Text

Amends 42 & 22 to Licenses NPF-68 & NPF-81,respectively, Including Rev to Denote Correct Location of Refs for Shutdown Margin Requirements for Mode 5 & Control Rod Bank Insertion Limits
	ML20082J309
Person / Time
Site:	Vogtle
Issue date:	08/21/1991
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
ML20082J312	List: ML20082J309; ML20082J323;
References
	NPF-68-A-042, NPF-81-A-022 NUDOCS 9108280031
	Download: ML20082J309 (9)
	v • d • e

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NUCLEAR REGULATORY COMMittSION

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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET N0. 50-424 V0GTLE ELECTRIC GENERATING PLANT UN'TJ 2

AMENDMENT TO FACILITY OPERATING LICENSE Ameridment No. 12 License No. NPF-68 1.

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

A.

The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees) dated March 29, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the At;t), and the Commission's rules and regulations set forth in 10 CFR Chapter 1; 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 set forth in 10 CFR Chapter I; D.

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

E.

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

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. 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 read as follows:

Technical Specifications and Fnvironmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 42, 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.

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

FOR THE NUCLEAR REGULATORY COMMISSION

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',.Daf148[.Matthews, Director Project Directorate !!-3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: August 21, 1991 I

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UNITED STATES l i NUCLEAR REGULATORY COMMISSION

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WASHINGTON. D.C. 20f65

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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION l

MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-425 i

V0GTLE ELECTRIC GENERATING PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No. 22 i

License No. NPF-81 1.

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

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

Unit 2 the facility) Facility Operating L cense No. NPF-81 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corpo-ration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees) dated March 29, 1991, complies with tie 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 set forth in 10 CFR Chapter I; D.

The issuance of this licerse 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.

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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 contained in Appendix A, as revised through Amendment No. 22, 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.

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

FOR THE NUCLEAR REGULATORY COMMISSION hj h)0V gl} Project Directorate 11-3 v

B. Matthews, Director Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: August 21, 1991

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i ATTACHMENT TO LICENSE AMENDMENT NO. 42 FACILITY OPERATING LICENSE NO. NPF-68 AND LICENSE AMENDMENT NO. 22 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NOS. 50-424 AND 50-425 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and i

contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain docurent completeness.

Remove Pages insert Pages 3/4 1-7* and 3/4 1-8 3/4 1-7* and 3/4 1-8 3/4 1-9* and 3/4 1-10 3/41-9* and 3/41-10 3/4 1-11* and 3/4 1-12 3/4 1-11* and 3/4 1-12 B 3/4 2-2 B 3/4 2-2

Overleaf pages contain no changes

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REACTIVITY CONT 00L SYSTEMS 3/4.1.2 BORATION SYSTEMS FLOW PATH - SHUTDOWN LIMITING CONDITION FOR OP'.]ATION 3.1.2.1 As a minimum, one of +ile following boron injection flow paths shall be OPERABLE:

a.

A flow path from the boric acid storage tank via a boric acid transfer pump and a charging pump to the Reactor Coolant System if the boric acid storage tank in Specification 3.1.2.Sa. is OPERABLE, or b.

A flow path frc:a the refueling water storage tank via a charging pump to the Reactor Coolant System if the refueling water storage tank in Specification 3.1.1.5b is OPERABLE.

AoPLICABILITY:

MODES 5 and 6.

ACTION:

With none of the above flow paths OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

i SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of-the above r6 quired flow paths shall be demonstrated OPERA?is a.

at least once per 7 days when the boric acid storage-tank is a re-i quired water source, verify that the applicable portions of the i

auxiliary building (TISL 12410 or TISL 12411,'TISL 12412 or TISL 12413, TISL 12414 or TISL 12415. TISL 12416 or TISL 12417. TISL 20900 or i

TISL 20901, TISL 20902 or TISL 20903, and TISL 20904 or TISL 20905) i are 172*F, and.the portions of the flow path for which ambient l

temperature indication are not provided are 1 65'F, and

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b.

-At least once per 31 days by verifying that each valve (manual, 3

power-operated, or automatic) in the flow path that is not locked, j

sealed, or otherwise secured in position, is in its correct

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

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REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING

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3.1.2.2 At least two of the following boron injection flow paths shall be OPERABLE:

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a.

One or more flow paths from the boric acid storage tank via a boric acid transfer pump and a charging pump to the Reactor Coolant System i

(RCS),and/or j

b.

One or more flow paths from the refueling water storage tank via charging pumps to the RCS.

l APPLICABILITY:

MODES 1, 2, 3, and 4.

l ACTION:

l With only one of the above required boron injection flow paths to the RCS OPERABLE, restore at least two boron injection flow paths to the RCS 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 and borated l

to a SHUTDOWN MARGIN as specified in the CORE OPERATING LIMITS REPORT for MODE 5 at 200*F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two. flow paths to i

OPERABLE status within the next 7 days-or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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SURVEILLANCE REQUIREMENTS 4.1.2.2 At least two of the above required flow paths shall-be demonstrated OPERABLE:

a.

At least once per 7 days when the boric acid tank is a required i

water source, verify that the applicable portions, of the auxiliary I

building (TISL 12410 or TISL 12411, TISL 12412 or TISL 12413,-

TISL 12414 or TISL 12415 TISL 12416_or TISL 12417, TISL 20900 or TISL 20901, TISL 20902 or TISL 20903, and TISL 20904 or lISL 20905) are > 72*F and the portions of the flow path for which ambient temperature indication are not provided are 165'F; b.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealea, or otherwise secured in position, is in its correct position; j

c.

At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2a. delivers at least 30 gpm to the RCS.

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V0GTLE UNITS - 1 & 2 3/4 1-8 Amendment NO. 42 (Unit 1) i Amendment No. 22 (Unit 2) i i

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REACTIVITY CONTROL SYSTEMS 4

i CHARGING PUMP - SHUTOOWN i

LIMITING CONDITION FOR'0PERATION f

'3.1.2.3 At least one charging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE.

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APPLICABILITY:

MODES 5 and 6.

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ACTION:

With no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

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I SURVEILLANCE REQUIREMENTS t

4.1.2.3 At least once per 18 months the above required charging pump shall be

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demonstrated OPERABLE by verifying that the flow path required by Specifica-tion 3.1.2.la is capable of delivering at least 30 gpa to the RCS.

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5 V0GTLE UNITS - 1 & 2 3/4 1-9 j

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REACTIVITY CONTROL SYSTEMS I

CHARGING-PUMPS - OPERATING LIMITING CON 0! TION FOR OPERATION i

3.1.2.4 At least two charging pumps shall be OPERABLE.

APPLICNBILITY:

MODES 1, 2, 3, and 4.

ACTION:

l With only one charging pump OPERABLE, restore at least two charging pumps 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 and borated to a SHUTDOWN MARGIN as specified in the CORE OPERATING LIMITS REPORT for_ MODE 5 at l

200*F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

t SURVEILLANCE REQUIREMENTS 4.1.2.4-At least-two charging pumps shall be demonstrated OPERABLE by testing i

pursuant to Specification 4.1.2.2c.

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V0GTLE UNITS - 1 & 2 3/4 1-10 Amendment NO. 42 (Unit 1) i Amendment No. 22 (Unit-2)

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REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCE - SHUT 00WN LIMITING CONDITION FOR OPERATION l

j 3.1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE:

a.

A Boric Acid Storage Tank with:

1)

A minimum contained borated water volume of 9504 gallons (19%

of instrument span) (LI-102A, LI-104A),

2)

A boron concentration between 7000 ppm and 7700 ppm, and 3)

A minimum solution temperature of 65"F (TI-0103).

b.

The refteling water storage tank (RWST) with:

t 1)

A minimum contained borated water volume of 99404 gallons (9% of instrument span) (LI-0990A&B, LI-0991A&B, LI-0992A, LI-0993A),

2)

A boron concentration between 2400 ppm and 2600 ppm, and i

3)

A minimum solution temperature of 54 F (TI-10982).

l APPLICABILITY:

MODES 5 and 6.

l ACTION:

With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or pcsitive reactivity changes.

SURVEILLANCE REQUIREMENTS 4.1.2.5 The above required borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1)

Verifying the boron concentration of the water, 2)

Verifying the contained borated water volume, and 3)

When the boric acid storage tank is the source of borated water and the ambient temperature of the boric acid storage tank room (TISL-20902, TISL-20903) is <72*F, verify the boric acid storage tank solution temperature is > 65 F.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature (TI-10982) when it is the source of borated water and the outside air temperature is less than 50 F.

1 V0GTLE UNITS - 1 & 2 3/4 1-11 l

REACTIVITY-CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2,6 As a minimum, the following borated water source (s) shall be OPERABLE as_ required by Specification 3.1.2.2:

a.

A Boric Acid Storage Tank with:

1)

A minimum contained borated water volume of 36674 gallons (81%

of instrument span) (LI-102A, LI-104A),

2)

A boron concentration between 7000 ppm and 7700 ppm, and 3)

A minimum solution temperature of 65'F (TI-0103),

b.

The refueling water storage tank (RWST) with:

1)

A minimum contained borated water volume of 631478 gallons (86%

of instrument span) (LI-0990A&B, LI-0991A&B,-LI-0992A, LI-0993A),

2)

A boron concentration between 2400 ppe and 2600 ppe, 3)

A minimum solution temperature of 54*F, 4)

A maximum solution temperature of 116*F (TI-10982), and 5)

RWST Sludge Mixing Pump Isolation Valves capable of closing on RWST low-level.

APPLICABILITY: H0 DES 1, 2, 3, and 4.

ACTION:

a.

With the Boric Acid Storage Tank inoperable and being used as-one of the above_ required borated water sources, restore the tank 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 borated to a SHUTDOWN MARGIN as specified in the CORE OPERATING LIMITS REPORT for MODE 5 at 200*F; restore the Boric Acid Storage Tank to OPERABLE status within the -

next 7~ days or be in COLD SHUTOOWN within the next_30 hours, b.

With the RWST inoperable, except for the Sludge Mixing Pump Isolation Valves, restore the tank to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

V0GTLE UNITS - 1 & 2 3/4 1-12 Amendment NO. 42 (Unit 1)

Amendment No. 22 (Unit 2)

4 POWER DISTRIBUTION LIMITS BASES AXIAL FLUX DIFFERENCE (Continued)

Although it is intended that the plant will be operated with the AFD within the target tand required by Specification 3.2.1 about the target flux difference, during rapid plant THERMAL POWER reductions, control rod motion will cause the AFD to deviate outside of the target band at reduced THERK\\L POWER levels.

This deviation will not affect the xenon redistribution suffi-ciently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duratien of the deviation is limited.

Accordingly, a 1-hour penalty deviation limit cumulative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is provided for operation outside of the target band but within the limits specified in the COLR while at THERMAL POWER levels between 50% and 90% of RATED THERMAL POWER.

For THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER, deviations of the AFD outside of the target band are less significant.

The penalty of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months actual time reflects this reduced significance.

Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm.

The computer deter-mines the 1-minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for two or more OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than 90% of RATED THERMAL POWER.

During operation at THERMAL POWER levels between 50% and 90% and between 15% and 50% RATED THERMAL POWER, the computer outputs an alarm message when the penalty deviation accumulates beyond the limits of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , respectively.

l Figure B 3/4 2-1 shows a typical monthly target band.

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F H

The limits on heat flux hot channel factor and nuclear enthalpy rise hot channel f actor ensure that:

(1) the design limits on peak local power density and minimum DNBR are not exceeded and (2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200 F ECCS acceptance criteria limit.

Each of these is measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3.

This periodic surveillance is sufficient to ensure that the limits are maintained provided:

a.

Control rods in a single group move together with no individual rod insertion differing by more than i 12 steps, indicated, from the group demand position; b.

Control rod banks are sequenced with a constant tip-to-tip distance i

between banks as described in Specification 3.1.3.6; l

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V0GTLE UNITS - 1 & 2 2 3/4 2-2 Amendment No.42 (Unit 1)

Amendment No.22 (Unit 2)

ML20082J309

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