Text

Amends 250 & 209 to Licenses DPR-52 & DPR-68,respectively, Including License Conditions to Require Implementation of Compensatory Measures,Consistent W/Commitment Made in Application
	ML20198J005
Person / Time
Site:	Browns Ferry
Issue date:	12/22/1997
From:	Hebdon F; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20198J009	List: ML20198J005; ML20198J017;
References
	NUDOCS 9801140018
	Download: ML20198J005 (22)
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k UNITED STATES p

NUCLEAR REGULATORY COMMIS810N wAsmwotow, p.c. seenweet

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TENNESSEE VALtrY AUTHORITY DOCKET NO. 50-260 BROWNS 7ERRY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICMSE Amendment No. 250 License No. DPR 52 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated June 19,1997, with additional information provided on August 15,1997, 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 shfety of the public, and (ii) that such activities will be conducted in comp!iance 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 satisfed.

9001140018 971222 PDR ADOCK 05000260 P

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Accordingly, the license is amended by changes to the Technical Speedications as indicated in the attachment to this licent amendment and paragraph 2.C.(2) of Facility i

Operating License No. DPR 52 is hereoy amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 250, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

Also, the license is amended by adding Paragraph 2.C.(15) on page 6 of Facility l

Opersiting License DPR 52.

~

(15) a. When eme wncy diesel generators are removed from service for up to 14 days for preventive t. sintenance under the provisions of Amendment No. 250, the licenses shall:

1. Require another offsite power source be available in addition to the i

requirements of Technical Specification 3.g.A.1.c that two offsite sources be available.

2. Restrict work activities affecting the ability to cross tie the associated Unit 3 emergency diesel generator to the 4-kV shutdown board for the emergency dies,el generator that is out of service.

3. Restrict work activities on the 500-kV switchyard cross tie breakers i

supporting the affected unit.

4. No high risk switchyard maintenance will be scheduled while the emergency diesel generator is out of service, if emergent conditions require performance of such high risk activities, such activities shall be approved by the Plant Manager and the Operations Manager. *High risk switchyard maintenan:e* is defined as an activity that if a single error or p.Dblem occurs, a ful. reactor scram, transient requiring a reduction in reactor power, and/or an tinplanned engineered safety features actuation requiring a report to tha NRC with!n 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , could occur.-

b. These provisions apply during the time period from January 1,1998 to February 1,1999, or completion of preventive maintenance under the provisions of Amendment No. 250, whichever occurs first.

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3-4.

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

FOR THE NUCLEAR REGULATORY COMMISSION

,#,M o Nd u FrederickJ.Hebd n Director Project Directorate ll 3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Attachments: 1. Pages 6 and 7 of License DPR 52*

2. Changes to the Technical Specifications Date ofissuance: December 22, 1997

Pages 6 and 7 are attached, for convenience, for the composite license to reflect this change.

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l 02)

The litansee is estherised to temporartir store lowlevel l

redi maties vaste la en esisting severed pavilles that le situated entside the seestity fanse, as presently leasted, het taside the site emelusies area. the total amenat of lee-level waste to be etered aball met esseed 1830 earles of total activity. Tkte sethertsattes aspires two years frem the effective date of this amendment and is subject to all the senditions and restrictions la TTA's appliaaties dated January 31, 1940.

t (13)

Comalestem Order dated Marea 85, 1983 is modified as fo11 eves in Attashment 1, for item II.y.1.1 and II.y.1.3 shange "12/31/44' to ' Prior to startsp la Sysle 6."

(14)

Browns Ferry peelear Plant shall taplement and asistata la effect all previelens sf the approved Fire Protettles Prestem as deberibed la the Final safety Analysis Report for SFN as appr@v d in the SEs dated December 4, 1988, March 4, 1991 March 31, 1993, November 2,1995 and Supplement dated Noveeber 3, 1989 aubject to the following prwision:

The liseases may make shaases to the approved fire protestice program withest prior approval of the Ceemittles saly it these thanges weald met adversely affect the ant 11ty to achieve and naistata safe ahetteva in the event of a fire.

(15)

a. When emergency diesel generators are removed from servia for up to 14 days for preventive maintenance under the provisions of Amendment No.

, the licensee shall:

1 Require another offsite power source be available in addition to the requirements of Technical Specification 3.g.A.1.c that two offsite sources be available.

2. Res..let work activities affecting the ability to cross tie the associated Unit 3 emergency diesel generator to the 4 kV shutdown board for the emergency diesel generator that is out of service.

3. Restrict work activities on the 500 kV switchyard cross tie breakers supporting the affected unit.

4, No high risk switchyard maintenance will be scheduled while the emergency diesel generator is out of service, if emergent conditions require performance of such high risk activities, such activities shall be approved by the Plant Manager and the Operations Manager 'High risk switchyard maintenance'is defined as an activity that if a single error or problem occurs, a full reactor scram, transient requiring a reduction in reactor power, and/or an unplanned engineered safety features actuation requiring a report to the NRC within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , could occur.

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b. These provisions apply during the time period from January 1,1998 to February 1,1999, or completion oipreventive maintenance urP' the provisions of Amendment No.

, whichever occurs first.

D.

This amended lisease is effective as of the date of issaanse ad shall empire attaight sa Joe 34, 3014.

FOR TER AT1Nt!C EMBBS! C0f008810N 3/

A. af a-w man A. 81anknese, Deputy Director for toaster Pro,festa Directorate of Licensias Attechment:

Appendices A & 3 - Te h aal Specifications Date of faevance JUN 38, 1974 i

BFN thit 2 -

hendment No. 250

ATTACHMENT TO LICENSE AMENDMENT NO. 250 EACILIW OPERATING LICENSE NO. DPR 52 QQCKET NO. 50 280 Revise the Appendix A Technical SpecMcations by removing the pages identified below and inserting the enclosed pa9es. The revised pa9es are identified by the captioned amendment number and contain marginallines indicating the area of change. 'Overieaf and "spillover pages are included fo maintain document completeness.

REMOVE INSERT 3.9/4.9 9 3.9/4.9 9 3.9/4.9 10 3.9/4.9 10' 3.9/4.9 15 3.9/4.9 15' 3.9/4.915a 3.9/4.915a 3.0/4.915b 3.9/4.915b" 3.0/4,915e 3.9/4.915c'

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i 2.t/d.9 AMEILIARY RLRCTRIOkL SYSTEM I

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=-ITinana som apemmeind stravait t awe meantmennenta 3.9.5.

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ahin 4.1.5.

maration ulth tammarabia Aquipment

/mismaat i

3.

When one of the units 1 3.

When one of the l

l and 3 diveel generator is units 1 and 3 diesel i

IWOPERABLE, sentinued generatore is feund REACTOR POWER OPERATION to to be INOPERABLE, I

permissible during the all of the remaining oucceeding 7 days.,

diesel generatore J

provided that 3 offeite shall be demonstrated i

to be OPERABLE within power sources are available as epocified 34 hours3.935185e-4 days 0.00944 hours 5.621693e-5 weeks 1.2937e-5 months , and power i

i in 3.9.A.1.s and all et availability for the the C's, RER (LPCI as,d aseeetated boarde eentainment oceling) oha11 he verified eyetene, and the remaining within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and i

three. unite 1 and 3 diesel at loset once per geraratere are OPsRApLs.

a bours thereafter.

l

[ Temporary Omage: De preceding 74ey 140 dses link may be entended to la days to support t

i completion of maintamanes activities during the tiene period froma January 1,1998, to February 1,1999, star which time this temporary change la no longer valid. His allowesos een be used only ones for each indh4 dual diesal pseerstor.)

If this requirement cannot he met, an orderly shutdown shall be initiated and the reactor shall be in the COLD SEUTDOWN CONDITION within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

-4.

Whon one unite 1 and 3 4.

When one 4-kV 4-kV shutdown board is shutdown bNed is INOPERABLE, eentinued found to be i

RSACTOR 70NRR OPERATION IROPERABLE, all is permisoihte for a period diesel generators i

i et a days provided that associated with the 2 offeito power sources remaining 4-kV are available se shutdown boarde shall specified in 3.9.A.1.e be 4emonstrated to be and the remaining 4-kV OPERABLE withta 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , shut 6uwn boards and and power availability associated diesel for the remaining 4-kV gereeratore, CS, RER (LPCI shutdown boards and containment ecoling) shall be verified systems, and all 480-V within 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and emerge r boards at least once per are OP If this 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

requiremen*, cannot be not, an orderly shutdown shall be initiated and the reactor shall be in l

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

SFN 3.f/4.9-9

E9ENDir 10. 250 Unit 3 i-

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mitrm muerarca mm LIMITING OoNDITIoalt POR Gramaviam sugygit t Amen am_tramwehrTE 3.9.3.

onaration with Inonarabia 4.9.3.

peeration With Inonarable Rouinment Anulanant 5.

When one of the shutdown 5.

When a shutdown bus buses is IleoPERABLE, le found to be MACTOR POWER OPSRAT3001 lle0PERABLE, all is permissible for a period 1 and 2 diesel of 7 days.

generators shall be proven OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

6.

When one of the 480-V 6.

When one units 1 diesel auxitie.ry boards and 2 diesel becomes IMOPERABLE, ausiliary board is MACTOR POWER OPERAT1000 found to be is permiselble for a period 11:0PERAsLs, each of $ days.

unit 1 and 2 diewel generator shall be proven opsRAsLa within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and power availability for the remaining diesel auxiliary board shall be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months theriea f tar.

7.

From and af ter the date that one of the three 250-V unit batteries and/or its associated battery board is found to be IleOPERABLE for any raason, continued MACTOR POWEA OPERATI0li is permissible during the succeeding 7 days. Racept for rootine surveillance testing, NRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of tha situation, the precautions to be taken during this period, and the plans to return the failed component to an OPERABLR state.

3 Fat 3.9/4.9-10 AMENDMENT NO,15 4

-Unit 2

3.9/4.9 hiruf t.f amy mt.netalent. arsftM

$1MITING ODNDITIONS.FOR.OPERAT?ON BURVIIll.hMet RROUIREMENTS 3.9.C.

Omaration in cold shutdown 4.9.C ggaration in Cold shutdown Whenever the reactor le in

1. No additional COLD SKUTDOWN CONDITION with surveillance is irradiated fuel in the required.

reactor, the availability of electric power shall be as specified in Section 3.9.A except as specified herein.

1.

At least two Units 1 and 2 diesel generators and their associated 4-kV shutdown boards shall be OPERABLE.

2.

An additional source of power ener ised and capable of et pp ying power to the Unite 1 and 2 shutdown beards consisting of at least one of the followings a.

One of the of feite power sources specified in 3.9.A.1.c.

b.

A third OPEPARLE diesel generator.

3.

At least one 400-V shutdown board for each unit must be OPERASM.

4.

One 480-V RMOV board og set is required for each RMOV board (2D or 23) roguared to support operation of the R'JL system in accordance with 3.5.3.9.

AMENDMENT N0. I 8 6 SFW 3.9/4.9-15 Unit 2

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3.9/4.9 patL1Lar ELucraicaL ataram l

1.1MITING anunfffoMa POR OttaATION BURVRft? u ct

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nimesi annaratara ammuiro( j 3.9.P pignal separators mamuired for 4.9.D for Unita 1. 2. and 3 shart Unita 1.

2.

and 3 Shared avac--

Avatama 1.

Whenever standby gas treatment to required to be OPERABLE in surve111ance requiremente are accordance with specification as specified in 4.9.A.1, 3.7.3 and/Lr control room 4.9.A.2, 4.9.A.3, and 4 9.A.4 emergency ventilation is with the following required to be OPERABLE in proviolones accordar.ee with specification 3.7.3, the associated diesel 1.

The testing provisions of generator aligned to supply 4.W.A.1.b do not apply emergeney power to that for a defueled unit.

equipment shall be OPERA 8LB.

3.

The son. mon accident a.

Standby gas treatment train signal testing required A and/or cordrol room by 4.9.A.3 requires the emergency ventilation train algnal to originate only A - Dional generator 1/2A from unite that require or 1/25.

OPERAS!LITY of who standby gas treatment b.

standby gas treatment train system and/or the control 8 - Diesel generator 1/2D toom emergency or 1/25.

ventilation system. This test will verify the c.

standby gas treatment trai's automatic start of the C - Diesel generator 3D.

6;esel generators aligned to the standby gas d.

Control room emergency treatment eyeten and/or ventilation train B -

the control enom Diesel generator 3C or 38.

emergency vs.stilation system.

[ Temporary Change When the aligned dlesel generator is inoperable on a unit that is not in cold shutdwn, refueling, or defueled, then Ts 1.C.2 applies for the purposes of OPERA 3!LITY determinations for the above affected equipment. This change le valid during the time period from January 1, 1998, to Pobruary 1, 1999).

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3.9/4.0 AUI!41ARY ELtcTarcAL arsTIM LiMYTIMG ra8DITIONS FOR OPERATION 3DRVEIf t ansCE mROUf RfRNTS i

3.9.D.

11amai canaratora aamuired for 4.9.D.

nimaal cenaratora moeuired

'Jnita 1.

2.

and 3 shared swat = =

for Units 1. 2.

and j Shared avstema 2.

tihen the diesel generator aligned to supply emergency power to the equi p nt in 3.9.D.1 is inoperable on a unit that is in cold shutdown, refueling, or le defueled, the equipment may be considered OPERABLE for the purpose of satietying the corresponding technical specification during the succeeding 30 days, provided that the redundant train (s) of equipment and their normal and emergency power supplies are OPERABLE.

3.

If specification 3.9.D.2 cannot be met, the affected equipment shall be declared inoperable.

l BFN 3.9/4.9-15b Unit 3

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UNITED STATES g

1 NUCLEAR RECULATORY GOMMISSION wAsmoTow, p.c. metweev

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TENNESSEE vat i FY AUTHORITY DOCKET NO. 50-296 BrtOWNS FERRY NUCI FAR PLANT. UNI'r 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.209 License No. DPR 68 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated June 19,1997, with additionalinformation provided on August 15,1997, 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 resaonable atsurance (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 com'>liance 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 satisfed.

l

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2-2.

Accordingly, the license is amended by changet to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-68 is hereby amended to read as follows:

(2) Technical Soncifica((ong The Technical Specifications contained in Appendices A and E, L. revised through Amendment No. 209, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

Also, the license is amended by adding Paragraph 2.D.(5) on page 6 of Facility Operating License DPR 68.

(5) a. When emergency diesel generators are removed from service for up to 14 days for preventive maintenance under the provisions of Amendment No. 209, the licensee shall:

1. Require another offsite power source be available in addition to the requirements of Technical Specification 3.9.A.1.c that two offsite sources be available.

2. Restrict work activities affecting the ability to cross tie the associated Unit 1/2 emergency diesel generator to the 4-kV shutdown board for the emergency diesel generator that is out of servica.

3. Restrict work activities on the 500-kV switchyard cross tie breakers supporting the affected unit.

4. No high risk switchyard maintenance will be scheduled while the emergency diesel generator is out of service, if emergent conditions require performance of such high risk activities, such activities shall be approved by the Plent Manager and the Operations Manager. 'High risk switchyard maintenance

is defined as an activity that if a single error or problem occurs, a full reactor scram, transient requiring a reduction in reactor power, and/or an unplanned engineered safety features actuation requiring a report to the NRC within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , could occur,

b. Thece provisions apply during the time period from January 1,1998 to February 1,1999, or completion of preventive maintenance under the provisions of Amendment No. 209, whichever occurs first.

3-4.

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

FOR THE NUCLEAR REGULATORY COMMISSION h

Frederick J. Hebdon, Director Pro}ect Directorate ll 3 Division of Reactor Projects.1/11 Office of Nuclear Reactor Regulation Attachments: 1. Pages 6 and 7 of License DPR48*

2. Changes to the Technical Specifications Date of lasvance: December 22, 1997

Pages 6 and 7 are attached, for convenience, for the composite license to reflect this change.

APR 01, 1993 (2) The lisensee la required, h sampleties of the Mark I Ovaars Group containment le&a-term program related to relief valve operation, to make soah modifications en a timely basis as may be mesessary to restere the eristmal dosisa safety earsias approved for the temstreetion permit and mood for the design of the torus structures wham esbjected to relief valve operetten.

(3) The facility may be modified as described La 'Arewas Ferry Nuclear Plant Omit 3 hergemey Core Coeliac Systems Lev Pressure Coolant !ajecties Nodifications for Performance Zaprovement (October 1977)* and as described la TVA's letter of December 28, 1977 tramanitting the aforementiemed 2eport and la TVA's supplemental letter of December 13, 1978.

(4) Coenission Order dated March 25, 1983 is modified as follows:

In Attachment le for item !!.F.1.1 and !!.F.1.2 change

12/31/84" to

Prior to Dait 2 startup in Cycle 6."

(5)

a. When emergency diesel generators are removed from servka for up to 14 days for preventive maintenance under the provisions of Amendment No.

, the licensee shall:

1. Require another onsite power source be available in addition to the requirements vf Technical Specification 3.g.A.1.c that two o# site sources be available.

2. Restrict work activities a#ecting the ability to cross tie the associated Unit 1/2 emergency diesel generator to the 4 kV shutdown board for the emergency diesel generator that is out of

service,

3. Restrict work activities on the 500 kV switchyard cross tie breakers supporting the aMected unit.

4. No high risk switchyard maintenance will be scheduled while the emergency diesel generator is out of service. If emergent conditions require performance of such high risk activities, such activities shall be approved by the Plant Manager and the Operations Manager, 'High risk switchyard maintenance"is defineci as an activity that if a single error or problem occurs, a full reactor scram, transient requiring a reduction in reactor power, and/or an unplanned engineered safety features actuation requiring a report to the NRC within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , could occur,

b. Tnese provisions apply during the time period from January 1,1998 to February 1,1999, or completion of preventive maintenance under the

- provisions of Amendment No.

, whichever occurs first.

l ars ARDIDMD(T E gH, 209 hit 3 l

R.

This amended license le effective as of the dote of isenance and shall aspire midnight sa July 2, 2016.

FOR TEE NOCLEAR REGULAT0ST C000t!8810N 1/ R. C. Befo== for Roger 8. Boyd, Director Division of Project Manegament Office of Nuclear Reactor Regulation Attechnent:

Appendices A & R -

Technical specifications Date of Issuance JUL 2 1976 i

g haerhent tb.209 i

thit 3 1

t ATTACHMENT TO LICENSE AMENDMENT NO. 209 FACILITY OPERATING LICENSE NO. DPR-68 DCCKET NO. 50 296 Revise the Appendix A Technical Spec % cations by removing the pages identified below and inserting the enclosed pa9es. The revised pages are identifed by the captioned amendment number and contain marginallines indicating the area of chan9e, Overleaf and "spillover pages are included to maintain document completerwss, REMOVE INSERT 3.9/4.9 7 3.9/4.9 7*

3.9/4.9 8 3.9/4.9 8 3.9/4.914a 3.9/4.9-14a 3.9/4.914b 3.9/4.9-14b"

3.9/4.9 AUXILT.ARY ELECTRICAL SYSTEM HB 14 1995 LIMITING twemITIONS POR OPERATION SURVIIf1ANCE REQUIREMENTS 3.9.A.

auwiliary Elmetrical Emui - nt 4.9.A.

Aurillarv Electrical Byatem e

4.9.P 4. (Cont'd) c.

The loss of voltage and degraded voltage relays which start the diesel generators from the 4-kV shutdown boards shall be calibrated annually for trip and reset and the measurements logged.

These relays shall be calibrated as I

specified in Table 4.9.A.4.c.

d.

4-kV shutdown board voltages shall be i

recorded once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

5.

htgie svatsma 5.

,g o-v RMOV maards 3D and 3E a.

Accident signal lo'jjt l

system is OPER ULE.

a.

Once per operating cycle, the automatic b.

400-volt load sheddia-transfer feature for 480-V RMOV

! vic system f boards 3D and 3E shall be functionally tested to verify auto-transfer capability.

6.

There shall be a sinimum of 35,280 gallons of diesel fuel in each of the 7-day diesel-generator fuel tank assemblies.

AM M

NO.I89 RFN 3.9/4.9-7 Unit 3

3.9/4.9 AUZILIARY ELECTRICAL RiSTEM LIMITimo conDITiama pom opamAttom sumvart_tANem amournaxrwTs 3.9.3.

Onoratien with Inonarabia 4.9.3.

onoration with Inoterable Ecruitunant gggjg ifherever the reactor is in STARTUP mode or RUN mode and not in a cold condition, the availability of electric power shall be as specified f.n 3.9.A except as specified brein.

b 1.

From and after the date

1. When only one that only one offsite offsite power source power source is available, is OPERABLE, all unit 3 reactor operation is diesel generators must perlaissible under this be demonJtrated to be condition for seven days.

OPERABL2 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

\\

and power availability for the associated boards shall i

be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at FJast once per S hours thereafter.

2.

When ene unit 3 diesel

2. When one unit 3 diesel generator (3A, 35, 3C, generator is found to be a

or ?D) is inoperable, inoperable, all of the continued reactor operation remaining unit 3 diesel i

is permissible during the generators shall be l

succeeding 7 days, provided demonstrated to be j

that two offsite power OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .,

sources are ava'*able as and power availability specified in n.1.c.

for the associated boards and all of the CS, Mm shall be verified within (LPCI and containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once stems, and the per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

cooling) s)kree unit 3 remaining diesel genteators are OPERABLE.

[ Temporary Change: ne proceding 7 day 1CO time limit may be extended to 14 deys to support cocpletion of malatemance actMtles during the time period from January 1.1998, to February 1.1999, aRet which time this 'emporary chasse is so longer valid. His eBowance can be need only once for each ladividual diesel scocrator.]

K If this requirement cannot be met, an orderly shutdown et.all be initiated and the reactor shall be shut down and in the cold condition within 24 bours.

BFN 3.9/4.9-s AMDDHENT E. 209 Unit 3

3.9/4.9 AUZILIARY.1LECTRICAL SYSTEM LIMITInc CONDITIONS POR OPERATION SURVIILIANCE REQUIRE 102NTS 3.9 D Dianal Generators Reautred fer 4.9.D piesel Generatora Re uired pnita 1.,2.

and 3 Shared svat -

for Unita 1.

2. and 3 Shared systems 1.

W5enevar standby gas treatmeat is required to be OPERABLE in surveillance requirements are accordance with specification se specified in 4.9.A.1, 3.7.3 and/or control room 4.9.A.2, 4.9.A.*, and 4.9.A.4 emergency ventilation is with the following required to be OPERA 3LE in provisions:

accordance with specification 3.7.3, the associated diesel 1.

The testing provisions of 9enerator aligned to supply 4.9.A.1.b do not apply emergency power to that for a defueled unit.

equipment shall be OPERABLE.

2.

The common accident a.

standby gas treatment train signal testing required A and/or control room by 4.9.A.3 requirea the emergency ventilation train signal to originate only A - Diesel generator 1/2A from units that require or 1/25.

OPERABILITY of the standby gas treatment b.

Standby gas treatment train system and/or the control 5 - Diesel generator 1/2D room emergency or 1/25.

ventilation system. This tort will verify the c.

Standby gas treatment train autcoatic start of the c - Diesel generator 3D.

diesel generators aligned

.)

to the :tandby gas d.

Control room emergency treatment system and/or ventilation train 3 -

the control room Diesel generator 3C or 33, emergency ventilation system.

(Teeporary Changes When the aligned diesel generster is inoperable on a unit that is not in cold shutdown, refueling, or defueled, then T3 1.C.2 applies for the purposes of OPERABILITY determinations for the above affected equipment. This change is valid during the time period from January 1, 1998, to F*bruary 1, 1999).

t bFN 2.9/4.9-14a AMENLHENI 10. 209 Unit 3 l

i

j k

3.9/4.9 AUXILIARY ELECT 5fCAL SYS113 LIMITING CONDITIONS FOR OPERATION PURVIILI.ANCE REOUIREMENTS e

3.9.D.

Diesel cenerators Recruired for 4.9.D.

Diesel cenerators 11gg gg Unita 1,

2.

and 3 shared Avstems

_for Unita 1, 2.

and 3 Lnared 2.

When the diesel generator aligned to supply emergency power to the equipment in 3.9.D.1 is inoperable en a unit that is in cold shutdown, refueling, or is defueled, the equipment may be considered OPERABLE for the purpose of satisfying the corresponding technical specification during the succeeding 30 days, provided that the redundant train (s) of equipment and their normal and emergency power supplies are OPERABLE.

3.

If specification 3.9.D.2 cannot be met, the affeeted equipment shall y

be declared inoperable.

SFN 3.9/4.9*14b Unit S

_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _

ML20198J005

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