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Amends 92 & 73 to Licenses NPF-9 & NPF-17,respectively, Changing Tech Specs by Deleting Surveillance Requirements Re Manual Transfer from Normal to Emergency Power Supplies for Pressurizer Heaters,Porvs & PORV Block Valves
	ML20154E812
Person / Time
Site:	McGuire, Mcguire
Issue date:	09/13/1988
From:	Matthews D; Office of Nuclear Reactor Regulation
To:	;
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ML20154E815	List: ML20154E812;
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	NUDOCS 8809190146
	Download: ML20154E812 (8)
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'o UNITED STATES E'

NUCLEAR REGULATORY COMMISSION

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DUKE POWER COMPAhY DOCKET NO. 50-369 McGUIRE AUCLEAR STATION. UNIT 1 AMEN 0fjENT TO FACILITY OPERATING LICENSE r

Amendment No. 92 License No. NPF-9 1.

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

A.

Tne application for amendment to the McGuire Nuclear Station, Unit 1 (the f acility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated June 24, 1968, 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 fcrth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the applicaticn, as amended, the prCYisions of the Act. /Ad the rules and regulations i

of the Commission; a

C.

There is ressenable assurance (1) that the activities authorized by i

this amendment can be conducted without endangering the health and safety of tne public, and (ii) that such activities will be conducted in compliance with the Commission's regulatieris set forth in 10 CFR Chapter I; J

D.

The issuance of this amendment will rot be inimical to the common

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defense and security or to the health and safety of the public; and I

E.

The issuance of this amendment is in acco-1'nce with 10 CFR Part 51 l

of the Commission's regulations and all %.. cable requirements have j

been satisfied.

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Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, e

and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby i

amended to read as follows.

l (2) _ Technical Specifications

(

i The Technical Specifications contained in Appendix A, as revised l

through Amendment No.

92, are hereby incorporated into the license, j

The licensee shall operate the facility in accordance with the t,

Technica) Specifications and the Environmental Protection Plan.

l 3.

This license amendment is effective as of its date of issuance.

I FOR THE NUCLEAR REGULATORY COMMISSION l

David B. Matthews, Director Project Directorate !!-3 Division of Reactor Projects-!/II

Attachment:

Technical Specification Changes

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Date of Issuance: September 13, 1988 t

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UNITED STATES I '~

NUCLEAR REGULATORY COMMISSION o

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OUAEPOWERCOMPAM DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDfiEflT TO FACILITY OPERAT!!lG LICENSE Amendment No. 73 License No. NPF-17 1.

The Nuclear Regulatory Cormission sthe Commission) has found that:

A.

The application for amendrent to the McGuire Nuclear Station.

Unit 2 (the f acility) Facility Operatino License No. NPF-17 filed i

bytheDukePowerCompany(thelicensee)catedJune 24, 1988, corplies with the standards and requirerents of the Atomic Energy Act of 1954, as amended (tne Acc) and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in ccnformity with the application, as amended, 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 aterdt.1ent can be conducted without endangering tne health and Safety of the public, and (ii) that such activities will be conducted in ccepliance with the Coraission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will n6t be inimical to the common defense and securt'y or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 cf the Cormission's regulations and all applicable requirements have been l

satisfied, i

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2.

Accordingly, the license is hereby amended by page changes to the Technical I

Specifications as indicated in the attachments to this license amendeent, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

73, are hereby incorporated into the license.

The licensee shall operate the facility in accordance with the j

Technical Specifications and the Environmental Prctection Plan.

i 3.

This license amendment is effective as of its date of issuance.

l FOR THE NUCLEAR REGULATORY COMMISSION t

i i

i David B. Matthews. Director Project Directerste 11-3 l

Division of Reactor Projects-!/I!

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Attachment:

Technical Specification Changes i

Date of Issuance:

september 13. 1988 i

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OFFICIAL RECORD COPY

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2-2.

Accordingly, the license is nereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amenoment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 73, are hereby incorporated into the license.

1he licensee shall eperate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amenoment is effective as of its date of issuance.

FOR THE HUCLEAR REGULATORY COMMISSION 0

David B. Matthews, Director Project Directorate !!-3 Division of Reactor Projects-!/l!

Attachment:

Technical Specificatien Changes Date of Issuance: September 13, 1988

i ATTACHMENT TO LICENSE AMEN 0 MENT NO. 92 FACILITY OPERATING LICENSE NO. NPF-9 00CKET NO. 50-369 5

_TO LICENSE AMENDMENT NO. 73 FACILITY OPERATING LICEhSE NO. hPF-17 COCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the encloseo pages.

The revised pages are identified by Atendment nuater and contain vertical lines indicating the areas of change.

Amended Page 3/4 4-9 3/4 4-10 1

REACTOR COOLANT SYSTEM 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION i

3.4.3 The pressurizer shall be OPERABLE with a water level of less than or equal to 92% (1600 cubic feet), and at least two groups of pressurizer heaters each having a capacity of at least 150 kW.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

With one group of pressurizer heaters inoperable, restore at least l

two groups to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 HOT SHUT 00WN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the Reactor trip breakers open within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

I SURVEILLANCE REQUIREMENTS t

i 4.4.3.1 The pressurizer water level shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.3.2 The capacity of each of the above required groups of pressurizer l

heaters shall be verified by energizing the heaters and measuring circuit current at '- '+ once per 92 days.

McGUIRE

.~S 1 and 2 3/4 4-9 Amendment No. 92 (Unit.)

Amendment No. 73 (Unit 2)

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REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.4 All power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

With one or more (PORV(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the black valve (s); otherwise, 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 SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s) or close the PORV and remove power from its associated solenoid valve; otherwise, 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 COLO 3 HUT 00WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

The provisions of Specification 3.0.4 are not arplicable.

SURVEILLANCE REQUIREMENTS 4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:

a.

Performance of a CHANNEL CALIBRATION, and b.

Operating the valve through one cceplete cycle of full trsvel.

4.4.4.2 Each block valve shall be demonstrated OPERAELE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet the requirements of ACTION a. in Specification 3.4.4.

t McGUIRE - UNITS 1 and 2 3/4 4-10 Amendment No. 92 (Unit 1)

Amendment No. 73 (Unit 2)

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ML20154E812

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