ML20248D268
| ML20248D268 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/18/1989 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248D272 | List: |
| References | |
| NUDOCS 8910040178 | |
| Download: ML20248D268 (27) | |
Text
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, Ig UNITED STATES g-NUCLEAR REGULATORY COMMISSION 5
j WASHINGTON, D. C. 20555
,e*
TENNESSEE VALLEY AUTHCRITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 171 License No. DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated February 14, 1989, as supplemented by letter dated July 14, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comis-sion's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be 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 of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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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 Operating License No. DPR-33 is hereby amended to read as folic.<s:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.171, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license anendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Suzan Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 18, 1989 1
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ATTACRMENT TO LICENSE AMENDMENT N0.171 FACILITY OPERATING LICENSE NO. DPR-33 e
DOCKET NO. 50-259 Revise the Appndix '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.
3.7/4.7-19
.3.7/4.7-19 3.7/4.7-20 3.7/4.7-20 3.7/4.7-51 3.7/4.7-51 3.7/4.7-52 3.7/4.7-52 3.7/4.7-53 3.7/4.7-53 3.7/4.7-53a 3.7/4.7-53a
- . L >
3.7/4.7 CONTAINMENT SYSTEMS-
' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emernency Ventilation 4.7.E Control Room Emergency j
Ventilation
- 1. Except as specified in.
- 1. At least once every 18 months, Specification 3.7.E.3 below, the pressure drop across the both control room emergency combined HEPA filters and pressurization systems charcoal adsorber banks shall shall be OPERABLE at all be demonstrated to be lesa than times when any reactor 6 inches of water at system vessel contains irradiated design flow rate (1 10%).
fuel.
1
- 2. a.'The results of the inplace
- 2. a. The tests and sample cold DOP and halogenated analysis of Specification hydrocarbon tests at design 3.7.E.2 shall be performed flows on HEPA filters and at least once per operating charcoal adsorber banks cycle or once every 1
shall show 199% DOP removal 18 months, whichever occurs and 199% halogenated first for standby service hydrocarbon removal when or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of tested in accordance with system operation and ANSI N510-1975.
following significant painting, fire, or chemical' i
release in any ventilation zone communicating with the system.
1 i
i
- b. The results of laboratory
- b. Cold DOP testing shall be carbon sample analysis shall performed after each show 190% radioactive methyl complete or partial iodide ~ removal at a velocity replacement of the HEPA-when tested in accordance filter bank or after any j
with ASTM D3803 structural maintenance'on (130*C, 95% R.H.).
the system housing.
CREVS is considered inoperable only because it does not meet its design basis for essentially zero unfiltered inleakage. REACTOR POWER OPERATION and fuel movement are acceptable until just PRIOR TO STARTUP for unit 2 cycle 7.
During cycle 6, CREVS must be demonstrated to be functional by performing all applicable surveillance.
In the event that the applicable surveillance are not successfully performed, the actions required by the LCO's must be complied with.
BFN 3.7/4.7-19 Amendment No. 143, 171 Unit 1 I
i
)
A
- 1 3.7/4.7 CONTAllOfENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS L
3.7.E. Control Room Emergency 4.7.E.
Control Room Emergency t'
Ventilation Ventilation c.. System' flow rate shall be
- c. Halogenated hydrocarbon shown to be within 110%
testing shall be performed design flow when tested in after each complete or accordance with ANSI partial replacement of the N510-1975.
charcoal adsorber bank or after any structural maintenance on the system housing.
'd. Each circuit shall be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
- 3. From and after the date that,
- 3. At least once every 18 months, one of the control room rutomatic initiation of the emergency pressurization control room emergency systems is made or found to pressurization system shall be be inoperable for any reason, demonstrated.
REACTOR POWER OPERATIONS or refueling operations are permissible only during the succeeding 7 days unless such circuit is sooner made OPERABLE.
- 4. If these conditions cannot be
- 4. During the simulated automatic met, reactor shutdown shall be actuation test of this system initiated and all reactors (see Table 4.2.G), it shall be shall be in COLD SHUTDOWN verified that the following within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for REACTOR dampers operate as indicated:
POWER OPERATIONS and refueling operations shall be terminated Close: FCO-150 B, D, E, F, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
and G Open: FCO-151, FCO-152 l
CREVS is considered inoperable only because it does not meet its design basis for essentially zero unfiltered inleakage. REACTOR POWER OPERATION and fuel movement are acceptable until just PRIOR TO STARTUP for unit 2 cycle 7.
During cycle 6, CREVS must be demonstrated to be functional by
-performing all applicable surveillance.
In the event that the applicable surveillance are not l
successfully performed, the actions l
required by the LCO's must be complied
,ith.
w BFN 3.7/4.7-20 Amendment Nos. 151, 158, 168, 171 Unit 1 l
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3.7/4.7 BASES (Crnt'd) l ti 3.7.E/4.7.E Control Room Emergency Ventilation L
The control room emergency ventilation system is designed to filter the control room atmosphere for intake air and/or for recirculation during control room isolation conditions. The control room emergency ventilation system is designed to automatically start upon control room isolation and to maintain the control room pressure to the design positive pressure so that all leakage should be out leakage. During cycle 6, CREVS has been declared inoperable only because it does not meet its design basis for essentially zero unfiltered inleakage. Reactor power operations and fuel movement are acceptable until just prior to startup for unit 2 cycle 7.
During cycle 6, CREVS must be demonstrated to be functional by performing all applicable surveillstces. In the event that the applicable surveillance are not successfully performed, the actions required by.the LCOs must be complied with.
High efficiency particulate absolute (HEPA) filters are in' stalled prior to the charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential intake of radioiodine to the control room. The inplace test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99 percent removal of DOP particulate. The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident conditions.
If the efficiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power Plants, Appendix A to 10 CFR Part 50.
Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If the system is found to be inoperable, there is no immediate threat to the control room and reactor operation or refueling operation may continue for a limited period of time while repairs are being made. If the system cannot be repaired within seven days, the reactor is shutdown and brought to Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or refueling operations are terminated.
-Pressure drop across the combined HEPA filters and charcoal adsorbers of less than six inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop should be determined at least once per operating cycle to show system performance capability.
The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated. Tests of the charcoal adsorbers with halogenated hydrocarbon shall be performed in accordance with USAEC Report-1082. Iodine removal efficiency tests shall follow ASTM D3803. The charcoal adsorber efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtaining at least two samples. Each sample should be at least two inches in diameter and a length equal to the thickness of the bed.
If test results are unacceptable, all adsorbent in the system shall be replaced with an adsorbent qualified according to Table 1 of Regulatory Guide 1.52.
The replacement tray for the adsorber tray removed for BFN 3.7/4.7-51 Amendment No. 143, 171 Unit 1
3.7/4.7 BASES (Cont'd)
,s.
the test should meet the same adsorbent quality. Tests of the HEPA filters with DOP aerosol shall be performed in accordance to ANSI N510-1975. Any HEPA filters found defective shall be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.
Operation of the system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month will demonstrate operability of the filters and adsorber system and remove excessive moisture built up on the adsorber.
If significant painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign materials, the same tests and sample analysis shall be performed as required for operational use. The determination of significance shall be made by the operator on duty at the time of the incident.
Knowledgeable staff members should be consulted prior to making this determination.
Demonstration of the automatic initiation capability is necessary to assure system performance capability.
3.7.F/4.7.F Primary Containment Purste System The primary containment purge system is designed to provide air to purge and ventilate the primary containment system. The exhaust from the primary containment is first processed by a filter train assembly and then channeled through the reactor building roof exhaunt system. During power operation, the primary containment purge and ventilation system is isolated from the primary containment by two isolation valves in series.
HEPA (high efficiency particulate air) filters are installed before the charcoal adsorbers followed by a centrifugal fan. The in-place test results should indicate a leak tightness of the system housing of not less than 99-percent and a HEPA efficiency of at least 99-percent removal of DOP particulate. The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 85-percent.
Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If the system is found to be inoperable, the Standby Gas Treatment System may be used to purge the containment.
Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 8.5 inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop should be determined at least once per operating cycle to show system performance capability.
The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated. Tests of the charcoal adsorbers with halogenated hydrocarbon shall be performed in accordance with USAEC Report-1062.
Iodine removal efficiency tests shall follow ASTM D3803. The charcoal adsorber efficiency test procedures should 3.7/4.7-52l Amendment No. 143, 171 BFN l
Unit 1 l
l l
3.7/4.7 BMES (Cont 'd) allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtaining at least two samples..Each sample should be at least two inches in diameter and a length equal to the thickness of the bed. If test results are unacceptable, all adsorbent in the system shall be replaced with an adsorbent qualified according to Table 1 of Regulatory Guide 1.52.
The replacement tray for the adsorber tray removed for the test should meet the same adsorbent quality. Tests of the HEPA filters with DOP aerosol shall be performed in accordance to ANSI N510-1975. Any HEPA
_ filters found defective shall be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.
If significant painting, fire, or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign materials, the same tests and sample analysis shall be performed as required for operational use. The determination of significance shall be made by the operator on duty at the time of the incident.
Knowledgeable staff members should be consulted prior to making this determination.
l l
BFN 3.7/4.7-53l Amendment No. 171 Unit 1 l
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I THIS PAGE INTENTIONALLY LEFT BLANK BFN 3.7/4.7-53a Amendment No. 171 Unit 1
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UNITED STATES.
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NUCLEAR REGULATORY COMMISSION O
.J' WASHINGTON, D..?. 20555 y *.. + g$
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.173 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by lennessee Valley Authority (the licensee) dated February 14, 1989, as supplemented by letter dated July 14. 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commis-ston's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
i 1
o 4
'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-52 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.173, 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 and shall be implemented within 30 days from the date of. issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (4 ww4 Suzanne ack, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
' Changes to the Technical Specifications Date of Issuance:
September 18, 1989
l;..,
ATTACHMENT TO LICENSE AMENDMENT NO. 173 FACILITY OPERATING LICENSE NO. DPR-52 1
DOCKET NO. 50-260 Revise the Appendix A Technical Specifications by removing the pages
~
identified below and inserting the enclosed pages. The revised pages are identified by the er.ptioned amendment number and contain marginal.
lines indicating the area of change.
l REMOVE INSERT 3.7/4.7-19 3.7/4.7-19 3.7/4.7-20 3.7/4.7-20 3.7/4.7-51 3.7/4.7-51 3.7/4.7-52 3.7/4.7-52 3.7/4.7-53 3.7/4.7-53 3.7/4.7-53a 3.7/4.7-53a
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'3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emeraency Ventilation 4.7.E Control Room Emeraency Ventilation
- 1. Except as specified in
- 1. At least'once every 18 months, Specification 3.7.E.3 below, the pressure drop across the both control room emergency combined HEPA filters and pressurization systems charcoal adsorber banks shall shall be OPERABLE at all be demonstrated to to be less times when any reactor than 6 inches of water at system vessel contains irradiated design flow rate (1 10%).
fuel.
- 2. a. The results of the inplace
- 2. a. The tests and sample cold DOP and halogenated analysis of Specification hydrocarbon tests at design 3.7.E.2 shall be performed flows on HEPA filters and at least once per operating charcoal adsorber banks cycle or once every shall show 199% DOP removal 18 months, whichever occurs and 199% halogenated first for standby service hydrocarbon removal when or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of tested in accordance with system operation and ANSI N510-1975.
following significant painting, fire, or chemical release in any ventilation zone communicating with the system.
- b. The results of laboratory
- b. Cold DOP testing shall be carbon sample analysis shall performed after each show 190% radioactive methyl complete or partial iodide removal at a velocity replacement of the HEPA when tested in accordance filter bank or after any with ASTM D3803 structural maintenance on (130*C, 95% R.H.).
the system housing.
CREVS is considered inoperable only because it does not meet its design basis for essentially zero unfiltered inleakage. REACTOR POWER OPERATION and fuel mosement are acceptable until Just PRIOR TO STARTUP for unit 2 cycle 7.
During cycle 6, CREVS must be demonstrated to be functional by performing all applicable surveillance.
In the event that the applicable surveillance are not successfully performed, the actions required by the LCO's must be complied with.
BFN 3.7/4.7-19 Amendment No. 139, 173 Unit 2
a js is' 1, :
g,3.7/4.7 CONTAINMENT SYSTEMS.
l'.
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
.3.7.E. Contro1' Room Emernency 4.7.E.
Control Room Emernency
' Ventilation Ventilation
- c. Systea flow rate shall be
- c. Halogenated hydrocarbon D
-shown to be within 110%
. testing shall be performed design flow when tested in after each complete or accordance with ANSI partial replacement of the-l N510-1975.
charcoal adsorber bank or after any structural maintenance on the system housing.
- d. Each circuit shall be
{
operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
- 3. From and after the date that
- 3. At least once every 18 months,-
one of the control room automatic initiation of the emergency pressurization control room emergency systems is made or found to pressurization system shall be be inoperable for any reason, demonstrated.
REACTOR POWER OPERATIONS or refueling operations are permissible only during the succeeding 7 days unless such circuit is sooner made OPERABLE.
- 4. If these conditions cannot be
- 4. During the simulated automatic met, reactor shutdown shall be actuation test of this systr.m initiated and all reactors (see Table 4.2.G), it shall be shall be in COLD SHUTDOWN verified that the following within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for REACTOR.
dampers operate as indicated:
POWER OPERATIONS and refueling operations shall be terminated' Close: FCO-150 B, D,'E, F, F
within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
and G.
Open: FCO-151, FCO-152 CREVS is considered inoperable only because it does not meet its design basis for essentially zero unfiltered inleakage.
REACTOR POWER OPERATION and fuel movement are acceptable until just PRIOR TO STARTUP for unit 2 cycle 7.
-During cycle 6, CREVS must be demon-strated to be functional by performing all applicable surveillance.
In the event that the applicable surveillance are not successfully performed, the actions required by the LCO's must be complied with.
BFN 3.7/4.7-20 Amendment No. 147, 154, 168, 173 Unit 2
3.7/4.7 BASES (C:nt'd) 3.7.E/4.7.E Control koom Emergency Ventilation The control room emergency ventilation system is designed to filter the control room atmosphere for intake air and/or for recirculation during control i
room isolation conditions. The control room emergency ventilation system is designed to automatically start upon control room isolation and to maintain the control room pressure to the design positive pressure so that all leakage should be out leakage. During cycle 6, CREVS has been declared inoperable only because it does not meet its design basis for essentially zero unfiltered inleakage. Reactor power operations and fuel movement are acceptable until just prior to startup for unit 2 cycle 7.
During cycle 6, CREVS must be demonstrated to be functional by performing all applicable surveillance.
In the event that the applicable surveillance are not successfully performed, the actions required by the LCOs must be complied with.
High efficiency particulate absolute (HEPA) filters are installed prior to the charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential intake of radiciodine to the control room. The inplace test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99 percent removal of DOP particulate.
The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident conditions. If the efficiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power Plants, Appendix A to 10 CFR Part 50.
Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If the system is found to be inoperable, there is no immediate threat to the control room and reactor operation or refueling operation may continue for a limited period of time while repairs are being made.
If the system cannot be repaired within seven days, the reactor is shutdown and brought to Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or refueling operations are terminated.
Pressure drop across the combined HEPA filters and charcoal adsorbers of less than six inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop should be determined at least once per operating cycle to show system performance capability.
The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated. Tests of the charcoal adsorbers with halogenated hydrocarbon shall be performed in accordance with USAEC Report-1082. Iodine removal efficiency tests shall follow ASTM D3803. The charcoal adsorber efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtaining at least two samples. Each sample should be at least two inches in diameter and a length equal to the thickness of the bed.
If test results are unacceptable, all adsorbent in the system shall be replaced with an adsorbent qualified according to Table 1 of Regulatory Guide 1.52.
The replacement tray for the adsorber tray removed for BFN 3.7/4.7-51 Amendment No. 139, 173 Unit 2
3.7/4.7 BalEl (Cont'd) the test should meet the same adsorbent quality. Tests of the HEPA filters with DOP aerosol shall be performed in accordance to ANSI N510-19?5. Any HEPA filters found defective shall be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.
Operation of the system for 10 bours every month will demonstrate operability of the filters and adsorber system and remove excessive moisture built up on the adsorber.
If significant painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign materials, the same tests and sample analysis shall be performed as required for operational use. The determination of significance shall te made by the operator on duty at the time of the incident.
Knowledgeable staff members should be consulted prior to making this determination.
Demonstration of the automatic initiation capability is necessary to assure system performance capability.
3.7.F/4.7.F Primary Containment Purae System The primary containment purge system is designed to provide air to purge and ventilate the primary containment system. The exhaust from the primary containment is first processed by a filter train assembly and then channeled through the reactor building roof exhaust system. During power operation, the primary containment purge and ventilation system is isolated from the primary containment by two isolation valves in series.
HEPA (high efficiency particulate air) filters are installed before the charcoal adsorbers followed by a centrifugal fan. The in-place test results should indicate a leak tightness of the system housing of not less than 99-percent and a HEPA efficiency of at least 99-percent removal of DOP particulate. The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 85-percent.
Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If the system is found to be inoperable, the Standby Gas Treatment System may be used to purge the containment.
Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 8.5 inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop should be determined at least once per operating cycle to show system performance capability.
The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated. Tests of the charcoal adsorbers with halogenated hydrocarbon shall be performed in accordance with USAEC Report-1082.
Iodine removal efficiency tests shall follow ASTM D3803. The charcoal adsorber efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, BFN 3.7/4.7-52 Amendment No. 139, 173 l
Unit 2
_ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ - _ _ _ _ _
l :.
p<
3.7/4.7 BASES (C:nt'd) mixing the adsorbent thoroughly and obtaining at least two samples. Each sample should be at least two inches in diameter and a length equal to the
.4 thickness of the bed. If test results are unacceptable, all adsorbent in the-L system shall be replaced with an adsorbent qualified according to Table 1 of L
The replacement tray for the adsorber tray removed for l
the test should meet the same adsorbent quality. Tests of the HEPA filters with DOP aerosol shall be performed in accordance to ANSI N510-1975. Any HEPA filters found defective shall be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.
If significant painting, fire, or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, I
chemicals or foreign materials, the same tests and sample analysis shall be l
performed as required for operational use. The determination of significance shall be made by the operator on duty at the time of the incident.
Knowledgeable staff members should be consulted prior to making this determination.
BFN 3.7/4.7-53l Amendment No. 173 Unit 2
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- THIS PAGE INTENTIONALLY LEFT BLANK BFN 3.7/4.7-53a Amendment No. 173 Unit 2
k.
UNITED STATES
- = '[
g NUCLEAR REGULATORY COMMISSION 5
- j.
~W ASHINGTON, D. C. 20555
- L*
f TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.142 License ~No. DPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated February 14, 1989, as supplemented by letter dated July 14, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comis-sion's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance nf 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 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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l 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-68 is hereby l
amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as L
revised through Amendment No.142, are hereby incorporated in the I
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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
Suzanne stant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 18, 1989
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i ATTACHMENT TO LICENSE AMENDMENT N0.~ 142 FACILITY OPERATING LICENSE NO. DPR-68 l'
DOCKET NO. 50-296
'I Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages i-are identified by the captioned amendment number and contain marginal I
lines indicating the area of change.
REMOVE INSERT 3.7/4.7-19 3.7/4.7-19 3.7/4.7-20 3.7/4.7-20 3.7/4.7-49 3.7/4.7-49 3.7/4.7-50 3.7/4.7-50 3.7/4.7-51 3.7/4.7-51 3.7/4.7-51a 3.7/4.7-51a
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- 3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emergenev Ventilation 4.7.E Control Room Emergency Ventilation
- 1. Except as specified in
- 1. At least once every 18 months, Specification 3.7.E.3 below, the pressure drop across the both control room emergency combined HEPA filters and pressurization systems charcoal adsorber banks shall shall be OPERABLE at all be demonstrated to to be less times when any reactor than 6 inches of water at vessel contains irradiated system design flow rate fuel.
(i 10%).
- 2. a. The results of the inplace
- 2. a. The tests and sample cold DOP and halogenated analysis of Specification hydrocarbon tests at design 3.7.E.2 shall be performed flows on HEPA filters and at least once per operating charcoal adsorber banks cycle or once every shall show 199% DOP removal 18 months, whichever occurs and 199% halogenated first for standby service hydrocarbon removal when or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of tested in accordance with system operation and ANSI N510-1975.
following significant painting, fire, or chemical release in any ventilation zone communicating with the system.
- b. The results of laboratory
- b. Cold DOP testing shall be carbon sample analysis shall performed after each show 190% radioactive methyl complete or partial iodide removal at a velocity replacement of the HEPA when tested in accordance filter bank or after any with ASTM D3803 structural maintenance on (130*C, 95% R.H.).
the system housing.
CREVS is considered inoperable only because it does not meet its design basis for essentially zero unfiltered inleakage.
REACTOR POWER OPERATION and fuel movement are acceptable until just PRIOR TO STARTUP for unit 2 cycle 7.
During cycle 6, CREVS must be demonstrated to be functional by performing all applicable surveillance.
In the event that the applicable surveillance are not successfully performed, the actions required by the LCO's must be complied with.
BFN 3.7/4.7-19 Amendment No. 114, 142 Unit 3
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3.7/4.7 CONTAINMENT 515tr.ris LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E.-Control Room Emerzenev 4.7.E.
Control Room Emerzency Ventilation Ventilation
- c. System flow rate shall be
- c. Halogensted hydrocarbon shown to be within 1 0%
testing shall be performed 1
design flow when tested in after each complete or accordance with ANSI partial replacement of the N510-1975.
charcoal adsorber bank or after any structural maintenance on the system housing.
- d. Each circuit shall be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
- 3. From and after the date that
- 3. At least once every 18 months, one of the control room automatic initiation of the emergency pressurization control room emergency
. systems is made or found to pressurization system shall be be inoperable for any reason, demonstrated.
REACTOR POWER OPERATIONS or refueling operations are permissible only during the succeeding 7 days unless such circuit is sooner made OPERABLE.
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- 4. If these conditions cannot be
- 4. During the simulated automatic met, reactor shutdown shall be actuation test of this system initiated and all reactors (see Table 4.2.G), it shall be shall be in COLD SHUTDOWN verified that the following within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for REACTOR dampers operate as indicated:
POWER OPERATIONS and refueling operations shall be terminated Close: FCO-150 B, D, E, F, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and G Open: FCO-151, FCO-152 l
CREVS is considered inoperable only because it does not meet its design basis for essentially zero unfiltered inleakage. REACTOR POWER OPERATION and fuel movement are acceptable until just PRIOR TO STARTUP for unit 2 cycle 7.
During cycle 6, CREVS must be demonstrated to be functional by performing all applicable surveillance.
In the event that the applicable surveillance are not successfully performed, the actions required by the LCO's must be complied with.
BFN 3.7/4.7-20 Amendment No. 122, 129, 139, 142
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l 3.7/4.7 BAEEE (C:nt'd)
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3.7.E/4.7.E Control Room Emergency Ventilation
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The control room emergency ventilation system is designed to filter the control room atmosphere for intake air and/or for recirculation daring. control room isolation conditions. The control room emergency ventilation system ic designed to automatically start upon control room isolation and to maintain the control room pressure to the design positive pressure so that all leakage should be out leakage. During cycle 6, CREVS has been declared inoperable only because it does not meet its design basis for essentially zero unfiltered inleakage. Reactor power operations and fuel movement are acceptable until just prior to startup for unit 2 cycle 7.
During cycle 6, CEEVS must be demonstrated to be functional by performing all applicable surveillance.
In h
the event that the applicable surveillance are not successfully performed, the actione required by the LCOs must be complied with.
High efficiency particulate absolute (HEPA) filters are installed prior to the charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential intake of radiciodine to the control room. The inplace test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99 percent removal of DOP particulate. The laboratory carbon sample test results should indicate a radioactive methyl iodide remeval efficiency of at least 90 percent for expected accident conditions.
If the efficiencies of the EEPA filters and charcon1 adsorbers are as specified, the resulting doses will be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power Plants, Appendix A to 10 CFR Part 50.
Operation of the fans significantly different from the design flow will chapse the removal efficiency of the HEPA filters and charcoal adsorbers.
f If the system is found to be inoperable, there is no immediate threat to the j
control room and reactor operation or refueling operation may continue for a limited period of time while repairs are being made.
If the system cannot be repaired within seven days, the reactor is shutdown and brought to Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or refueling operations are terminated.
Pressure drop across the combined HEPA filters and charcoal adsorbers of less than six inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressere drop should be determined at least once per operating cycle to show j
systar performance capability.
l The frequency of tests and sample analysis are necessary to show that the HEPA 1
filters and charcoal adsorbers can perform as evaluated. Tests of the charcoal adsorbers with halogenated hydrocarbon shall be performed in accordance with DSAEC Report-1082.
Iodine removal efficiency tests shall I
follow ASTM D3803.
The charcoal adsorber efficiency test procedures should l
allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtaining at least two samples. Each sample should be at least two inches in diameter and a length equal to the thickness of the bed.
If test results are unacceptable, all adsorbent in the system shall be replaced with an adsorbent qualified according to Table 1 of Regulatory Guide 1.52.
The replacement tray for the adsorber tray removed for BFN 3.7/4.7-49 Amendment No. 114, 142 Unit 3
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'3.7/4.7 DASES (Cont'd)'
.the test ahould meet'the same adsorbent quality. Tests of the HEPA filters
-*o with DOP aerosol shall be performed in accordance to ANSI N510-1975. Any HEPA
-filters found defective shall be replaced with filters qualified pursuant to Regulatory Position C.3.d of Reguletory Guide 1.52.
L1 Operation of the system for 10 houro every month will demcastrate operability of~the filters and adsorber system and remove excessive moisture built up on rbe adsorber.
if significant painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign materials, the same cests and sample analysis shall be performed as rect 31 red for operational use. The determination of significance shall be made by the operator on duty at the time of the incident.
Knowledgeable staff members should be consulted prior to making this determination.
Demonstration of the automatic initiation capability is necessary to assure system performance capability.
3.7.F/4.7.F Primary Contcintnent Purae Sysitm L
The Primary Containment Purge System is designed to provide air to purge and Eventilate the primary containment system. The exhaust from the primary containment is first processed by a filter train assembly and then channeled through the reactor building roof exhaust system. During power operation, the primary containment purge and ventilation system is isolated from the primary containment by two isolation valves in series.
HEPA (high efficiency particulate air) filters are installed before the charcoal adeorbers followed by a centrifugal fan. The in-place test results should indicate a leak tightness of the system housing of not less than 99-percent and a HEPA efficiency of at least 99-percent removal of DOP particulate. The laboratory carbon sample test results should indicate a radioactive methyl. iodide removal efficiency of at least 85-percent.
Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If the system is found to be inoperable, the Standby Gas Treatment System may be used to purge the containment.
Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 8.5 inches of water at the system design flow rate will indicate that the filters mad'adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop should be determined at least once per operating cycle to show system performance capability.
The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated. Tests of the charcoal adsorbers with halogenated hydrocarbon shall be performed in accordance with USAEC Report-1082.
Iodine removal efficiency tests shall follow ASTM D3803. The charcoal sdsorber efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, BFN 3.7/4.7-50 l Amendment No. 114, 142 l
Unit 3
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'3.7/4.7 BASES (Crnt'd)
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mixing the adsorbent thoroughly and obtaining at least two samples. Each sample should be at least two inches in diameter.and a length equal to the p*'
thickness of the_ bed.. _If test results are unacceptable, all adsorbent in the
-system shall be replaced with an adsorbent qualified according to Table 1 of Regulatory Guide 1.52.
The replacement tray for the adsorber tray removed for the test should meet the same adsorbent quality.. Tests of the HEPA filters with DOP aerosol shall be performed in accordance to ANSI N510-1975. Any HEPA filters found defective shall be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.
If significant painting, fire, or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign materials, the same tests and sample analysis shall be performed as required for operational use. The determination of significance shall be made by the operator on duty at the time of the incident.
Knowledgeable staff members should be consulted prior to making this determination.
d BFN 3.7/4.7-51 Amendment No. 142 Unit 3
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e BFN 3.7/4,7-51a Amendment No. 142 Unit 3
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