Text

Amends 187 & 192 to Licenses DPR-44 & DPR-56,respectively, Revising Surveillance Requirements to Eliminate Unnecessary Diesel Generator Testing or Offsite Power Source Becomes Inoperable
	ML20065H880
Person / Time
Site:	Peach Bottom
Issue date:	04/05/1994
From:	Chris Miller; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20065H883	List: ML20065H880; ML20065H890;
References
	NUDOCS 9404150196
	Download: ML20065H880 (13)
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E UNITED STATES 5i

'E NUCLEAR REGULATORY COMMISSION

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WASHINGTON. D.C. 20555-0001 PHILADELPHIA ELECTRIC COMP.AE1 PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.187 License No. DPR-44 1.

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

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated November 17, 1993, 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; 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 condu::ted i

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 or safety of the public; and l

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.

.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-44 is hereby amended to read as follows:

9404150196 940405 hDR ADOCK 05000277; PDR 1

. (2) Technical Specificationi The Technical Specifications contained in. Appendices A and B, as revised through Amendment No. 187, are hereby incorporated in the.

license.

PEC0 shall operate the far.ility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

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Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 5, 1994

p ATTACHMENT TO LICENSE AMENDMENT NO.187 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Remove Insert 219 219 220 220 220a 220a 4

i J

Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.8 Ooeration with Inocerable Eauioment 4.9.B.

Ooeration with Inocerable Eouioment Whenever the reactor is in Run Mode or Startup Mode with the reactor not in a Cold Condition, the availability of electric power shall be as :pecified in 3.9.A, except as follows:

1.

With one offsite circuit required by

1. When it is determined that one Specification 3.9.A.1 inoperable, offsite circuit required by restore at least two offsite circuits to Specification 3.9.A.1 is OPERABLE status within 7 days or be in inoperable, verify the least HOT SHUTDOWN within the next 12 OPERABILITY of the remaining hours and in COLD SHUTDOWN within the A.C. sources by performing following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirement 4.9.A.I.1.a within I hour and once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

2.

With two independent off-site circuits

2. None required by Specification 3.9.A.1 inoperable, continued operation is permissible, provided the four diesel generators and associated emergency busses are operable, all core and containment

{

cooling systems are operable and reactor power level is reduced to 25% of the

design, i

i

-219-Amendment no. 69, 149, 173,187 l

Unit 2' PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.8 (Continued) 3.

With one diesel generator inoperable 3.

When it is' determined that restore the inoperable diesel. generator one diesel generator'it and associated emergency bus.to OPERABLE inoperable, verify the ~

status within 7 days or be in at least OPERABILITY of the remaining HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months A.C. sources by performing and in COLD SHUTDOWN within the Surveillance Requirement following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.9.A.I.l.a within I hour.and once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.-

. Verify within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months that-

. required systems subsystems,-

-trains, components, and devices that depend on the remaining diesel generators as.a source of emergency.

power are OPERABLE.

If the diesel generator became inoperable-for any.

reason other than preplanned.

. preventative maintenance, or

. testing, either determine-within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that remaining operable diesel generators are not inoperable

due to common cause failure or demonstrate the:

OPERABILITY of the remaining operable diesel generators by performing Surveillance.

Requirement:4.9.A.1.2.a.3 for ~l one diesel.at a time, within 1

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

and at least.once per 72. hours thereafter, j

i 1-

This test is required to be completed regardless of when the inoperable diesel generator is restored to OPERABILITY for. failures that are'potentially generic to the-

. remaining diesel generators and for which appropriate alternative testing cannot be-designed..-

H 220 Amendment n.o. 6,.773,187 n

=

Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.8 (Continued) 4.

With one diesel generator and one 4.

When it is determined that offsite circuit required _by one diesel generator and Specification 3.9.A.1 inoperable, one offsite circuit required restore at least two offsite by Specification 3.9. A.1 circuits or four diesel are inoperable, verify the generators to OPERABLE status OPERABILITY of the remaining within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the time A.C. sources by performing of initial loss or be in at Surveillance Requirement least HOT SHUTDOWN within the 4.9.A.1.1.a within I hour next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN and once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

thereafter. Verify within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , that required systems, subsystems, trains, components, and devices that depend on the remaining diesel generators as a source of emergency power are OPERABLE.

If the diesel generator became inoperable for any reason other than preplanned preventative maintenance, or testing, either determine within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that remaining operable diesel generators are not inoperable due to common cause failure or demonstrate the OPERABILITY of the remaining diesel generators by i

performing Surveillance Requirement 4.9.A.l.2.a.3 for one diesel generator at a i

time, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months *.

5.

From and after the date that one of the 5.

None 125 volt battery systems is made or found to be inoperable for any reason, continued reactor operation is permissible during the succeeding three i

days within electrical safety I

considerations, provided repair work is initiated in the most expeditious manner to return the failed component to an l

operable state, and Specifications 3.5.F and 3.9.B.3 are satisfied.

i i

i

This test is required to be completed regardless of when the inoperable diesel generator is restored to OPERABILITY for failures that are potentially generic to the remaining diesel generators and for which appropriate alternative testing cannot be j

designed.

-220a-Amendment no. 131, 173, 187

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UNITED STATES l'

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NUCLEAR REGULATORY COMMISSION

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W ASHINGTON, D.C. 20555-0001 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 192 License No. DPR-56 1.

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

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated November 17, 1993, complies,:ith 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; 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; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health or' 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 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-56 is hereby amended to read as follows:

. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.192, are hereby incorporated in the license.

PEC0 shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR ~ REGULATORY COMMISSION CfCwh b$(

Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 5, 1994

,e 9

k 1

ATTACHMENT TO LICENSE AMENDMENT NO.192 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix A-Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Remove Insert 219 219 220 220 220a 220a i

Unit 3 4.

LIMITINGCONDITIONSFOROPERAT10N SURVEILLANCE REQUIREMENTS 3.9.8 Doeration with Inocerable Eautoment 4.9.B.

Ooeration with Inocerable Eouioment Whenever the reactor is in Run Mode or Startup Mode with the reactor not in a cold condition, the availability of electric power shall be as specified in 3.9.A except as follows:

1.

With one offsite circuit required by

1. When it is determined that one Specification 3.9.A.1 inoperable, offsite circuit required by restore at least two offsite circuits to Specification 3.9.A.1 is OPERABLE status within 7 days or be in inoperable, verify the least HOT SHUTDOWN within the next 12 OPERABILITY of the remaining hours and in COLD SHUTDOWN within the A.C. sources by performing following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirement 4.9.A.1.1.a within I hour and once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

2.

With two independent off-site circuits

2. None required by Specification 3.9 A.1 inoperable, continued operation is permissible, provided the four diesel generators and associated emergency busses are operable, all core and containment cooling systems are operable and reactor power level is reduced to 25% of the design.

-219-Amendment no. 65, 152, 176,192

_,o Unit 3

.t PBAPS

+

LIMITING CONDITIONS FOR OPERATION.

SURVEILLANCE REQUIREMENTS 3.9.8 -

-(Continued)-

m 3.

With one diesel generator inoperable 3.

When it is determined that-restore.the inoperable. diesel-generator one diesel generator.is znd associated emergency bus to OPERABLE inoperable, verify the status within 7 days or be in at.least OPERABILITYLof the remaining HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

.A.C. sources Toy performing, and in COLD SHUTDOWN within-the Surveillance. Requirement following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

-4.9.A.1.1.a:within 1-hour and once per:8 hours thereafter -

. Verify within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months that-y required ~ systems, subsystems, trains,-components, and devices that' depend on the remaining diesel generators-as a source of emergency power.are OPERABLE.

If the diesel generator' became inoperable for any reason other than preplanned preventative maintenance, or-testing, either determine within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that.

remaining operable diesel generators are not inoperable-due to consen cause failure or demonstrate.the.

OPERABILITY of the remaining-operable' diesel generators-by.

performing Surveillance Requirement 4.9.A.1.2.a.3 for l-

.one diesel:at~~a time, within e 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months * :and at 'least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months thereafter..

oThis test is required to be completed regardless of when _ the inoperable diesel

- generator'is restored to OPERABILITY for failures that are.potentially-generic to the remaining' diesel generators and for which appropr.iate alternative testing cannot be designed.-

220

-Amendment no. 55, 175, 192 7

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,o Unit 3 PBAPS i

LIli! TING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.8 (Continued) 4.

With one diesel generator and one 4.

When it is determined that offsite circuit required by one diesel generator and Specification 3.9. A.1 inoperable, one offsite circuit required restore at least two offsite by Specification 3.9.A.1 circuits or four diesel are inoperable, verify the generators to OPERABLE status OPERABILITY of the remaining within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the time A.C. sources by performing of initial loss or be in at Surveillance Requirement least HOT SHUTDOWN within the 4.9.A.1.1.a within I hour next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN and once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

thereafter. -Verify within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , that required systems, subsystems, trains, components, and devices that depend on the remaining diesel generators as a source of emergency power are OPERABLE.

If the diesel generator became inoperable for any reason other than preplanned preventative maintenance, or testing, either determine within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that remaining operable diesel generators are not inoperable due to conson cause failure or demonstrate the OPERABILITY of the remaining diesel generators by performing Surveillance Requirement 4.9.A.1.2.a.3 for one diesel generator at a time, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months *.

5.

From and after the date that one of the 5.

None 125 volt battery systems is made or found to be inoperable for any reason, continued reactor operation is permissible during the succeeding three days within electrical safety considerations, pro'vided repair work is initiated in the most expeditious manner to return the failed component to an operable state, and Specifications 3.5.F and 3.9.B.3 are satisfied.

This test is required to be completed regardless of when the inoperable diesel generator is restored to OPERABILITY for failures that are potentially generic to the remaining diesel generators and for which appropriate alternative testing cannot be designed.

-220a-Amendment no. 1 8, 176, 192

ML20065H880

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