Text

Amends 26 & 7 to Licenses NPF-68 & NPF-81,respectively, Allowing Operational Mode Changes While Control Room Ventilation Tech Spec Action Statement Are in Effect
	ML20005G284
Person / Time
Site:	Vogtle
Issue date:	01/09/1990
From:	Matthews D; Office of Nuclear Reactor Regulation
To:	; Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA
Shared Package
ML20005G285	List: ML20005G284; ML20005G287;
References
	NPF-68-A-026, NPF-81-A-007 NUDOCS 9001180385
	Download: ML20005G284 (11)
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UNITED STATES

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GEORGIA POWER COMPAliY OGLETHORPE POWER CORPORATION -

4 MutilCIPAL ELECTRIC AUTHORITY OF GEORGI A CITY OF DALTON, CEORGIA

_ V0GTLE ELECTRIC GENERATING PLAMT, UNIT 1 AMENINENT TO FACILITY OPEF.ATING LICENSE a

Amendment No. 26

-i License No. NPF-68 l

1.

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

The app (lication for amendment to the Vogtle Electric. Generating Plant, A.

Unit 1 the facility) Facility Operating Licen:e 11o. NPF-68 filed by 1

the Ge,rgia Power Company acting for itself, Cglethorpe Power Corpo-ration; Municipal Electric Authority of Georgia, and City of Dalton, i

Georgia, (the licensees) dated May 19, 1989, 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 fcrth in 10 CFR Chapter I; B.

The facility will operate in ccoformity with the application, as amended, the provisions of the Act, and the rules and regulations i

a of the Commission;.

C.

There is reasonable assurance (i) that the activitier atthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in ccmpliance with the Ccnmiission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license awndment will not be inimical to the common defense and security or to the health and safety of the public; l

and E.

The issuance of this amendment is u accurdance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied.

9001180385 900109 PDR ADOCK 05000424 P

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2 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-68 is hereby amended to road as follows:

hchnical Specifications and Envitchnentel Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 26, and the Environmental Prots: tion Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendrent is effective as of its date of-issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION c@

Cavid B. Matthews, Director Project Directorate 11-3 l

Division of Reactor Projects - I/II l

Office of Nuclear Reactor Regulation

Attachment:

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Technical Specification Changes Date of Issuance:

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UNITED STATES

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g NUCLEAR REGULATORY COMMISSION j

W ASHINGTON, D. C. 20555

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GEORGIA POWER COMPANY OGLE 1HORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DAL1Cli, GEORGIA V0GTLE ELECTRIC GENERATING PLANT, UNIT 2

.n1ENDMENT 10 FACILITY CPERATING LICENSE Amendment No. 7 License No NPF-81 1.

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

A.

The application for hmendment to the Vogtle Electric Generating Plant,-

Unit 2 (the f acility) Fecility Operating License No. NPF-81 filed by the Georgia Power Company acting for itself,.0glethorpe Power Corpo-ration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensees) dated May 19, 1989, complies with the star.dards 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, as anended, 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. set forth in 10 CFR Chapter I; D.

The issuance of this license amendment will rot 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 Ccmission's' regulations and all applicable requirements have i

i been satisfied.

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2 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-81 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contalied in Appendix A, as revised through M.endmeist No. 7

, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

Tbis license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMISSION l

f s6 David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II 0ffice of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes l

Date of Issuance:

4

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ATTACHMENT TO LICENSE AMENDMENT NO. 26 FACILITY OPERATING LICENSE NO. NPF,

ANC LICENSE AMENDMENT NO. 7 FACILITY OPERATING LICENSE NO. NPF-81 DOCKETS NOS. 50-424 Al0 60-425 Replace the following pages of the Apptndix "A". Technical Specifications with the enclosed pages.

The revised pages are identified by' Anendment number and contain vertical lines indicating the areas of change. The corresponding overleaf paEes are also provided to maintain document completeness.

Amended Page Overleaf Page 3/4 3-27 3/4 3-27a 3/4 3-28 3/4 7-14 3/4 7-13 3/4 7-14a i

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TABLE 3.3-2 (Continued)

ACTION STATEMENTS (Continued)

ACTION 24 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

ACTION 25 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within

~

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 26 - With the ' number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore at least one channel-to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiateandmaintainoperationof.thegntrolRoomEmergency Filtration System in the Emergency mode l

ACTION 27 - a)

With one channel inoperable in a unit, restore the

~

inoperable channel to OPERABLE status within 7 days OR within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain operation of one Control Room Emergency Filtration System (CREFS)g n the unaffected unit in the i

p emergency mode *,

i b)

With one channel inoperable in each unit, restore each inoperable channel to OPERABLE status within 7 days OR withinthenext6hoursinitiateandmaintaig*operationof 4

one CREFS in each unit in the emergency mode l

c)

With two channels inoperable in a unit, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either 1) initiate and maintain operation ~of the two.CREFS in the unaffected unit

OR 2) initiate and maintain g

operation of one CREFS in each unit in the emergency mode *.

d)

With three channels inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the two CREFS in the emergency mode in the unit with only one channel inoperable *,

l e)

With four channels inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of two CREFS in the emergency mode *.

l ACTION 28 - a)

With one channel inoperable in a unit, restore the inoperable channel to OPERABLE status within 7 days, OR within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either 1) lock' closed the affected and lock open-the unaffected OSA intake dampers

OR 2)

.l.

initiateandmgntainoperationofoneCREFSinthe emergency mode l

The initiated CREFS shall be Train B unless Train B is inoperable.

The provisions of Specification 3.0.4 are not applicable to either unit.

l V0GTLE UNITS - 1 & 2 3/4 3-27 AMEN 0 MENT N0.26 (UNIT 1)

AMENDMENT N0.7 (UNIT 2).

TABLE 3.3-2 (Continued)

ACTION STATEMENTS (Continued) b)

With one channel inoperable in each unit, restore each inoperable channel to OPERABLE status within 7 days OR within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiatg*and maintain operation of one CREFS in the emergency mode l

ci With two channels inoperable in a unit, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either 1) lock closed the affected and lock open the unaffected OSA intake dampers

OR 2) initiate and maintain l-operg on of one CREFS in each unit in the emergency-mode

[

d)

With three channels inoperable, within 1 bour either 1) 4 lock closed the 05A intake dampers of the unit with two inoperable channels and lock open the other OSA intake i

dampers and either restore the remaining affected channel to OPERABLE status within 7 days OR ir.itiate and maintain g

operation of one CREFS in the emergency mode

in the l

following6hoursOR2)initiateandmaintaigoperationof one CREFS in each unit in the emergency mode *.

l e)

With four channels inoperable, within'1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and' maintainopera)*ionofoneCREFSineachunitinthe emergency mode l

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The initiated CREFS shall be Train B unless Train B is inoperable.

i

The provisions of Specification 3.0.4 are not applicable-to either unit.

l V0GTLE UNITS - 1 & 2 3/4 3-27a AMENDMENT NO. 26 (UNIT 1) i AMENDMENT NO. 7 (UNIT 2)

r TABLE 3.3-3 o

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS g

TOTAL SENSOR ALLOWANCE ERROR FUNCTIONAL UNIT (TA)

Z (S)

TRIP SETPOINT ALLOWABLE VALUE s

1.

Safety Injection (Reactor Trip, Feedwater Isolation, Component e.

Cooling Water, Control Room Emergency m

Filtration System Actuation, Start Diesel Generators, Containment Cooling Fans, Nuclear Service Cooling Water, Containment Isolation, Containment Ventilation Isolation, and Auxiliary Feedwater Motor-Driven Pumps) a.

Manual Initiation N.A.

N.A.

N. A.

N.A.

b.

Automatic Actuation Logic N.A.

.N.A.

N.A.

N. A.

N.A.

y and Actuation Relays M

c.

Containment Pressure--High 1

2. 7 0.71 1.67

< 3.8 psig

-< 4.4 psig (PI-0934, PI-0935, PI-0936) d.

Pressurizer Pressure--Low 13.1 10.71 1.67

> 1870 psig

-> 1860 psig (PI-0455A,B&C, PI-0456 & PI-0456A,-

PI-0457 & PI-0457A, PI-0458 &

PI-0458A) e.

Steam Line Pressure--Low 13.0 10.71 1.67 3 585 psig*

2 570 psig (LOOP 1 LOOP 2 LOOP 3

' LOOP 4 i

PI-0514A,B&C PI-0524A&B.

PI-0534A&8 PI-0544A,B&C PI-0515A PI-0525A-PI-0535A PI-0545A l

PI-0516A.

PI-0526A PI-0536A PI-0546A) 2.

Containment Spray a.

Manual Initiation N.A.

N. A.

N.A.

N. A.

N.A.

b.

Automatic Actuation Logic N. A.

N.A.

(

and Actuation Relays c.

Containment Pressure--High-3 3.1 0.71 1.67-

'< 21.5 psig

-< 22.4 psig l

(PI-0934, PI-0935, PI-0936,

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i PI-0937)

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PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK i

LIMITING CONDITION FOR OPERATION 3.7.5 The Ultimate Heat Sink (VHS).shall be OPERABLE with:

a.

Two OPERABLE Nuclear Service Cooling Water (NSCW) tower basins each with:

4 1.

A minimum water level (LI-1606-train A, LI-1607-train B) in the NSCW tower basin of 80.25 ft (plant elevation of 217' 3") (73%

of instrument span) 2.

A maximum water temperature (TJR-1690/1-train A, TJR-1691/1-train B) of 90 F.

b.

Two OPERABLE trains of NSCW tower fans, each train consisting of.

four fans and associated spray cells.

1 c.

Two OPERABLE NSCW transfer pumps.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With the UHS inoperable due to water level and/or water temperature, a.

restore the VHS to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be intat least i

HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the i

following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

1 b.

With the VHS inoperable due to inoperable fans and/or associated spray cells, restore to OPERABLE status within'72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; 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 SHUTDOWN with-in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With the UHS inoperable due to an inoperable NSCW transfer pump, c.

restore the transfer pump to OPERABLE status within 8 days or imple-ment an alternate method of transfer of basin content; 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 SHUT 00WN' within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Implementation of the alternate method-of transfer of basin content shall not exceed 31 days.

The provisions of Specification 3.0.4 are not applicable.

q SURVEILLANCE REQUIREMENTS 4.7.5 The ultimate heat sink shall be determined OPERABLE:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the water level and water temperature to be within their limits.

L b.

At least once per 31 days by verifying that the required ~ number of fans start and operate for at least 15 minutes, The NSCW transfer pumps will be tested pursuant to the requirement c.

of Specification 4.0.5.

V0GTLE UNITS - 1 & 2 3/4 7-13 l

1

a PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM (COMMON SYSTEM)

LIMITING CONDITION FOR OPERATION e

3.7.6. Four independent Control Room Emergency Filtration Systems (CREFS) shall be OPERABLE.

APPLICABILITY:

Either Unit in MODES 1, 2, 3, and 4.

MODES 5 and 6 during movement of irradiated fuel or movement of loads over irradiated fuel.

ACTION:

With both units in MODES 1, 2, 3, or 4:

With one Control Room Emergency Filtration System inoperable, a.

restore the inoperable system to OPERABLE status within 7 days OR initiate and maintain operation of one train of the CREFS in the unaffected unit in the emergency mode #* OR within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months lock closed l

the affected and lock open the unaffected unit's OSA intake dampers and place the affected unit 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 SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months **.

l-b.

With one Control Room Emergency Filtration System inoperable.in each unit, restore each inoperable system to OPERABLE status within 7 days OR initiate and maintain operation of both remaining CREFS in i

the emergency mode *,

l' With two Control Room Emergency Filtration Systems inoperable in a L

c.

unit, initiate and maintain operation of both trains of CREFS in the 1

unaffected unit in the emergency mode

0R within I h.our lock closed l

the affected and lock open the unaffected unit's OSA intake dampers and place the affected unit in at least H0T STANDBY within the next 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 **.

l-With only one unit in MODES 1, 2, 3, or 4:

With one Control Room Emergency Filtration System inoperable in an a.

operating unit, restore the inoperable' system to OPERABLE status within 7 days OR initiate and maintain operation of one train of the CREFS in the shutdown unit in the emergency' mode #*.

l b.

With one Control Room Emergency Filtration System inoperable in a shutdown unit, restore the inoperable system to OPERABLE status within 7 days OR either 1) lock closed the affected and_ lock open the unaffected unit's OSA intake dampers

OR 2) initiate and maintain operation of one train of CREFS in the operating unit in the emergency mode #*,

j With one Control Room Emergency Filtration System inoperable in each c.

unit, restore each ineperable system to OPERABLE status within 7 days OR lock closed the shutdown unit's OSA intake-dampers and lock open the operating unit's OSA intake dampers and initiate and maintain operation of the remaining CREFS train in the shutdown unit in the emergency mode *.

l

The initiated CREFS shall be Train B unless Train B is inoperable.

The provisions of Specification 3.0.4 are not applicable to either unit.

- The provisions of Specification 3.0.4 are not applicable to the unaffected unit.

V0GTLE UNITS - 1 & 2 3/4 7-14 AMENDMENT N0. 26 (UNIT 1)

AMENDMENT N0. 7 (UNIT 2)-

PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) d.

With two Control Room Emergency Filtration Systems inoperable in an operating unit, initiate and maintain operation of. both CREFS trains in the shutdown unit in the emergency Jode*,

l With two Control Room Emergency Filtration Systems inoperable in a e.

shutdown unit, either 1) lock closed the affected and lock open the unaffected unit's OSA intake damper 3* OR 2) initiate and maintain l

operation of both trains of the CREFS in the operating unit in.the emergency mode *.

l With both units in MODES 5 or 6, during movement of irradiated fuel or movement of loads over irradiated fuel in either unit.

With one Control Room Emergency Filtration System inoperable, a.

restore the inoperable system to OPERABLE status within 7 days OR either 1) lock closed the affected and lock open the unaffected unit's OSA intake dampers

OR 2) initiate and maintain operation of l

one train of the CREFS in the unaffected unit in the emergency mode #*.

.l b.

With one Control Room Emergency Filtration System inoperable in each unit, restore the inoperable system to OPERABLE status within 7 days-

+

OR initiate and maintain operation of one train of CREFS in the i

emergency mode *.

I With two Control Room Emergency Filtration Systems. inoperable in a c.

unit, either 1) lock closed the affected and lock open the unaffected unit's 05A intake dampers *, 0R 2) initiate and maintain l

operation of_one train of the CREFS in the unaffected unitiin'the; emergency mode *.

l d.

With three Control Room Emergency Filtration systems inoperable, either 1) lock closed the OSA intake dampers of the unit with two inoperable systems and lock open the OSA intake dampers of.the unit with one inoperable system and restore the.one inoperable system to OPERABLE status within 7 days OR initiate and maintain operation of-i the remaining train of CREFS in the emergency mode **; OR 2) initiate j'

l and maintain operation of the remaining train of CREFS in the emergency mode **.

l s

With four Control Room Emergency Filtration Systems inoperable or e.

with the OPERABLE CREFS required to be-in the emergency mode by i

ACTION a, b, c, or d above not ca OPERABLE emergency power source, pable of being powered by an suspend all operations involving movement of irradiatett fuel or movement of loads over irradiated e

fuel.

SURVEILLANCE REQUIREMENTS 4.7.6 Each Control Room Emergency Filtration System shall_be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is less than or equai to 85 F.

E#The initiated CREFS shall be Train B unless Train B is inoperable.

The provisions of Specification 3.0.4 are not applicable to either unit.

- The provisions of Specification 3.0.4 are not applicable-to either unit for entry into MODE 6 or 5.

V0GTLE UNITS - 1 & 2 3/4 7-14a AMENDMENT NO. 26 (UNIT 1),

AMENDMENT _ N0. 7 (UNIT 2)

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ML20005G284

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