Text

Amends 97 & 89 to Licenses NPF-2 & NPF-8,respectively, Revising TS 3/4.4.5 & Bases 3/4.4.5
	ML20012G693
Person / Time
Site:	Farley
Issue date:	03/08/1993
From:	Jeffrey Mitchell; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20012G694	List: ML20012G693; ML20012G695;
References
	NUDOCS 9303110368
	Download: ML20012G693 (14)
	v • d • e

.

r.* u%q'o, UNITED STATES

['

^,

NUCLEAR REGULATORY COMMISSION g

p WASHINGTON. D C. 20555

,e#

...+

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. NPF-2 1.

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

A.

The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated October 13, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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.

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:

i l

9303110368 930308 PDR ADOCK 05000348 P

PDR

t r

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as I

revised through Amendment No. 97, 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 COMMISSION

. f. h Y

jfkJocelynA.Mitchell,ActingDirector i

Project Directorate 11-1 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 8, 1993 F

..-..A L l

s.

ATTACHMENT TO LICENSE AMENDMENT NO. 97 l

TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Paoes Insert Paoes 3/4 4-8 3/4 4-8 3/4 4-8a B3/4 4-2 83/4 4-2 B3/4 4-2a b

r i

f

{

REACTOR COOLANT SYSTEM l

3/4.4.5 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.5 Both power-operated relief valves (PORVs) and their associated block l.

I valves shall be OPERABLE.

l APPLICABILITY: MODES 1, 2, and 3.

'{

ACTION:

a.

With one or both PORVs inoperable because of excessive seat leakage, within I hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s) with power maintained to the 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 H0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one PORV inoperable due to causes other than excessive seat i

leakage, within I hour either restore the PORV to OPERABLE status or close its associated block valve and remove power'from the block i

valve; restore the PORV to OPERABLE status within the following 72' hours 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 t

SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

j i

c.

With both PORVs inoperable due to causes other than excessive seat l

leakage, within I hour either restore at least one PORV to OPERABLE status or close its associated block valve and remove power from the block valve and 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 .

d.

With one block valve inoperable, within I hour restore the block

]

valve to OPERABLE status or place its ' associated PORV in manual ~

.i control. Restore the. inoperable block valve to OPERABLE status 1

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 .

-l e.

With both block valves inoperable, within I hcur restore both block I

valves to OPERABLE status or place their associated PORV in manual control.

Restore at least one block valve to OPERABLE status within i

the next hour and restore the remaining inoperable block valve 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 HOT SHUTDOWN within the-l following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

f.

The provisions of Specification 3.0.4 are not applicable.

a FARLEY-UNIT 1 3/4 4-8 AMENDMENT NO. 26, 97 i

9 REACTOR COOLANT SYSTEM SURVEILLANCE REOUTREMENTS 4.4.5.1 Each PORY shall be demonstrated OPERABLE at least once per 18 months by:

a.

Operating the PORV through one complete cycle of full travel during MODE 3 or 4, and b.

Operating the PORV through one complete cycle of full travel using the backup PORV control system, and c.

Performing a CHANNEL CALIBRATION of the actuation instrumentation.

4.4.5.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b or c in Specification 3.4.5.

l FARLEY-UNIT 1 3/4 4-8a AMENDMENT NO.

97

REACTOR COOLANT SYSTEM BASES r

3/4.4.2 and 3/4.4.3 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig.

Each safety valve is designed to relieve 345,000 lbs per hour of saturated steam at the valve set point. The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown.

In the event t

that no safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpres-surization.

In addition, the Overpressure Protection System provides a diverse means of protection against RCS overpressurization at low temperatures.

During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2735 psig.

The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss of load assuming no reactor trip until the first Reactor Protective System trip set point is reached r

(i.e., no credit is taken for a direct reactor trip on the loss of load) and also assuming no operation of the power operated relief valves or steam dump valves.

Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.

3/4.4.4 PRESSURIZER The limit on the maximum water volume in the pressurizer assures that the parameter is maintained within the normal steady state envelope of operation assumed in the SAR. The limit is consistent with the initial SAR assumptions.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation. The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system. The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability of the plant to control Reactor Coolant Pressure and establish natural circulation.

3/4.4.5 RELIEF VALVES (PORVs)

The power operated relief valves and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump. Operation of the PORVs minimizes the undesirable opening of the spring-loaded pressurizer code safety valves.

l l

1 FARLEY-UNIT I B 3/4 4-2 AMENDMENT NO. 26, 97 1

REACTOR COOLANT SYSTEM BASES The OPERABILITY of the PORVs and block valves is determined on the basis of their being capable of performing the following functions:

A.

Manual control of PORVs to control reactor coolant system pressure. This is a function that is used for the steam generator tube rupture accident and for plant shutdown.

B.

Maintaining the integrity of the reactor coolant pressure boundary. This i

is a function that is related to controlling identified leakage and ensuring the ability to detect unidentified reactor coolant pressure boundary leakage.

C.

Manual control of the block valve to:

(1) unblock an isolated PORV to allow it to be used for manual control of reactor coolant system pressure (Item A), and (2) isolate a PORY with excessive seat leakage (Item B).

1 D.

Manual control of a block valve to isolate a stuck-open PORV.

The Surveillance Requirements found in Specification 4.4.5.1 for the PORVs

[

and Specification 4.4.5.2 for the block valves improve reliability and provide the assurance that the PORVs and block valves can perform their functions. The PORVs are stroke tested during MODES 3 or 4 with the associated block valves closed in order to eliminate uncertainty introduced by testing the FORVs at lesser system temperatures than expected during actual operating conditions.

The block valves are exempt from the surveillance requirements to cycle the valves when they have been closed to comply with the ACTION requirements. This precludes the need to cycle the valves with full system differential pressure or when maintenance is being performed to restore an inoperable PORV to operable status. Surveillance requirement 4.4.5.1.b includes testing which demonstrates the functionality of the backup PORV control system.

t FARLEY-UNIT 1 B 3/4 4-2a AMENDMENT NO. 97 t

~ f[

[o, UNITED STATES g

NUCLEAR REGULATORY COMMISSION y

g E

WASHINGTON, D. C. 20555 8

%,...../

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. NPF-8 1.

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

A.

The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated October 13, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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.

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:

?

. (2)

Technical Specifications The Technical Specifications contained in appendices A and 8, as revised through Amendment No. 89, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance wi'.h 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 COMMISSION h

f J

[ProjectDirectorateII-I ocelyn A. Mitchell, Acting Director

~

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachmer,t:

Changes to the Technical Specifications Date of Issur.nce:

March 8, 1993 L_____-___-___-____-______________-_______-_____-__-________----_

1 t

ATTACHMENT TO LICENSE AMENDMENT NO. 89 TO FACILITY OPERATING LICENSE NO. NPF-8 l

i 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.

!'l Remove Paaes Insert Paaes 1

3/4 4-8 3/4 4-8 i

t 3/4 4-8a l

B3/4 4-2 B3/4 4 l l

83/4 4-2a

-j i

I I

I l

f 4

9 f

m

T REACTOR COOLANT SYSTEM i

3/4.4.5 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.5 Both power-operated rei tef valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY.1 MODES 1, 2, and 3.

ACTION:

a.

With one or both PORVs 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) with power maintained to the 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 PORV inoperable due to causes other than 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 to OPERABLE status or close its associated block valve and remove power from the block valve; restore the PORV 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 .

c.

With both PORVs inoperable due to causes other than excessive seat leakage, within I hour either restore at least one PORV to OPERABLE status or close its associated block valve and remove power from the block valve and 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 .

d.

With one block valve inoperable, within I hour restore the block valve to OPERABLE status or pleca its associated PORY in manual control.

Restore the inoperable block valve 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 .

e.

With both block valves inoperable, within I hour restore both block valves to OPERABLE status or place their associated PORY in manual control.

Restore at least one block valve to OPERABLE status within the next hour and restore the remaining inoperable block valve 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 HOT SHUTDOWN within the following 6

)

hours.

f.

The provisions of Specification 3.0.4 are not applicable.

I FARLEY-UNIT 2 3/4 4-8 AMENDMENT NO. O, 89

REACTOR COOLANT SYSTEM SURVEILLANCE REOUTREMENTS 4.4.5.1 Each PORV shall be demonstrated OPERABLE at least once per 18 months by:

a.

Operating the PORV through one complete cycle of full travel during MODES 3 or 4, and b.

Operating the PORV through one complete cycle of full travel using the backup PORY control system, and c.

Performing a CHANNEL CALIBRATION of the actuation instrumentation.

4.4.5.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b or c in Specification 3.4.5.

i t

FARLEY-UNIT 2 3/4 4-8a AMENDMENT NO.

89

REACTOR COOLANT SYSTEM BASES 3/4.4.2 and 3/4.4.3 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig.

Each safety valve is designed to relieve 345,000 lbs per hour of saturated steam at the valve set point.

The relief capacity of a single safety valve is' adequate to relieve any overpressure condition which could occur during shutdown.

In the event that no safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpres-surization.

In addition, the Overpressure Protection System provides a diverse means of protection against RCS overpressurization at low temperatures.

During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2735 psig.

The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss of load assuming no reactor r

trip until the first Reactor Protective System trip set point is reached (i.e., no credit is taken for a direct reactor trip on the loss of load) and also assuming no operation of the power operated relief valves or steam dump valves.

r Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.

3/4.4.4 PRESSURIZER i

i The limit on the maximum water volume in the pressurizer assures that the parameter is maintained within the normal steady state envelope of operation assumed in the SAR. The limit is consistent with the initial SAR assumptions.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation. The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system. The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability of the plant to control Reactor Coolant Pressure and establish natural circulation.

3/4.4.5 RELIEF VALVES (PORVs)

The power operated relief valves and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump. Operation of the PORVs minimizes the undesirable opening of the spring-loaded pressurizer code safety valves.

l FARLEY-UNIT 2 B 3/4 4 AMENDMENT NO. 58, 85, 89

REACTOR COOLANT SYSTEM BASES The OPERABILITY of the PORVs and block valves is determined on the basis of their being capable of performing the following functions:

i A.

Manual control of PORVs to control reactor coolant system pressure. This is a function that is used for the steam generator tube rupture accident and for plant shutdown. This function has been classified as safety related for more recent plant designs.

B.

Maintaining the integrity of the reactor coolant pressure boundarf. This is a function that ' related to controlling identified leakage and ensuring the ability to detect unidentified reactor coolant pressure boundary leakage.

C.

Manual control of the block valve to:

(1) unblock an isolated PORV to allow it to be used for manual control of reactor coolant system pressure (Item A), and (2) isolate a PORV with excessive seat leakage (Item B).

D.

Manual control of a block valve to isolate a stuck-open PORV.

The Surveillance Requirements found in Specification 4.4.5.1 for the PORVs and Specification 4.4.5.2 for the block valves improve reliability and provide the assurance that the PORVs and block valves can perform their functions. The PORVs are stroke tested during MODES 3 or 4 with the associated block valves closed in order to eliminate uncertainty introduced by testing the PORVs at lesser system temperatures than expected during actual operating conditions.

The block valves are exempt from the surveillance requirements to cycle the valves when they have been closed to comply with the ACTION requirements.

This precludes the need to cycle the valves with full system differential pressure or when maintenance is being performed to restore an inoperable PORV to operable status.

Surveillance requirement 4.4.5.1.b includes testing which demonstrates the functionality of the backup PORV control system.

l r

i FARLEY-UNIT 2 B 3/4 4-2a AMENDMENT NO.

89

ML20012G693

Text

Attachment:

Navigation menu

Search