ML20072R153

Amends 150 & 140 to Licenses DPR-77 & DPR-79,respectively, Re Containment Spray Subsystems

ML20072R153
Person / Time
Site:	Sequoyah
Issue date:	03/18/1991
From:	Donohew J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20072R156	List: ML20072R153 ML20072R159
References
NUDOCS 9103220214
Download: ML20072R153 (13)

Text

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UNITED STATES g

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NUCLE AR REGULATORY COMMISSION n

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e TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-327 SEQUOYAH NUCLEAR PLANT UNIT 1 AMENDMENT TO FACILITY t :ERATING LICENSE Amendment No.150 License No. DPR-77 3.

Tha Nuclear Regulatcry Comission (the Comission) has found thatt A.

The application for amendmer,t by Tennessee Valley Authority (the licensee)datedNovember 20,1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Connission's rules and regulations set forth in 10 CFR Chapter 1; B.

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

Thereisreasonableassurance-(i)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i

cor. ducted in compliance with the Comitsion'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-publict and E.

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

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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 Ope" ting License No. DPR-77 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.150, are hereby incorporated in the license. The licensee shall operate the f acility in accordance with the Technical Specifications.

3.

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

FCR THE NUCLEAR REGULATORY C0411SSION L

A.

Frederi h J. }!tbdon, Director Project Directorate 11-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Pegulation

Attachment:

Changes to tht Technical Specifications

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Date of issuance: March 18, 1991 l

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ATTACHfiENT TO LICENSE AMENDMENT NO.150

= FACILITY OPERATING LICENSE NO. DPR DOCKET-NO. 50-327 Revise the Apper, dix A Technical Specifications by removing the' pages identified below and inserting the_ enclosed pages. - The revised panet are identified by the captioned amendment. number and contain marginal lines indicating the area of enange.

REMOVE-INSERT V11

-VII-

-3/4 6 3/4 6-16 B3/4 6 B3/4 6-3

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AD'd LIMITING CONDITIONS FOR OPERATION AND SURVL'tLANCE REQUIREMENTS SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS Cold Leg Injection Accumulators...........................

3/4 5-1 Deleted...................................................

3/4 5-3 3/4.5.2 ECCS SUBSYSTEMS - T,yg greater than or equal to 350'F.....

3/4 5-4 3/4.5.3 ECCS SUBSYSTEMS - T,yg ess than 350'F....................

3/4 5-8 3/4.5.4 DELETED...................................................

3/4 5-10 3/4.5.5 REFUELING WATER STORAGE TANK..............................

3/4 5-11 3/4. 6 CONTAINMENT SYSTEMS 3/4.F 1 PRIMARY CONTAINMENT Containment Integrity.....................................

3/4 6-1 Containment Leakage.......................................

3/4 6-2 Containment Air Locks.....................................

3/4 6-7 Internal Pressure.........................................

3/4 6-9 Air Temperature...........................................

3/4 6-10 Containment Vessel Structural Integrity...................

3/4 6-11 Shiel d Buildi ng Structural Integri ty......................

3/4 6-12 Emergency Gas Treatment System (Cleanup Subsystem)........

3/4 6-13 Containment Ventilation System............................

3/4 6-15 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray Subsystems..............................

3/4 6-16 Lower Containment Vent Coo 1ers............................

3/4 6-16b i

SEQUOYAH - UNIT 1 VII Amendment No. 67, 69, 116, 140 150

CONTAIhMENTSSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS e

CONTAINMENT SPRAY SUBSYSTEMS LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray subsystems shall be OPEPlcLE with i

each subsystem comprised of:

I a.

A Containment-Spray train with:

1.

One OPERABLE Containment Spray pump.

2.

On' OPERABLE Containment Spray heat exchang)r,

-3.

An OPERABLE Containment Spray pump flow path capable of taking suction from the refueling water storage tank and transferring suction to the containment sump, and b.

A RHR Spray train with:

1.

One OPERABLE residual heat removal pump, 2.

One OPERABLE residual heat removal heat exchanger, and 3.

-An OPERABLE residual heat removal pump flow path capable of taking suction from the containment sump and supplying flow to the spray header.

APPLICABILITY:- MODES,1. 2, 3 and 4.*

ACTION:-

With one containment spray subsystem inoperable, restore the inoperable sub-system to 0FERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />;- restore the inoperable subsystem to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be-in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.2.1.1-Each Containment Spray train shall be demonstrated OPERABLE:

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

. power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

• 0PERABILITY of RHR Spray trains is not required in MODE 4.

SEQUOYAH - UNIT.1 3/4 6-16 Amendment 12, 69 150

CONTAl$MENTSSTEMS 3ASES 3/4.6.1.8 EMERGENCY GAS TREATMENT SYSTEM (EGTS)

The OPERABILITY of the EGTS cleanup subsystem ensures that during LOCA conditions, containment. vessel leakage into the annulus will be filtered through the HEPA filters and charcoal adsorber trains prior to discharge to the atmosphere. ~This requirement is necessary to meet the assumptions used in the accident analyses and limit the site boundary radiation doses to within the limits of 10 CFR.100 during LOCA conditions.

Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the absorbers and HEPA filters.

ANSI N510-1975 will be used as a procedural guide for surveillance testing.

3/4.6.1.9 CONTAINMENT VENTILATION SYSTEM Use of the containment purge lines is restricted to only one pair (one supply line and one exhaust line) of purge system lines at a time to ensure that the tite boundary aose guidelines of 10 CFR Part 100 would not be exceeded in the event of a loss of coolant accident during purging operations.

The analysis of this accident assumed purging through the largest pair of lines (a 24-inch inlet line and a 24 inch outlet line), a pre-existing iodine spike in the reactor coolant and four second valve closure times.

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SUBSYSTEMS The OPERABILITY of the containment spray subsysterhs ensures that contain-ment depressurization and cooling capability will be avail.able in the event of a LOCA.* The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.

3/4.6.2.2 CONTAINMENT COOLING FANS The OPERABILITY of the lower containment vent coolers ensures that ade-quate. heat removal capacity is available to provide long-term cooling following a non-LOCA event.

Postaccident use of these coolers ensures containment tem-peratures remain within environmental qualification limits for all safety-related equipment required to remain functional, 3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be.isclatec from the outside environment in the event of a-release of radioactive material to the containment atmosphere or pressurization of the containment.

Containment isolation within the time

-limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a L

LOCA.

By letters dated March 3, 1981, and April 2, 1981, TVA will submit a report on the operating experience of the plant no later than startup after the first refueling.

This information will be used to provide a basis to re-evaluate the adequacy of the purge and vent time limits.

l SEQUOYAH - UNIT 1 B 3/4 6-3 Amendment No. 67, 114, 150 l

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UNITED STATES

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^79 NUCLEAR REGULATORY COMMISSION E

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TENHESSEE VALLEY AUTHORITY DOCKET N3. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.140 License No. OPR-79 1.

The Nuclear Reguh mission (the Ccmission) has found that:

v A.

The application 1or amendment by Tennessee Valley Authority (the licensee) dated November 20, 1990, complies with the standards and requirements of the Atomic Er.ergy Act of 1954, as amended (the Act),

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

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

Thereisreasonableassurance(1)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this 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 Commission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is aniended 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 anwnded to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised-through Amendment No.140, 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.

FOR THE NllCLEAR REGULATORY COMMISSION hL.w0.

C' FrederfEk J. hebdon, Director Project Directorate.11-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Ch6r.ges to the Technical Specifications Date of 1ssuance: March 18,1991 l

."t 1

ATTACHMENT-TO LICENSE AMENDMENT fl0.140 FACILITY 0PERATING LICEllSE NO. DPR-79 4

DOCKET NO. 50-328 4

Revise the Appendix A Technical Specifications by removing the pages

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identified below and inserting the-enclosed pages. The revised pages are _ identified by.the ceptioned amendment nunter and Onntain marginal lines indicating the area of-change.

Overleaf pages*. are provided to maintain document-ccmpleteness.

REMOVE INSERT j

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VII Vill VIII*

3/4 6 3/4 6-16 B3/4 6-3 B3/4 6-3 1

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVE'LLANCE REQUIREMENTS

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SECTION PAGE 3/4.5 EHERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS Cold Leg Inject 6 Accumulators...........................

3/4 5-1 Deleted...................................................

3/4 5-3 3/4.5.2 ECCS SUBSYSTEMS - T,yg greater than or equal to 350'F.....

3/4 5-4 3/4.5.3 ECCS SUBSYSTEMS - T,yg less than 350'F....................

3/4 5-8 3/4.5.4 DELETED...................................................

3/4 5-10 3/4.5.5 _ REFUELING WATER STORAGE TANK..............................

3/4 5-11 3/4.6 CONTAINHENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity.....................................

3/4 6-1 Containment Leakage.......................................

3/4 6-2 Containment Air Locks.....................................

3/4 6-7 Internal Pressure.........................................

3/4 6-9 Air Temperature...........................................

,.e4 6-10 Containment Vessel Structural Integrity...................

3/4 6-11 Shi eld Building Structural Integrity......................

3/4 6-12 Emergency Gas Treatment System (Cleanup Subsystem)........

3/4 6-13 Containment Ventilation System............................

3/4 6-15 3/4.6.2-DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray Subsystems..............................

3/4 6-16 Lower Containment Vent Coo 1ers............................

3/4 6-16b SEQUOYAH - UNIT 2 VII Amendment No. 59, 61, 131 140

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_INDEX-LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRE SECTION PAGE

.3/4.6.3 CONTAINMENT ISOLATION VALVES..............................

3/4 6-17 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers......,................................

3/4 6-24 E l e c t r i c Hy d rog e n R e c omb i ne rs.............................

3/4 6-25 3/4.6.5 ICE CONDENSER Ice Bed..................................................

3/4 6-26 Ice bed Temperature Monitoring System.....................

3/4 6-28 Ice Condenser Doors.......................................

3/4 6-29 Inlet Door Position Monitoring System....................,

3/4 6-31 Divider Barrier Personnel Access Doors and Equipment Hatches.......................................

3/4 6-32 Containment Air Return Fans...............................

3/4 6-33 Floor Drains..............................................

3/4 6-34 Refueling Canal Drains....................................

3/4 6-35 Divider Barrier Sea1......................................

3/4 6-36

.3/4.6.6 VACUUM RELIEF VALVES......................................

3/4 6-38 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety. Valves.............................................

3/4 7-1 A ux i l i a ry F e e dwa t e r Sys tem................................

3/4 7-5 Condensate Storage Tank...................................

3/4 7 Activity..................................................

3/4 7-8 Main Steam Line Isolation Valves..........................

3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........

3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM............................

3/4 7-12 3r4.7.4-ESSENTIAL RAW COOLING WATER SYSTEM

' Essential Raw Cooling Water System.......................

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3/4 7-13 SEQUOYAH'- UNIT 1 L

VIII Amendment No.116 JIIN 1 Nb3 l

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CONTA[NMENTSSTEMS

.1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SUBSYSTEMS LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray subsystems shall be OPERABLE with each subsystem comprised of:

a.

A Containment Spray trair, with:

1.

One OPERABLE Containment Spray pump.

2.

One OPERABLE Containment Spray heat exchanger.

- 3.

An OPERABLE Containment Spray Pump flow path capable of taking l

suction from the refueling water storage tank and transferring I

suction to the containment sump, and b.

A RHR Spray train with:

1.

One OPERABLE residual heat removal pump.

2.

One OPERABLE residual heat removal heat exchanger, and 3.

An OPERABLE residual heat removal pump flow path capable of taking suction from the containment sump and supplying flow to the spray header.

APPLICABILITY:

MODES 1, 2, 3 and 4.*

ACTION:

With one containment spray su~ system inoperable, restore the inoperable sub-o system to OPERABLE s_tatus within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, restore the inoperable subsystem to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.2.1.1 Each Containment Spray train shall be demonstrated OPERABLE:

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

power. operated or automatic) in the flow path that is not locked sealed,.or otherwise secured in position, is in its correct position.

• 0PERABILITY of RHR Spray trains is not required in MODE 4.

SEQUOYAH --UNIT 2 3/4 6-16 Amendment No. 61 140 y

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CONTAI'NMENT SYSTEMS

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3/4.6.1.8 EMERGENCY GAS TREATMENT SYSTEM (EGTS)

The OPERABILITY of the EGTS cleanup subsystem ensures that during LOCA conditions, containment vessel leakage into the annulus will be filtered through the HEPA filters and charcoal adsorber trains prior to discharge to the atmosphere.

This requirement is necessary to meet the assumptions used in the accident analyses and limit the site boundary radiation doses to within the limiti, of 10 CFR 100 during LOCA conditions.

Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the absorbers and HEPA filters.

ANSI N510-1975 will be used as a procedural guide for surveillance testing.

3/4.6.1.9 CONTAINMENT VENTILATION SYSTEM Use of the containment purge lines is restricted to only one pair (one supply line and one exhaust line) of purge system lines at a time 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 purging operations.

The analysis of this accident assumed purging through the largest pair-of lines (a 24 inch inlet line and a 24 inch outlet line), a pre-existing iodine spike in the reactor coolant and four second valve closure times.

3/4.6.2 DEPRESSURI2ATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SUBSYSTEMS The OPERABILITY-of the containment spray subsystems ensures that contain-ment depressurization and cooling capability will be available in the event of a LOCA. -'The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.

3/4.6.2.2 CONTAINMENT COOLING FANS l

The OPERABILITY of the lower containment vent coolers ensures that ade-l quate heat removal capacity is available to provide long-term cooling following a non-LOCA event.

Postaccident use of these coolcrs ensures containment tem-

.peratures remain within environmental qualification limits for all safety-related equipment required to remain functional.

3/4. 6.'3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the

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event of a release of radioactive material to the containment atmosphere or pressurization of the containment.

Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

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SEQUOYAH - UNIT 2 B 3/4 6-3 Amendment No. 59 l

140 l

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