Text

Amends 112 & 103 to Licenses NPF-2 & NPF-8,respectively, Changing TS to Implement Recommended Changes from GL 93-05, Line Item TS Improvements to Reduce Surveillance Requirements for Testing During Power Operation
	ML20081H505
Person / Time
Site:	Farley
Issue date:	03/20/1995
From:	Bateman W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20081H507	List: ML20081H505; ML20081H510;
References
	GL-93-05, GL-93-5, NUDOCS 9503240262
	Download: ML20081H505 (18)
	v • d • e

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[pm EtGgIt UNITED STATES NUCLEAR REGULATORY COMMISSION 5

f WASHINGTON, D.C. 2056Mm01

\\...../

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

DOCKET NO. 50-143 j

f JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICEf(S1 Amendment No. 112 License No. NPF-2 l

1.

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

A.

The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated January 9.-1995, 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 operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) 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 I

conducted in compliance with the Comission's regulations; D.

The issuance of this license amendment will not be inimical to the comon 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 Comission'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.

NPF-2 is hereby amended to read as follows:

1 9503240262 950320 PDR ADOCK 05000348 l

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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.112, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY ComISSION 1

'Lv -~

% ~~-

William H. Bateman, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 20, 1995 1

1

l ATTACHMENT TO LICENSE AMENDMENT NO.112 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-318 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

l

' Remove Paaes Insert Paoes 3/4 1-15 3/4 1-15 3/4 3-41 3/4 3-41 3/4 5-2 3/4 5-2 3/4 6-11 3/4 6-11 3/4 6-20 3/4 6-20 3/4 10-1 3/4 10-1 I

l f

I

r

-p REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) -

b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c)'

A power distribution map is obtamed from the movable incore detectors and F (Z) and F5 are verified to be within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and Q

.d)

De 'IliERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

SURVFIf LANCE REOUIREMENTS I

4.1.3.1.1 De position of each full length rod shall be detenmned to be wnhin the group demand limit by venfying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when l

the Rod Position Deviation Monitor is inoperable, then 6"f4 the group positions at least once por 4 l

hours.

j 4.1.3.1.2 Each full length rod not fully insened in the core shall be deternuned to be OPERABLE by movement of at least 10 steps in any one directen at least once per 92 days.

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i FARLEY - UNIT 1 3/4 1-15 AMENDMENTNO 26,111

m TABLE 4.3-3 mp RADIATION MONITORING INSTRUMENTATION SURVFII I ANCE REOUInFMENTS C3 CHANNEL MODES IN WHICH q

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INS 11tUMENT CHECK CAUBRA110N 1Y.ST REOUIRED 1.

AREA MONTIORS s

a.

Fuel Socrage Ptol Asen l

(R-5)

S R

Q e

b.

Contaansment Ases(R-27AAB)

S R

N/A I, 2, 3, 4 2.

PROCESS MONITORS a.

Fuel Storage Pool Area 5

Gaseous Activity-sa h,

Ventilation System isolation (R-25 AAB)

S R

Q l

b.

Containneemt i.

G==aa== Actmty a) Purge and Fuhause Isolation (R-24 AAB)

S R

Q ALL MODES l

b) RCS leakage Desectson (R-12)

S R

Q 1,2,3 & 4 l

ii. Particulaec Activity RCS Imkage Detection (R-II)

S

.R Q

I,2,3 & 4 l

5 c.

Control Roosa Isolatoon S

R Q

I,2,3. 4 and during l

g neowenent of k

irradiased fuel or z

- ono.d.

.O

,,,,i,,,g,,segg,,g

With fuel in the storage pool or building.

" With irradiased heel in the storage pool A

yi-i l

k EMERGENCY CORE COOLING SYSTEMS 4

$URVFH T ANCE REGI!TRFMFNTE (Canein=0 b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months aRer each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron nancantranon of the '

plator solution. This surveillance is not required when the volwne increase makeup source is the RWST and the RWST has not been diluted since ve.'.f,*g that the RWST -

boron concentration is within the accumulator boron aaae=*ranon limit.

l

,, At least once per 31 days when the RCS pressure is above the F-11 estpost by venfying c.

that power to each isolation valve w&i is asennaaread by a locked open disconnect device t

d.

At least once per 18 months by venfymg that each accumulator isolation valve opens automatically under each of the following conditions:

1.

When the RCS pressure (actual or simulated) exceeds the P-11 (Pressurimer i

Pressure Block of Safety Iryoction) setpoint, i

2.

Upon receipt of a safety injection test signal.

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i FARLEY-UNIT 1 3/45-2 AMENDMENT NO. 33, 11 l

L*.

l CONTAINMENT SYSTEMS' 3/4 6 2 DEPRESSURIZATION AND COOLING SYSTEMS i

CONTAINMENT SPRAY SYSTEM

-i LIMII[NG CONDITION FOR OPERATION l

3.6.2.1 Two irs rer.t containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the contamment sump.

APPLICABILITY-MODES 1,2,3 and 4.

i ACTION:

t With one containment spray system inoperable, restore the inoperable spray system 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 ; restors the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the followns 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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SURVFIf f ANCE REOUIREMENTS 4.6.2.1 Each contamment spray system shall be demonstrated OPERABLE:

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At least once per 31 days by verifying that each valve (manual, power operated or

}

a.

automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in

-t its correct position.

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b.

By verifying, that on recirculation flow, each pump develops s' discharge pressure of greater

.l than or equal to 210 psig when tested pursuant to Speci5 cation 4.0.5.

l c.

At least once per 18 months during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its corfect position l

an a Phase B test signal.

i 2.

Verifymg that each spray pump starts automatically on a Phase B test signal.

I d.

At least once por 10 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

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l FARLEY - UNIT 1 3/4 6 11 AMENDMENT NO. 26, 112 h

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+f CONTAINMENT SYSTEMS

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i ELECTRIC HYDROGEN RECOMBINERS - W LIMITING CONDITION FOR OPERATION t

'3.6.4.2' Two ter containment hydrogen recombiner systems shall be OPERABLE i

t APPLICABILTIY:

MODES I and 2.

ACTION-I J

)

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status I,

within 30 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 SURVFif LANCE REOUIREMENTS i

4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:

At least once each refueling interval by verifying during a recombiner system a.

functional test that the minimum hester sheath temperature increases to greater than or equal to 700'F within 90 minutes. Upon reaciung 700*F, acrease the power setting to maximum power for two minutes and verify that the power inster ren$s greater than or equal to 60 KW.

b.

At least once each refueling interval by:

l 1.

Performms a CHANNEL CALIBRATION of all recombaar astrumentation and control circuits.

4 I

2.

Verifying through a visual exanunaten that there is no evidonos of abnormal conditions within the recombiners (i.e., loose wiring or structural manart==,

l deposits of foreign matenals, etc.)

3.

Verifying the integrity of all heater electncal circuits by performmg a.

insistance to ground test following the above required fi-l test. The,

mistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.

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AMENDMENTNO; zg,11 l FARLEY - UNIT 1 3/4 6-20 i

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+ - - + -, -. - - - -. - -

c. -

t J/410 SPECIAL TEST EXCEPTIONS i

f 3/4.10.1 SHUTDOWN MARGIN t

LIMITING CONDITION FOR OPERATION I

3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for

[

measurement of dbntrol rod worth and shutdown margin provided the reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod (s).

ATPLICABILflY-MODE 2.

f ACTION:

t With any full length control rod not fully inserted and with less than the above reactivity a.

equivalent available for trip insertion, immediately initiate and continue boration at greater than or equal to 7000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

i b.

With all full length control rods fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 30 spm of a solution containing greater than or equal to 7000 ppm boron or its equivalent until ths,

SHUTDOWN MARGIN :vquired by Specification 3.1.1.1 is restored.

SURVFif f ANCE REOUIREMENTS 4.10.1.1 The position of each full length rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

f 4.10.1.2 Each full length rod not fully inserted shall be heated capable of full insertion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the i

SHUTDOWN MARGIN to less than the limits of Speci6caten 3.1.1.1.

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i P

r FARLEY - UNIT 1 3/4 10-1 AMENDMENT NO.26, 11; i

p uco y.-

4 UNITED STATES 0

3 NUCLEAR REGULATORY COMMISSION E

f WASHINGTON, D.C. 20 6 0001 l-SOUTHERN NUCLEAR OPERATING COMPANY. INC.

DOCKET NO 50-364 JOSEPH M. FArtEY NUCLEAR PLANT. UNIT 2 t

AMENDMENT TO FACILITY OPERATING LICENSE

[

Amendment No.103 I

License No. NPF-8 l

1.

The Nuclear Regulatory Consission (the Ccamission) has found that:

A.

The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated January 9,1995, 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 i

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 license amendment will not be inimical to the I

common defense and security or to the health and safety of the i

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. NPF-8 is hereby amended to read as follows:

a

E i

! s (2)

Technical Specifications 1

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.103, are hereby incorporated in the i

license.

Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COPMISSION w

do--

William H. Bateman, Director Project Directorate 11-1 Division of Reactor Projects - I/II i

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications i

Date of Issuance:

March 20, 1995 I

l i

i l

l ATTACHMENT TO LICENSE AMENDMENT NO.103 TO FACILITY OPERATING LICENSE NO. NPF-8 1

DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

, Remove Paaes Insert Paaes i

3/4 1-15 3/4 1-15 3/4 3-41 3/4 3-41 3/4 5-2 3/4 5-2 3/4 6-11 3/4 6-11 i

3/4 6-20 3/4 6-20 i

3/4 10-1 3/4 10-1 i

l 1

h i

i

i REACTIVITY CONTROL SYSTEMS i

LIMITING CONDITION FOR OPERATION (Continued) b)

ne SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is deternuned f

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

t c)

A power distribution map is obtained from the movable incore hc.ers and I

F (Z) and Fh are verified to be within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and Q

d)

He THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the

~

high neutron flux trip serpoint is reduced to less than or equal to 85% of RATED HIERMAL POWER.

SURVEILLANCE REOUTREMENTS l

4.1.3.1.1 He position of each full length rod shall be detemuned to be within the group demand 7

limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when

{

the Rod Position Deviation Monitor is inoperable, then verifying the group positions at least once per 4 i

hours.

s 4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 92 days.

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1 AMENDMENT NO.103 FARLEY - UNIT 2 3/4 1-15 j

arl TABLE 4.3 3 g

RADIATION MONITORING INSTRUMENTATION SURVFII I ANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENI CHECK CALIBRATION

ITST REOUIRED w

1.

AREA MONITORS a.

Fuel Storage Pool Area l

(R-5)

S R

Q b.

Containment Area (R-27A&B1 S

R N/A 1, 2, 3, 4 2.

PROCESS MONITORS a.

Fuel Storage Pool Area wk Gaseous Activity -

wi Ventilation System l

~

isolation (R-25 AAB)

S R

Q a

b.

Containment

i. Gaseous Activity a) Purge and Exhaust l

Isolation (R-24 AAB)

S R

Q ALL MODES b) RCS leakage Detecuon i

(R-12)

S R

Q I,2,3 & 4 l

ii. Particulate Activity h

RCS Leakage Detection b

(R-II)

S R

Q I,2,3 & 4 l

6 7

c.

Control Room isolation S

R Q

1,2,3. 4 and during l

movement of h

irradiated fuel or z

- onoads O

over irradiased fuel

With fincl in the storage pool or building.

" With irradiated fuel in the storage pool.

.. ~.

i

.t EMERGENCY CORE COOLING SYSTEMS t

i

~ SURVFff f AN('E RFOUTRFMFNTS (('antinuad)

I i

b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume inenase of greater than or equal to 1% of tank volume by verifying the boron concentration of the accumulator solution. This surwillance is not required when the volume increase makeup sonrce is the RWST and the RWST has not been diluted since voif/4 that the RWST boron cancentration is within the accumulator boron conamtration limit.

At least once per 31 days when the RCS pressure is above the P-ll setpost by S Zyirg l

c.

that power to each isolation valve operator is 6-" by a locked open Ascane device.

i i

d.

At least once per 18 months by venfymg that each accumulator iaalatian valve opens automatically under each of the following conditions-r i

1.

When the RCS pressure (actual or simulated) exceeds the P-ll (Pressurizer Pressure Block of Safety Injection) setpoint,

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2.

Upon receipt of a safety injection test signal.

s t

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FARLEY - UNIT 2 3/45-2 AMENDMENT NO. 26,103

O!

CONTAINMENT SYSTEMS 3/4 6 2' DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two i%t containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the containment sump..

j l

APPLICABILITY-MODES 1,2,3 and 4.

ACTION With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status i

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 ; restore the inoperable spray I

system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.2.1 Each containment spray system shall be herated OPERABLE:

At least once per 31 days by verifying that each valve (manual, power operated or a.

automatic) in the flow path that is not locked, scaled, or otherwise secured in position, is in j

its correct position.

-3 b.

By verifymg, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 210 psig when tested pursuant to Specification 4.0.5.

j c.

At least once per 18 months during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a Phase B test signal.

1 2.

Verifying that each spray pump starts automatically on a Phase B test signal.

d.

At least once per 10 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

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FARLEY - UNIT 2 3/4 6-11 AMENDMENT NO.103

y, CONTAINMENT SYSTEMS

g-.

ELECTRIC HYDROGEN RECOMBINERS - W 1

LIMITING CONDITION FOR OPERATION 3.6.4.2 Two ie containment hydrogen recombiner systems shall be OPERABLE.

1 APPLICABILITY:

MODES I and 2.

5 ACTION.

l With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status 1

within 30 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 .-

l SURVEILLANCE REOUIREMENTS I

4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:

At least once each refueling interval by verifying during a recombiner system a.

functional test that the minimum heater sheath temperature increases to greater i

than or equal to 700*F within 90 minutes. Upon reaching 700*F, increase the power setting to maximum power for two minutes and verify that the power meter repds 3

greater than or equal to 60 KW.

y a

b.

At least once each refueling interval by:

l-

-i 1.

Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits.

2.

Verifying through a visual exammation that there is no evidence of abnormal conditions within the recombiners (i.e., loose wiring or structural connections, i

deposits of foreign materials, etc.)

3.

Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functio.W testi The resistance to ground for any heater phase shall be greater than or equal to i

10,000 ohms.

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l FARLEY - UNIT 2 3/4 6-20 AMENDMENT NO.103

{

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" Tal L

3/4.'10 SPECIAL TEST EXCEPTIONS 3/4 10.1 SHUTDOWN MARGIN i-r LIMITING CONDITION FOR OPERATION q

~ 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for l

measurement of control rod worth and shutdown margin provided the reactivity equivalent to at least the -

highest estunated control rod worth is available for trip insertion from OPERABLE control rod (s).

i APPLICABILITY:

MODE 2.

ACTION:

[

t With any full length control rod not fully inserted and with less than the above reactivity

{

a.

equivalent available for trip insertion, immediately initiate and continue boration at greater than or equal to 7000 ppm buron or its equivalent until the SHUfDOWN MARGIN required by Specification 3.1.1.1 is restored.

b.

With all full length control rods fully inserted and the reactor suberitical by less than the above l

reactivity equivalent, immediately initiate and continue boration at greater than or equal to 30 spm i

of a solution containing greater than or equal to 7000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REOUIREMENTS 4.10.1.1 The position of each full length rod either partially or fbily withdrawn ball be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each full length rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the i

SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

i i

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f FARLEY - UNIT 2 3/4 10-1 AMENDMENT NO.103 j

a L

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ML20081H505

Text

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