Text

Amends 143,139 & 114 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Authorizing Rev to Limiting Condition for Operation to Require Later Std for Iodine Testing & Analysis of Charcoal Filter Samples
	ML20149M029
Person / Time
Site:	Browns Ferry ; (DPR-33-A-143, DPR-52-A-139, DPR-68-A-114)
Issue date:	02/12/1988
From:	Zech G; NRC OFFICE OF SPECIAL PROJECTS
To:	;
Shared Package
ML20149M031	List: ML20149M029; ML20149M043;
References
	TAC-64709, TAC-64710, TAC-64711, NUDOCS 8802250258
	Download: ML20149M029 (39)
	v • d • e

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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o TENNESSEE VALLEY AUTHORITY DCCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDf TENT TO FACILITY OPERATING LICENSE \\

Amendment No.143 License No. OPR-33 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) cated February 11, 1987, 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; E.

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 atendment 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 issaance of this amendrent 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 aa nded 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 llPR-33 is hereby amended to read as follows:

(2) Technical Specifjcations The Technical Specifications contained in Appendices A and B, as j

revised through Amendment No. 143, are hereby incorporated in the license. The licensee shall operate the facility in s:cordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE hUCLEAR RE0llLATORY COMMISSION f.-

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Gary G. Zech, Assistant Director for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: February 12, 1988 I

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ATTACHMENT TO LICENSE APENDMENT N0.143 FACILITY OPERATING LICENSE NO. DPR-33 DCCKET NO. 50-259 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. Overleaf pages* are provided to maintain document completeness.

i REPOVE INSERT 3.7/4.7-13 3.7/4.7-13*

3.7/4.7-14 3.7/4.7-14 3.7/4.7-19 3.7/A.7-19 3.7/4.7-20*

3.7/4.7-20*

3.7/4.7-21 3.7/4.7-21 3.7/4.7-22*

3.7/4.7-22*

3.7/4.7-47 3.7/4.7-47 3.7/4.7-48 3.7/4.7-48 3.7/4.7-51 3.7/4.7-51 3.7/4.7-52 3.7/4.7-52 l

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1 l

4 3.7/4.7 CONTAIWMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B. Standby Gas Treatment System 4.7.B.

Standby Gas Treatment System

1. Except as specified in

1. At least once per year, Specification 3.7.B.3 below, the following conditions all three trains of the shall be demonstrated, standby. gas treatment system shall be OPERABLE at all a.

Pressure drop across times when secondary the combined HEPA containment integrity is filters and charcoal

required, adsorber banks is less than 6 inches of water at a flow of 9000 cfm (i 10%).

b.

The inlet heaters on each circuit are tested in accordance with ANSI NS10-1975, and are capable of an output of at least 40 kW.

c.

Air distribution is uniform within 20%

acrocs HEPA filters and charcoal adsorbers.

BFN 3.7/4.7-13 Unit 1 l

3.7/4.7 CONTAINMENT SYSTEMS LYMYTIMC CONDITIOMs FOR OPERATION SURVEILLAMCE REQUIREMENTS 3.7.B. Standby Cas Treatment System 4.7.B.

Standby Cas Treatment System

2. a. The results of the in-place

2. a. The tests and sample cold DOP and halogenated analysis of hydrocarbon tests at 1 10%

Specification 3.7.B.2 design flow on HEPA filters shall be performed at and charcoal adsorber banks least once per operating shall show 199% DOP removal cycle or once every and 199% halogenated 18 months whichever hydrocarbon removal when occurs first for standby tested in accordance with service or after every ANSI N510-1975.

720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation and 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 carbon sample analysis be performed after shall show 190% radioactive methyl iodide removal when each complete or partial replacement of the HEPA tested in accordance with ASTM D3803 (130*C, filter bank or after any 95% R.H.).

structural maintenance on the system housing.

c. System shall be shown to

c. Halogenated hydrocarbon operate within 110% design flow.

testing shall be performed after each complete or partial replacement of the charcoal adsorber bank or af ter any structural j

maintenance on the i

system housing.

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BFN 3.7/4.7 14 Amendment No.143 unit 1

3.7/4.7 CONTAIWMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emeraency Ventilation 4.7.E Control Room Emergency Ventilation

1. Except as specified in

1. At least once per operating Specification 3.7.E.3 below, cycle, not to exceed both control room emergency 18 months, the pressure drop pressurization systems across the combined HEPA shall be OPERABLE at all filters and charcoal adsorber tim /s when any reactor banks shall be demonstrated to vessel contains irradiated to be less than 6 inches of fuel.

water at system design flow rate (i 10%).

2. a. The results of the in-place

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 0.2 hours 0.00119 weeks 2.7396e-4 months of tested in accordance with system operation and ANSI N530-1975.

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 systert housing.

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 af ter any structural maintenance on the system housing.

d. Each circuit shall be operated at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months every month.-

BFN 3.7/4.7-19 endment No. 143 Unit 1

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3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emerzency 4.7.E.

Control Room Emergency Ventilation Ventilation

3. From and after the date that

3. At least once pcr operating one of-the control room cycle not to exceed 18 months, emergency pressurization automatic initiation of the sys(pms is made or found to control room emergency be INOPERABLE for any reason, pressurization system shall be reactor operation or refueling demonstrated-operations is 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 4.2.0), it shall be shall be in Cold Shutdown verified that the following within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for reactor dampers operate as indicated:

operations and refueling operations shall be terminated Close: FCO-150 B. D E, and F within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Open:

FCO-151, FCo-152 BF{

3.7/4.7 20

l 1.7/4.7 CONTAINMENT SYSTEMS l*

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS =

l 3.7.F. Primary Containment Purae 4.7.F.

Primary containment Purae t

Systes 3131 3

1. The primary containment shall

1. At least once per operating be normally vented and purged cycle, not to exceed 18 months.

through the primary containment the pressure drop across the purse system. The standby gas combined HEPA filters and trea'tment system may be used charcoal adsorber banks shall when primary containment purge be demonstrated to be less than system is INOPERABLE.

8.5 inches of water at system design flow rate Q 10%).

L

2. a. The results of the in-place

2. a. The tests and sample cold DOP and halogenated analysis of Specification hydrocarbon tests at design 3.7.F.2 shall be performed flows on HEPA filters and at least onco per operating charcoal adsorber banks shall cycle or once every show 199% DOP removal and 18 months, whichever occurs 199% halogenated hydrocarbon first or after 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months removal when tested in of system operation and accordance with following significant ANSI N510-1975.

painting, fire or chemical release in any ventilation s

zone communicating with the system.

b. The results of laboratory

b. Cold DOP testing shall be

[

carbon sample analysis performed after each shall show 185% radioactive complete or partial cethyl iodide removal when replacement of the HEPA l

tested in accordance with filter bank or after any ASTM D3803 structural maintenance on l

(130*C 95% R.H.).

the system housing.

c. System flow rate shall be

c. Halogenated hydrocarbon shown to be within !10% of testing shall be performed design flow when tested in after each complete or accordance with ANSI N510-partial replacement of the 1975.

charcoal adsorber bank or after any structural maintenance on the system I

housing.

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BFN 3,7/4.7-21 Amendnent No.143 j

Unit 1 i

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1

3.7/4.7 CONTAIWMENT SYST(HS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.G.

Containment Atmosphere 4.7.G.

Containment'&tmosphere Dilution System (CAD)

Dilution Sysitem (CAD) 1.

The Containment Atmosphere 1.

System p9erability Dilution (CAD) System shall i

be OPERABLE with:

a.

Two independent a.

At least

.t c e systems capable of por month cycle supplying nitrogen each soler3id l

l to the drywell and operated air /

l to ru s,

nitrogen valve through at least one complete cycle of full travel and verify that each l

manual valve in the flow path is open.

b.

A minimum supply of b.

Verify that the CAD 2,500 gallons of System contains a l

liquid nitrogen per minimum supply of system.

2,500 gallons of liquid nitrogen twice per week.

i 2.

The Containment Atmosphere 2.

h&ien FCV 84-8B is Dilution (CAD) System shall INOPERABLE, each i

be OPERABLE whenever the solenoid operated reactor mode switch is in air / nitrogen valve the "RUN" position.

of System B shall be cycled through at least one complete cycle of full travel and each manual valvs in the flow path of System B shall be verified open at least once per week.

3.

If one system is INOPERABLE, i

the reactor may remain in operation for a period of 30 days provided all active components in the other system are OPERABLE.

l BFN Unit 1 3.7/4,7-22 l

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3.7/4.7 BASES (Cznt'd)

The primary containment leak rate test frequency is based on maintaining adequate assurance that the leak rate remains within the specification. The leak rate test frequency is based on the NRC guide for developing leak rate testing and surveillance of reactor containment vessels.

Allowing the test intervals to be extended up to 10 months permits some flexibility needed to have the tests coincide with scheduled or unscheduled shutdown periods.

The penetration and air purge piping leakage test frequency, along with the containment leak rate tests, is adequate to allow detection of leakage trends. Whenever a bolted double-gasketed penetration is broken and remade, the space betw4en the gaskets is pressurized to determine that the seals are performing properly.

It is expected that the majority of the leakage from valves, penetrations and seals would be into the reactor building. However, it is possible that leakage into other parts of the facility could occur.

Such leakage paths that may affect significantly the consequences of accidents are to be minimized.

The primary containment is normally slightly pressurized during period of reactor operation. Nitrogen used for inerting could leak out of the containment but air could not leak in to increase oxygen concentration.

Once the containment is filled with nitrogen to the required concentration, determining the oxygen concentration twice a week serves as an added assurance that the oxygen concentration will not exceed 4 percent.

3.7.B/3.7.C Standby Cas Treatment System and Secondary Containmtal The secondary containment is designed to minimize any ground level release of radioactive materials which might result from a serious accident.

The reactor building provides secondary containment during reactor operation, when the drywell is sealed and in service; the reactor building provides primary containment when the reactor is shutdown and the drywell is open, as during refueling.

Because the secondary containment is an integral part of the complete containment system, secondary containment is required at all times that primary containment is required as well as during refueling.

The standby gas treatment system is designed to filter and exhaust the reactor building atmosphere to the stack during secondary containment isolation conditions.

All three standby gas treatment system fans are designed to automatically start upon containment isolation and to maintain the reactor building pressure to the design negative pressure so that all leakage should be in-leakage.

High efficiency particulate air (HEpA) filters art installed before and after the charcoal absorbers to minimize potential release of particulates to the 4

environment and to prevent clogging of the iodine absorbers.

The charcoal j

absorbers are installed to reduce the potential release of radioiodine to the environment.

The in place test results should indicate a system leak j

4 tightness of less than 1 percent bypass leakage for the charcoal absorbers and a HEpA efficiency of at least 99 percent removal of DOP particulates.

The laboratory carbon sample test results should indicate a radioactive methyl Lodide removal efficiency of at least 90 percent for crpected accident conditions.

If the efficiencies of the HEPA filters and charcoal absorbers are as specified, the resulting doses will be less than the 10 CFR 100 j

guidelines for the accidents analyzed.

Operation of the fans significantly different from the design flow will change the removal efficiency of the HEpA filters and charcoal absorbers.

{

DFN 3.7/4.7-47 Amendment No.143 Unit 1

3.7/4.7 BASES (C:nt'd)

Only two of the three standby gas treatment systems are needed to clean up the reactor building atmosphere upon containment isolation.

If one system is found to be inoperable, there is no immediate threat to the containment system performance and reactor operation or refueling operation may continue while repairs are being made.

If more than one train is inoperable, the plant is brought to a condition where the standby gas treatment system is not required.

4.7.B/4.7.C Standby Cas Treatment System and Secondary Containment Initiating reAptor building isolation and operation of the standby gas treatment system to maintain at least a 1/4 inch of water vacuum within the secondary containment provides an adequate test of the operation of the reactor building isolation valves, leak tightness of the reactor building and performance of the standby gas treatment system.

Functionally testing the initiating sensors and associated trip logie demonstrates the capability for automatic actuation.

Performing these tests prior to refueling will demonstrate secondary containment capability prior to the time the primary containment is opened for refueling.

Periodic testing gives sufficient confidence of reactor building integrity and standby gas treatment system performance capability.

The test frequencies are adequate to detect equipment deterioration prior to i

significant defects, but the tests are not frequent enough to load the filters, thus re' acing their reserve capacity too quickly.

That the testing frequency is adeqiate to detect deterioration was demonstrated by the tests which showed no loss of filter efficiency after two years of operation in the ruRRed shipboard environment on the US Savannah (ORNL 3726).

Pressure drop across the combined HEPA filters and charcoal adsorbers of less than j

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, j

Heater capability, pressure drop and air distribution 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 refrigerant shall be performed in accordance with USAEC Report DP-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 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.

All elements of the heater should be demonstrated to be functional and operable during the test of heater capacity.

Operation of each filter train for a minimum of 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months each month will prevent moisture buildup in the filters and adsorber system.

BFN 3.7/4.7-48 Amendment NO. 143 Unit 1

3.7/4.7 BASES (C:nt'd) 3.7.E/4.7.E Control Room Emeraency Ventilation 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.

High efficiency particulate absolute (HEPA) filters are installed before the charcoal adsor'bers to prevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential intake of radioiodine to the control room. The in-place 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 particulates. 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 Critorion 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 i

j 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 HEP /.

filters found defective shall be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.

mendment No.143 BFN 3.7/4.'-51 Unit 1 l

3.7/4.7 BASg3 (CCnt'd)

Operation of the system for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 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 staf f members should be consulted prior to naking this

' dete rmination.'

Demonstration of the automatic initiation capabl11ty is necessary to assure system performance capability.

3.7.F/4.7.F primary Containrent Purte System The primary containment purge system is designed to provide air to purge and ventilate the primary containment system. The exhaust from the primar/

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 containtent by two isolation valves in series.

HEPA (high efficiency particulate ele) 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 particulstes. The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 81,-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 tombined HEpA filters and charco&i 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 adrorbers 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 BFN Unit 1 3.7/4.7-52 Amendment No. 143

s p os co e

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c UNITED STATES

!

3 y, i

NUCLEAR REGULATORY COMMISSION e

WA5HING TON, D. C. 20655 t

l

s%.

TENNESSEE VALLEY AUTHORITY 00CKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment NO 139 License No. OPR-52 1.

The Nuclear Pegulatory Coninission (the Comission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated February 11, 1987, 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 it 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 authori:ed by this amenoment can be conducted without endancering 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 l

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 attachrent to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-52 is hereby amended to read as follows:

(2) Technical Specifications TFe Technical Specifications contained in Appendices A and B, as revised through Amenoment No.139, 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 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

-)

%'$ Ahck Gary G. Zech, Assistant Director for Projects TVA Projects Division Office of Special Projects i

Attachrent:

Changes to the Technical i

Srecifications Cate of Issuance: February 12. 1988 l

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ATTACHMENTTOLICENSEAMENDPENTNO.$b9 FACILITY OPERATING LICENSE NO. DPR-52 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 captioned amendment number and centain marginal lines indicating the area of change. Overleaf pages* are provided to maintain docurent completeness.

REMOVE INSERT 3.7/4.7-13 3.7/4.7-13*

3.7/4.7-14 3.7/4.7-14 3.7/4.7-19 3.7/4.7-19 3.7/4.7-20*

3.7/4.7-20*

3.7/4.7-21 3.7/4.7-21 3.7/4.7-22*

3.7/4.7-22*

3.7/4.7-47 3.7/4.7-47 3.7/4.7-48 3.7/4.7-48 3.7/4.7-51 3.7/4.7-51 3.7/A.7-52 3.7/4.7-52 0

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3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPER/ TION SURVEILLANCE REQUIREMENTS 3.7.B. Standby Gas Treatment System 4.7.B. Standby Gas Treatment System

1. 2xcept as specified in 1.

At least once per year, i

Specification 3.7.B.3 below, the following conditions all three trains of the shall be demonstrated.

l standby. gas treatment system shall be OPERABLE at all a.

Pressure drop across times when secondary the combined HEPA containment integrity is filters and charcoal required.

adsorber banks is less than 6 inches of water at a flow of 9000 cfm (i 10%).

b.

The inlet heaters on each circuit are tested in accordance with ANSI N510-1975, and are capable of an output of at least 40 kW.

c.

Air distribution is uniform within 20%

across HEPA filters and charcoal adsorbers.

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BFN 3.7/4.7 13 Unit 2 i

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1 3.7/4,7 CONTAINMENT SYSTEMS l

LIMITING CONDITIONS FOR OPERATION SURVEILfAMCE REOUInturaTs l

3.7.B. Standby Gar Treatment System 4.7.5.

Standby Gas Treatment System

2. a. The results of the in-place

2. a. The tests and sample l

cold DOP and halogenated analysis of hydrocarbon tests at 1 10%

Specification'3.7.B.2 design flow on HEPA filters shall be performed at and charcoal adsorber banks least once per operating shal'1 show 1 9% DOP removal cycle or once every 9

and 199% halogenated 18 months whichever hydrocarbon removal when occurs first for standby l

tested in accordance with service or af ter every ANSI N510-1975.

720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system I

operation and 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 L

carbon sample analysis be performed after shall show 190% radioactive each complete or partial methyl iodide removal when replacement of the HEPA tested in accordance with filter bank or after any j

ASTM D3803 (130'C, structural maintenance l

95% R.H.).

on the system housing.

c. System shall be shown to

c. Halogenated hydrocarbon operate within 110% design testing shall be

flow, performed after each complete or partial replacement of the charcoal adsorber bank or after any struttural maintenance on the system housing.

3,7/4,7 14 Amendment No. 139 BFN Unit 2

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 per operating Specification 3.7.E.3 below, cycle, not to exceed both control room emergency 18 months, the pressure drop pressurization systems across the combined HEPA shall be OPERABLE at all filters and charcoal adsorber time's when any reactor banks shall be demonstrated to vessel contains irradiated to be less than 6 inches of

fuel, water at system design flow rate (i 10%).

2. a. The results of the in-place

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 0.2 hours 0.00119 weeks 2.7396e-4 months 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.

c. System flow rate shall be

c. Halogenated hydrocarbon shown to be within r10%

testing shall be performed i

design flow when tested in after each complete or accordance with ANSI partial replacement of the N510-1975, charcoal adsorber bank or ef ter any structural maintenance on the system housing.

d. Each circuit shall be

[

operated at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months every month.

BFN 3.7/4.7 19 Amendment No. 139 I

unit 2 i

e

l 3.7/4.7 CONTAINMENT SYSTEMS LINITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emeraency 4.7.E.

Control Room Emeraency l

Ventilation Ventilation

3. From t.nd after the date that

3. At least once per operating one of the control room cycle not to exceed 18 months, emergency pressurization automatic initiation of the syst, ems is made or found to control room emergency be INOPERABLE for any reason, pressurization system shall be reactor operation or refueling demonstrated.

operations is permissible only during the succeeding 7 days unless such circuit is sooner I

made OPERABLE.

l

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.C), it shall be j

shall be in Cold Shutdown verified that the following within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for reactor dampers operate as indicated:

l operations and refueling j

operations shall be terminated Close: FCo-150 B. D, E and F l

within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Open:

FCO-151 l

FCO-152 i

l 1

l I

i BFN 3.7/4.7 20 Unit 2

3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

3. 7.F. Primary Containment Purae 4.7.F.

Primary Containment Purae System FYstem

1. The primary containment shall

1. At least once per operating be normally vented and purged cycle, not to exceed 18 months, through the primary containment the pressure drop across the purge system.

The standby gas combined HEPA filters and treatment system may be used charcoal adsorber banks shall when primary containment purge be demonstrated to be less than system is INOPERABLE.

8.5 inches of water at system design flow rate (i 10%).

2. a. Tha results of the in-place

2. a. The tests and sample cold Dop and halogenated analysis of Specification hydrocarbon tests at design 3.7.F.2 shall be performed flows on HEpA filters and at least once per oper4 ting I

charceal adsorber banks shall cycle or once every show 199% DOP removal and 18 months, whichever occurs 199% halogenated hydrocarbon first or after 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months removal when tested in of system operation and accordance with following significant ANSI N510-1975.

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 performed after each shall show 1 5% radioactive complete or partial 8

methyl iodide removal when replacement of the HEpA tested in accordance with filter bank or after any ASTM D3803 structural maintenance on (130'C 95% R.H.).

the system housing.

c. System flow rate shall be

c. Halogenated hydrocarbon shown to be within 110% of testing shall be performed design flow when tested in after each complete or accordance with ANSI N510-partial replacement of the i

1975.

charcoal adsorber bank or af ter any structural 1

maintenance on the system housing,.

I BFN 3.7/4.7-21 Amendmer.t No. 139 Unit 2 a

3.7/4.7 CONTAINMENT SYSTEMS l

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

'i 3.7.G. Containment Atmosphere 4.7 G.

Containment Atmosphere j

Dilution System (CAD)

Dilution System (CAD) 1.

The Containment Atmosphere 1.

System Ocorability Dilution (CAD) System shall be OPERABLE with:

s.'Two independent a.

At least once systees capable of cer month cycle supplying nitrogen each solenoid to the drywell and operated air /

torus,

nitrogen valve I

through at least one complete cycle of full travel and verify that each manual talve in the flow path is open.

b. A minimum supply of i

b.

Verify that the CAD 2,500 gallons of System contains a i

liquid nitrogen per system.

minimum supply of 2.500 gallons of liquid nitrogen twice per week.

2.

The Containment Atmosphere Dilution (CAD) System shall be OFtRABLE whenever the l

reactor mode switch is in the "RUN" position.

3.

If one system is IN0pERABLE.

the reactor may remain in operation for a period of 30 days provided all active components in the other system are OPERABLE.

h[ft2 3*P#4*I'22

3.7/4.P BASES (Cont'd)

The primary containment leak rate test frequency is based on maintaining adequate assurance that the leak rate remains within the specification. The leak rate test frequency is based on the NRC guide for developing leak rate testing and surveillance of reactor containment vessels. Allowing the test intervals to be extended up to 10 months permits some flexibility needed to have the tests coincide with scheduled or unscheduled shutdown periods.

The penetration and air purge piping leakage test frequency, along with the

{

containment leak rate tests, is adequate to allow detection of leakage trends.

Whenever a bo(ted double-gasketed penetration is broken and remade, the space between the gaskets is pressurized to determine that the seals are performing properly.

It is expected that the majority of the leakage from valves, i

penetrations and seals would be into the reactor building.

However, it is possible that leakage into other parts of the facility could occur.

Such leakage paths that may affect significantly the consequences of accidents are to be minimized.

l The primary containment is nornally slightly pressurized during period of reactor e

operation. Nitrogen used for inerting could leak out of the containment but air could not leak in to increase oxygen concentration. Once the containment is i

filled with nitrogen to the required concentration, determining the oxygen concentration twice a week serves as an added assurance that the oxygen concentration will not exceed 4 percent, 3.7.B/3.7.C Standby Gas Treatment System and Secondary Containment The secondary containment is designed to minimize any ground level release of radioactive materials which might result from a serious accident.

The reactor building provides secondary containment during reactor operation, when the drywell i

is sealed and in service; the reactor building provides primary containment when the reactor is shutdown and the drywell is open, as during refueling.

Becauce the secondary containment is an integral part of the complete containment system, secondary containment is required at all times that primary containment is required as well as during refueling.

i l

The standby gas treatment system is designed to filter and exhaust the reactor building atmosphere to the stack during secondary containment isolation conditions.

All three standby gas treatment system fans are designed to automatically start upon containment isolation and to maintain the reactor building pressure to the design negative pressure so that all leakage should be in-leakage.

High efficiency particulate air (HEPA) filters are installed before and after the charcoal absorbers to minimize potential release of particulates to the

[

environment and to prevent clogging of the iodine absorbers.

The charcoal absorbers are installed to reduce the potential release of radioiodine to the environment.

The in-place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal absorbers and a HEpA l

efficiency of at least 99 percent removal of DOP particulates.

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 absorbers are as specified, the resulting doses will be less than the 10 CFR 100 guidelines for the accidents analyzed.

Operation of the fans significantly different from the design flow will 4

change the removal efficiency of the NEPA filters and charcoal absorbers, s

BFW 3.7/4.7 4; Amendment No. 139 Unit 2 i

I J

. yn.

3.7/4.7 BASES (C:nt'd)

Only two of the three standby gas treatment systems are needed to clean up the reactor building atmosphere upon containment isolation.

If one system is found to be inoperable, there is no immediate threat to the containment system performance and reactor operation or refueling operation may continue while repairs'are being made.

If more than one train is inoperable, the plant is brought to a condition where the standby gas treatment system is not required.

4.7.B/4.7.C Standby Cas_Tyeatment System. gad Secondary Containment Initiating reactor bhilding' isolation and operation of the standby gas treatment system to maintain ut least a 1/4 inch of water' vxcuum within the secondary containment provides an adequate test of the oper3 tion of<the reactor building isolation valves, leak tightnews of the reactor buildit.3 and performance of the standby gas treatment system. Functionally testing the initiating sonnors and associated trip logic demonstrates the capabill3y for automatic actuation.

Performing these tests prior to refueling will demonstrate secondary concainment capability prior to the time the primary containment is opened for refueling.

Periodic testing gives sufficient confidence of reactor building integrity and standby gas treatment system performance capability.

The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are not frequent enough to load the filters, thus reducing their reserve capacity too quickly.

That the testing frequency is adequate to detect deterioration was demonstrated by the tests which showed no loss of filter efficiency af ter two years of operation in the rummed shipboard environment on the US Savannah (ORNL~372{).

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 i

excessive amounts of foreign matter.

Heater capability. pressure drop and air I

distribution should be determined at least once per operating cycle to show systea 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 refrigerant shall be performed in accordance with USAEC Report DP-1082.

Iodine removal efficiency tests shall follow ESIM D3803.

The charcoal adsorber efficiency test procedures should allow for the removal of one adeorber tray,~ emptying of one bed from the tray,,aixing the adsorbent thoroughly and obtaining at least two samples.

Each sample should be at least two inches in diameter and a length equal to thy thickness of the bed.

If test results are unacceptable, all adsorbent in the. system shall te replaced with an adsorbent qualified according to Table 1 of 'Aegulatory Guide 1.52.

The replacement tray for the adsorber tray removed for the test shonld 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.

All elements of the heater should be demonstrated to be functional and operable during the test of heater capacity.

Operation of each filter train for a minimum of 10 hourt each month will prevent moistut% buildup in the filters and adsorber system.

BFN 3.7/4.7-40 Amendment No. 139 Unit 2 h

3.7/4.7 BASES (Cont'd) i L

3.7.E/4.7.E Control Room 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 room isolation conditions.

The control room emergency ventilation system is l

designed to automacically 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.

High efficiency particulate absolute (HEPA) filters are installed before the charcoal adsor'bers to provont clogging of the iodine adsorbers. The charcoal j

adsorbers are installed to reduce the potential intake of radioiodine to the control room.

The in-place 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 particulates.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 ate not clogged by excessive amounts of foreign matter.

Pressure drop should be determined at least once per operating cycle to ehow system performance capability.

The frequency of tests and sample analysis &re 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 adsorbant 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 Pocition C.3.d of Regulatory Guide 1.52.

BFN 3.7/4.7-51 Amendment No. 139 Unit 2

y --

,3 i

/

7 3.7/4.7 RASES (Cont'd)

Operation of the system for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months every/mont'h will demonstrate operability l

of the filter the adsorber.3 _a,nd adsorber system and remove excecsive moisture built up on i

If significant pa!Rting, fire or chemical release occurs such that the HEPA.

filter or charcoall adsorber could become contaminated from The fumes, chemicals or foreisn mater:als, t'he same tests and sample analysis shall be performed as requirrQ for oper>tional use.. The determination of significance shall be made by the operator on duty aD the time of the ine!Jent.

Knowledgeable staff taaebers should be consulted prior to making this i

determination.

Demonstertion of the automatic initiation capability is necessary to assure system performance capability.

l 3.7.F/4.7.F Primary Containment Purge System I

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 *ystem.

During power operation, the primary containment purge and ventilatlon system is isolated from the primary i

containment by two isolation valves in series, i

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

)

particulates.

The laboratory carbon sample test results should indicate a i

radioactive methyl iodide removal efficiency of at least 85-percent.

Operation of the fans significantly different from the design flow will change the removal ef ficiency of ths 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 S.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 an6 Lysis 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 mixing the adsorbent thoroughly and obtaining at least two sample should be at least two inches in diameter and a length equal to the Each thickness of the bed.

If test rmaults 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 BFN Unit ?.

3.7/4.7-52 Amendment No.139 m_,

[

'g UNITED STATES

!

3,,

NUCLEAR REGULATORY COMM!SSION n

{

WASHINGTON, D. C. 20555

\\,...../

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.114 License No. OPR-68 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated february 11, 1987, complies with the standards and recuirements of the Atomic Energy Act of 1054, as amended (the Act),

ano 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 ruler and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted withoet endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; j

i D.

The issuance of this amendment will not be inimical to the comon i

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 rec.uirements have been satisfied.

l l

i 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachmen* to this license amendment and paragraph 2.C.(2) of Facility Operating License flo. GPR-66 is hereby amended to read as follows:

i (2) Techtical Specifications The Technical Specificatier.s contained in Appendiccs A and B, as revised through Amendment No. 114,<are hereby incorporated in the license. The licensee shall operate the tacility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall I

be implemented within 60 days from the date of issuance.

l FOR THE NUCLEAR REGULATOP.Y COMMISSION

,./

3 c: 3 M-jc(s.

Gary G. Zech, Assistant Director for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to the Technical Specifications j

Cate of Issuance: February 12, 1988 t

i l

l l

ATTACFFENT TO LICENSE AMENDHENT NO.114 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET FO. 50-295 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. Overleaf pages* are provided to maintain document completeness.

REMOVE INSERT 3.7/4.7-13 3.7/4.7-13*

3.7/4.7-14 3.7/4.7-14 3.7/4.7-19 3.7/4.7-19 3.7/4.7-20*

3.7/4.7-20*

3.7/4.7-21 3.7/4.7-21 3.7/4.7-22*

3.7/4.7-22*

3.7/4.7-45 3.7/4.7-45 3.7/4.7-46 3.7/4.7-46 3.7/4.7-49 3.7/4.7-49 3.7/4.7-50 3.7/4.7-50 i

r I

i i

l I

I i

i l

i

r 3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B. Standby Gas Treatment System 4.7.B Standby Cas Treatment System

1. Except as specified in

1. At least once per year, Specification 3.7.B.3 below.

.the following conditions all-three trains of the shall be demonstrated, standby gas treatment system shall be OPERABLE at all a.

Pressure drop across times when secondary the combined HEPA containment integrity is filters and~ charcoal

required, adsorber 'oanks is less than 6 inches of water at a flow of 9000 cfm (i 10%).

b.

The inlet heaters on each circuit are tested in accordance with ANSI N510-1975, and are capable of an output of at least 40 kW.

c.

Air distribution is uniform within 20%

across HEPA filters and charcoal adsorbers.

t i

l BFN 3.7/4.7-13 Unit 3 l

l

3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B. Standby Gas Treatment System 4.7.B.

Standby Gas T e_a h t_ System t

2. a. The results of the in-place cold DOP and halogenated

2. a. The tests and sample hydrocarbon tests at analysis of 1 10%

design flow on HEPA filters Specification 3.7.B.2 and charcoal adsorber banks shall be performed at shall show 199% DOP removal least once per operating and 199% halogenated cycle or once every hydrocarbon removal when 18 months whichever tested in accordance with occurs first for standby ANSI N510-1975.

service or af ter every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation and following significant painting, fire or chemical release in any ventilation zone communicating with the system.

b. The results of laboratory carbon sample analysis

b. Cold DOP testing shall shall show 1907. radioactive be performed after methyl iodide removal when each complete or partial tested in accordance with replacement of the HEPA ASTM D3803 (130*C, filter bank or after any 95% R.H.).

structural maintenance on the system housing,

c. System shall be shown to operate within 1 0% design

c. Halogenated hydrocarbon 1

flow.

testing shall be performed after each complete or partial replacement of the charcoal adsorber bank or after any structural maintenance on the system housing.

1 BFN Unit 3 3.7/4.7_14 klendment fl0. 114 l

l l

r t

1 3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 1

3.7.E. Control Room EmerRency Ventilation 4.7.E Control Room Emergency Ventilation

1. Except as specified in

1. At least once per operating Specification 3.7.E.3 below, cycle, not to exceed both control room emergency 18 months, the pressure drop pressurization systems across the combined HEPA shall be OPERABLE at all filters and charcoal adsorber times when any reactor banks shall be demonstrated to vessel contains irradiated to be'less than 6 inches of

fuel, water at system design flow rate (i 10%).

2. a. The results of the in-place

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 9

1 9% halogensted first for standby service hydrocarbon removal when or after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of tested in accordance with system operation and ANSI N510-1975.

following significant painting, fire, or chemical release in any ventilation zone conpunicating with the system.

b. The results of laboratory

b. Cold DOP testing shall be carbon sample analysis shall performed af ter 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.

c. System flow rate shall be

c. Halogenated hydrocarbon shown to be within 10%

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 0.00278 hours 1.653439e-5 weeks 3.805e-6 months every month.

BFN 3.7/4.7-19 Unit 3 l

3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR_0PERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room EmerRency 4.7.E.

Control Room EmerRency Ventilation Ventilation

3. From and after the date that one of the control room

?. At least once per operating emergency pressurization cycle not to exceed 18 months, systems is made or found to automatic initiation of the be INOPERABLE for any reason.

control room emergency reactor operation or refuelists pressurization system shall be demonstrated.

operations is permissible only during the succeeding 7 days unless such circuit is sooner made OPERABLE.

4 If these conditions cannot be 4.

met, reactor shutdown shall be During the simulated automatic initiated and all reactors actuation test of this system shall be in Cold Shutdown (see Table 4.2.G), it shall be within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for reactor verified that the following operations and refueling dampers operate as indicated:

operations shall be terminated within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Closo: F00-150 B, D, E, and F Open:

FCO-151, FCO-152 l

BFN Unit 3 3,7/4,7 20

s 3.7/4,7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3. 7.F. Primary Containment Purne 4.7 F, Primary Containment Purne System System

1. The primary containment shall

1. At least once per operating be normally vented and purged cycle, not to exceed 18 months, through the primary containment the prescure drep across the purge system. The standby gas combined HEPA filters and treatment system may be used charcoal adsorber banks shall when primary containment purge be demonstrated to be less than system is INOPERABLE.

8.5 inches of water at system design flow rate (i 10%).

2. a. The results of the in-place

2. a. The tests tnd sample cold DOP and halogenated analysis of Specification hydrocarbon tests at design 3.7 F.2 shall be performed flows on HEPA filters and at least once per operating charcoal adsorber banks shall cycle or once every show 199% DOP removal and 18 months, whichever occurs 1 9% halogenated hydrocarbon first or af ter 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 9

removal when tested in of system operation and accordance with following significant ANSI N510-1975.

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 performed after each shall show 185% radioactive complete or partial methyl iodide removal when replacement of the HEPA tested in accordance with filter bank or after any ASTM 23803 structural maintenance on (130*C 95% R.H.),

the system housing,

c. System flow rate shall be

c. Halogenated hydrocarbon shown to be within 10% of testing shall be performed design flow when tested in after each complete or accordance with ANSI N510-partial replacement of the 1975.

charcoal adsorber bank or af ter any structural maintenance on the system housing.

BFN 3.7/4,7-21 Amendment NO. 114 Unit 3 1

3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.G.

Containment Atmosphere 4.7.G.

Containment Atmosphere Dilution System (CAD)

Dilution System (CAD) 1.

The Containment Atmosphere 1.

System operability Dilution (CAD) System shall be OPERABLE with:

'a.

Two independent a.

At least once per systems capable of month cycle each supplying nitrogen solenoid-operated to the drywell and aie/ nitrogen valve to ru s,

through at least one complete cycle of full travel and verify that each manual valve in the flow path is open.

b.

A minimum supply of b.

Verify that the CAD 2,500 gallons of System contains a liquid nitrogen per minimum supply of system.

2,500 gallons of liquid nitrogen twice por week.

2.

The Containment Atmosphere Dilution (CAD) System shall be OPERABLE whenever the reactor mode switch is in the "RUN" position.

3.

If one system is INOPERABLE, the reactor may remain in

{

operation for a period of 30 days provided all active components in the other

{

system are OPERABLE.

i 4.

If Specifications 3.7.G.1 and 3.7.G.2, or 3.7.G.3 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown condition 9

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l 5.

Primary containment pressure shall be limited to a maximum of 30 psis during repressurization following a loss of coolant accident.

BFN 3.7/4.7 22 Unit 3

3.7/4.7 BASES (Cont'd)

The primary containment leak rate test frequency is based on maintaining adequate assurance that the leak rate remains within the specification.

The leak rate test frequency is based on the NRC guide for developing loak rate testing and surveillance of reactor containment vessels. Allowing the test intervals to be extended up to 10 months permits some flexibility needed to have the tests coincide with scheduled or unscheduled shutdown periods.

The penetration and air purge piping leakage test frequency, along with the containment leak rate tests, is adequate to allow detection of leakage trends. Wheneyer a bolted double-gasketed penetration is broken and remade, the space between the gaskets is pressurized to determine that the seals are performing properly.

It is expected that the majority of the l9akage from valves, penetrations and seals would be into the reactor building. However, it is possible that leakage into other parts of the facility could occur.

Such leakage paths that may affect significantly the consequences of accidents are to be minimized.

The primary containment is normally slightly pressurized during period of reactor operation. Nitrogen used for inerting could leak ceh of the containment but air could not leak in to increase oxygen concentration.

Once the containment is filled with nitrogen to the required concentration, determining the oxygen concentration twice a week serves as an added assurance that the oxygen concentration will not exceed 4 percent.

3.7.B/3.7.C Standby Gas Treatment System and Secondary Containment The secondary containment is designed to minimize any gesund level release of radioactive materials which might result from a serious accident.

The reactor building provides secondary containment during reactor operation, when the drywell is sealed and in service; the reactor building provides primary containment when the reactor is shutdown and the dryweil is open, as during refueling.

Because the secondary containment is an integral part of the complete containment system, secondary containment it required at all times that primary containment is required as well as during enfueling.

The standby gas treatment system is designed to filter and exhaust the reactor building atmosphere to the stack during secondary containment isolation conditions. All three standby gas treatment system fans are designed to automatically start upon containment isolation and to maintain the reactor building pre;sure to the design negative pressure so that all leakage should I

be in-leakage.

High efficiency particulate air (HEPA) filters are installed before and after the charcoal absorbers to minimize potential release of particulates to the environmect and to prevent clogging of che iodine absorbers.

The charcoal absorbers are installed to reduce the potential release of radioiodine to the environment.

The in-place test resuits should indicate a system leak tightness of less than 1 percent by9 ass leakage for the charcoal absorbers and a HEPA efficiency of at least 99 porcent removal of DOP particulates. The laboratory carbon sample test results should indicate a radioactive methyl iodido removal ef ficiency of at least 90 percent for expected accident conditions.

If the efficiencies of the HEPA filters and charcoal absorbers are as specified, the resulting doses will be less than the 10 CFR 100 guidelines for the accidents analyzed.

Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA 1

filters and charcoal absorbers.

BFN 3.7/4.7-45 Amendment No. 114 Unit 3 t

3.7/4.7 BASES (Cont'd)

Only two of the three standby gas treatment systems are needed to clean up the reactor building atmosphere upon containment isolation.

If one system is found to be inoperable, there is no immcdiate threat to the containment system performance and reactor operation or refueling operation may continue while repairs are being made. If more than one train is inoperable, the plant is brought to a condition where the standby gas treatment system is not required.

4.7.B/4.7.C Standby Gas Treatmsnt System and Secondary Containment Initiating rea,ctor building isolation and operation of the standby gas treatment system to maintain at least a 1/4 inch of water vacuum within the secondary containment provides an adequate test of the operation of the reactor building isolation valves, leak tightness of the reactor building and performance of the standby gas treatment system.

Functione.lly testing the initiating sensors and associated trip logic demor.strates the capability for automatic actuation.

Performing these tests prior to refueling will demonstrate secondary containment capability prior to the time the primary containment is opened for refueling.

Periodic testing gives sufficient confidence of reactor building integrity and standby gas treatment system performance capability.

The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are not frequent enough to load the filters, thus reducing their reserve capacity too quickly.

That the testing frequency is adequate to detect deterioration was demonstrated by the tests which showed no loss of filter efficiency af ter two years of operation in the rugted shipboard environment on the US Savannah (ORNL 3726).

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 cloggad by excessive amounts of foreign matter.

Heater capability, pressure dcop and air distribution 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 refrigerant shall be performed in accordance with USAEC Report DP-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 tan system shall be replaced with an adsorbent qualified according to Table 1 of Restlatory Guide 1.52.

The replacement tray for the adsorber tray removed for the test should meet the same cdsorbent 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.

All elements of the heater should be demonstrated to be functional and operable during the test of heater capacity.

Operation of each filter train for a minimum of 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months each month will prevent moisture buildup in the filters and adsorber system.

BFN Unit 3 3.7/4.7-46 Amendment NO. 114

3.7/4.7 BASES (Cont'd) 3.7.E/4.7.E Control Room 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 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.

High efficiency particulate absolute (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers.

The charcoal adsorbers are installed to reduce the potential intake of radiolodine to the control room.

The in-place 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 particulates.

The laboratory carbon sample test results chould indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident conditions.

2f 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 repalca are being made.

If the system cannot be repaired within seven days, the recetor is shutdown and brought to Cold Shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 boa 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.

BFN 3.7/4.7-49 Amendment No, 114 Unit 3

3.7/4.7 BASES (Cont'd)

Operation of the system for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 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 de te rmination. '

Demonstration of the automatic initiation capability is necessary to assure system performance capability.

3.7.F/4.7.F Primary Containment Purze 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 particulates.

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 ta be inoperable, the Standby Gas Treatment System may be used to purge the cot.:ainment.

Pressure drop acrots the combined HEPA filters and charcoal adsorbers of less than 8.5 inches of =vtor at the system design flow rate will indicate that the filters and adsorters are not clogged by excessive amounts of foreign matter.

Pressure drop should be determined at least once per operating cycle to show system performance capt.r.ility.

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 mixing the adsorbent thoroughly and obtaining at least tw sample should be at least two inches in diameter and a length equal to the Each thickness of the bed.

!f 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 t3 3.7/4.7-50 Amendment No. 114

v t e Letter Sequence Other
TAC:64709, (Approved, Closed) TAC:64710, (Approved, Closed) TAC:64711, (Approved, Closed)
Initiation Request Acceptance... Administration Questions Answers Results Approval Other: ML18031B207, ML20149M029
MONTHYEAR1987-02-11 [Table View]

Person / Time
ML20149M029
Site:	Browns Ferry (DPR-33-A-143, DPR-52-A-139, DPR-68-A-114)
Issue date:	02/12/1988
From:	Zech G NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20149M031	List: ML20149M029 ML20149M043
References
TAC-64709, TAC-64710, TAC-64711, NUDOCS 8802250258
Download: ML20149M029 (39)
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ML20149M029

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