ML18283B725

Letter Submitting Amendments No. 18 and 15 to Facility Licenses No. DPR-033 and DPR-52 for Browns Ferry Nuclear Plant, Units No. 1 and 2. Amendments Include Changes No. 16 to TS in Response to 11/07/1975 Request

ML18283B725
Person / Time
Site:	Browns Ferry
Issue date:	12/19/1975
From:	Purple R Office of Nuclear Reactor Regulation
To:	Watson J Tennessee Valley Authority
References
Download: ML18283B725 (58)

Text

Docket Nos.

50-259 and 50-260 L1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.

C.

20056 December 19, 1975

'IR~

l4(p Tennessee Valley Authority ATTN; hlr. James E.

Watson hlanager of Power 818 Power Building Chattanooga, Tennessee 37201 Gentlemen:

The CDIIImission has issued the enclosed Amendmonts No.

18 and 15 to Facility Licenses No.

DPR-33 and DPR-52 for the Browns Ferry Nuclear Plant, Units 1 and 2.

These amendments include Changes No.

16 to the Tcchnical Specifications and are in response to your request of November 7,

1975.

Thc amcndmcnts revise thc Interim Tcclu>ical Specifications to remove the requirements for certain cooling and ventilation cquipmcnt that are no longer needed.

The cooling requirements aro reduced since thc decay heat of thc fuel has been greatly reduced with the clapscd time since reactor operation.

The ventilation requircIrients are reduced for thc same reason and because t)Ic need to control air movement to prevent thc spread of. chloride contanIination no longer exists with thc burned cables and soot having been rcIIIovcd from the plant.

This change is rcquircd in order to Allo>> the installation of thc per-manent control and power 'supplies to this equipment and in the case of the Standby Gas Treatment System to allow the connection of the third train of thc system to accommodate the requirements of Unit 3.

This equipmont and their associated systems also are involved in the retest program that is required prior to return to operation.

You have informed us that this work must be started at this time so as not to adv'crsely impact your restoration schedule.

The Interim Technical Specifications as

amcndcd, continuo to ensure that the two units will remain in a safe and stable posture during the period of the remaining restoration work with thc fuel stored in the fuel storage pools.

Copies of thc related Safety Evaluation and the Federal Register Notice are also enclosed.

Sincerely, Operating Reactors Branch tl Division of Reactor Licensing Fnclosures:

See next page 1

PL,OWOO<lb t1l

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'7.'4I r

0 December 19, 1975

Enclosures:

1.

Amendment No.

18 to DPR-33 2.

Amendment No.

15 to DPR-52 3.

Safety Evaluation 4.

Federal Register Notice cc w/enclosures:

H. S. Sangcr General Counsel 629 Ncw Sprankle Building Knoxville, Tennessee 37919 Mr, ii'illiam E. Garner Route 4, Box 354 Scottsboro, Alabama 35768 Mr. 1'homas Lec Hammons Chairm ~n, Limestone County Board of Rcvcnuc

Athens, Alabama 35611 Athens Public Library South and Forrcst

Athens, Alabama 35611 cc w/enclosures 5 incoming:

Mr. Jim Payne, Director Office of Urb;m F< Federal Affairs 1312 Andrew Jackson Bui.lding Nashville,,Tennesscc

. 37219

~ UNITED STATI.-:S NUCLEAR REGULATORY COMMISSlON WASHINGTON, D.

C.

70555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROtPilS FERRY NUCLEAR PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

18 License No.

DPR-33 1,

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

A.

Thc application for amendment by Tennessee Valley Authority (the licensee) dated November 7,

1975, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and tile Commission's rules and regula-tions sct forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangoring the health and safety of: the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; and 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, 2.

Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to tlIis license amend-ment and Paragraph 2.C.(2) of Facility License No.

DPR-33 is hereby amended to read as follows:

e

"2.C. (2)

Technical S ec ifications II The Technica1 Specifications contained in Appendices A

and 8, as revised, are hereby incorporated in the license.

Tho licensee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Chango No. 16."

3.

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

FOR THE NUCLEAR REGULATORY CO)4/ISSION

(

(

Robert A. Purple, Chic%

Operating Reactors Branch I'I Di.vision of Reactor Licensing

Attachment:

Change No.

16 to the Tcchnical Specifications Date of Issuance; December 19, 1975

~

~

NUCLEAR REGULATORY COMMISSION WASHINGTON, O.

C.

20555 TENNESSL'E VALLEY AUTIIORITY DOCKET NO.

SO-260 BRONNS FERRY NUCLEAR PLANT UNIT 2 PJ1ENDMENT TO FACILITY OPERA'1'ING LICENSE Amendment No.

15 License No.

DPR-52 l.

The 'Nuclear Regulatory Commission (the Commission) has found that:

A.

The application For amendment by Tonnosseo Valley Authorit>

(tho licensee) dated November 7,

1975, complies with the standards and requirements of tho Atomic Energy Act of 1951, as amended (the Act), and tho Commission's rules and regula-tions 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.

Thoro is reasonable assurance'i) that tho activities authorized by this amendment can bc conducted without endangering -the health and sa"cty of. tho public, and (ii) that such activities will be conducted in compliance with the Commission's regula-tions; and D.

The issuance of thi.s amendment will not be inimical to thc common defense and security or to the health and safety of the public.

2.

Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amend-ment and Paragraph 2.C.(2) of Facility License No.

DPR-S2 is hereby amended to read as follows:

e

2-

"2.C. (2)

Technical S ecifications The Technical Specifications contained in Appendices A

and B, as revised, aro hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No.

16."

3.

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

FOR TllE NUCLEAR REGULATORY COMMISSION

~ C~

C Robert A. Purple, Chi f Operating Reactors Branch Pl Division of Reactor Licensi.ng

Attachment:

Change No.

16 to the Tcchnical Speci fications

[)ato of Issuance:

December 19, 1975

ATTACHhfENT TO LICENSF. AhfENDhH;NT NO.

18 TO LICENSE NO. DPR-33 AND LICENSE AhfENDhfFNT NO.

15 TO LICENSE NO.

DPR-52 (CHANGE NO.

16 TO THE TEC)APICAL SPECIFICATIONS)

DOCKET NOS.

50-2SO ANn 50-260 Revise Appe>>dix A as follows:

Remove the pages listed below and insert identically numbered.

pages.

Table 3.2.A (page 54) 131 13la 132 133 134 135 144 146 147 148

'49 176 176a 206 256a

e

Table 3.2.A SURVEILLANCE INSTRUMENTATION Minimum 8 of Operable Instrument Channels Instrument t Instrument-Type Indication and Ran e

Alarm Settin Notes LI-3-206 or LR-3-53 or LI-3-53 or LI-3>>55 and LX-3-46A or 46B PI-3-54 PR-3-53 Reactor Water Level Reactor Pressure Indicator 0" to 60" Lov > 27", high <39" Recorder 0" to 60" Indicator 0" to 60" Indicator 0" to 400" Indicator +60" to -155" Indicator 0-1200 psig High < 1040 psig Recorder 0-1200 psig (1)(4)

(i)(5)

~

PR-64-50 and Dryvell Pressure PI-64-67 Recorder 0-80 psig Indicator 0-80 psig (1)(S)

TI-64-52A and TR-64-52 TI-64-55A and TIS-64-55 LI-64-54A or LI-64-66 Dryvell Temperature Suppression Chamber Water Temperature Suppression Chamber Mater Level Indicator 0-400'.

High < 145 F.

Recorder 0-400'.

Indicators 0-400'.

High < 90' Indicator -25 to

+25 II (1)(5) eg0 (1)(4)

(1) (4)

Control Rod Position Continuity SRM A~ Be C, D Neutron Monitorin'g Indicator.

and Recorder O.l to 10~ cps

-100 to t.10 sac.

(period)

Pownscale

> 3 cps Retract permit 100 cps Upscale HI < 10 cps Upscale HI-HI<5x105cps Period

> 30 sec.

())())

(t)'IO 4Jl LS-78-2A LS-78-2B TR-74-80 pT 17 Fuel Storage Pool level NA high Fuel Storage Pool level NA lov 0

Fuel pool temperature Recorder 0-600 F

<EL 663'/2"

>EL 662' 1/2"

< 125 F 0

(6) (7)

(6) (7)

(6) (7)

~

u a

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shall be capable of manual operation.

Diesel generators must also be available to power the pumps.

A service water supply must be avail-able.

flow, another ccrc spr "y pump with an available diesel genera-tor shall be selected, and all active components in the flow paths shall be ~~ediately demonstrated to be capable of delivering flow.

B.

Ra.";iriu' iieet Raaovrl Svataic RiiRS (Containaanc and Shutccam Coolin l.

Residual Heat Removal Syotem Vesting Item 7"..eceeaanc r

l.

N>cnevcr irradiated fuel is stored in the spent fuel pool, a cooling system for the spent fuel pool shall maintain the temperature of t.he oui=1 pool coolant <125'F.

2.

When irradiated fuel is stored in the spent fuel pool, any cor(-

bination of two pumps and asso-ciated heat exchangers from the spent fuel cooling or RHR supple-mental cooling systems shall be available f'rom different operabl diesel generators to maintain fuel pool temperatures as speci-a, Pump operability Upon restoration and monthly there-at\\ es b.

Notor oper-ated valve operability Upon restoration and monthly there-af ter.

RHR pump (containment and sup-pression pooL cooling) or asso-ciated heat ex'changer is incap-able of delivering 'flow and removing heat at a

ime when flow capability anc heat removal are

equired, the remaining RHR pump and associated heat ex-changer and available diesel generator, and all active com-2.

When it is dcte~ined that "one ponents

~n ~he flow path 131

'shall be dexonstra-ed to be DEC i0 t975

I

I I IMITQ/0 CONDITIONS FOR OPERA 0

Lied in 3,5,C,l.

When a fuel pool cooling pump is required to be opera-ting or as a backup, the associated RHCCWS loop and service water system must be functional.

3, Whenever irradiated fuel is stored in the fuel pool, the gates on the fuel transfer canal between Unit 1 and Unit 2 shall bo left in place and the transfer canal drain valves 1-78-561 and 1-78-S62 shall be shut, and the fuel pool gates between the fuel pools and the reactor cavities shall be installed with the canal blocks in place.

'a

LIMITIN:.CONl)ITIONS FOR OPL'RATI SUnvr ILLANcr. Rr.,

rMFITS 3'

CORE CONTAINMENT AND FUl L POOL COOLING SYSTEMS RHR Service Water S stem Rl{RSMS Emer enc E ui ment Coolin Water l.

When a RHR pump is required to be operating or as a backup for supplemental cooling, an asso-ciated RHRSW pump must be func-tional and aligned to RHR header service corresponding to.the selected IUiR pump.

2.

At all times, at least 2 Rl!RSW pumps shall be assigned to EECW header service with one pump assigned to each header.

Each pump must run continuously with its loss of voltage trip deactivate

, or it shall be capable of automatic start irt its normal D/G load sequencing mode of operation.

Each pump shall be assigned to a separate diesel power supply.

3.

Prior to restoration of any non-essential EECW loads that could result in exceeding the capacity of one RHRSW pump, a

second RHRSW pump will be assigned to each EECW header.

132 4.S CORE CONTAINMENT AND FUEL

'POOL COOLING SYSTEMS capable of delivering flow and heat removal immediately and weekly thereafter until the inoperable RHR pump and associated heat exchanger is returned to service or an alter-nate pump and heat exchanger with an available diesel gene-rator selected and verified.

C.

S ent Fuel Pool Coolin iG 1.

The spent fuel pool water temperature shall be checked and recorded at least every 8

hours'.

When it is determined that the the RHR or fuel pool cooling pump

~for spent fuel pool cooling is incapable of heat removal, another RHR or fuel pool cooling pump capable of being supplied with diesel power shall be selected and all active components required for heat removal shall be demon-strated to be capable of delivering

'flow.

DEC 19 1975

e

~

I OffTINC C.'ONUITIONS F01( OPE1IATION SIJRUI'.TI.l.t'ICE HEI U II<ILYI'.NTS 3,5 Rl'ONTAIIVII'.NT hND FUEL OOL COOLING SYSTEHS S.S co>>;

c'>>:Ye.::o>ssY POOL COOLZNC.Y'Yl'AS Each pump moat run continuously with its loss of voltage trips deactivated or it shall be cap-able of automatic start in its normal D/G load sequencing mode of operation.

Each pump on the same header shall be L

I assigned to a separate diesel power supply e S

Upon restora<<

'l cooling pump is as follows:

~Pre ueuc a.

Pump opera-

'bility tion" and monthly there.

after if not in continuous 3.'outine-surveillance for an joperating or backup RHR or fuel

service,

b. Hotor-oper-ated valve operability Upon restor tion and monthly there-after RHR Service Mater S stem (RIIR~SMS And Emex enc E uinmen" Coolin,"

Mater S stem EECMS l.

IUIR Service Mater System Each of the required R11RSM 4.

1&enever irradiated fuel is stored in the spent fuel pool, two independent flow paths for water make up to the spent fuel pool shall be available from two RHRSN pumps, capable of being supplied by separate diesel power.

pumps and associated essential contxol valves on the RllR heat exchanger headers shall be demonstrated to be functional upon res oration and once every.

three months thereafter if not in continuous service.

~ 'W>P QL7'I

0

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MITING CONDITIONS FOR OPERATION

~ 5 E

CONTAINMENT AND FUEL POOL COOLING SYSTEMS E'.

Maintenance of Filled Dischar e

~Pi e Whenever the core spray system or RHR systems are required to be functional, the discharge piping from the pump discharge of these systems to the last block valve shall be filled.

The condensate head tank shall be aligned to serve the discharge piping of the RHR and CS pumps.

The pressure SURVEILLANCE RE< U lREMENTS

4. 5 CORE CONTAINMENT AND FUEL POOL COOLING SYSTEMS

2. 'ECW System Each of the RHRSW pumps assigned to EECW service and associated essential control valves on the EECW headers sha11 be demonstrated I

1 to function once every three months..

3.

Wtsen it is determined that one RIIRSW pump and associated con-trol valves on an RHR,heat, piping of the RHR and CS pumps shall indicate not less than listed below.

exchanger header are incapable of delivering flow at a time when flow delivery capability is required, another RHRSW PI<<75-20 PX<<75-48 PI"74-, 51 PZ-74-65 70 psig 70 psig 70 psig 70 psig pump and associated heat ex-changers and available diesel generator and all active com-ponents in the flow paths shall be demonstrated to be capable of delivering flow immediately and weekly thereafter.

134 4.

When it is determined that one RHRSW pump and associated DEC 1 9 1975

~

I i i ttVtNC CONDITIO:~S FOR OPFRATIOm SuRVrn.LAnCR RF. trtREMENTS

4. 5 CORK CONTAINNKNT ANO FURL POOL COOLING RYSTFMIi control valves on an EEL header is incapable of deliver-ing flow at a time when flow delivery capability is required, an alternate RHRSM pump on a corresponding diesel generator shall be selected and assigned to the same EECW header.

5.

I At intervals not to exceed 7 days each independent fuel pool makeup flow path from its respective EECQ header to the fire hose outlet con-nection on the refueling floor willbe tested to verify make-up water supply avaU.ability, iG F,

,Maintenance of Filled Dischar e

~Pi e 135 The following surveillance require-ments shall be adhered to to assure that the dis'charge piping of the core spray system and RtS system

,are filled:

DEC 19 1975

3,S uhszs:

coRr.

coNTATetrNT ann FURL. pooL, coot.r>n: svsTrws 3,5,B Residual Heat Removal S stem RHRS Containment and Shutdown

~Caolin The decay heat removaL requirements for one unit in the cold shutdown condition can be conservatively met by the operation of one RHR pump and its associated RHR heat exchanger in the shutdown cooling mode I

The total heat load for the heat exchanger is estimated to be less than one-fourth of the heat exchanger capability under the required flow and temperature conditions.

The low decay heat and absence of pressure which could foster an unacceptable loss of coolant allows ample time for manual operat'ion in accordance with established opar*tins inatructiona.

144 DEG 19 j975

I4

'. $.5 11A.'tl:S:

COkR COtlTAIlOtt!NT A'il> ISttit. POOI. COOLIltC SYSTPSS t

0 ~ 5.C S~cnt F<<cl Pnol Coolin.:

The spent fuel pool cooling system consists of two 600 gpm pumps and heat exchangers.

Figure D-2 of the TVA Safety Analysis of the BFNP Units 1 and 2 included as Part VI,Section E of the "Plan for Evaluation, Repair~ and Return to Service of Browne Perry Units 1 and 2 0'farch 22, 197@ Fire)" shows that one pump and associated heat exchanger are capable of maintaining the spent fuel.coolant temperature below 125'F based on the Browne Ferry actual power operational decay heat curve.

Zn response to NRC Question 10.1, dated Harch 25, 1971, TVA committed to modify and upgrade the spent fuel pool cooling system to qualify as a Seismic Class I system.

The system was subsequently analyzed and designed in accordanco with the requirements of ANSI B 31.1.0, 1967.

The loadin" combinations and allowable stiesses used in the analysis vere in'accordance with ASHE Section XII, Subsection NC, 1971 requirements.

The analysis meets the intent and requirements'of Asnr;Section III, 1974.

All piping, valves, and equipment as shown

'in Figurc </10.1-1 of the response, except that identified as nonseismfc>

were analyzed, The gates on the fuel transfer canal between Unit 1 and Unit '2'will be left in place and the txans'fer canal dxain line will be valved out.

This provides xedundant seismically qualified barriers for the prevontion of pool leakage through the transfex canal.

DEC 19 57$

e

3:P BASES:

COkL CONTAXNNENT AtB) SUl'.l. BOO!. COOI.INC SYSTP ik 3.5.C S ent Fuel Pool Coolin continued The decay heat removal requirements for a full core stored in the fuel pool can be conservatively met by the operation of one RHR pump and its associated RliR heat exchanger in the fuel pool cooling mode.

The total heat load for this mode is estimated to be less than 20 per cent of the heat exchanger capability under the required flow and temperature conditions.

>46 DEC 19 1975

~

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3. 5 ltASES:

i 3.5.D 16 COVl'..n!nAI!BIINT A"Il: ~"::".

":i. CnW.I;Y: SYSTBI.,

R)IR Service Water S stem RHRSMS Emer enc E ui ent Coolin Mater The decay heat removal cooling water requirements for two units in the cold shutdown condition can be conservatively met by the operation of one RHRSM pump on one heat exchanger on each unit One RHRSM pump is required for each unit if the units are using heat exchangers which are not on the same service water header, Four R~M pumps are presently available and capable of delivering flow to meet this require-

ment, Less than one-half the flow delivery capability of each pump is needed to remove the -present decay heat for each unit The low decay heat level and ample flow delivery capability allow ample time for manual operation in accordance with established operating instructions.

The standby emergency equipment cooling water (EECM) requirements for two units in the cold shutdown condition can be adequately mat by the operation of one RHRSW pump, if non-essential loads are valved out.

The EECW system is not required for normal plant shutdown operation because the required cooling water is supplied by the raw cooling water system.

The principal immediate need for EECW flow is in the event that a.diesel engine should be started.

In this case, EECW flow must be established at once.

To meet this requirement;two RHRSW pumps are assigned to EECW service and are aligned to separate supply headers.

When restoration

'or testing activities require addition of any non-essential EECW loads which could exceed thc capacity of one RHRSW pump, an additional pump will be assigned to service

~

on each EECW header.

Each of the required pumps will operate continuously (with loss of voltage trips deactivated) or they will be capable of auto-matic start in their normal diesel generator load sequencing mode of operation.

Thc required RHRSM pumps are assigned to 4.16-kV shutdown boards which. have aasociated oper'able diesel generators>

147

~

~

DEC 19 3S75

3 ~ 5 llASI'5>>.'

'.D CO<Cr'.

C<)NTArrr'<<'.CtT~Arni <'U<:.r.

t O<~r. <:<>nr,<.:<<: SV.";rr~<S I<<III tarvtca:>>Iatmr S ataai~ll.'III~W'i

!<<acr~ant K at arnt Rani>>~ma lla a S stem t'.ECWS Continued In the unlikely event that all make up capability is lost, water can b6 supplied to the reactor or fuel pool by certain RHRSM pumps directly from the river.

The Dl or D2 RHRSrf pumps can pump through the KKSW header and standby.coolant supply line in to MR loop II on Unit 1, or RHR loop I on Unit 2.

From the RHR loop the water can be routed to the reactor through the LPCI in)ection valves or the fuel pool through the fuel pool system connections on each RllR loop.

An alternate path is available which is independent of the lOiR and fuel pool cooling systems.

The alternate path will only require any one of four RHRSV pumps and manual valve operation to provide make up coolant directly to the fuel pool through a hose connected to either the north or south EECW header hydrant.

The RHRSN pump has an on site power source.

The make up capability provided, by the RHRSN pump far exceeds the amount needed to replace the water lost at the'aximum evaporation rate possible with the present decay heat.

=- ~

3. 5 BASES:

3;5.E CORE CONTAIN!<I:NT AND FUI:I. POOI.

COOT.INC Maintenance of Filled Dischar e Pi e If the discharge piping of the core spray and RHR system are not filled, a water hsamer can develop in this piping when the pump and(or pumps are started, To minimize damage to the discharge piping and to ensure added margin in the operation of these

systems, this Y<<>>ic>>

, Specification requires the discharge lines to be filled whenever the system is in a functional condition, If a discharge pipe is not filled, the pumps that supply that line must be assumed to be nonfunctional for Technical Specification purposes, The core spray and RHR system discharge piping high point vent is visually checked for water flow prior to any pump operation to ensure that the lines are filled, The visual checking will avoid starting the core spray or RHR'ystem with a discharge line not fi'lied.

In addition to the visual observation and to,ensure a filled discharge'line other I

than prior'o testing, a head tank located, approximately 100 feet above the discharge line high point supplies makeup water for these systems.

System discharge pressure indicators are used to determine the water level above the discharge line high point.

The indicators will reflect approximately 30 psig for a water level at the high point and approxi-mately 70 psig for a water level at the head tank and are monitored daily to ensure that the discharge lines are filled.

149

LIMITINGCONDITIONS FOR OPERATIONS SURVEILLANCE RE UIREMENTS 3.7 ONTAINMENT.SYSTEMS

4. 7 CONTAINMENT SYSTEMS B.

Stand Gas Treatment B.

Standb Gas Treatmen" When the fuel is stored in the fuel When required to be in service, pool and the reactor zone ventilation operation of one train of the 1G system is removed from service, one train of the standby gas treatment system shall be in operation on the reactor building zone of the affected unit.

1e standby gas treatment system shall be verified and documented once per shift.

C.

Reactor Buildin Ventilation When fuel is stored in the fuel pool, the reactor building zone for units C.

Reactor Buildin Ventilation When fuel is stored in the fuel pool, operation of the ventilation 1 and 2 shall be ventilated by one supply and one exhaust fan per zone, fans for the reactor building zone shall be verified daily.

except as specified in 3.7.B.

176

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LIB CNG CONDITIONS FOR OPERATIONS 3.7 CONTAINMENT SYSTEMS D.

INOPERABLE COMPONENTS Whenever the requirements of specifications 3.7.B and 3.7.C cannot be met, all fuel handling activities or any activity over irradiated fuel in the vessel or fuel pool shall not be permitted.

176m

BASES:

Cntrl'AtNNEllT SYSTEtlS Ao PAIMAHY MNTAINKNT This specification ensures indication of adequate information regarding status of the drywall pressure and temperature and suppression chamber water level and temperature when fuel is in the reactor.

Mhen fuel is removed this re" quirement is no longer necessary.

Monitoring of information concerning these primary containment parameters will ensure that sufficient control of these parameters can be manually initiated in a timely manner.

%f*

B, 'STANDBY"GAS TREATMENT Before making the normal reactor zone ventilation inoperable, one standby gas treatment train must be operating to provide a means to remove equipment heat and to maintain environmental temperature control in the affected reactor building zone.

1 8 C,

REACTOR BUILDING ZONES Reactor building equipment heat removal and environmental temperature control will be provided by manual operation of the building ventilation systems.

One ventilation supply fan and one ventilation exhaust fan in each reactor building zone willmaintain ambient temperatures at an acceptable level.

206 DEC 19 1975

e

IhfITING CONDITIONS FOR OPERATION 3.10 CORE ALTERATIONS H.

Restoration,llork l.

All fuel from both cores shall be stored in their fuel storage pools.

2.

After all fuel from both cores is stored in its respective fuel s orage pool and the fuel pool gates are installed >>ith canal blocks in place, removal of fire damaged equipment may be carried out in accordance>>ith the "Plan for Evaluation,

Repair, and Return to Service of Bro>>ns Ferry Units 1 and 2" and revisions thereto up to and including Revision l0 as supplemented by licensee's letter dated June ll, 1975 (Gillcland to Rusche, NRC) 256a

e

t uNITED STATES l NUCLEAR REGULATORY COViMISSION

'LVASHINGTON, D.

C.

20555 SAFETY EVALUATION BY TIIE OFFICF. OF NUCLFAR REACTOR REGULATION SUPPORTING IQ'tENDMENT NO.

18 TO FACILITY LICENSF. NO.

DPR-33 AND AMENDMENT NO.

15 TO FACILITY LICENSE NO.

DPR-52 (OIANGES NO.

16 TO TECIINICAL 'SPECIFICATIONS)

TENNESSEE VALLEY AUTlIORITY BRONHS FERRY NUCLEAR POlItER PLANT, UNITS 1

AND 2 DOCKET NOS.

50-259 AND 50-260 1.0 Introduction On i~larch 22,

1975, a fire at. Browns Ferry Nuclear Plant required shut down of Units 1 and 2.

The.fire damaged.control and power supply cables to much of thc equipmcnt and temporary cabling was installed to return certain equipmcnt to operability.

On Junc 13, 1975, the Nuclear Regulatory Commission (NRC) issued Interim Technical Specifications for Browns Ferry Units 1 and 2.

Those specifications took into consideration the condition,and disposition of the fuel and specified the required equipment,

systems, and administ'rativc procedures to ensure that the two units would remain in a safe and stable posture during the period of defucling and fuel storage ih the fuel storage pools.

On September 2,

1975, NRC issued Amendments No. 14 and 11 to the operating 1'iccnses for Units 1 and 2, respectively, to allow the commencement of. certain restoration work at the plant with the fuel from Units 1 and.2 remaining in thc fuel storage pools.

At this time, certain equipmcnt and systems that are required by thc Interim Technical Specifications issued June 13,

1975, are no longer needed because the present plant and fuel conditions have changed from those considered at.the time of issuance of those Tcchnical Specifications.

By deleting the requirements for equip-ment that is not necessary, the licensee can take that equipment out of service in order to install its permanent control and poIi'er cables and perform the tests that will be required by the retest program prior to returning the plant to operation.

Some equipment also must be taken out of service in order to interconnect it with equipmcnt associated with the construction of Unit 3..

The systems involved in 'this change request, are:

(1)

The Residual Heat Removal System (RHR).

(2)

The Residual Heat Removal Service Water System (RHRSN).

1 (3)

The Fuel Pool Cooling and Cleanup System (FPCCS).

(4)

The Standby Gas Treatment System (SGTS).

These changes only affect the Interim Technical Specificationsthat cover this period of time during restoration and are not a part of the proposed Technical Specifications dated August 13, 1975, associated with returning the plant to operation following restoration.

Those changes are the subject of a separate action.

2.0 Evaluation 2.1.

Residual Heat Removal S stem RHR The Interim Technical Specifications required the RHR system to be operable for fuel cooling when the fuel was in the react'or vessel and as a backup to the FPCCS when the fuel was in the fuel storage pool.

The first of these needs does not apply because the fuel is now in the fuel storage pools and this Technical Specification change includes a

specification that does not allow fuel to.be placed in the reactor vessels.

In June

1975, one FPCCS pump and heat exchanger did not have sufficient capacity to ensure that the pool temperature could always be controlled to less than 125oF.

Therefore, the second FPCCS pump and heat exchanger was required and in order to ensure backup cooling supply, the RHR system was required to be operable.

Under present conditions, the decay heat load of the fuel has reduced to a point where one FPCCS pump and heat exchanger can maintain the pool temperature less than 125oF.

This was confirmed by Glow and tem-perature measurements made at t'e plant in the FPCCS to determine the present decay heat load of the fuel and assuming 90 F cooling water available from the river, the ultimate heat sink.

Therefore, the second FPCCS pump and heat exchanger with separate diesel power supply can provide the required backup for cooling.

In addition, ifit is desired to take one or both of the FPCCS pumps out of service, the RHR system is required to provide the backup cooling supply, the pri-mary cooling supply, or both.

There are four pumps and heat exchangers in the RHR system of each unit.

Any two of these can fulfillthe requirements for both primary and backup fuel pool cooling through cross connections to the FPCCS.

This change does not relax the functional requirements of the Technical Specifications for fuel pool cooling, i.e.,

independent cooling capability to maintain the pool temperature less than 125 F from both a primary and backup cooling system.

This change modifies the designation of what constitutes the primary and backup cooling systems.

I 2.2 Residual IIcat Removal Service Nater S stem (RHRSN)

- The RHRSN system providos the cooling for the RHR system.

The speci-fication for this system has boon changed to require that an RHRSN pump must be functional and aligned to MR header service corresponding to the selected MIR pump when the RHR is required to be operating or as backup for tuel pool cooling.

This specification reflects the change in requirements for the RIIR system discussed in Section 2.1 and is found acceptable on the same basis.

The requirement for at least two RHRSIF pumps to be assigned to separate Emergency Equipment Cooling Nater (EECN) headers with both pumps running continuously or capable of automatic start remains unchanged.

However, an additional requirement has been added requiring an addi-tional RIIRSN pump to be put in service prior to adding any non-essential EECN loads that could result in exceeding the capacity of the one MIRSN pump.

This will ensure that the cooling capacity described in the Safoty Analysis Report is always maintained without any reduction in safety margin.

2.3 Fuel Pool Coolin and Cleanup S stem (FPCCS The specifications issued June 13, 1975, required two FPCCS pumps and heat exchangers be provided as the primary cooling supply for the fuel pool.

As described in Section

2. 1, the present heat load of the stored fuel can bo adequately cooled by the use of one FPCCS pump and heat exchanger.

The requirement to maintain the pool water temperature less than 125oF remains unchanged.

Therefore, the margin to pool boiling is 'not reduced.

In fact, wj.th the reduced deca>

heat load of the stored fuel, the amount of time to reach boiling temperature in the pool after loss of all cooling is now extended to approximately six days.

'I'herefore, the specification for this system has been changed to allow one FPCCS pump and heat exchanger to function as the primary or bact'up cooling supply for the fuel pool.

At this time, this specification provides at least as much'argin of safety as the specification issued on Juno 13, 1975, provided at that time.

2.4 Standb Gas Treatment S stem (SGTS)

The specifications issued June 13, 1975, required that one train of the SGTS be functional with fuel stored in the fuel pool, The SGTS was not needed for airborne,radioactivity considerations (see the SER published with the Juno 13, 1975 amendments).

The SGTS was required as backup to the Reactor Building Ventilation System to maintain an air flow in the event of loss of normal ventilation.

This was to prevent chloride contamination from the reactor building from spreading to the fuel pool area and to exhaust the water vapors generated from the fuel pool in the event of loss of pool cooling.

Under the present conditions, all burned cabling has been removed from the plant and soot contamination has been thoroughly removed.

The long time (approximately six days until boiling) now available in the event of loss of pool cooling in order to re-establish venti-lation obviates the need to maintain the SGTS operable at all times.

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Therefore, there is no longer a requirement to maintain this system operable to ensure backup ventilation.

The system will be used if the ventilation system is removed from service.

3.0 Conclusions We have concluded, based on the considerations discussed above, that:

(1) because the change does not involve a significantincreasc in the probability or consequences of accidents previously considered and does not involve a signifi.cant increase in a safety margin, the change does not involve a significant hazar'ds consideration, (2) there is reasonable assurance that thc health and safety of the public will not be endangered by operation in tho proposed

manner, and (3) such acti-vities will bo conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.

Date:

December 19, 1975

UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-259 AND 50-260 TENNESSEE VALLEY AUTHORITY NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSES Notice is hereby given that the U.S. Nuclear Regulatory Commission (the Commission) has issued Amendment No.

18 to Facility Operating License No.

DPR-33 and Amendment No.

15 to Facility Operating License No. DPR-52 issued to Tennessee Valley Authority (the licensee) which revised Technical Specifications for operation of the Browns Ferry Nuclear Plant, Units 1 and 2, located in Limestone County, Alabama.

C The amendments are effective as of'the date of issuance.

The amendments revise the Interim Technical Specifications to remove the requirements for certain cooling and ventilation equipment that are no longer needed.

The cooling requirements are reduced since the decay heat of the fuel has been greatly reduced with the elapsed time since reactor operation.

The ventilation requirements are reduced for the same reason and because the need to control air moVement to prevent the spread of chloride contamination no longer exists with the burned cables and soot having been removed from the plant.

These amendments do not allow the licensee to return the plant to operation.

These amendments only affect the Interim Technical Specifications that cover this period of time during restoration and are not a part of the proposed Technical Specifications dated August 13, 1975, associated with returning the plant to operation following restoration.

Those changes are the subject of a separate licensing action.

2 This change is required in order to allow the installation of the permanent control and power supplies to this equipment and in the case of the Standby Gas Treatment System to allow the" connection of the third train of the system to accommodate the requirements of Unit 3.

This equipment and their associated systems also are involved in the retest program that is required prior to return to operation.

The licensee informed us that this work must be started at this time so as not to adversely impact the restoration schedule.

The Interim Technical Speci-fications, as

amended, continue to ensure that the two units will remain in a safe and stable posture during the period of the remaining restora-tion work with the fuel stored in the fuel storage pools.

The application for these amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations.

The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.

Prior public notice of these amendments is not required since the amendments do not involve a significant hazards consideration.

'I For further details with respect to this action, see (1) the appli-cation for amendments dated November 7, 1975, (2) Amendment No. 18 to License No.

DPR-33 and Amendment No. 15 to License No. DPR-52 with Changes No. 16, and (3) the Commission's related Safety Evaluation.

All of these items are available for public inspection at the Commission's Public Document

Room, 1717 H Street, NN., Washington, D.C.,

and at the Athens Public Library, South and Forrest,

Athens, Alabama 35611.

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3-A copy of'items (2) and (3) may be obtained upon request addressed to the U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, Attention:

Director, Division of Reactor Licensing.

Dated at Bethesda, hfaryland, this 19th day of December 1975.

FOR Tile NUCLEAR REGULATORY CODED'1ISSION Robert, A. Purple, Chief Operating Reactors Branch Nl Division of Reactor Licensing

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