Text

Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B
	ML20113A805
Person / Time
Site:	Farley
Issue date:	06/20/1996
From:	; SOUTHERN NUCLEAR OPERATING CO.
To:	;
Shared Package
ML20113A802	List: ML20113A799; ML20113A805;
References
	NUDOCS 9606250348
	Download: ML20113A805 (51)
	v • d • e

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a Enclosure 4 Joseph M. Farley Nuclear Plant Request to Revise Technical Specifications:

Pane Channe Instructions and Revised TS and TS Bases Panes l

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l 9606250348 960620 PDR ADOCK 05000348 P PDR

s Enclosure 4 Joseph M. Farley Nuclear Plant Request to Revise Technical Specifications:

1 Page Change Instructions and Revi3ed TS Pages Unit 1 TS ,

l Eagg Instruction 3/46-1 Replace 3/4 6-2 Replace 3/4 6-3 Replace 3/4 6-4 Replace 3/4 6-5 Replace i 3/4 6-9 Replace 3/4 6-10a Replace 3/4 6-10b Replace 3/4 6-15 Replace 6-24 Replace B 3/4 6-1 Replace B 3/4 6-2 Replace Unit 2 TS Eagg Instruction 3/46-1 Replace 3/4 6-2 Replace 3/46-3 Replace 3/4 6-4 Replace 3/46-5 Replace 3/4 6-9 Replace 3/4 6-10a Replace 3/4 6-10b Replace 3/4 6-15 Replace 6-24 Replace B 3/4 6-1 Replace B 3/4 6-2 Replace E4-1

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l 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT l

CONTAINMENT INTEGRITY s

LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour 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 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations

not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges,.or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3.1.

b. By verifying that each containment air lock is OPERABLE per specification 3.6.1.3.

c. By conducting visual examinations and leakage rate testing in accordance with the Containment Leakage Rate Testing Program.

Except valves, blind flanges, deactivated automatic valves and the equipment hatch which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days. The blind flange on the fuel transfer canal flange shall be verified closed after each draining of the canal.

s FARLEY-UNIT 1 3/4 6-1 AMENDMENT NO.

CONTAINMENT SYSTEMS CONTAINHENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited in accordance with the Containment Leakage Rate Testing Program.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

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With the measured containment leakage rates exceeding the overall Containment I Leakage Rate Testing Program acceptance criteria, restore the measured

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containment leakage rates to within the acceptance criteria 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 .

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the test l schedule and shall be determined in conformance with the criteria specified in the Containment Leakage Rate Testing Program. l l

FARLEY-UNIT 1 3/4 6-2 AMENDMENT NO.

I CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

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4 FARLEY-UNIT 1 3/4 6-3 AMENDMENT NO.

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CONTAINMENT SYSTEMS i

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CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with both doors l closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air j lock door shall be closed.

l APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a. With one containment air lock door inoperable

1. Maintain at least the OPERABLE air lock door closed and

]i either restore the inoperable air lock door to OPERABLE j status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door

closed.

2. Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days. ]

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, 3. Otherwise, be in at least HOT STANDBY within the next six

hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

1 j 4. The provisions of Specification 3.0.4 are not applicable.

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b. With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door I closed; restore the inoperable air lock to OPERABLE status within I 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next six hours I and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With containment air lock leakage rates resulting in exceeding the overall Containment Leakage Rate Testing Program acceptance criteria, restore the leakage rates to within the acceptance criteria 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 .

FARLEY-UNIT 1 3/4 6-4 AMENDMENT NO.

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CONTAINMENT SYSTEMS l

SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

4 a. By verifying leakage rates in accordance with the containment Leakage Rate Testing Program.

b. At least once per six months by verifying that only one door in each air lock can be opened at a time.

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FARLEY-UNIT 1 3/4 6-5 AMENDMENT NO.

i CONTAINKENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. Removing one wire from each of a dome, vertical and hoop tendon checked for lift off force and determining that:

1. The corrosion level over the entire length of the tendon wires has not progressed since the original installation or the previous surveillance.

2.

There are no changes in physical appearance of the sheathing filler material.

3. A rainimum tensile strength of 240,000 pounds per square inch for at least three wire samples (one from each and and one at mid-length) cut from each removed wire. Failure of any one of the wire samples to meet the minimum tensile strength test is evidence of abnormal degradation of the containment structure.

4.6.1.6.2 End Anchoraces and Adiacent Concrete Surfaces The structural integrity of the end anchorages and adjacent concrete surfaces shall be demonstrated by determining through inspection that no adverse changes have {

occurred in the visual appearance of the end anchorage concrete exterior ,

surfaces or the concrete crack patterns adjacent to the end anchorages.

Inspections of the concrete shall be performed during the first Type A )

l containment leakage rate tests only (reference Specification 4.6.1.2) while '

the containment is at its maximum test pressure.

4.6.1.6.3 Containment Surfaces The structural integrity of the exposed ,

accessible interior and exterior surfaces of containment including the '

containment liner plate shall be determined during shutdown by a visual inspection of these surfaces. This inspection shall be performed in accordance with the containment Leakage Rate Testing Program to verify no adverse changes in appearance or other abnormal degradation.

I FARLEY-UNIT 1 3/4 6-9 AMENDMENT NO.

1 CONTAINMENT SYSTEMS CONTAINHENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION b) One OPERABLE de-activated 48-inch outside containment purge supply or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, and one OPERABLE de-activated 8-inch outside containment purge supply or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, or

3. 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 .

c. With the leakage rate for containment purge supply or exhaust penetrations exceeding the limit of Specification 4.6.1.7.3.b, reduce the leakage to within the limit:

1. Prior to entering MODE 4 following the next COLD SHUTDOWN if the existing leakage is determined during quarterly testing pursuant to Specification 4.6.1.7.2, or

2. Prior to entering MODE 4 if exccas leakage is determined during COLD SHUTDOWN pursuant to Specification 4.6.1.7.3.

SURVEILLANCE REQUIREMENTS 4.6.1.7.1 The 48-inch containment purge supply and exhaust isolation valves shall be determined de-activated in the closed position at least once per 31 days.

4.6.1.7.2 At least once per 92 days, each penetration containing 8-inch and 48-inch containment purge supply and exhaust isolation valves with resilient material seals shall be demonstrated OPERABLE by verifying that when the leakage rates from degradation tests for both penetrations are added to the leakage rates for all other valves and penetrations subject to Type B and C l tests, the combined leakage rate is less than or equal to 0.60 L a-l FARLEY-UNIT 1 3/4 6-10a AMENDMENT NO.

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CONTAINKENT SYSTEMS CONTAINMENT VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 1 4.6.1.7.3 Each containment purge supply and exhaust penetration containing isolation valves with resilient material seals shall be demonstrated OPERABLE prior to startup after each COLD SHUTDOWN, if not performed in the previous 92 ,

days, by verifying that l

a) When the measured leakage rate is added to the leakage rates for ;

all other valves and penetrations subject to Type B and C tests, {

the combined leakage rate is less than or equal to 0.60 L , and '

b) The leakage rate for each containment purge supply and exhaust penetration is less than or equal to 0.05 La*

i In addition, the leakage rate for the containment purge isolation valves shall be compared to the previously measured leakage rate (for the containment purge isoi. Lion valves) to detect excess valvo degradation. An engineering evaluation shall be performed to determine what corrective action, if any, is necessary.

4.6.1.7.4 The resilient material valve seals of the 48-inch and the 8-inch containment purge supply and exhaust isolation valves shall be replaced at least once per 5 years.

FARLEY-UNIT 1 3/4 6-10b AMENDMENT NO.

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CONTAINMENT SYSTEMS I

SURVEILLANCE REQUIREMENTS (Continued) )

4.6.3.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by: ;

a. Verifying that on a Phase A containment isolation test signal, i each Phase A isolation valve actuates to its isolation position. I

b. Verifying that on a Phase B containment isolation test signal, ,

each Phase B isolation valve actuates to its isolation position.

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4.6.3.3 The isolation time of each power operated or automatic valve of i Table 3.6-1 shall be determined to be within its limit when tested pursuant to {

Specification 4.0.5. 1 4.6.3.4 The containment purge isolation valves shall be demonstrated j OPERABLE prior to startup after each COLD SHUTDOWN if not performed in the l previous 3 months by verifying that when the measured leakage rate is added to l the leakage rates for all other Type B and C penetrations, the combined l leakage rate is less than or equal to 0.60L a. In addition, the leakage rate for the containment purge isolation valves shall be compared to the previously measured leakage rate (for the containment purge isolation valves) to detect excess valve degradation.

i An engineering evaluation shall be performed to determine what corrective action, if any, is necessary.

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d FARLEY-UNIT 1 3/4 6-15 AMENDMENT NO.

ADMINISTRATIVE CONTROLS 6.15 HAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous, Solid)

This specification deleted. Refer to the Offsite Dose Calculation Manual and the Process Control Program.

6.16 CONTAINMENT LEAKACE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in R9gulatory guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.

The peak calculated containment internal pressure for the design basis loss ,

of coolant accident, Pa is 48 peig. '

The maximum allowable containmo.at leakage rate, La, at Pa, is 0.15% of containment air weight per day.

Leakage rate acceptance criteria ares

a. Containment overall leakage rate acceptance criterion is s 1.0 La.

During plant startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 La for the combined Type B and C tests, and s 0.75 La for Type A tests;

b. Air lock testing acceptance criteria are:

1) overall air lock leakage rate is 5 0.05 La when tested at 2 Pa*

2) For each door, leakage rate is s 0.01 La when pressurized to 2 10 poig.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program. '

The provisions of Specification 4.0.3 are applicable to the containment Leakage Rate Testing Program.

FARLEY-UNIT 1 6-24 AMENDMENT NO.

B 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, inconjunctionwiththeContainmentLeakageRateTestingProgram,l will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAF. AGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, Pa . As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 La during performance of the periodic test to account for l possible degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the requirements of 10 CFR 50, Appendix J, Option B and NRC Regulatory Guide 1.163.

3/4.5.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillanca testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosph6re of 3.0 psig and 2) the containment peak pressure does not exceed the desig., pressure of 54 psig during LOCA conditions.

FARLEY-UNIT 1 B 3/4 6-1 AMENDMENT NO.

GI CONTAINKENT SYSTEMS BASES The maximum peak pressure expected to be obtained from a LOCA event is 48 psig. Even with an initial positive pressure of up to 3 psig, the maximum containment pressure will remain below the design limit of 54 psig.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA or steam line break accident.

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! 3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY l This limitation ensures that the structural integrity of the containment .

l will be maintained comparable to the original design standards for the life of I

( the facility. Structural integrity is required to ensure that the containment l

will .. stand the maximum pressure of 48 peig in the event of a LOCA. The

! me.2wresent of the containment lift off force, visual examination of tendons, l an %avi.jes and exposed interior and exterior surfaces of the containment, and l the containment leakage tests are sufficient to demonstrate this capability. l The surveillance requirements for demonstrating the containment's structural integrity are in compliance with the recommendations of paragraph C.l.3 of Regulatory Guide 1.35 " Inservice Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structure," January 1976.

3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM l The 48-inch containment purge supply and exhaust isolation valves are required to be closed in MODES above COLD SHUTDOWN since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident, Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.

The use of the containment purge lines is restricted to the 8-inch vent supply and exhaust isolation valves to ensure that the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of a loss-of-coolant accident during venting operations.

FARLEY-UNIT 1 B 3/4 6-2

b 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINKENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour 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 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations

not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in l Table 3.6-1 of Specification 3.6.3.1.

b. By verifying that each containment air lock is OPERABLE per

Specification 3.6.1.3.

c. By conducting visual examinations and leakage rate testing in accordance with the Containment Leakage Rate Testing Program.

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Except valves, blind flanges, deactivated automatic valves and the equipment hatch which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days. The blind flange on the fuel transfer canal flange shall be verified closed after each draining of the canal.

l FARLEY-UNIT 2 3/4 6-1

I CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited in accordance with the Containment Leakage Rate Testing Program.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the measured containment leakage rates exceeding the overall Containment Leakage Rate Testing Program acceptance criteria, restore the measured containment leakage rates to within the acceptance criteria 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 .

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the l test schedule and shall be determined in conformance with the criteria .

specified in the Containment Leakage Rate Testing Program. l l

2 FARLEY-UNIT 2 3/4 6-2

l CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

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FARLEY-LNIT 2 3/4 6-3 AMENDMENT NO.

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CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 EachcontainmentairlockshallbeOPERABLEwithbothdoorsclosedl except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed.

l AP.LICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a. With one containment air lock door inoperable:

! 1. Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door

closed.

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! 2. Operation may then continue until performance of the next l required overall air lock leakage test provided that the !

OPERABLE air lock door is verified to be locked closed at f least once per 31 days.

3. Otherwise, be in at least HOT STANDBY within the next six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4. The provisions of Specification 3.0.4 are not applicable.

b. With the containment air lock inoperable, except as the result of I an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With containment air lock leakage rates resulting in exceeding the overall containment Leakage Rate Testing Program acceptance criteria, restore the leakage rates to within the acceptance criteria 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 . ,

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CONTAINKENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE l

a. By verifying leakage rates in accordance with the Containment Leakage Rate Testing Program.

b. At least once per six months by verifying that only one door in each air lock can be opened at a time.

FARLEY-UNIT 2 3/4 6-5 AMENDMENT NO.

i h CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.1.6.2 End Anchoraces and Adiacent Concrete Surfaces The structural integrity of the end anchorages of all tendons inspected pursuant to Specification 4.6.1.6.1 and adjacent concrete surfaces shall be demonstrated by determining through inspection that no appa.fent changes have occurred in the visual appearance of the end anchorage or the concrete crack patterns adjacent to the end anchorages. Inspections of the concrete shall be performed during the first Type A containment leakage rate tests (reference Specification 4.6.1.2) while the containment is at its maximum test pressure.

4.6.1.6.3 containment surfaces The structural integrity of the exposed accessible interior and exterior surfaces of containment including the containment liner plate shall be determined during shutdown by a visual inspection of these surfaces. This inspection shall be performed in accordance with the Containment Leakage Rate Testing Program to verify no apparent changes in appearance or other abnormal degradation.

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FARLEY-UNIT 2 3/4 6-9 AMENDMENT NO.

I CONTAINKENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION b) One OPERABLE de-activated 48-inch outside containment purge supply or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, and one OPERABLE de-activated 8-inch outside containment purge supply or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, or

3. 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 .

c. With the leakage rate for containment purge supply or exhaust penetrations exceeding the limit of Specification 4.6.1.7.3.b, reduce the leakage to within the limit:

1. Prior to entering MODE 4 following the next COLD SHUTDOWN if the existing leakage is determined during quarterly testing pursuant to Specification 4.6.1.7.2, or

2. Prior to entering MODE 4 if excess leakage is determined during COLD SHUTDOWN pursuant to Specification 4.6.1.7.3.

SURVEILLANCE REQUIREMENTS 4.6.1.7.1 The 48-inch containment purge supply and exhaust isolation valves shall be determined de-activated in the closed position at least once per 31 days.

4.6.1.7.2 At least once per 92 days, each penetration containing 8-inch and 48-inch containment purge supply and exhaust isolation valves with resilient material seals shall be demonstrated OPERABLE by verifying that when the leakage rates from degradation tests for both penetrations are added to the leakage rates for all other valves and penetrations subject to Type B and C l tests, the combined leakage rate is less than or equal to 0.60 L a*

FARLEY-UNIT 2 3/4 6-10a AMENDMENT NO.

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l CONTAINMENT VENTILATION SYSTEM i

SURVEILLANCE REQUIREMENTS (Continued) l 4.6.1.7.3 Each containment purge supply and exhaust penetration containing isolation valves with resilient material seels shall be demonstrated OPERABLE prior to startup after each COLD SHUTDOWN, if not performed in the previous 92 days, by verifying that:

1 a) When the measured leakage rate is added to the leakage rates for all other valves and penetrations subject to Type B and C tests, the combined leakage rate is less than or equal to 0.60 L sa and b) The leakage rate for each containment purge supply and exhaust penetration is less than or equal to 0.05 L ,

In addition, the leakage rate for the containment purge isolation valves shall be compared to the previously measured leakage rate (for the containment purge isolation valves) to detect excess valve degradation. An engineering evaluation shall be performed to determine what corrective action, if any, is l necessary.

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l 4.6.1.7.4 The resilient material valve seals of the 48-inch and the 8-inch l containment purge supply and exhaust isolation valves shall be replaced at l least once per 5 years. l l

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CONTAINMENT SYSTEMS j i

SURVEILLANCE REQUIREMENTS (Continued) l I

4.6.3.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a. Verifying that on a Phase A containment isolation test signal, l each Phase A isolation valve actuates to its isolation position.

b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 The containment purge isolation valves shall be demonstrated OPERABLE prior to startup after each COLD SHUTDOWN if not performed in the previous 3 months by verifying that when the measured leakage rate is added to the leakage rates for all other Type B and C penetrations, the combined l leakage rata is less than or equal to 0.60L . In addition, the leakage rate for the containment purge isolation valves shall be compared to the previously measured leakage rate (for the containment purge isolation valves) to detect excess valve degradation.

An engineering evaluation shall be performed to determine what corrective action, if any, is necessary.

4 FARLEY-UNIT 2 3/4 6-15 AMENDMENT NO.

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ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous, 1 Solid)

This specification deleted. Refer to the Offsite Dose calculation Manual and the Process Control Program.

6.16 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option l B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory guide 1.163, " Performance-Based l Containment Leak-Test Program," dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa is 48 psig.

l The maximum allowable containment leakage rate, La, at Pa, is 0.15% of l containment air weight per day.

l Leakage rate acceptance criteria are:

I

a. Containment overall leakage rate acceptance criterion is 5 1.0 La.

During plant startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 La for the combined Type B and C tests, and 5 0.75 La for Type A tests; ~

b. Air lock testing acceptance criteria are

1) Overall air lock leakage rate is s 0.05 La when tested at 2 Pa.

2) For each door, leakage rate is s 0.01 La when pressurized to 2 10 psig.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to the containment Leakage Rate Testing Program.

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FARLEY-UNIT 2 6-24 AMENDMENT NO.

L _--- _ -

1:

4 3/4.6 CONTAINMENT SYSTEMS 4

f BASES j 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY 4

j Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyces. This restriction, inconjunctionwiththecontainmentLeakageRateTestingProgram,l

will limit the site boundary radiation doses to within the limits of

, 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE i

! The limitations on containment leakage rates ensure that the total

} containment leakage volume will not exceed the value assumed in the accident

] analyses at the peak accident pressure, P.a As an added conservatism, the i

measured overall integrated leakage rate is further limited to less than or 2

equal to 0.75 La during performance of the periodic test to account for l possible degradation of the containment leakage barriers between letinge i tests.

1 The surveillance testing for measuring leakage rates are consistent with the requirements of 10 CFR 50 Appendix J Option B and NRC Regulatory Guide 1.163.

3/4.6.1.3 CONTAINMENT AIR LOCKS i

The 1Laitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage -

3 during the intervals between air lock leakage tests.

1 j- 3/4.6.1.4 INTERNAL PRESSURE 4

The 1Laitations on containment internal pressure ensure that 1) the i containment structure is prevented from exceeding its design negative pressure j

' differential with respect to the outside atmosphere of 3.0 psig e7d 2) the containment peak pressure does not exceed the design pressure of El psig during LOCA conditions.

l 1

1 FARLEY-UNIT 2 8 3/4 6-1

CONTAINMENT SYSTEMS BASES The maximum peak pressure expected to be obtained from a LOCA event is 48 psig. Even with an initial positive pressure of up to 3 psig, the maximum containment pressure will remain below the design limit of 54 psig.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA or steam line break accident.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 48 peig in the event of a LOCA. The visual examination of tendons, anchorages and exposed interior and exterior surfaces of the containment, and the containment leakage tests, along with the data obtained from Unit 1 tendon surveillance, are sufficient to demonstrate this capability.

The surveillance requirements for demonstrating the containment's structural integrity are in compliance with the recommendations of paragraph )

{ C.1.3 of Regu17. tory Guide 1.35 " Inservice Surveillance of Ungrouted Tendons in 1 Prestressed Concrete Containment Structures," January 1976. l l 3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM l

The 48-inch containment purge supply and exhaust isolation valves are required to be closed in MODES above COLD SHUTDOWN since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident. Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.

The use of the containment purge lines is restricted to the 8-inch vent supply and exhaust isolation valves to ensure that the site boundary dose l guidelines of 10 CFR Part 100 would not be exceeded in the event of a loss-of-l coolant accident during venting operations.

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FARLEY-UNIT 2 B 3/4 6-2 t - , -_ -. - .

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Enclosure 5 Joseph M. Farley Nuclear Plant Request to Revise Technical Specifications:

l Marked -Uo TS and TS Bases Pages l

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l 1

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1 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

WPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 one hour 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 l SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIRFMEhfS l ]

l 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

i

a. At least once per 31 days by verifying that all penetrations

not I l capable of being closed by OPERA 8LE containment automatic isolation i

valves and required to be closed during accident conditions are l closed by valves, blind flanges, or deactivated automatic valves i secured in their positions, except as provided in Table 3.6-1 of l Specification 3.6.3.1.

, b. By verifying that each containment air lock is OPERABLE per l Specification 3.6.1.3.

l gbd c. 3fter each clos g of each penetr ion subject to T if opened fol wing a Type A or test, by leak ra testing the B testing, b 9.(,,\.'l seal with g at P en the measured M04y leakage r efort$e(seseal48 psig) nd verifying is added to the 1that age rates deter-l Ah mined p suant to Specifi tion 4.6.1.2.d for all other Type B and C pen rations, the co ned leakage rate i less than or equal to h ProDrun 0.6 .

(ns.nere.3ycon4um)y;,atexa;,,m,334lggr,t,,,te3%g w

_a.wiik %. Con >Jammt Le%e. F2e. TEA Preysm .

"Except valves, blind flanges, deactivated automatic valves and t e equipment hatch which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need I

not be performed more often than once per 92 days. The blind flange on the fuel transfer canal flange shall be verified closed after. each draining of the canal. ,

6 FARLEY-UNIT 1 3/4 6-1 AMEN 0 MENT NO. 26, zi

g_ __ _ _.__

t i CONTAINMENT SYSTEMS f CONTAINMENT LEAKAGE i

LIMITING CONDITION FOR OPERATION C'"N 1

m 4.ccordwc w;W %.f )

3.6.1.2 Containment leakage rates shall be limited +tr:e Teskj Pr.y

" k )

a. An overall in grated leakage rat of: !

l 1. Less han or equal to L 0.15 percent by w ght of the j fylod .h co ainment air per 24 ours at P,, (48 ps ), or l 2. Less than or equal oL 0 I.

j f o] TAM "j containment air r 24 bo,urs.106 at a percent y weight of red ed pressure of the P ' \

t j (24 psig). 1 A cambined leak e rate of less than equal to 0.60 L for all

, penetrations d valves subject to T e B and C tests, 0 hen ,

i pressurized J t

y.P -

-/ =.

Lqe h N g gy f APPLICA8ILITY: MES _1, _2 _3 And_4 owa 4e i (Edigh,Kd't,F;W.,rfa.]Feske, h menvred.c.afunm.d [4c. rdes to

! ACTION: , wih.A k. ute@cc cri% wikin f be er be in JMf Hvi swo81

) b^ 4t. Atd 6_kovr3 hd.in C.ou) slWrDowN wi% the ,Ollowie "3o hosrJ.

j With ;i@ ';) the measured d..; el; ^.-.di;F;i;f containmes feaKage rates

~ ~

~

j xceedin 0.75 L 0.75 L , as ap icab e, or (c) wi leakage rate for" IpenetrItions nd valves subject the measured mbine M Types B and tests i exceeding 0.60 , restore the erall integrated akage rate to ss than or j equal to 0. L ,or less tha r equal to 0.75 L , as applicable and the /

combined akagIratefor penetrations sub t to Type B a C tests to l

. less th or equal to 0.6 L, prior to incre ing the Reacto Coolant Systen j empe ture above 200*F SURVEILLANCE REQUIREMENTS 4

4. 6.1. 2 The , containment leakage rates shall be demonstrated at the felle i ii test schedule and shall be determined in conformance with the criteria i specified in '.;;;ndr 2 M ' ^ C.'" it = in; th: -

f: f:= cf j fI;01t;t!.0(1070.%dyod{ des ['LhFg -^h:d- --'$ P j

a. Three Type shall be ests (Overall tegrated Contai ont Leakage te) nducted at 40 10 month interv s during shut wn at ,

[

ing each 10 y r service eithe (48 psig) or tP pe d. "The third st of hac(24 psig) h set s 1 be conducte during the utdown for the year plant ins ice inspectio -

FARLEY-UNIT 1 3/4 6-2 AMEN 0 MENT N0. 26 l

J

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. If any periodic Type A test fails meet nither 0.75 L r 0.75 L the test schedule for subsequen ype A testo shall be eviewedanb, approved by the Commission. i two consecut ve Typ i

tests fail to meet either 0.75 L or 0.7 L , a Type A test sha be performed at least every 18 months il two consecutive Ty A tests meet either 0.75 L a which time the above t t schedule may be resume 8.or0.75L t

c. The accuracy f each Type A test shal e verified by a supplemental test whic -

1. onfirms the accuracy of e Type A test by verifying th the g difference between supp emental and Type A test data i ithin 0.25 L,, or 0.25 L Q;}3 2. Has a duration fficient to establish accurate 1' the change in

, leakage rate tween the Type A test and the pplemental test.

m

3. Requires he quantity of gas injected in the containment or '

fro ram bled f os the containment during the s plemental test to be f equ alent to at least 25 percent of he total measured leakage r

{ P, (48 psig) or Pt (24 psig.)

d. T e B and C tests shall be conduc d with gas at P 48 psig) at '

ntervals no greater than 24 mon sexceptfortests(involvingair locks.

e. Air locks shall be teste nd demonstrated OPERABLE per sur 11ance Requirement 4.6.1.3.

f. All test leakage r es shall be calculated using obs ved data converted to ab ute values. Error analyses sha be performed to select a bala ed integrated leakage seasureme systes.

g. The prov ons of Specification 4.0.2 are t applicable, n ;s p q e ku 6 a & L FARLEY-UNIT 1 3/4 6-3 AMENDMENT NO. 26

l CONTAINMENT SYSTEMS l CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock sha11 be_0PERA8LE w M th doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closedg.and-o ^p Mosedb -

b. An ove 11 air loc 'ieakage rate /f less th or equal t 0.05L*at) j" not than P 48 psig). '/ ^

^ ../

_.>~'

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a. With one containment air lock door inoperable:

1. Maintain at least the OPERA 8LE air lock door closed and either restore the inoperable air lock door to OPERA 8LE status within l 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERA 8LE air lock door closed.

2. Operation say then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.

3. Otherwise, be in at least HOT STAN08Y within the next six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4. The provisions of Specification 3.0.4 are not applicable.

b. With the containment air lock inoperable, except as the rasult of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status withia 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANOBY within the next six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

C. le)d canN a ined d r lodc. l e +Argc, do regin se.y tytee A3 h ove ar C% Nam + Le.+Jc4ac. ftde-Clu k, %. Tu R3 Pnp eeg bet ecHeria

gu s m y _p, redocc. ec; m Me- ))

wh i have er be_ in d led hot Sm08Y wh h nut 6 hwi wi in tol.o 5Hv roowN wi% tie follow;n3 30 h e s. ,

FARLEY-UNIT 1 3/4 6-4 AMENDNCNT NO. 26

1 CONTAINMZNT SYSTEM 3 *d hb SURVI!LLANCE REQUIREMENTS w}k k C 6 b t L Q R de. G R Nym. ,

e - .

J 4.6.1.3 Each containment air lock shall be demonstrated OPERARIJs

a. After each opening, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verifying the leakage rate is less than or equal to 0.01 La when the volume between the door seals is pressurised to greater than or equal to

}, 10 peig for at least 15 minutes.

P M

b. By conducting an overall air lock leakage test at not less ?.han Fa (48 peig) and by verifying the over all airlock leakage rats is within its 0

1. At least once per six months, and

2. Prior to establishing CONTAINMENT INTEGRITY if opened when CONTAINMENT INTEGRITY was not required when maintenance has been performed on the als lock that could affect the air lock sealing capability,' and *

J b, /. At least once per six months by verifying that only one door in each air lock can be opened at a time.

OS A The provisions of specification 4.0.2 are not applicable.

Exemption to Appendia 0}M "J of 10 CFR 50 FARLEY-UNIT 1 3/4 6-5 AMENDNINT NO. 1I8 i

~

.a. .

'4' e

CO n.T A l fd'D.! SY STE 'G SURVEILLACE REQUIREliENTS (Continued) b.

Removing one wire from each of a dome, vertical and hoop tenden checked for lif t off force and determining that:

1. The corrosion level over the entire length of the tendon wires has not progressed since the original installation or the previous surveillance.

2.

There are no changes in physical appearance of the sheathing filler material.

3.

A minimum tensile strength of 240,000 pounds per square inch for at least three wire samples (one from each end and one at mid-length) cut from each removed wire. Failure of any one of the wire samples to meet the minimum tensile strength test is evidence of abnormal degradation of the containment structure.

4.6.1.6.2 End Anchorages and Adjacent Concrete Surfaces The structural integrity of tne end anchorages and adjacent concrete surfaces shall be demonstrated by determining through inspection that no adverse changes have occurred in the vi suo' tonearance of the end anchorage concrete exterior surfaces or the coi.< 9 a Jack patterns adjacent to the end anchorages, ,

t inspections of the r nP shall be performed during the first Type A containrant leakage . " , sts only (reference Specification 4.6.1.2) while the containment is at its maximum test pressure. i (fo#4.+1 Sirfm D g y,g, i 4.6.1.6.30.i r.e f N ete The structural integrity of thpcontainment liner plate ^

shall be determined during ee shutdown for th; first .,pe A ceatein eut leekege re,tc tcet cal, (cefecence Speci ficetica t. .1.21 by a visual inspection of t+e pl:tc :-d ;;rifyi ,3 no adverse changes in appearance or other abnomal degradation.

R.xposed Ltc.u3ible., ibricr uck Kj g ins RJhloc5Wbuufon O mod j) ge,rhme.ge, d in tc.coedwt. chm s kdk b e- ^g

{

w A h htunmt Lu ky k k [C.5 b a /uv\ b V' Llog FARLEY-Uf;IT 1 3/4 6-9 Af1ENDf tE!!T NO. 5 7 1

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CONTAINMENT SYSTEMS j CONTAINMENT VENTILATION SYSTEM

LIMITING CONDITION FOR OPERATION b) One OPERABLE de-activated 48-inch outside containment purge supply or both supply and exhaust isolation valves secured in ,

the closed position or secured by use of a blind flange, and one l l OPERABLE de-activated 8-inch outside containment purge supply

, or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, or j 3. 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 j SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

I

c. With the leakege rate for containment purge supply or exhaust penetrations exceeding the limit of Specification 4.6.1.7.3.b, reduce

the leakage to within the811mit

, 1. Prior to entering RODE 4 following the next COLD SHUTDOWN if the existing leakage is determined during quarterly testing pursuant to Specification 4.6.1.7.2, or 4

1 2. Prior to entering MODE 4 if excess leakage is determined during

] COLD SHUTDOWN pursuant to Specification 4.6.1.7.3.

I j SURVE!LLANCE REQUIREMENTS j

i 4.6.1.7.1 The 48-inch containment purge supply and exhaust isolation valves shall be determined de-activated in the closed position at least once per 31

days.

i

! 4.6.1.7.2 At least once per 92 days, each penetration containing 8-inch and

! 48-inch containment purge supply and exhaust isolation valves with resilient

]$ pet material seals shall be demonstrated OPERABLE by verifying that when the leakage j ,,,,g 4, rates from degradation tests for both penetrations are added to the leakage

rates d:t:r 'n:d p.r;.;nt t; Sp;;i'ic:ti;n t.S.I.2.d for all other valves and i Pr.a tas c

penetrations subject to Type B and C tests, tne combined leakage rate is less than or equal to 0.60 La-i 2

l FARLEY-UNIT 1 3/4 6-10a AMENDMENT NO. 74 l

4

'1 4

li CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.6.1.7.3 Each containment purge supply and exhaust penetration containing isolation valves with resilient material seals shall be demonstrated OPERABLE prior to startup after each COLD SHUTDOWN, if not performed in the previous 92 days, by verifying that:

a) When the measured leakage rate is added to the leakage rates d;ter;;ine; pr.nnt tc 0;;;ifi;;tien 4.0.1." 4 for all other valves and 3 " " Vg penetrations subject to Type 8 and C tests, the combined leakage rate is 9

less than or equal to 0.60 La, and h Proyg b) The leakage rate for each containment purge supply and exhaust penetration is less than or equal to 0.05 La- l l

In addition, the leakage rate fqr the containment purge isolation valves shall be compared to the previously measured leakage rate (for the containment purge isolation valves) to detect excess valve degradation. An engineering evaluation shall be performed to determine what corrective action, if any, is necessary.

4.6.1.7.4 The resilient material valve seals of the 48-inch and the 8-inch containment purge supply and exhaust isolation valves shall be replaced at least once per 5 years.

AENDMENT NO. 33, 74 l l F ARLEY-UNIT 1 3/4 6-10b l

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l CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l 4.6.3.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERA 8LE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a. Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.

b. Verifying that on a Phase 8 containment isolation test signal, each Phase B isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 The containment purge isolation valves shall be demonstrated OPERABLE prior to startup after each COLD SHUTOOWN if not performed in the previous 3 ht'Pn**)

-}., cou, months by verifying that when the measured leakage rate is added to the leakage rates d tmind pr:=nt t !;ni"=ti= t.5.1.2.4 for all other Type 8 and d C penetrations, the combined leakage rate is less than or equal to 0.60L,.

In addition, the leakage rate for the containment purge isolation valves shall be compared to the previously measured leakage rate (for the containment purge isolation valves) to detect excess valve degradation.

An' engineering evaluation shall be performed to determine what corrective action, if any, is necessary.

FARLEY-UNIT 1 3/4 6-15 AMEN 0 MENT NO. 26

ADMINISTRATIVE CONTROLS

....c.......c.uce2cosace...u .s. w .............................................

6.15 Sol 1d) NAlot CHANcf t To eADf 0 ACTIVE WASTE . TREATN

, Gaseous, This specification deleted.

Process Control Program.

Refer to the Offsite Dose Calculation M l

l 6.16 CONTAINMENT LEAKAGE RATE TESTING PROGRAM l A program shall be established to implement the leakage rate testing of f containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J '

Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163,

' Performance-Based Containment Leak-Test Program,' dated September 1995.

The peak calculated containment intemal pressure for the design basis loss of coolant accident, P is 48 psig. ,

The maximum allowable containment leakage rate, L. , at P. , is 0.15% of , l containment air weight per day.

Leakage rate acceptance criteria are:

a. Containment overall leakage rate acceptance criterion is s 1.0 L,. During plant startup following testing in accordance with this program, the leakage }

rate acceptance criteria are $ 0.60 L, for the ccmbined Type B and C tests, and ;

5 0.75 L, for Type A tests;

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is s 0.05 L, when tested at 2 P,.

2) For each door, leakage rate is s 0.01 L, when pressurized to 210 psig. ,

Spec Euhon The provisions of hR 4.0.2 do not apply to the test frequencies specified in the y Containment Leakage Rate Testing Program.

p ped %%

S The provisions ofSR 4.0.3 are applicable to the Containment Leakage Rate Testing Program

FAALD. WIT 1 6 24 m g, y, 39 24~c> f. > ti; I

l 3/4.6 CONTAINMENT SYSTEMS BASE 5 -

3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY U ') )

Primary CONTAll#4ENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restric-tion, in conjunction with the Ld:;; :t; !!:it; tier., will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P As an added conservatism, the -

measured overall integrated leakage rate is. further limited to less than or

4 ;r 0.75 L ,

equal test to 0.75 to account L,for possibke, degradation of the containment leakage barriers;;

c between leakage tests.

The surveillance testing for measuring leaka e r te re SonsittLnt wi the_ tegu,tresents foL _fg: J'E."j" ;f 10 CFR 50 A p ;w T op f e 6 m p,th j

D39dN 3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAlletENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

3/4.6.1.4 INTERNAL PRESSURE The liettations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of 3.0 psig and 2) the containment peak pressure does not exceed the design pressure of 54 psig during LOCA conditions.

FARLEY-UNIT 1 8 3/4 6-1 M MO M NO. 26 l

l

l 1

CONTAINMENT SYSTEMS

' BASES

) - ..............&...............................................................

j psig. The maximum peak pressure expected to be obtained from a LOCA Even with an initial positive pressure of up to 3 psig, the maximum containment pressure will remain b? low the design limit of 54 psig.

3/4.6.1.5 AIR TEMPERATURE i

overallThe limitations on containment average air temperature ensure that the (

3 containment average air temperature does not exceed the initial i temperature break accident.condition assumed in the accident analysis for a LOCA or stea l 3/4.6.1.6 I

! CONTAINMENT STRUCTURAL INTEGRITY 1 This limitation ensures that the structural integrity of the containment I' 1

will the be maintained comparable to the original design standards for the life of facility.

will withstand the maximum pressure of 48 psig in The. the event i e measurement

'ee f. J s age tes s of the containment lift off force, visual exa ,

D'sufficient to demonstrate this capability.

4

' Contuo !

1 e surveillance requirements for demonstrating the containment's l l

C.I.3 of Regulatory Guide 1.35 ' Inservice Surveillance l

Prestressed Concrete Containment Structures," January 1976.

3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM i

i The 48-inch containment purge supply and exhaust isolation valves are I i required to be closed in MODES above COLD SHUTDOWN since these valves have n been demonstrated capable of closing during a LOCA or steam line break accident.

Maintaining these valves closed during plant operations ensures that excessive j quantities purge of radioactive materials will not be released via the containment system.

The use of the containment purge lines is res et

" to th 8 i ch vent gu 1 o F a 00 uN t coolant accident during venting operations. xce ed in the event of a loss-of-l FARLEY - UNIT 1 I 8 3/4 6-2 12/16/93

%3 2

00

l' 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT l CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour 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 j SHUTOOWN within the following 30 hour:. '

SURVEILLANCE NEQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations

not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are clcsed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3.1.

b. By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.

b t336 c. After each cl ing of each.pene ation subject to ype B testing, b 4 4,g,g if opened f lowing a Type A B test, by lea ate testing the 3 -

seal with as at P and verifying t t when the measured 6,hdAoved leakage ate for t$es(48 psis is added to th leakage rates deter-e se i mine ursuant to Speci cation 4.6.1.2.d or all other Type B and g gT" Cp etrations, the bined leakage ra islessthanorequalto)

O L,. By can h M3 vi.wd eswio.h 5 .wd leap ette Testka d

in At.coeduue. y% h Cetunewt Letby. bA Tesh'a3 S yuw.

"Except valves, blind flanges, deactivated automatic va ves and the equ pment hatch which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days. The blind flange on the ;

fuel transfer canal flange shall be verified closed after each draining of ;

the canal. '

FARLEY-UNIT 2 3/4 6-1

I CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION in a.ccordwcc. w;}h 140 3.6.1.2 Containment leakage rates shall be limited w C%tdammt Luay ihte-g g.

a. An overall in grated leakage ra of:

1. Less han or equal to L 0.15 percent by w ght of the ]

WMh ~

co ainment air per 24 ours et P,, (48 ps ), or [

\ 2. Less than or equal oL 0 f>('o}(a# containment air r 24 ko,urs.106 at a percent y weight of red ed pressure of the P '

t (24 psig).

l )

. A combined leak e rate of less than equal to 0.60 L for all j penetrations d valves subject to T e B and C tests, 0 hen /

pressurized y.P -

= = = , , -.

j, .

APPLICABILITY: __MQDES 1, 2 _ M* ^*

18 (TGigtiTt,i-;Qita, eeshee %e, mmvrcdmhinmd erkaw rds b ACTION: wiNA Ke_. ueeptwcc cnleda. wih j heve or be in almf Hvi stme84 l With;'e%y W 4t- Atd 6 kovr.s h4ia c.omsfWrcewro w(E_thc., fwltow_kQo hodrJ. '

r (:)- the measured 1., a!! f r'aFn ; containment leakage rates. ~

xceedin 0.75 L 0.75 L , as ap icable, or (c) wi the measured mbine O M leakage rate for' Ipenetrktions nd valves subject Types B and tests exceeding 0.60 erall integrated akage rate to ss than or equal to 0. L ,, restore the r equal to 0.75 L , as applicable and the combined akag$orlesstha rate for penetrations sub t to Type 8 a C tests to less th or equal to 0.6 L* prior to incre ing the Reacto Coolant Systes Qempe ture above 200*F SURVEILLANCE REQUIREMENTS

4. 6.1. 2 The , containment leakage rates shall be demonstrated at the ' ell; ir,-

test schedule and shall' be determined in conformance with the criteria

' ' ^ "" "^ ' - - ' - - - " ' ' ' - - - " ' -

o2 5s pec i fi ed in '---

'- - - 7eA

. t0! t'45.0-(1UEId 1 P % ~

a. Three Type ests (overall tegrated Contai ent Leakage te) shall be eithe nducted at 40 10 month interv s during shut (48 psig) or t P, (24 psig) ing each 10 y r service wnat][ l pe d. ,The third st of lach set s I be conducte during the l utdown for the year plant ins ice inspectio '

FARLEY-UNIT 2 3/4 6-2

l J

, CONTAINMENT SYSTEMS

_ SURVEILLANCE REQUIREMENTS (Continued) w If any periodic Type A test fails to meet either 0.75 L or 0.75 L ,

the test schedule for subsequent Type A tests shall be feviewed approved by the Commission. If two consecutive Type A test 1 to meet either 0.75 L or 0.75 L , a Type A test shall be formed at leastevery18monfhsuntiltoconsecutiveType sts meet either 0.75 L g at which time the above t schedule may be

, resume 8.or0.75L

c. The accuracy of each Type A te hall be verified by a supplemental test which:

i

1. Confirms t ccuracy of the Type A test by verifying that the differ e between supplemental and Type A test data is within 0 L,, or 0. 25 Lt* '

. Has a duration sufficient to establish accurately the c e in leakage rate between the Type A test and the suppl al test.

De a

3. Requires the quantity of gas injected int e containment or j M bled from the containment during the pienental test to be i equivalent to at least 25 percen the total measured leakage pc 0% at P, (48 psig) or Pt (24 p .

d. Type B and C tests shal conducted with gas at P 48 psig) at intervals no great an 24*mraths except for testl (involving air l j locks. i e Air 1 s shall be tested and dtnonstrated OPERABLE per Surveillance I. rement 4.6.1.3.

l

f. All test leakage rates shall be calculated using observed d converted to absolute values. Error analyses shall be ormed to select a balanced integrated leakage measurement s es. -

g. The provisions of Specification 4.0.2 ar t applicable.

This is a one-time tion to 10 CFR 50.46 Appendix J.

The 24 month i al may be extended during the first fuel cycle allow individual penetrations to be tested as p1 conditions permit, but in no case shall any vidual test interval extend beyond the first refueling outage. If plant conditions support earlier testing or if incidents occur which could jeopardize the leak tight integrity of a penetration, the testing will be performed at that time.

Thi s f g e. bs bem M c N .

FARLEY-UNIT 2 3/4 6-3 Amendment No. 10 e

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l CONTAINMENT SYSTENS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERA 8LE M oth doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closedg.ah M oved b

b. An ov 11 air loc gDM not ss than P eakage rate /f less th 48 psig). /_ _

or equal t 0.05 L, at j

APPLICABILITY: H0 DES 1, 2, 3 aIn4.

ACTION:

a. With one containment air lock door inoperable:

1. Maintain at least the OPERA 8LE air lock door closed and either restore the inoperable air lock door to OPERA 8LE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERA 8LE air lock door closed.

2. Operation say then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.

3. Otherwise, be in at least HOT STAN08Y within the next six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4. The provisions of Specification 3.0.4 are not applicable.

b. With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERA 8LE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STAN08Y within the next six hours and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

C. (Ahd cadinntM 43r lock. leke rdei Nsde% 'n exue&3 h om a cm Nn,m + Le g e 8de

.g.j.'^ To 43 Paye ce9 bet crHer'a, redore. Mt lage cJe.s to wi% %t ceuf% e tr M Wiki A l hour celot iA d lt4# hot'.5TMwuBY wihin b nut 6 hovri ud. in t o t.t> 5HurooWN W i t% de. ~IbNowin3 lo hou3, ,

FARLEY-UNIT 2 3/4 6-4

I Bv ver;f in lulabe, n}e.s ,n unebec '

CONTAINMENT SYSTEMS I b wA N. C=khed L%e R4. Lu Peges.

-=^ a SURVEILLANCE REQUIREMENTS ,^

l 4.6.1.3 Each containment air lock shall be demonstrated oPERAR!J '

a. After each open g, eacept when the a lock is being used f multiple ente e, then at least once r 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by veri ing the leakage ate is less than or al to 0.01 La when t volume between t door eeale is preneu sed to greater than o equal to G A'A 10 peig or at least 15 minute

% b. By nducting an overall a lock leakage teet at less than Pa peig) and by the over all airlock akage rate is

(

ithinitslimitgerify

1. At least once per sia monthe, and

2. Prior to est inhing CONTAINMENT I RITY if opened when CONTAIMMENT NT3GRITT was not requi when maintenance hae ,

been perf on the air lock t could affect the air lock l esaling apability,' and ,

b/. At least once per sia months by verifying that only one door in each air lock can be opened at a time.

{

1 i

l l

1 Odds :n F '

p8 Oj'W # The pro eione of specif tion 4.0.2 e not applicable.

Em ption to Append "J' of 10 50.

FARLEY-UNIT 2 3/4 6-5 AMENDMENT NO. 109 i

n- .

ll CONTA!N! TNT SYSTEftS SURVEILLANCE REQUIREMENTS (Continued) 4.6.1.6.2 End Anchorages and Adjacent Concrete Surfaces The structural integrity of the end ancnorages of all tendons inspected pursuant to Specification 4.6.1.6.1 and adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes have occurred in the visual appearance of the end anchorage or the concrete crack patterns adjacent to the end anchorages. Inspections of the concrete shall be performed during the first Type A containment leakage rate tests (reference Specification 4.6.1.2) while _ the Sontainment is at its maximum test pressure. gest snfeces.

Cont &yMVNiet St 4.6.1.6.(3c un:r Pr;;; The structural integrity of thp- containm shall be determinea during h shutdown f;r tr.e first . r. ,, -............ ,m.sor ret; t;;t 'referen;; Op;;ifi;;tien t.0.1.2) by a visua inspection offth; liner plete verifjing no apparent changes in appearance or other abnonnal degradation.

1

%0Jtd Letti$lhlt. loktier M 7k. supes.en sktil be exterioc suctuu .f ca,%est In cluclia %e '

i ptAb(MEr s A Lt. cord 4 Met Wa hn Ac Cau t LaAge RA ')

Teskg P nym to verify /

FARLEY-UNIT 2 3/4 6-9 AMENOMENT N0.49

l CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION b) One OPERABLE de-activated 48-inch outside containment purge supply or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, and one OPERABLE de-activated 8-inch outside containment purge supoly or both supply and exhaust isolation valves secured in tne closed position or secured by use of a blind flange, or

3. 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 ,

c. With the leakage rate for containment purge supply or exhaust penetr'ations exceeding the limit of Specification 4.6.1.7.3 b reduce the leakage to within theilimit:

1. Prior to entering A00E 4 f ollowing the next COLD SHUTOOWN if the existing leakage is determined during quarterly testing pursuant to Specification 4.6.1.7.2, or

2. Prior to entering MODE 4 if excess leakage is deterinined during COLD SHUTDOWN pursuant to Specification 4.6.1.7.3.

SURVEILLANCE REQUIREMENTS 4.6.1.7.1 The 48-inch containment purge supply and exhaust isolation valves shall be determined de-activated in the closed position at least once per 31 days.

4.6.1.7.2 At least once per 92 days, each penetration containing 8-inch and 48-incn containment purge supply and exhaust isolation valves with resilient l 5Ea mod material seals shall be demonstrated OPERABLE by verifying that when tne leakage !

rates from degradation tests for both penetrations are added to the leakage 6Pym rates c:t:-e:d pr:== t pui f i c.t i u, : .: .1.: .: for all otner valves and penetrations subject to Type B and C tests, the combined leakage rate is less than or equal to 0.60 La- ,

i i

I F ARLEY-UNIT 2 3/4 6-10a AMEN 0 MENT NO. 66

._ . _ _ . -. . _ _ . . - ~

l' CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

.. . .. ---.. .----... .n..... ................ ....

4.6.1.7.3 Each containment purge supply and exhaust penetration containing isolation valves with resilient material seals shall be demonstrated OPERA 3LE prior to startup after eacn COLD SHUTDOWN, if not performed in the previous 92 days, by verifying that; a) When the measured leakage rate is added to the leakage rates d tc.-i ad I ec p rooved pu.-^ u; t 0; Spe-i fi etien t.0.1.2.o for all other val ves and penetrations subject to Type B and C tests, the combined leakage rite is g p,,0% less than or equal to 0.60 La, and b) The leakage rate for each containment purge supply and exhaust penetration is less than or equal to 0.05 La-In addition, the leakage rate fo.r the containment purge isolation valves s all be compared to the previously measured leakage rate (for the containment p/ge isolation valves) to detect excess valve degradation. An engineering evalaation shall be performed to detennine what corrective action, if any, is necessary.

4.6.1.7.4 The resilient material valve seals of the 48-inch and the 8-inch containment purge supply and exhaust isolation valves shall be replaced at least once per 5 years.

I FARLEY-UNIT 2 3/4 6-10b AMEN 0 MENT NO. 66

i CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a. Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.

b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.

l 4.6.3.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

l 4.6.3.4 The containment purge isolation valves shall be demonstrated OPERABLE prior to startup after each COLD SHUTDOWN if not perfonned in the previous 3 S " "j months by verifying that when the measured leakage rate is added to the leakage P rates d:te 4n:d pur:urnt te Speci'ic:ti:n '.5.1.2.d for all other Type B and h Pr o rgg C penetrations, the combined leakage rate is less tt)an or equal to 0.60L,s.

In addition, the leakage rate for the containment purge isolation valves hall be compared to the previously measured leakage rate (for the containment purge isolation valves) to detect excess valve degradation.

An engineering evaluation shall be performed to determine what corrective action, if any, is necessary. l j l

FARLEY-UNIT 2 3/4 6-15

l' 1?i ADMINISTRATIVE CONTROLS W CHNES TO RADICACTIVE WASTE TREATNfv.

SYSTEMS (Liquid. Gaseous ane This specification deleted.

Process Control Progras. Refer to the Offsite Dose Calculation Manual 6.16 CONTAINMENT LEAKAGE RATE TESTING PROGRAM l

A program shall be established to implement the leakage rate testing of containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J Option B, as modified by approved exemptions. This program shall be in l accordance with the guidelines contained in Regulatory Guide 1.163, l

' Performance-Based Containment Leak-Test Program,' dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, P, is 48 psig.

The maximum allowable containment leakage rate, L. , at P. , is 0.15% of containment air weight per day.

Leakage rate acceptance criteria are:

a. Containment overall leakage rate acceptance criterion is $ 1.0 L,. During plant startup following testing in accordance with this program, the leakage rate acceptance criteria are 5 0.60 L, for the combined Type B and C tests, and 5 0.75 L, for Type A tests;

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is s 0.05 L, when tested at 2 P,.

2) For each door, leakage rate is s 0.01 L, when pressurized to 210 Psig.

The provisions of b 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

spes.F.u %

The provisions ofb 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

FARLEY Ull!T 2 6 24 MWOWIT 110. 4. 91

l 3/4.6 CONTAIWENT SYSTEMS _

BASES

~-

3/4.6.1 PRIMARY CONTAffe4ENT r .

S 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAIMENT INTEGRITyensures that the release of radioactive materials from the containment paths and associated leak rates (atmosphere will be restricted to those leakage assumed in the accident analyses. This restric-tion, in conjunction with the f.. Lei,. rete-Waftetten, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAI MENT LEAKAGE The limitations on containment leakage rates ensure that the total contain-ment at the leakage voltmepressure, peak accident will not exceed P the value assuesd in the accident analyses .

As an added conservatise, the seasured

overall integrated leakage rate is. further limited to less than or equal to .

0.75 L er 0.7",-L , ee Jcetrie,.during performance of the periodic test to accounf for possible degradation of the containment leakage barriers between leakage tests.

The surve111ance testing for esasuring leakage rates are consis nt with the requirements of ?;;;rA "J"-vf-10 CFR 50g 4y ggg 3/4.6.1.3 CONTAIletENT AIR LOCKS RtDAt , CW4c.1.1(,L The limitations on closure and leak rata for the containment air lock:,

are leakrequired rate. to meet the restrictions on CONTAllgENT INTEGRITY and containment Surveillance testing of the air lock seals provide assurance that the overall air lock leakage w111 not became excessive due to seal desage during the intervals between air lock leakage tests.

3/4.6.1.4 INTERNAL PRES $URE The limitations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside ataesphere of 3.0 peig and 2) the contairueent during LOCA peak praesure does not exceed the design pressure of 54 psig conditions. l FARLEY-UNIT 2 8 3/4 6-1 1

I s

e

1:

CONTAINMENT SfSTEMS BASES 6..............................................................

' The maximus peak pressure expected to be obtained from a LOCA event is 48 psig. Even with an initial positive pressure of up to 3 psig, the maximum containment pressure will remain below the design limit of 54 psig.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA or steam line break accident.

3 / 4 . 6.1. 6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will .be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 48 psig in the event of a LOCA. The visual examination of tendons, anchorages and exposed 01 terior and extertoe e surfaces of the containment, and the T,H ! leakage tes@ along with the data r

obtained from capability. Unit 1 tendon surveilflance sufficient to demonstrate this The surveillance requirements for demonstrating the containment's structural integrity are in compliance with the recomendations of paragraph C.1.3 of Regulatory Guide 135 ' Inservice Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structures," January 1976.

3 /4. 6.1. 7 CONTAINMENT VENTILATION SYSTEM The 48-inch containment purge supply and exhaust isolation valves are required to be closed in MODES above COLD SHUTDOWN since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident.

Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not ce released via the containment purge system.

The use of the containment purge lines is restricted to the 8-inch vent supply and exhaust isolation valves to ensure that the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of a loss-of-coolant accident during venting operations.

. FARLEY - UNIT 2 8 3/4 6-2 12/16/93 W>

Sf U

I

ML20113A805

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