Text

Amends 21 & 2 to Licenses NPF-68 & NPF-81,revising Tech Specs 3.3.3.6,3.4.4,3.7.1.2,3.7.7,3.9.1,Table 3.3-4 & Table 4.3-3 to Delete Footnotes No Longer Applicable
	ML20245G495
Person / Time
Site:	Vogtle
Issue date:	08/08/1989
From:	Matthews D; Office of Nuclear Reactor Regulation
To:	; City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp
Shared Package
ML20245G503	List: ML20245G495; ML20245G509;
References
	NPF-68-A-021, NPF-81-A-002 NUDOCS 8908160040
	Download: ML20245G495 (21)
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NUCLEAR REGULATORY COMMISSION r,;

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GEORGIA POWER COMPANY l

OGLETHORPE POWER CORPORATION MUNICIPAL ELECTIC AUTHORITY 0F GEORGIA i

CITY-0F DALTON, GEORGIA V0GTLE E'LECTRIC GENERATING PLANT, UNIT 1

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I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No. NPF-68 1.

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

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

Unit 1 the facility) Facility Operating License No. NPF-68 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 April 5,1989,. complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's. rules and regulations set forth in 10 CFR Chapter I; B..

The facility will operatt in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangeririg 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 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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Accordingly, the license. is hereby amended by page changes to the Technical i

Specifications-as indicated in the attachments to this license amendment

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and paragraph 2.C.(2) of Facility-Operating License No. NPF-68.is hereby amended to read as follows:

.(2) Technical Specifications and Environmental Protection' Plan L

~ The Technical Specifications contained in Appendix A, as revised through Amendment'No. 21, 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!amendraent is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:

David B. Matthews David B. Matthews, Director l

Project Directorate II-3 4

Division of. Reactor Projects-I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance:

August 8, 1989 1

0FFICIAL RECORD COPY

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2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-68 is hereby amended to read as follows:

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

21, 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 David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

Attachment:

Technical 5 specification Changes Date of Issuance:

August 8, 1989

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GEORGIk POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORCIA VCGTLE ELECTRIC GENERATING PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATIllG LICENSE I

Amendment No. 2 I

License No. NPF-81 1.

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

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

Unit 2 the facility) Facility Operating License No. NPF-81 filed by j

the Georgia Power Company acting for itself, Oglethorpe Power Corpo-ration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensees) dated April 5,1989, complies with the 3

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, 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 amendment can be conducted without endangering the health and i

safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set furth 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; i

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 i

been satisfied, l

1 I

1 1

. _ =.

- 2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of facility Operating License No. NPF-81 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Techr.ical Specifications contained in Appendix A, as revised through Amendment No. 2, 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 Protecticn Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:

David B. Matthews David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: August 8,.989 h

0FFICIAL RECORD COPY LS:hPpJJ-3 fPM:PDII-3 0GC-F Md 11-3 MRo j4 Hop kins:

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Accordingly, the license is hereby amendeo by page changes to the Technical Specifications as. indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. IlPF-81 is hereby amended to read as follows:

'(2). Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 2

,'and the Environmental Protection Plan l

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 dd David B.

atthews, Director Project Directorate II-3 Division of Reactor Projects-1/II 4

Office of Nuclear Reactor Regulation I

Attachment:

Technical Specification Changes I

Date of Issuance:

August 8, 1989 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 21 FACILITY OPERATING LICENSE NO. NPF-68 l

AND LICENSE AMENDMENT NO. 2 t

FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NOS. 50-424 AND 50-425 l

Replace the following pages of.the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding L

overleaf pages are also provided to maintain document completeness.

Amended Page Overleaf Page 3/4 3-46 3/4 3-45 3/4. 3-48 3/4 3-47 l

3/4 3-58 3/4 3-57 3/4 4-10 3/4 4-9 l

3/4 7-4 3/4 7-3 l

3/4 7-17 3/4 7-18 3/4 9-1 3/4 9-2 4

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INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITION FOR OPERATION

' 3.3.3.1 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-4 shall be OPERABLE with their Alarm / Trip Setpoints within the specified limits.

. APPLICABILITY:

As shown in Table 3.3-4.

ACTION:

With a radiation monitoring channel Alarm / Trip Setpoint for plant a.

operations exceeding the value shown in Table 3.3-4, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels for plant operations inoperable, take the ACTION shown in Table 3.3-4.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

i SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST for the MODES and at the frequencies shown in Table 4.3-3.

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I TABLE NOTATIO._NS.

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a During movement of irradiated fuel er movement of loads over irradiated fuel within containment.

b During movement of. irradiated fuel or movement of loads over irradiated

fuel, RE-2565 is considered OPERABLE if the Particulate (RE-2565A) and-Iodine-c (RE-2565B) Monitors are OPERABLE, or the noble gas monitor (RE-2565C) is l

OPERABLE.

l ACTION STATEMENTS ACTION 29 -

With the number of OPERABLE Channels less than the Minimum i

Channels OPERABLE requirement, satisfy the ACTION requirements of Specification 3.4.6.1.

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INSTRUMENTATION

. ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels 'shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

As shown in Table 3.3-8 l

l SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE:

a.

Every 31 days by performance of a CHANNEL CHECK, and b.

Every 18 months by performance of a CHANNEL CALIBRATION.

l V0GTLE UNITS - 1 & 2 3/4 3-58 Amendment No. 21 (Unit 1)

Amendment No. 2 (Unit 2)

s REACTOR COOLANT SYSTEM.

3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.3 The pressurizer shall be OPERABLE with a water volume of less than or equal to 92% (1656 cubic feet), (LI-0459A, LI-0460A, LI-0461A) 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 only one group of pressurizer heaters OPERABLE, restore at least 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 SHUTDOWN 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 System 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. hours.

l SURVEILLANCE REQUIREMENTS 4.4.3.1 The pressurizer water volume shall be determined to be within its l

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 j

heaters shall be verified by energizing the heaters and measuring circuit l

current at least or.ce per 92 days.

L 1

l 4

V0GTLE UNITS - 1 & 2 3/4 4-9 w__-__-___________

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. REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES-

. LIMITING CONDITION FOR OPERATION 3.4.4 A1.1 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, because of excessive seat

. leakage, 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); 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 HOT SHUTDOWN within the-following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one or more PORV(s) inoperable due to causes other than exces-sive seat leakage, 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 block valve, and 1.

With only one PORV OPERABLE, restore at least a total of two PORVs to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 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 , or 2.

With no PORVs 0PERABLE, restore at least one PORV to OPERABLE.

status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 (1) restore c.

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; and (2) apply ACTION b above, as appropriate, for the isolated PORV(s).

d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.4.1 Each PORV shall be demonstrated OPERABLE at least once per 18 months by:

a.

Operating the valve through one complete cycle of full travel, and b.

Performing a CHANNEL CALIBRATION.

I V0GTLE UNITS - 1 & 2 3/4 4-10 Amendment No. 21 (Unit 1) i Amendment No.

2 (Unit 2)

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TABLE 3.7-2

)

STEAM LINE SAFETY VALVES PER LOOP j

LIFT SETTING VALVE NUMBER (i 1%)*

ORIFICE SIZE 3

SG-1 SG-2 SG-3 SG-4 1.

PSV 3001 PSV 3011 PSV 3021 PSV 3031 1185 psig 16.0 in,

z 2.

PSV 3002 PSV 3012 PSV 3022, PSV 3032 1200 psig 16.0 in,

2 3.

PSV 3003 PSV 3013 PSV 3023 PSV 3033 1210 psig 16.0 in,

2 4.

PSV 3004 PSV 3014 PSV 3024 PSV 3034 1220 psig 16.0 in,

2 1

5.

PSV 3005 PSV 3015 PSV 3025 PSV 3035 1235 psig 16.0 in,

2 l

The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

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

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4 '

o PLANT SYSTEMS' AUXILIARY FEEDWATER SYSTEM

- LIMITING CONDITION FOR OPERATION 3 7.1.2 At.least three independent steam generator auxiliary feedwater

. pumps and associated flow paths shall be OPERABLE with:

o

.-Two motor-driven' auxiliary feedwater pumps, each capable of being a.

powered from separate emergency busses, and b.

One steam turbine-driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY:

MODES 1, 2, and 3.

l ACTION:

With one auxiliary feedwater pump inoperable, restore the required a.

auxiliary feedwater 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 within the next 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 .

b.

With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY 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 .

c.

With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

L i

SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1)

Verifying that each motor-driven pump develops a discharge pressure of greater than or equal to 1605 psig at a flow of greater than or eq:al to 150 gpm (FI-15101, FI-15102);

2)

Verifying that the steam turbine-driven pump develops a dis-charge pressure of greater than or equal to 1675 psig at a flow of greater than or equal to 145 gpm (FI-15100) when the seccndary steam supply pressure (PI-5105A, PI-5105B) is greater than 900 psig.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

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l V0GTLE UNITS - 1 & 2 3/4 7-4 Amendment No. 21 (Unit 1)

Amendment No.

2 (Unit 2)

E-__ _ - - _ _ _

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y PLANT SYSTEMS' 3/4.7.7 PIPING PENETRATION AREA FILTRATION AND EXHAUST SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7 Two independent Fiping Penetration Area Filtration and Exhaust Systems shall be OPERABLE.

A. APPLICABILITY:

MODES 1, 2, 3, and 4 ACTION:

With one Piping Penetration Area Filtration and Exhaust System inoperable, restore the inoperable system to OPERABLE status within 7 days 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 .

SURVEILLANCE REQUIREMENTS 4.7.7 Each Piping Penetration Area Filtration and Exhaust System shall be demonstrated OPERABLE:

I At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.

from the control room, flow (FI-12629, FI-12542) through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heater control circuit energized; b.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communi-cating w'th the system by:

1.

Verifying that the cleanup system satisfies the in place testing acceptance criteria of greater than or equal to 99.95% filter retention while operating the system at a flow rate of 15,500 cfm i 10% and performing the following tests:

i (a) A visual inspection of the piping penetration area filtration and exhaust system shall be made before each DOP test or activated carbon adsorber section leak test in accordance l

with Section 5 of ANSI N510-1980.

J (b) An in place DOP test for the HEPA filters shall be performed in accordance with Section 10 of ANSI N510-1980.

(c) A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall be performed in accordance with Section 12 of ANSI N510-1980.

V0GTLE UNITS - 1 & 2 3/4 7-17 Amendment No. 21 (Unit 1)

Amendment No. 2 (Unit 2)

{

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0

\\

~

PLANT SYSTEMS

~

3/4.7.7 PIPING PENETRATION AREA FILTRATION AND EXHAUST SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 2)

Verifying within 31 days atter removal that a laboratory analysis of a representative carbon sample obtained in accordance with Section 13 of ANSI N510-1980 meets the laboratory testing cri-teriora of greater than or equal to 99.8% when tested with methyl iodide at 30'C and 70% relative humidity.

3)

Verifying a system flow rate of 15,500 cfm i 10% during system operation when tested in accordance with Section 8 of ANSI N510-1980.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation, by verifying, c.

within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtained in accorciance with Section 13 of ANSI N510-1980 meets the laboratory testing criteria of greater than or equal to 99.8% when tested with methyl iodide at 30*C and 70%

relative humidity; d.

At least once per 18 months by: -

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the system at a flow rate of 15,500 cfm i 10%.

2)

Verifying that the system starts on a Containment Ventilation Isolation test signal, 3)

Verifying that the system maintains the Piping Penetration Fil-tration Exhaust Unit Room at a negative pressure of greater than or equal to 1/4 inch Water Gauge relative to the outside atmosphere (PDI-2550, PDI-2551), and 4)

Verifying that the heaters dissipate 8014 kW when tested in accordance with Section 14 of ANSI N510-1980.

e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95% of the DOP when they are tested in place in accordance with Section 10 of ANSI N510-1980 while operating the system at a flow rate of 15,500 cfm i 10%.

f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with Section 12 of ANSI N510-1980 while operating the system at a flow rate of 15,500 cfm i 10%.

V0GTLE UNITS - 1 & 2 3/4 7-18

3]4_. 9 REFUELING OPERATIONS 3/4.9.1 BORONJ QNCENTPFION LIMITING CONDITION FOR OPERATIDW 3.9.1 The buron concentration of all filled oortions of the Reactor Coolant System and the refueling canal shall be maint'ained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions are met:

a.

AK f 0.95 or less, ur l

eff b.

A boron concentration of greater than or equal to 2000 ppm.

l Additionally, valves 1208-04-175, 1208-U4-177, 1208-U4-183, and 1208-U4-176 shall be closed and secured in position.

APPLICABILITY:

MODE 6.

ACTION:

With the requirements of a. and b. above not satisfied, immediately a.

suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 30 gpm of a solutian containing greater than or equal to 7000 ppm boron or its equivalent until K,77 is reduced to less than i

or equal to 0.95 or the boron concentration is restored to greater than or equal to 2000 ppm, whichever is the more restrictive.

b.

With valves 1208-U4-175, 1208-U4-177, 1208-U4-183s and 1208-U4-176 not closed and secured in position, immediately close and secure in position.

SURVEILLANCE REQUIREMENTS 4.9.1.1 The boron concentration of the Reactor Coolant System and the refueling

)

canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

i 4.9.1.2 Valves 1208-04-175, 1208-U4-177, 1208-04-183, and 1208-U4-116 shall be verified closed and secured in nosition by mechanical stops at least once par 31 days.

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V0GTLE UNITS - 1 & 2 3/4 9-1 Amendment No. 21 (Unit 1)

Amendment No. 2 (Unit 2)

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a L ;; y REFUFLING OPERATIONS-L 3/4.9.2 INSTRUMENTATION I

LIMITINGQ0NDITIO'lFOROPERATION

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3.9.2 As'a minimum, two Sourre Range Neutron Flux Monitors (NI-0031B,0&E,.

i NI-O'0328,0&G) shall be OPERABLE, uch with continuous visual ir.dicatfro in the

-1 contro' room and cne with audible indication in the containment and control room.

AP.PLICABILIT'd N0DE 6.

1j Ag13:

]

With une of the 3bc,ve required clonitors ineperable or not operating, A.

'immediately suspend all opet ations involving CORE ALTERATIONS or positive reectivity changes.

b.

With both of the above required monitors inoperable or not opersting, determine the boron concentration of the Reactor Coolant System at I

least once ner 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

i l

1 SURVEILLANCE REQUIREMENTS 4.9.2 Each Source Range Neutron Flux Monitor (NI-00318,0&E, NI-00328,D&G) shall be demonst-aced OPERABLE by performance of:

a.

A CHANNEL CH2CK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the initial stait of CORE ALTERATIONS, and An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days.

c.

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

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ML20245G495

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