Text

Amends 215,231 & 188 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Responding to 930929 Application Re Testing Stds for Charcoal Used in Ventilation Sys at Plant
	ML18038B130
Person / Time
Site:	Browns Ferry
Issue date:	02/13/1995
From:	Hebdon F; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML18038B131	List: ML18038B130; ML18038B132;
References
	DPR-33-A-215, DPR-52-A-231, DPR-68-A-188 NUDOCS 9502160316
	Download: ML18038B130 (70)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 TENNESSEE VALL'EY AUTHORITY DOCK T O. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT 1

AMENDMENT TO FACILITY.OPERATING LICENSE Amendment No.

215 L'icense No. OPR-33 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated September 29',

1993, complies. with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

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

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

9502i603i6 9502i3 PDR ADOCK 05000259 P

PDR

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4 CO NME S

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LIMITING CONDITIONS FOR OPERATIO SURVEIL CE RE UIREME S

3.7.B.

Standb Gas Treatment S stem 4.7.B.

Standb Gas Treatment est erg

2. a.

The results of the in-place cold DOP and halogenated hydrocarbon tests at g 10%

design flow on HEPA filters and charcoal adsorber banks shall show g99%

DOP removal and g99% halogenated hydrocarbon removal when tested in accordance

.with ANSI N510-1975.

2 ~ a ~ The tests and sample analysis of Specification 3.7.B.2 shall be performed at least once per operating cycle or once every 18 months whichever occurs first for standby service or after 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 shall show g90% radioactive methyl iodide removal when tested in accordance with ASTM D3803.

b. Cold DOP testing shall be performed after each complete or partial replacement of the HEPA filter bank or after any structural maintenance on the system housing.

c.. System shall be shown to operate within +10% design flow.

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

BFN Unit 1 3.7/4.7-14 Anendment Ho. 215

4 CONT INME SYSTEMS LIMITI G CONDITIONS FOR OPERATION 3.7.E. Control Room Emer enc Ventilation SUR ILLANCE RE UIRE S

4.7.E Control Room Emer e c

1. Except as specified in Specification 3.7.E.3 below, both control room emergency pressurization systems shall be OPERABLE at all times when any reactor vessel contains irradiated fuel.

1. At least once every 18 months, the pressure drop across the combined HEPA filters and charcoal adsorber banks shall be demonstrated to be less than 6 inches of water at system design flow rate (g 10K).

2. a.

The results of the inplace cold DOP and halogenated hydrocarbon tests at design flows on HEPA filters and charcoal adsorber banks shall show g99X DOP removal and g99A halogenated hydrocarbon removal when tested in accordance with ANSI N510-1975.

2. a.

The tests and sample analysis of Specification 3.7.E.2 shall be performed at least once per operating cycle or once every 18 months, whichever occurs first for standby service or after 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 shall show g90/ radioactive methyl iodide removal at a velocity when tested in accordance with ASTM D3803.

b. Cold DOP testing shall.be performed after each complete or partial replacement of the HEPA filter bank or after any structural maintenance on the system housing.

BFN Unit 1 3.7/4.7-19 lnendnent No. 2l5

4 CONTAINME SYS EMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREME S

3.7.E. Control Room Emer enc Ventilation 4.7.E.

Control Room Emer enc Ventilation

c. System flow rate shall be shown to be within +10K design flow when tested in accordance with ANSI N510-1975.

c. Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the 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.

3. From and after the date that one of the control room emergency pressurization systems is made or found to be inoperable for any reason, REACTOR POWER OPERATIONS or refueling operations are permissible only. during the succeeding 7 days unless such circuit is sooner made OPERABLE.

3. At least once every 18 months, automatic initiation of the control room emergency pressurization system shall be demonstrated.

4. If these conditions cannot be met, reactor shutdown shall be initiated and all reactors shall be in COLD SHUTDOWN within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for REACTOR POWER OPERATIONS and refueling operations shall be terminated within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4. During the simulated automatic actuation test of this system (see Table 4.2.G), it shall be verified, that the necessary dampers operate as required.

BFN Unit 1 3.7/4.7-20 AMENOMBlTNO; y g 3

ii I

4 CONTAINMENT SYSTEMS ITI G COND TIONS FOR OPE TION SURVEIL CE RE UIREME S

3.7.F. Pr ma Conta nme t ur e

~Sseem 4.7.F.

r ma Contai est erg r e

1. The primary containment purge system shall be OPERABLE for PURGING, except as specified in 3.7.F.2.

a. The results of the in-place cold DOP and halogenated hydrocarbon tests at design flows on HEPA filters and charcoal adsorber banks shall show 2, 99% DOP removal and g 99% halogenated hydro-carbon removal when tested in accordance with ANSI N510-1975.

b. The results of laboratory carbon sample analysis shall show g 85% radioactive methyl iodide removal when tested in accordance with ASTM D3803.

c. System flow rate shall be shown to be within. + 10%

of design flow when tested in accordance with ANSI N510-1975.

2. If the provisions of 3.7.F.l.a, b,

and c cannot be met, the system shall be declared inoperable.

The provisions of Technical Specification 1.C.1 do not apply.

PURGING may con-tinue using the Standby Gas Treatment System.

3. a.

The 18-inch primary contain-ment isolation valves asso-ciated with PURGING may be open during the RUN mode for a 24-hour period after entering the RUN mode and/or for a 24-hour period prior to entering the SHUTDOWN mode.

The OPERABILITY of

1. At least once every 18

months, the pressure drop across the combined HEPA filters and charcoal adsorber banks shall be demonstrated to be less than 8.5 inches of water at system design flow rate (g 10%).

a. The tests and sample analysis of Specifica-tion 3.7.F.l shall be performed at least once per operating cycle or once every 18 months, whichever occurs first or after 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. Cold DOP testing shall be performed after each complete or partial replacement of the HEPA filter 'bank or after any structural mainte-nance on the system housing.

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

BFN Unit 1 3.7/4.7-21 rJMIldIMlt iso l5

0

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4

'CONTAINME SYS MS LI ITING CONDITIO S FOR OPERATION 3.7.F.

Prima Containment Pur e

~sstem 3.7.F.3 (Continued)

SURVEILLANCE RE U RE S

4.7.F.

Prima Containment Pur e

~Sstes these primary containment isolation valves is governed by Technical Speci ficati on 3.7.D.

b.

Pressure control of the containment is normally performed by VENTING through '2-inch primary containment isolation valves which route effluent to the Standby Gas Treatment System.

The OPERABILITY of these primary containment isolation valves is governed by Technical Specification 3.7.D.

3.7.G.

Containment Atmos here Dilution S stem CAD 4.7.G.

Containment Atmos here Dilution S stem CAD 1.

The Containment Atmosphere Dilution (CAD) System shall be OPERABLE with:

1.

S stem 0 erabilit a.

Two independent systems capable of supplying nitrogen to the drywell and torus.

a.

Cycle each solenoid operated air/nitrogen valve through at least one complete cycle of full travel in accordance with Specification 1.0.MM, and at least once per month verify that each manual valve in the flow path is open.

BFN Unit 1 b.

A minimum supply of 2,500 gallons of liquid nitrogen per system.

3.7/4.7-22 b.

Verify that the CAD System contains a

minimum supply of 2,500 gallons of liquid'itrogen twice per week.

AMENDMENTNo. y 8 g

41 0

I 11 L

3.7/4.7 BASES (Cont'd) 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 after two years of operation in the ru ed shipboard environment on the US Savannah

(~OR ~).

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.

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 D3803-89.

The charcoal adsorber efficiency test procedures should allow for the removal of one adsorber t a

, 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.

With doors closed and fan in operation, DOP aerosol shall be sprayed externally along the full linear periphery of each respective door to check the gasket seal.

Any detection of DOP in the fan exhaust shall be considered an unacceptable test result and the gaskets repaired and test repeated.

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 material, 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.

BFN Unit 1 3.7/4.7-33 Pwenor>ent Ho. 215

0 I

3.7/4.7

~8 SES (Cont'd)

Demonstration of the automatic initiation capability and OPERABILITY of filter cooling is,necessary to assure system performance capability. If one standby gas treatment system is inoperable,. the other systems must be tested daily.

This substantiates the availability of the 'OPERABLE systems and thus reactor operation and refueling operation can continue for a limited period of time.

3.7.D/4.7.D

'Prima Containment Isolation Valves The Browns Ferry Containment Leak Rate Program and,Procedures contains the list of all the Primary Containment Isolation Valves for which the Technical Specification requirements apply.

The procedures are subject to the change control provisions for plant procedures in the administrative controls section of the Technical Specifictions.

The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:

(l) stationing an operator, who is in constant communication with the control room, at the valve controls, (2) instructing this operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.

".Double isolation valves are provided on lines penetrating the primary containment and open to the free space of the containment.

Closure of one of the valves in each line would be sufficient to maintain the integrity of the pressure suppression system.

Automatic initiati'on is required to minimize the potential leakage paths from the containment in the event of a LOCA.

~Grou 1 Process lines are isolated by reactor vessel low water level (378")

in order to allow for removal of decay heat subsequent to a scram, yet isolate in time for proper operation of the core standby cooling systems.

The valves in Group 1, except the reactor water sample line valves, are also closed when process instrumentation detects excessive main steam line flow, low pressure, or main, steam space high temperature.

The reactor water sample line valves isolate only on reactor low water level at 378".

~Gros 2 Isolation valves are closed by reactor vessel'ow water level (538")

or high drywell pressure.

The Group 2 isolation signal also "isolates" the reactor building and starts the standby gas treatment system.

It is not desirable to actuate the Group 2 isolation signal by a transient or spurious signal.

~Gros

- Process lines are normally in use, and it is therefore not desirable to cause spurious isolation,due to high drywell pressure resulting from nonsafety related causes.

To protect the reactor from a possible pipe break BFN Unit 1 3.7/4.7-34 AMENDMEHTNO. 2 X 2

4i I

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3.7/4.7 BASES (Cont'd) 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 cl'ogged 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 D3803-89.

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.

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 determination.

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

3.7.F/4.7.F Prima Containment Pur e

S stem The Primary Containment Purge System is a non-safety related system that is normally isolated and normally not required to be functional during power operation.

The system is designed to provide the preferred exhaust path for purging the primary containment system; however,, the Standby Gas Treatment System can be used to perform the equivalent function.

BFN Unit 1 3.7/4.7-37 Ar..endnent A.o. 215

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3.7/4.7 BASES (Cont'd)

When. the Primary Containment Purge System is in operation, the exhaust from the primary containment is first processed by a filter train assembly and then channeled through the reactor building roof exhaust system.

The filter train assembly contains a HEPA (high efficiency particulate air) filter, charcoal adsorber, and centrifugal fan.

In-place tests are performed to ensure leak tightness of the filter train assembly of at least 99K and a HEPA efficiency of at least 99K removal of DOP particulates.

Laboratory tests are performed on adsorber carbon samples to ensure an 85'A removal efficiency for radioactive methyl iodide.

Tests are performed to ensure that the system is not operating at a flow significantly different from the design flow, which may affect the removal efficiency of the HEPA filters and charcoal adsorbers.

The pressure drop across the.combined HEPA filters and charcoal adsorbers is checked once per operating cycle to be less than 8.5 i'nches of water at the system design flow rate to ensure that the filters and adsorbers are not clogged with excessive amounts of foreign matter.

The above tests 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 D3803-89.

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.

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.

The primary containment isolation valves associated with the purging of the primary containment are FCV 64-17, 64-18, 64-19, 64-29, 64-30, 64-32, 64-33, and 76-24.

These valves may be open for a 24-hour period after entering the RUN mode and/or for a 24-hour. period prior to entering the SHUTDOWN mode.

Closure of these large diameter valves within the 24-hour period is needed to BFN Unit 1 3.7/4.7-38 Ps>endnent iso.

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT UNI AMENDMENT 0 FACILITY OPERA ING C

NS Amendment No. 231 License No.

DPR-52 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the 1'icensee) dated September 29,

1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

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

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulati'ons 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.

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:

3'.

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No.231, are hereby incorporated in the license.

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

This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.

FOR'HE NUCLEAR REGULATORY COMMISSION v.r<

Frederick J.

He on, Director Project Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

peb~a~ ]3

]995

'4l J

ATTACHMENT TO LICENSE AMENDMENT NO. 2 FACILITY OPERATING LICENSE NO.

DPR-52 DOCKET NO. 50-260 Revise the Appendix A Technical Specificat'ions by removing the pages identified below and inserting the enclosed pages.

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

Overleaf* pages are provided to maintain document completeness.

REMOYE 3.7/4.7-13 3.7/4.7-14 3.7'/4.7-19 3.7/4.7-20 3.7/4.7-'21 3.7/4.7-22 3.7/4.7-33 3.7/4.7-34 3 '/4.7-37 3.7/4.7-38

~INSE T 3.7/4.7-13*

3.7/4.7-14.

3.7/4.7-19 3.7/4.7-20*

3.7/4.7-21 3.7/4.7-22*

3.7/4.7-33 3.7/4.7-34*

3.7/4.7-37 3.7/4.7-38

II I

4 CO SYS S

LIMITING CO ITIONS FOR OPERATIO SURVEIL C

RE UI 3.7.B.

Standb Gas Treatment S stem 4.7.B.

Standb Gas reatme t S te Except as specified in Specification 3.7.B.3, belov, all three trains of the standby gas treatment system shall 'be OPERABLE. at all times when secondary containment integrity is required.

l.

At least once per year, the folloving conditions shall be demonstrated.

a.

Pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches of vater at a flov of 9000 cfm (g 10K).

b.

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

c.

Air distribution is uniform vithin 20K across HEPA filters and charcoal adsorbers.

BFN Unit 2 3.7/4.7-13 AMENOMENT NO. 1 7 7

0 I

4 CONTAINME S

S E

S'IMI'TING CONDITIONS FOR OPERATION SURVEILLA CE RE UIREME S

3.7.B. Standb Gas Treatment S stem 2.. a. The results of the in-place cold DOP and halogenated hydrocarbon tests at g 10K design flow on HEPA filters and charcoal adsorber banks shall show g99X DOP removal and g99/

halogenated'ydrocarbon removal when tested in accordance with ANSI N510-1975.

4.7.B.

2 ~ a ~

Standb Gas eatment

~Sstem The tests and sample analysis of Specification 3.7.B.2 shall be performed at

.least once per operating cycle or once every 18 months whichever occurs first for standby service or after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation and'ollowing signifi'cant painting, fire, or chemical release in any ventilation zone communicating, with the system.

b. The results of laboratory carbon sample analysis shall show g90X radioactive methyl iodide removal when tested in accordance with ASTM D3803.

b. Cold DOP testing shall be performed after each complete or partial replacement of the HEPA filter bank. or after any structural maintenance on the system housing.

c. System shall be shown to operate within +10/ design flow.

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

BFN "Unit 2 3.7/4.7-14 Pnendrsent Iio. 231

li

~ ~

4 CO AINMENT SYSTE S

LI ITING COND TIO S

FOR OPERAT ON SUR CE E

3.7.E. Control Room Emer enc Ventilation 4.7.E Control Room Emer e c

l. Except as specified in Specification 3.7.E.3 below, both control room emergency pressurization systems shall be OPERABLE at all times when any reactor vessel contains irradiated fuel.

1. At least once every 18 months, the pressure drop across the combined HEPA filters and charcoal adsorber banks shall be demonstrated to to be less than 6 inches of water at system design flow rate (g 10K).

2. a.

The results of the inplace cold DOP and halogenated hydrocarbon tests at design flows on HEPA filters and charcoal adsorber banks shall show g99X DOP removal and g99Ã halogenated hydrocarbon removal when tested in accordance with ANSI N510-1975.

2. a.

The tests and sample analysis of Specification 3.7.E.2 shall be performed at least once per operating cycle or once every 18 months, whichever occurs first for standby service or after 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 shall show y90/ radioactive methyl iodide removal at a velocity when tested in accordance with ASTM D3803.

b. Cold DOP testing shall be performed after each complete or partial replacement of the HEPA filter bank or after any structural maintenance on the system housing.

BFN Unit 2 3.7/4.7-19

~~endurant No. 231

~ Cv

4 CONTAINME SYSTEMS LI IT G CONDITIONS FOR OPE IO SURVEI CE 3.7.E. Control Room Emer enc 4.7.E.

Cont ol porn Emer e c

c. System flow rate shall be shown to be within glOX design flow when tested in accordance with ANSI N510-1975.

c. Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the 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.

3. From and after the date that one of the control room emergency pressurization systems is mad'e or found to be inoperable for any reason, REACTOR POWER OPERATIONS or refueling operations are permissible only during the succeeding 7 days unless such circuit is sooner made OPERABLE.

3. At least once every 18 months, automatic initiation of the control room emergency pressurization system shall be demonstrated.

e. If these conditions cannot be met, reactor shutdown shall be initi'ated and all reactors shall be in COLD SHUTDOWN within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for REACTOR POWER OPERATIONS and refueling operations shall be terminated within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4. During the simulated automatic actuation test of this system (see Table 4.2.G), it shall be verified that the necessary dampers operate as required.

BFN Unit 2 3.7/4. 7-20 AMENOMENTNo. 3 0 S

41 I

~ '

4 CONTAINME SYSTEMS LI G

CO ITIONS FOR OPERATION SURVE L CE E U REME S

3.7.F.

P ima Containment Pur e

~Ss tetg 4.7.F.

a Co ta nt

~Ss tery 1.

The primary containment purge system shall be OPERABLE for PURGING, except as specified in 3.7.F.2.

a.

The results of the in-place cold DOP and halogenated hydrocarbon tests at design flows on HEPA filters and charcoal adsorber banks shall show g 99% DOP removal and g 99% halogenated hydro-carbon removal when tested in accordance with ANSI N510-1975.

b.

The results of laboratory carbon sample analysis shall show g 85% radioactive methyl iodide removal when tested in accordance with ASTM D3803.

c.

System flow rate shall be shown to be within + 10%

of design flow when tested in accordance with ANSI N510-1975.

3 ~

a ~

The 18-inch primary contain-ment isolation valves asso-ciated with PURGING may be open during the RUN mode for a 24-hour period after entering the RUN mode and/or for a 24-hour period prior to entering the SHUTDOWN mode.

The OPERABILITY of

2. If the provisions of 3.7.F.l.a, b,

and c cannot be met, the system shall be declared inoperable.

The provisions of Technical Specification 1.C.l do not apply.

PURGING may con-tinue using the Standby Gas Treatment System.

l.

At least once every 18

months, the pressure drop across the combined HEPA filters and charcoal adsorber banks shall be demonstrated to be less than 8.5 inches of water at system design flow rate (g 10%).

a.

The tests and sample analysis of Specifica-tion 3.7.F.l shall be performed at least once per operating cycle or once every 18 months, whichever occurs first or after 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.

Cold DOP testing shall be performed after each complete or partial replacement of the HEPA filter bank or after

.any structural mainte-nance on the system housing.

c.

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

BFN Unit 2 3.7/4.7-21 Anendnent No. 231

Cl 0

4 CO AIHMEHT S STEMS LIMITIHG COHDITIO S FOR OPERATIOH SURVE L CE RE U 3.7.F.

Pri a

Cont nment Pur e

~Ss teil 4.7.F.

rima Conta ent Pu e

~Ss~e 3.7.F.3 (Continued) these primary containment isolation valves is governed by Technical Specification 3.7.D.

b.

Pressure control of the containment is normally performed by VEHTIHG through 2-inch primary containment isolation valves which route effluent to the Standby Gas Treatment System.

The OPERABILITY of these primary containment isolation valves is governed by Technical Specification 3.7.D.

3.7.G.

Containment Atmos here Dilution S stem CAD 4.7.G.

Containment Atmos here Dilution S stem CAD 1.

The Containment Atmosphere Dilution (CAD) System shall be OPERABLE with:

1.

S stem 0 erabi it a.

Two independent systems capable of supplying nitrogen to the drywell and torus.

a.

Cycle each solenoid operated air/nitrogen valve through at least one complete cycle of full travel in accordance with Specification 1.0.MM, and at least once per month verify that each manual valve in the flow path is open.

b.

A minimum supply of 2,500 gallons of liquid nitrogen per system.

b.

Verify that the CAD System contains a

minimum supply of 2,500 gallons of liquid nitrogen twice per week.

BFN Unit 2 3.7/4.7-22 AMENDMENTga, f9 7

0

'I I

3.7/4.7 BASES (Cont'd) 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 after two years of operation in the ru ed shipboard environment on the US Savannah (ORtg~~2 ).

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.

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 ADTN D3803-89.

The charcoal adsorher efficiency test procedures

-: should allow for the removal of one adsorber tra

, 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.

With doors closed. and fan in operation, DOP aerosol shall be sprayed externally along the full linear periphery of each respective door to check the gasket seal.

Any detection of DOP in the fan exhaust shall be considered an unacceptable test result and the gaskets repaired and test repeated.

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 material, 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.

BFN Unit 2 3.7/4.7-33 Anendnent Vo. 231

4l I

3.7/4.7 Q~S S (Cont'd)

Demonstration of the automatic initiation capability and OPERABILITY of filter cooling is necessary to assure system performance capability. If one standby gas treatment system is inoperable, the other systems must be tested daily.

This substantiates the availability of the OPERABLE systems and thus reactor operation and refueling operation can continue for a limited period of time.

3.7.D/4.7.D Prima Containment Isolation Va es The Browns Ferry Containment Leak Rate Program and Procedures contains the list of all the Primary Containment Isolation Valves for which the Technical Specification requirements apply.

The procedures are subject to the change control provisions for plant procedures in the administrative controls section of the Technical Specifications.

The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:

(1) stationing an operator, who is in constant communication with the control room, at the valve controls, (2) instructing this operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.

Double isolation valves are provided on lines penetrating the primary containment and open to the free space of the containment.

Closure of one of the valves in each line would be sufficient to maintain the integrity of the pressure suppression system.

Automatic initiation is required to minimize the potential leakage paths from the containment in the event of a LOCA.

~Gros Process lines are isolated by reactor vessel low water level (2 398") in order to allow for removal of decay heat subsequent to a scram, yet isolate in time for proper operation of the core standby cooling systems.

The valves in Group 1, except the reactor water sample line valves, are also closed when process instrumentation detects excessive main steam line flow, low pressure, or main steam space high temperature.

The reactor water sample line valves isolate only on reactor low water level at g 398".

~G".o."

2 Isolation valves are closed by reactor vessel low water level (538")

or high drywell pressure.

The Group 2 isolation signal also "isolates" the reactor building and starts the standby gas treatment system.

It is not desirable to actuate the Group 2 isolation signal by a transient or spurious signal.

~Gros

- Process lines are normally in use, and it is therefore not desirable to cause spurious isolation due to high drywell pressure resulting from nonsafety related causes.

To protect the reactor from a possible pipe break BFN Unit 2 3.7/4.7-34 AMENDMENTNO 2 2 7

Ik

3.7/4.7

~8 SES (Cont'd) 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 folios ASTE 03803-89.

The charcoal adsorher efficiency test procedures should allow.for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and'btaining at least two samples.