Text

Amends 217 & 205 to Licenses DPR-77 & DPR-79,respectively, Implementing Change to 10CFR50,app J to Incorporate Option B,Voluntary performance-based Option,For Determining Frequency for Performing Type A,B & C Clrt
	ML20097F202
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Site:	Sequoyah
Issue date:	02/05/1996
From:	Hebdon F; NRC (Affiliation Not Assigned)
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ML20097F208	List: ML20097F202; ML20097F221;
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t UNITED STATES s

j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 2006H001

\\...../

TENNESSEE VALLEY AUTHORITY

)

DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 217 License No. DPR-77 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated December 8, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (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 Comission's regulations; D.

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

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

9602150330 960205 ADOCKOS00g7 DR

a

. 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. DPR-77 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 217, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance, to be implemented within 45 days.

FOR THE NUCLEAR REGULATORY COMMISSION

)#

Frederick J. He on, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 5, 1996 4

ATTACHMENT TO LICENSE AMENDMENT N0. 217 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-7 3/4 6-7 3/4 6-8 3/4 6-8 3/4 6-11 3/4 6-11 3/4 6-15 3/4 6-15 3/4 6-17 3/4 6-17 B3/4 6-1 B3/4 6-1 B3/4 6-2 B3/4 6-2 6-18a

s e

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION l

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 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 R16 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 l

secured in their positions, except for valves that are open under R207 j

administrative control as permitted by Specification 3.6.3.

i R134 b.

By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.

c.

Perform required visual examinations and leakage rate testing in I

accordance with the Containment Leakage Rate Testing Program.

Except valves, blind flanges, and deactivated automatic valves which are located inside the annulus or containment or the mainsteam valve vaults and are locked, sealed or otherwise secured in the closed position. These l

penetrations shall be verified closed during each COLD SHUTDOWN except that l'

such verification need not be performed more often than once per 92 days.

R195 l

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SEQUOYAH - UNIT 1 3/4 6-1 Amendment Nos. 203 217, 176, 12, 130

191, l

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4e a

8 CONTAINMEHL SYSTEMS SECONDARY CONTAINMENT BYPASS LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Secondary containment bypass leakage rates shall be limited to a combined bypass leakage rate of less than or equal to 0.25 percent L, for all R207 penetrations that are secondary containment BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING when pressurized to P,.*

l APPLICABILITY: MODES 1, 2,

3 and 4.

ACTION:

R180 With the combined bypass leakage rate exceeding 0.25 L, for BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING, restore the combined bypass leakage rate from BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING to less than or equal to 0.25 L, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 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 .

Enter the ACTION of LCO 3.6.1.1,

" Primary Containment" when Secondary Containment Bypass Leakage results in exceeding the overall containment leakage rate acceptance criteria.

SEQUOYAH - UNIT 1 3/4 6-2 Amendment No. 12, 71, 176, 203, 217

o a

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT BYPASS LEAKAGE lR180 SURVEILLANCE REQUIREMENTS 4.6.1.2 The secondary containment bypass leakage rates shall be demonstrated:

R180 a.

The combined bypass leakage rate to the auxiliary building shall be determined to be less than or equal to 0.25 Ig by applicable Type B and C tests in accordance with the Containment Leakage Rate Test program, except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the R180 containment is pressurized to P.

(12 psig) during each Type A test.

b.

Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 P. (13.2 psig) and the seal system capacity is adequate to maintain system pressure (or fluid head for the containment spray system and RHR spray system valves at penetrations 48A, 48B, 49A and 49B) for at least 30 days.

c.

The provisions of Specification 4.0.2 are not applicable.

SEQUOYAH - UNIT 1 3/4 6-3 Amendment No. 12, 71, 101, 102,217 127, 130,

176, l

1 l

a CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION t

3.6.1.3 Each containment air lock shall be OPERABLE

with both 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 closed.

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 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.

l 1

2.

Operation may then continue until performance of the next I

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.

i 3.

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

l 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; i

restore the inopc:able air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or l

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

R16

1.

An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2.

Enter the ACTION of LCO 3.6.1.1,

' Primary Containment" when air lock leakage results in exceeding the overall containment leakage rate acceptance criteria.

SEQUOYAH - UNIT 1 3/4 6-7 Amendment No. 12, 217

3 m

CONTAINMENT SYSTEMS

(

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

a.

By verifying leakage rates in accordance with the containment Leakage Rate Test Program.

l b.

At least once per 6 months by verifying that only one door in each I

air lock can be opened at a time.

l l

SEQUOYAH - UNIT 1 3/4-6-8 Amendment Nos. 48, 176,217

D e

CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined during shutdown by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel. This inspection shall be performed in accordance with the Containment Leakage Rate Test Program to verify no apparent changes in appearance of the surfaces or other abnormal degradation. Any abnormal degradation of the containment vessel detected during the above required inspections shall be reported to the Commission pursuant to R40 Specification 6.6.1.

1 I

1 SEQUOYAH - UNIT 1 3/4 6-11 Amendment No. 36, 176,217 l

J

e C

e CONTAINMENT SYSTEMS l

CONTAINMENT VENTILATION SYSTEM l

LIMITING CONDITION FOR OPERATION i

3.6.1.9 One pair (one purge supply line and one purge exhaust line) of containment purge system lines may be open; the containment purge supply and exhaust isolation valves in all other containment purge lines shall be closed.

Operation with purge supply or exhaust isolation valves open for either purging R22 or venting shall be limited to less than or equal to 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months per 365 days.

The 365 day cumulative time period will begin every January 1.

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

ACTIONS a.

With a purge supply or exhaust isolation valve open in excess of R124 the above cumulative limit, or with more than one pair of containment purge system lines open, close the isolation valve (s) in the purge line(s) 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 .

b.

With a containment purge supply and/or exhaust isolation valve having a measured leakage rate in excess of 0.05 L, restore the inoperable valve to OPERABLE status within 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months $, otherwise be R124 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 4.6.1.9.1 The position of the containment purge supply and exhaust isolation valves shsAl be determined at least once per 31 days.

4.6.1.9.2 The cumulative time that the purge supply and exhaust isolation valves are open over a 365 day period shall be determined at least once per 7 days.

4.6.1.9.3 At least once per 3 months, each containment purge supply and exhaust isolation valve shall be demonstrated OPERABLE b R180 measured leakage rate is less than or equal to 0.05 L,.* y verifying that the j

l l

l

' Enter the ACTION of LCO 3.6.1.1,

" Primary Containment" when purge valve I

leakage results in exceeding the overall containment leakage rate acceptance criteria.

1 SEQUOYAH - UNIT 1 3/4 6-15 Amendment No. 18, 120, 176,217

D CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 Each containment isolation valve shall be OPERAELE.*

R207 APPLICABILITY:

MODES 1, 2,

3 and 4.

ACTION:

a.

With one or more of the isolation valve (s), except containment vacuum R207 relief isolation valve (s), inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:

1.

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , R201 or 2.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or i

3.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange; or 4.

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 .

b.

With one or more containment vacuum relief isolation valve (s) inoperable, lR207 the valve (s) must be returned 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , c.

The provisions of Specification 3.0.4 do not apply.

lR207 SURVEILLANCE REQUIREMENTS 4.6.3.1 Deleted R207

1.

Penetration flow path (s) may be unisolated intermittently under administrative controls.

2.

Enter the ACTION of LCO 3.6.1.1, " Primary Containment" when containment isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.

SEQUOYAH - UNIT 1 2/4 6-17 Amendment No. 12, 197, 203, 217

.m t

e 3/4.6 CONTAINMENT SYSTQig BASES 3/4.6.1 PRIMARY CONTAINMENT The safety design basis for primary containment is that the containment R100 must withstand the pressures and temperatures of the limiting design basis accident (DBA) without exceeding the design leakage rates.

The DBAs that result in a challenge to containment OPERABILITY from high pressures and temperatures are a loss of coolant accident (LOCA), a steam line break, and a rod ejection accident (REA).

In addition, release of significant fission product radioactivity within containment can occur from a LOCA or REA.

In the DBA analyses, it is assumed that the containment is OPERABLE such that, for the DBAs involving release of fission product radioactivity, release to the environment is controlled by the rate of containment leakage. This leakage rate limitation will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

The containment was designed with an allowable leakage rate of 0.25 percent of containment air weight per day.

This leakage rate, used in the evaluation of offsite doses resulting from accidents, is defined in the Containment Leakage Rate Test Program, as Ig: the l

maximum allowable containment leakage rate at the calculated peak containment internal pressure (P ) resulting from the limiting DBA.

The allowable leakage R180 rate represented by Ig forms the basis for the acceptance criteria imposed on all containment leakage rate testing.

Primary containment INTEGRITY or operability is maintained by limiting leakage to within the acceptance criteria of the Containment Leakage Rate Test Program.

3/4.6.1.2 SECONDARY CONTAINMENT BYPASS LEAKAGE

~

R180 The safety detsign basis for containment leakage assumes that 75 percent of the' leakage from the primary containment enters the shield building annulus for filtration of the emergency gas treatment system.

The remaining 25 percent of the primary containment leakage, which is considered to be bypassed to the auxiliary build.ing, is assumed to exhaust directly to the atmosphere without filtration durAng the first 5 minutes of the accident. After 5 minutes, any bypass leakage to the auxiliary building is filtered by the auxiliary building gas treatment system. A tabulation of potential secondary containment bypass SEQUOYAH - UNIT 1 B 3/4 6-1 Amendment No. 102, 127, 176, 217

e 3/4.6 CONTAINMENT SYSTEMS BASES leakage paths to the auxiliary building is provided in the Containment Leakage Rate Test Program. Restricting the leakage through the bypass leakage paths to 0. 2 5 Ig provides assurance that the leakage fraction assumptions used in the evaluation of site boundary radiation doses remain valid.

lR180 3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are 1

required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak j

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 i

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 annulus atmosphere of 0.5 psig and 2) the containment peak pressure does not exceed the maximum allowable internal lBR pressure of 12 psig during LOCA conditions.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that 1) the containment air mass is limited to an initial mass sufficiently low to prevent exceeding the maximum allowable internal pressure during LOCA conditions and 2) lBR the ambient air temperature does not exceed that temperature allowable for the continuous duty rating specified for equipment and instrumentation located within containment.

The containment pressure t;ansient is sensitive to the initially contained air mass during a LOCA.

The contained air mass increases with decreasing temperature.

The lower temperature limits of 100*F for the lower compartment, 85'F for the upper compartment, and 60*F when less than or equal to 5% of RATED THERMAL POWER will limit the peak pressure to an acceptable value. The upper temperature limit influences the peak accident temperature slightly during a BR LOCA; however, this limit is based primarily upon equipment protection and anticipated operating conditions. Both the upper and lower temperature limits are consistent with the parameters used in the accident analyses.

3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment steel vessel will be maintained comparable to the original design standards for the life of the facility.

Structural integrity is required to ensure that the BR vessel will withstand the maximum pressure of 12 psig in the event of a LOCA.

l Periodic visual inspections in accordance with the Containment Leakage Rate l

Test Program are sufficient to demonstrate this capability.

l l

l i

l l

l SEQUOYAH - UNIT 1 B 3/4 6-2 Amendment No. 102, 127, 176, 203/17 l

l 1

l

I l-e e

ADMINISTRATIVE CONTROLS l

h.

Containment Lemkaae Rate Testinq Procram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54 (o) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions. Visual examination and testing, including test intervals and extensions, shall be in accordance with Regulatory Guide (RG) 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995 with exceptions provided in the site implementing instructions.

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

is 12.0 psig.

The maximum allowable containment leakage rate, Lg, at P,,

is 0.25% of the l

primary containment air weight per day.

Leakage rate acceptance criteria are:

a.

Containment overall leakage rate acceptance criteria is_s 1.0 Ig.

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

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is s 0.05 Ig when tested at a P..

l 2)

For each door, leakage rate is s 0.01 Ig when pressurized to 6 psig for at least two minutes.

a The provisions of SR 4.0.2 do not apply to the test frequencies specified j

in the. Containment Leakage Rate Testing Program.

The provisions of SR 4.0.3 are applicable to the Containment L'eakage Rate Testing Program.

3 SEQUOYAH - UNIT 1 6-18a Amendment No.

217 1

i l

f u:u

[4 g

UNITED STATES S

NUCLEAR REGULATORY COMMISSION E

f WASHINGTON, D.C. 200mH001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE0VOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.207 License No. DPR-79 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated December 8, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's' regulations; D.

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

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

i 1

. 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. DPR-79 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 207, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

j 3.

This license amendment is effective as of its date of issuance, to be implemented within 45 days.

FOR THE NUCLEAR REGULATORY COMMISSION a-t Frederick J. Hebdbn, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 5, 1996 S

ATTACHMENT TO LICENSE AMENDMENT N0. 107 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-7 3/4 6-7 3/4 6-8 3/4 6-8 3/4 6-11 3/4 6-11 3/4 6-15 3/4 6-15 3/4 6-17 3/4 6-17 B3/4 6-1 83/4 6-1 B3/4 6-2 B3/4 6-2 6-19 6-19 6-19a i

= _

1 4

4 3/4.6 CONTAINMENT SYSTEMS 3/4.E.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION l

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

.x 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 conditione are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative entrol as permitted by Specification 3.6.3.

R193 b.

By verifying that each containment air lock is in compliance with R117 the requirements of Specification 3.6.1.3.

l c.

Perform required visual examinations and leakage rate testing in accordance with the Containment Leakage Rate Testing Program.

i 1

Except valves, blind flanges, and deactivated automatic valves which are located inside the annulus or containment or the main steam valve vaults are i

locked, sealed or otherwise secured in the closed position. These penetrations lR183 j

shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

I J

SEQUOYAH - UNIT 2 3/4 6-1 Amen'dment Nos. 117, 167, 183, 193,207 i

e CONTAINMENT SYSTEMS SECONDARY CONTAINMENT BYPASS LEAKAGE l

LIMITING CONDITION FOR OPERATION 3.6.1.2 Secondary containment bypass leakage rates shall be limited to a l

l

, combined bypass leakage race of less than or equal to 0.25 L,,

for all l

penetrations that are secondary containment BYPASS LEAKAGE PATHS TO THE R193 AUXILIARY BUILDING when presssurized to P,.*

l APPLICABILITY: MODES 1, 2,

3 and 4 R167 ACTION:

With the combined bypass leakage rate exceeding 0.25 L, for BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING, restore the combined bypass leakage rate from i

BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING "o less than or equal to 0.25 L, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 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 .

l l

Enter the ACTION of LCO 3.6.1.1,

" Primary Containment" when Secondary containment Bypass Leakage results in exceeding the overall containment leakage rate acceptance criteria.

l 4

SEQUOYAH - UNIT 2 3/4 6-2 Amendment Nos. 63, 167, 193, 207 l

l l

l

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1 O

4 CONTAINMENT SYSTEMS SECONDARY CONTAINMENT BYPASS LEAKAGE IR167 SURVEILLANCE REQUIREMENTS 4.6.1.2 The secondary containment bypass leakage rates shall be demonstrated:

a.

The combined bypass leakage rate to the auxiliary building shall be determined to be less than or equal to 0.25 L, by applicable Type B and C tests in accordance with the Containment Leakage Rate Test Program, except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the R167 containment is pressurized to P,,

(12 psig) during each Type A test.

l b.

Leakage from isolation valves that are sealed with fluid from a seal R167 system may be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 P.

(13.2 psig) and the seal system capacity is adequate to maintain system pressure (or fluid head for the containment spray system and RHR spray system valves at penetrations 48A, 48B, 49A, and 49B) for at least 30 days, c.

The provisions of Specification 4.0.2 are not applicable.

1 SEQUOYAH - UNIT 2 3/4 6-3 Amendment Nos. 63, 90, 104, 117, 207 126, 139, 167

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e CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE

with both doors closed l

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.

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 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.

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, j

i 3.

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 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 a inoperable air lock door, maintain at least ene 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 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 .

1.

An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2.

Enter the ACTION of LCO 3.6.1.1,

" Primary Containment" when air lock leakage results in exceeding the overall containment leakage rate acceptance criteria.

SEQUOYAH - UNIT 2 3/4 6-7 Amendment No. 207

CONTAINMENT SYSTEPdS SURVEILLANCE REQUIREMENTS i

4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

l a.

By verifying leakage rates in accordance with the Containment Leakage l

Rate Test Program.

1 b.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

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l t

SEQUOYAH - UNIT 2 3/4 6-8 Amendment Nos. 40, 167, 207 l

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4 4

EQNTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2,

3 and 4.

ACTION:

With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined during shutdown by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel. This inspection shall be performed in accordance with the Containment Leakage Rate Test Program to verify no apparent changes in appearance of the surfaces or other abnormal degradation. Any abnormal degradation of the containment vessel detected during the above required inspections shall be reported to the Commission pursuant to R28 Specification 6.6.1.

l 1

SEQUOYAH - UNIT 2 3/4 6-11 Amendment No. 28, 167,207

1 6 a CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.9 One pair (one purge supply line and one purge exhaust line) of containment purge system lines may be open; the containment purge supply and exhaust isolation valves in all other containment purge lines shall be closed.

Operation with purge supply or exhaust isolation valves open for either purging or venting shall be limited to less than or equal to 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months per 365 days R9 The 365 day cumulative time period will begin every January 1.

APPLICABILITY: MODES 1, 2,

3, and 4.

ACTION:

a.

With a purge supply or exhaust isolation valve oper. in excess of the lR109 above cumulative limit, or with more than one pair of containment purge system lines open, close the isolation valve (s) in the purge line (s) 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 .

b.

With a containment purge supply and/or exhaust isolation valve having a measured leakage rate in excess of 0.05 L, restore the inoperable R109 valve to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , o$herwise 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 4.6.1.9.1 The position of the containment purge supply and exhaust isolation valves shall be determined at least once per 31 days.

4.6.1.9.2 The cumulative time that the purge supply and exhaust isolation R9 valves are open over a 365 day period shall be determined at least once per 7 days.

4.6.1.9.3 At least once per 3 months, each containment purge supply and exhaust isolation valve shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than or equal to 0.05 Ig.*

lR167

Enter the ACTION of LCO 3.6.1.1,

" Primary Containment" when purge valve leakage results in exceeding the overall containment leakage rate acceptance criteria.

SEQUOYAH - UNIT 2 3/4 6-15 Amendment No.

9, 109, 167,207

1 a4 CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 Each containment isolation valve shall be OPERABLE.*

APPLICABILITY: MODES 1, 2,

3 and 4.

ACTION-R193 a.

With one or more of the isolation valve (s), except containment vacuum relief isolation valve (s), inoperable, maintain at least one isolation R188 valve OPERABLE in each affected penetration that is open and either:

1.

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or 2.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or 3.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange; or 4.

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 .

lR193 b.

With one or more containment vacuum relief isolation valve (s) inoperable, the valve (s) must be returned to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in R188 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.

The provis1ons of Specification 3.0.4 do not apply.

SURVEILLANCE REQUIREMENTS 4.6.3.1 Deleted

1.

Penetration flow path (s) may be unisolated intermittently under administrative controls.

2.

Enter the ACTION of LCO 3.6.1.1,

" Primary Containment" when containment isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.

SEQUOYAH - UNIT 2 3/4 6-17 Amendment No. 193, 207

6 e l-3/4.6 CONTAINMENT SYSTEMS l

l BASES R167 3/4.6.1 PRIMARY CONTAINMENT The safety design basis for primary containment is that the containment must withstand the pressures and temperatures of the limiting design basis accident (DBA) without exceeding the design leakage rates.

The DBAs that result in a challenge to containment OPERABILITY from high pressures and temperatures are a loss of coolant accident (LOCA), a steam line break, and a rod ejection accident (REA).

In addition, release of significant fission product radioactivity within containment can occur from a LOCA or REA.

In the DBA analyses, it is assumed that the containment is OPERABLE such that, for the DBAs involving release of fission product radioactivity, release to the environment is controlled by the rate of containment leakage.

This leakage rate limitation will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

The containment was designed with an allowable leakage rate of 0.25 percent of containment air weight per day.

This leakage rate, used in the evaluation of offsite doses resulting from accidents, is defined in the Containment Leakage Rate Test Program, as L,: the l

maximum allowable containment leakage rate at the calculated peak containment internal pressure ( P,) resulting from the limiting DBA.

The allowed leakage R167 rate represented by Lg forms the basis for the acceptance criteria imposed on i

all containment leakage rate testing.

I Primary containment INTEGRITY or operability is maintained by limiting leakage to within the acceptance criteria of the Containment Leakage Rate Test Program.

3/4.6.1.2 SECONDARY CONTAINMENT BYPASS LEAKAGE The safety design basis for containment leakage assumes that 75 percent of the leakage from the primary containment enters the shield building annulus for filtration by the emergency gas treatment system. The remaining 25 percent I

of the primary containment leakage, which is considered to be bypassed to the auxiliary building, is assumed to exhaust directly to the atmosphere without filtration during the first 5 minutes of the accident. After 5 minutes, any bypass leakage to the auxiliary building is filtered by the auxiliary building gas treatment system.

A tabulation of potential secondary containment bypass R167 i

SEQUOYAH - UNIT 2 B 3/4 6-1 Amendment Nos. 91, 139, 167, c'

6 =.

J/4.6 CONTAINMENT SYSTEMS BASES leakage paths to the auxiliary building is provided in the Containment Leakage Rate Test Program.

Restricting the leakage through the bypass leakage paths to

0. 2 5 Lg provides assurance that the leakage fraction assumptions used in the evaluation of site boundary radiation doses remain valid.

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 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 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 annulus atmosphere of 0.5 psig and 2) the containment peak pressure does not exceed the maximum allowable internal BR pressure of 12 psig during LOCA conditions.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that 1) the containment air mass is limited to an initial mass sufficiently low to prevent BR exceeding the maximum allowable internal pressure during LOCA conditions and

2) the anbient air temperature does not exceed that temperature allowable for the continuous duty rating specified for equipment and instrumentation located within containment.

The containment pressure transient is sensitive to the initially contained air, mass during a LOCA.

The contained air mass increases with decreasing temperature. The lower temperature limits of 100*F for the lower compartment, 85*F for the upper ccmpartment, and 60*F when less than or equal to 5% of RATED BR THERMAL POWER will limit the peak pressure to an acceptable value.

The upper temperature limit influences the peak accident temperature slightly during a LOCA; however, this limit is based primarily upon equipment protection and anticipated operating conditions. Both the upper and lower temperature limits are consistent with the parameters used in the accident analyses.

3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment steel vessel will be maintained comparable to the original design standards for the life of the facility.

Structural integrity is required to ensure that the BR vessel will withstand the maximum pressure of 12 peig in the event of a LOCA.

Periodic visual inspections in accordance with the Containment Leakage Rate Test Program are sufficient to demonstrate this capability.

SEQUOYAH - UNIT 2 B 3/4 6-2 Amendment No. 91, 139, 167, 193,207

L M e

ADMINISTRATIVE CONTROLS 3)

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the R134 measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

h.

Containment Leakace Rate Testino Procram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54 (o) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions. Visual examination and testing, including test intervals and extensions, shall be in accordance with Regulatory Guide (RG) 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995 with exceptions provided in the site implementing instructions.

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

is 12.0 psig.

The maximum allowable containment leakage rate, L,

at P.,

is 0.25% of the primary containment air weight per day.

Leakage rate acceptance criteria are:

a.

Containment overall leakage rate acceptance criteria is s 1. 0 Lg.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 Is for the combined Type B and Type C tests, and s 0.75 L, for Type A tests; b.

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is s 0.05 Ig when tested at a P,.

2)

For each door, leakage rate is s 0.01 Ig when pressurized to a 6 psig for at least two minutes.

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

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

6.9 REPORTING REOUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted in accordance R64 with 10 CFR 50.4.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

SEQUOYAH - UNIT 2 6-19 Amendment No. 28, 50, 64, 66, 134, 207

l s*

ADMINISTRATIVE CONTROLS l

RIARTUP REPORI (continued) 6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison

]

of these values with design predictions and specifications. Any corrective j

actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6,9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e.,

initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

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j SEQUOYAH - UNIT 2 6-19a Amendment No. 28, 50, 64, 66, 134, 207

ML20097F202

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