERABLE channel in tne same trip

)

system is monitoring that parameter.

(c) With only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trtp Function to occur.

In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for I

that Trip Function shall be taken.

(d) A channel is OPERABLE if 2 of 4 instruments in the channel are OPERABLE.

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(e) With reactor steam pressure 3 500 psig.

(f) Closes only RWCU outlet isolation valve.

i (g) Alarm only.

1 (h) Isolates containment purge and vent valves.

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BRUNSWICK - UNIT 2 3/4 3-17a Amendment No.178 l

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ML20058D227

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