ML20099E184

Proposed Tech Spec Changes Re Limiting Conditions for Operation,Surveillance Requirements & Bases for Diesel Generator Operability,In Response to Generic Ltr 84-15

ML20099E184
Person / Time
Site:	Hatch
Issue date:	11/07/1984
From:	GEORGIA POWER CO.
To:
Shared Package
ML20099E167	List: ML20099E164 ML20099E184
References
GL-84-15, TAC-55865, TAC-55866, TAC-56522, TAC-56523, NUDOCS 8411210150
Download: ML20099E184 (53)

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L ATTAOiMENT 1 f

PROPOSED OIANGES TO 'DE e

IWIOf 1 AND 2

'IEOfiICAL SPECIFICATIONS t

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OPERATING LICENSE DPR-57 p

EDWIN I.. HATCH NUCLEAR PLANT - UNIT 1

. PROPOSED CHANCES TO TECHNICAL SPECIFICATIONS The^ proposed changes to'the Technical. Specifications (Appendix A to 4

Operating License DPR-57) would be incorporated as follows:-

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REMOVE PAGE INSERT'PAGE

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k' LIMITING COND1TIONS FOR OPERATION SURVEILLANCE REQUIhEMENTS

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3.5kA.2 1 Operation with Inoperable

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Surveillance with Inoperable s

-l Components -

cComponents 1

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If one'CS system loopcis;inoper '

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able,'the reactor.may. remain-in'

' core spray loop is inoperable o

' operation.for a period not..to.

Eat a! time when operability is1 g%xceed - seven; (7) ~ days providing -

1 required, ti.a other. core spray e.;

v O all active components in the:

loop,:and the RHR system;LPCI.

shallbedemonstratedto:!l*~

f^:f.,[j.otherCSsystem-loop,theRHRh "g;pfaysEen LPCI m

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be operable. immediately. : The-.

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? gene'rators-(per Specification operable core. spray loop'.shalli, T

4.9.A.2.a)(are operable.

be demonstrated to be. operable daily until both-loops are l'

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1 returned to normal operation.

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1. M if Specification 3.5.A.1 a or*

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' 3.5.A.2'cannot'be met the reactod shall be placed.in the 3./'# eld Shutdow'n Cendition within

"#ffhours.

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Residual Heat Removal (RHR)

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Residual Heat Removal (RER)

Qg(LPCI and Containment System (LPCI and Containment.

Coo 2hiyode)

Cooling Mode) t >

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Normal Operational Tests

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RHR system testing shall be

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performed as follows:

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Item

. Frequency 1

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,a. The RHR System Ahall be operable:

a. Air test on once/5 years drywell head-j '" )'(1) Prior t'o r83etor startup f

ers and nozzles from a co#1d condition, or and air'or j

water test on d1 (2) When irradiated. fuel is in torus headers y

j the reactor vessel and the

' and nozzles reactor pressure is greater than atmospheric except as i

stated in Specification

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LIMITING CONDITIONS FOR OPERATION :

SURVEILLANCE REQUIREMENTS.

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! ? [3[5,B.1 ; Normal System Availalillity (Cont.)l (4.5.B.1 ! Normal Operations 1xTestsi K y4 1

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Item'

. Frequency" 9:;-

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f donelRHR, loop with two pumpsforitwo b'.j Simulatied

'! Oncl/ Ope rating'. ~

. loops'with;one: pump periloop shallf

' ;Automaticc Cycle

?be operablerin'the1 shutdown cooling.

1::

' Actuation--

, smodeJwhen irradiated. fuel:isiinzthe l Test:

l.re'accor vesseliand,the' reactor-pres-

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i sure)is atmosphesic except prior' to).

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a reactor startup as' stated'in Speci-

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ification 3.5.B.1.'a.

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c..Thereactorsliallnot)bestartedIupi

c.iSystem flow

.Once/3. months; f-withlthe.RHRisystem su' plying.

rate: Each:

j-p coolin'g:to the fuel pool..

RHR' pump...

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=shall deliver _

-d.' During reactor power o'peration, the.

at11 east.7700' t

LPCI system discharge cross-tie ~.

gpm against.a.

W' s

valve', El1-F010,'-shall be'in the system head-of; A

closed' position and:the' associated

-at'least_20 psig.

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valve motor-starter-circuit-

. breaker shall be locked in th'e=

d. Pump. Opera-

~0nce/ month?

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off; position.. In addition,.an~

abilityi

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.nnnunicator which indicates that

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the cross-tie valve is not:in the

e. Motor Oper-

_Once/ month-s fully closed position shall be

.ated valve

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available in.the control room.

operability-

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e. Both' recirculation pump' discharge f.Bothrecirculation'.pumpdischarge\\<..f valves shall be operable prior to

-valves shall be tested for oper -

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-reactor startup' (or closed if per--

ability ' during ; anyioutage exceeding (

'mitted elsewhere in these speci-48 hours, if operability tests have, fications).

not been-performe'd-during the preceding month.

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2.. Operation with Inoperable

2. Surveillance with Inoperable.

Components Components-

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a. One LPCI Pump Inoperable ~

a. One LPCI-Pump Inoperable-

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If one LPCI pump is inoperable,lthe When one LPCI pump 'is ino\\perable-reactor may remain in operation for the remaining LPCI pumps and asso U a period not to exceed seven (7).

ciated flow paths, and_the Core 5

days provie

• that the remaining Spray s'ystem shall be; demonstrated'.

j LPCI pumps, both LPCI subsystem-to be operable immediat ly and O'

. flow, paths,-the Core Spray system, daily thereafter,.until the incper I f

and the associated diesel genera-able LPCI pump is restored to' tors. (per Specification 4.9. A.2.a) l normal service.

are operable.

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.b.'One LPCI Subsystem Inoperable.

b. One LPCI Subsystem Inoper ble i

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= A LPCI subsystem is " considered to When one LPCI subsystem is.inoper-be inoperable.if (1) both of the able,.all-active components of the H LPCI pumps within that-system are remaining LPCI subsystem and the t.

' inoperable;(2) the active <

Core Spray-system shall be. demon '

Zw Lvalves'in'the:sub' system flow path-strated.to be operable,;immediatelyc areiinoperable..

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LIMITING' CONDITIONS FOR OPERATION

--SURVEILLANCE REQUIREMENTS

( ett 365 a'.2. J operation with iknoperable'

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Surveillance with Inoperable

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(Components (Cdntinued)'

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I"foneLUCI:sbbsystemisinoper

andl daily thereaf ter, until the -

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'able, :the ' reactor may - remain in'-

inoperable'LPCI~ subsystem-is' Loperation,for'a period not to'.

restored.to normal': service.

j, exceed seven;.(7)' days provided?

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that all' active' components of the:.

remaining LPCI ' subsystem, th'e : Core'

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Spray.. system,.and the assoc 1ated-

. diesel generators (per-Sp'ecifica-ftion 4.9.A.2.a) are' operable.

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> LIMITING CONDITIONS FOR 0PERATION:

-SURVEILLANCE'REQUIRENENTS N: 3$5&C.3iTwo= Pumps Inoperable.

< 1 5'.'Cl3.-1Two Pumps-Inoperable?

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Ifi two ; RHR1 servicei water: pumps.f are-

'. When ;two. RHR ; service 3 wate r pumps 4

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L inoperable, fthe ( reac to r i may ;re-.

L are ? inoperable, - the l: remaining.

'mainJinioperation<for.a period.

not 'to. exceed seven1(7)(days.: pro-

' operable RHR service water'sub-

systems'shall befdemonstrated-ivided alliredundantfactive com-?

to.befoperable':immediately ~.

ponents.in both ofcthe RHR-r and. daily thereaf ter: for.. seven (7)

. service'waterisubsystems'are' "daysior until the inoperable

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operable.

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components are' returned to normali

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- operation'.-

14.RShutdown Requirements

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'If' Specifications 3.5.C-cannot be met,1the'reactort

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shall be(placed in the Cold' Shut-:

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2down' Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

LD..High Pressure-Coolant' Injection:

'D..HighEPressure Coolant Injection

- (HPCI) System' (HPCI) System:

1.. Normal System Availabilit'y

- 1. Normal Operational Tests HPCI system testing shall be

-performed as.follows*

Itemi Frequency

'a. The HPCI System shall be

a. Simulated Once/ Operating

' operable:

Automatic Cycle

Actuation

-(l') Prior 'to reactor startup Test' from a' cold condit' ion, or-(2)'when irradiated fuel is in the reactor vessel and.the-reactor pressure'is greater-

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than ll3 psig, except as stated in Specification 3.5.D.~2.

b. Flow : rate at Once/3 months normal reactor

. vessel oper-ating pressure and

-Flow rate at Once/ Operating 150 psig.

Cycle reactor pressure 3.5-6 fj, f _

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' LIMITING CONDITIONS FOR 0PERATION

. SURVEILLANCE REQUIREMENTS-

' ' $3.5.G Mini== Core and CodtiainmentI i

3.5.Gh Surveillance of Core and'Contain--

Cooling System Availability :

Lment-Cooling Systems:

During any; period when one Ufa

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When it:is determine'd that one.

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the standby diesel: generators.

.'of the standby diesel-generators j

mis' inoperable, continued l reactor-is. inoperable, all of the'compo-n

= operation is-limited to.-72: hours *

.nentsiin'.the RHR, system LPCI:

R 1unless operability offthe'

' mode and. containment' cooling-

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idiesel'generatortis restored.

mode connected;to the operable.

within this period. :During suchE idiesel. generators.shall.be de-

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'ponents in the RHR' system'LPCI'

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.monstrated to be operable im-72Lhours* all of :the com--

'mediatel'y and daily thereafter..

mode and' containment cooling imodeshall be operable.. If this?

t requirement cannot:be met, an~

orderly shutdown shall_be ini-tiated and the-reactor shall be inithe-Cold Shutdown Condition'-

?within 24' hours. --Specification-f3.9 provides;further. guidance on J'

. electrical' system availability.

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Any combination of inoperable components in the core and con-tainment cooling systems shall not; defeat the capability of~

the remaining operable components to fulfill the core and contain-

ment cooling functions.

When irradiated fuel is.in'the reactor vessel and the reactor is in the Cold-i:

Shutdown Condition, both core spray systems and the.LPCI-and containment

! cooling subsystems of the RHR system 4

i may.be inoperable provided that the shut-

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down cooling subsystem of the RHR system is-operable in accordance with Specification 3.5.B.1.b and that'no work is being done which I,

'has the potential for draining the reactor vessel.

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• Each diesel is allowed to.be out-of-service for 7 days once per year for

. preventive maintenance. - In addition a total of-two 18-day out-of-service intervals-are allowed per' year:for major repairs of-the Plant Hatch emer-fgency diesel-generators.

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-LIMITING > CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 1/4._ H. Maintenance of-Filled Dis' charge.

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Maintenance of-Filled Discharge ~

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Pipes Pipes Whenever the core. spray system,

' The ;following surveillance re-

.LPCI,'HPCI, or RCIC are required

-quirements shall be performed-to be operable.the~ discharge pip--

to assure that the discharge ling fromethe pump > discharge of_these:

-piping'of the core spray;sys-systems to the'last block valve

. tem, LPCI, HPCI,fand RCIC areL shall be filled.- The suction of the filled when-. required:

HPCI pumps'shall_be aligned to the condensate storage tank.

1.

Every month prior to the testing of the IPCI avd-core spray _ systems,.the dis-charge piping of these systems shall be vented.

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LIMITING. CONDITIONS'FO?COPERATION

-SURVEILLANCE REQUIREMENTS *--

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j335JUPlant-serv [ce' Water? System

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' jl'.'?NormalAvailabilit'yi i1EThe: automatic pump starti

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jfunctionsand,automatiez i

.,s eThel reactor shallinot be-

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? isolation functions'shalli J

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j; 1be' tested once..per' operating-

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- aade criticalx from1the - -

3.,

_t yy Uc'old shutdown condition}

cycle.~.

T' tunless the: Plant! Service.

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<aWaterl System!(includingl4l plantiservice. water l pumps:

andithe.standbyJservicei

.-wateri pump), is operable.'.

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d.iInoperable Componenti'

-2. Inoperable Componentis -

a. The'stan'dby service-water-a.1With.the: standby; service' pump ;may be inoperable for.

water? subsystem _ inoperable:

a 'perio.d :not c to exceed' 60 :

tfor-up to?60 days,?providec

days provided that;an alter-

Unit-1 service water, cooling.

lnate Unit-1 plant service {

to the IB diesel?generatori

' water _ cooling source to the

~.by_ verifying.0PERABILITY offan

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IB diesel? generator is falternate' Unit.l' service' water" OPERABLE.'

cooling source lwithin:;8: hours.-

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Otherwise,' declare 1the~1B diesel generator inoperable'.-_ '

and take.the action required ^

by Specification 3.9.B.2.

b. Oite PSW pump may-be in -

b. When one PSW pump ~is made Loperable for a period not or,found to be-: inoperable, to~ exceed 30 days provided the sta'ndby service water all diesel generators are pump, the three. remaining'.

operable.per Specification' PSW pumps, and both'PSW 4.9.A.2.a.

divisions shall be-demon-strated_to-be operable immediately and weekly

.thereafter.

c. One PSW pump and the stand-

c. When one PSW pump and the

' by service water pump may standby' service' water pump be inoperable for a period are.nade or found to be-not to exceed 30 days pro-inoperable, the three re-vided all diesel generators maining PSW pumps, and both are operable'per Specification PSW divisions shall be'

'4.9.A.2.a.

demonstrated to be operable immediately and weekly thereafter.

id. Two;PSW pumps or one PSW

d. When two PSW pumps or'one-PSW

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division may be inoperable for division are made or found to_

a period not to exceed 7 days.

..be inoperable the standby

provided the diesel generators service water pump and all

. associated with the operable

-active components of the-

-PSW components are operable

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operable' division or divi-per Specification,4.9.A.~2.a.

sions shall-be demonstrated ~ ;l to be operable immediately and daily thereafter.

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' LIMITING CONDITIONScFOR OPERATION' SURVEILLANCF RFOUTREMENTR

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D i3.'SiJC P'lant Service Water System'

4.5.J lPlant Service Water? System-4 i.

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l2 Inoperable ~~ Components (Cont'd)'

2.)InoperableComponents[(Cont'd)

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,._e.ITwo:PSW[pumpsf.orone.PWS.l r

v.e. When two PSWfpumps'or one~

] division fand the; standby __;

,PSWidivision,' and.the:

s iservicefwater. pump maycbe:in.

-standby: service water pump ~

4 x; operable for aLperiod'not tot 1are made;or found'to;bei i f exceedi7/ daysi provided ~ the --

inoperable,sall activej,

'idieseltgenerators? associated" '

' components.of.the.operableg-a

' division or' divisions shall l;.

-withithefoperable PSW,com i Eponents;areLoperable pers

- bei demonstrated - to' be

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Specification: 4.9.' A.2.'a.~.

operable immediately.and::

Ddaily thereafter.;

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-Foreachcondi$ ion:above"in"which'

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.the. standby (service: water pump?is inoperable,' cooling water:tondiecel-s generator 1BLshall befintertied'

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zwith the PSW divisional! piping: supply.

EWhen! cooling water:to. diesel- _

J3.' Shutdown Requirements

generator _1B is'intertied L5 with the PSW divisional s.

If the requirements of Specifications'

- pipingisupply,'ioperability

!3.5.~J.1-'and 3.5.J.2 cannot be met of the divisional interlock ~ -

.the reactor shall be"pla'ced in the

' valves shall1be' demonstrated.'

i cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.5.K Equipment Area Coolers

4.5.K: Equipment Area Coolers :

L 1.-The equipment area coolers 1.lEach equipment area coo'ler-

~

serving the Reactor Core: Iso-is operated in conjunction lation CoolingD(RCIC), High with the equipment served by Pressure Coolant Injection that'particular. cooler;:

-(HPCI), Core Spray =or Residual therefore,fthe equipment' area'

~

Heat Removal (RHR) pumps must coolers are tested at the

.be-operable at all times when same - freque'ncy.- as i the pumps the pump or pumps served by which they serve.

that. specific cooler-is cona

-sidered'to be operable.

2. When an equipment area cooler is not operable, the pump (s) served by that' cooler must be

' considered inoperable for Technical Specification'pu' poses.

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. BASES POR' LIMITING' CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS:

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'3.5C CORE AND' CONTAINMENT' COOLING SYSTEMS

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f A. ' - Core ' Spray ~ '(CS) c System tle yNormal' System' Availability Analysespresented;inSection'6~ofths'FSARand)AppendixI'of-theHNP-2 PSAR ' demonstrated that ' the ; core spray ; system fprovides 1 adequate l cooling toi the: core-to dissipate?the energy; associated with the loss-of-coolanti 0

faccident an'd to limit fuel clad temperature to'below.2,300 F which~ assures'

that core geometry remains' intact ?and'to limit-any clad.retal-water: reaction :

~

to less - than one' percenti: Core spray distribution has been shown in tests -

i of systems similar in design to HNP-1 t.o ' exceed the minimum requirements..

'In' addition,1 ccoling effectiveness has been-demonstrated at less than half ~

the rated flow-in simulated' fuel-assemblies with heater, rods to duplicate-the decay heat' characteristics.of' irradiated fuel.

Thecintent of the CS. system specifications is. to prevent operation above atmospheric pressure-without'all associated equipment being operable.

However,'during' operation, certainLeomponents may.be out of service:for.

,7

-the-specified; allowable repair times. LTh'e allowable repair times _have

been selected using engineering judgment based: on experiences and supported by. availability analysis. Assurance of the availability of the remaining systems.is increased by demonstrating operability immediately and by requiring selected testing during the outage period.

When.the reactor. vessel pressure is atmospheric, the limiting conditions

-for operation are less. restrictive.. At atmospheric pressure,-the minimum

. requirement is for one supply of makeup water to the core.1.Requ' iring two-operable'RHR pumps -and one 'CS pump provides redundancy to-ensure makeup water. availability.

2.

Operation with Inoperable Components.

Should one core spray' loop become inoperable:. the remaining core spray loop and the RHR system are demonstrated to be operable to ensure their

]

availability should the need for' core cooling arise. These provide-extensive margin over the operable equipment needed for adequate core cooling. With due regard for this margin, the allowable. repair time.

of 7 days was chosen.

B.

Residual Heat' Removal (RHR)' System-(LPCI and Containment Cooling Mode) 1.

Normal Systen Availability The-RHR system LPCI mode is designed to provide-emergency cooling to the core by flooding in the event of;a loss-of-coolant-accident.- This system

-is completely. independent of the-core spray system; however, it does-function in combination'with the core spray system to prevent excessive

' fuel clad temperatures. The LPCI node of the RHR system and the core spray

=

i system provide adequate cooling for break areas-of approximately 0.2 square-feet up to and including the_ double-ended recirculation line break j

.without-assistance from the high-pressure emergency core cooling systems.

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.3.5.B.l. :N$rmal' System Ava'ilability-(Continuedl Observa' tion of-the sta'te'd requirementsIfor the containment _ cooling. mode

' assures that the' suppression pool and,the drywell will be-sufficiently cooled? following a loss-of-coolant-- accident,1 to prevent primary contain 1 Lment overpressurization. The containment cooling. function of-the RHR system is~ permitted only'after.the core has reflooded to the two-thirds; core height level. :This prevents inadvertently divertin'g water needed

.for_ core flooding to the less urgent: task'of_ containment. cooling. The two-thirdsicore height-level interlock ^may be manually bypassed by a.

~keylock switch.

The intent-of the RHRLsystem specifications is-to prevent operation above atmospheric pressure without all associated equipment being.oper-able. However, ' during operation',' _certain components may be out of service for the specified allowable: repair times.~

The allowable repair-times have=been selected using engineering judgment; based on experiences and supported by. availability analysis.- Assurance of.the' availability-of the~ remaining systems'is increased by_ demonstrating _ operability immediately and by requiring selected testing during the outage period.

When the reactor vessel pressure is atmospherie, the limiting conditions for operation are less restrictive. At atmospheric pressure, the minimum requirement is for one supply of makeup water to the core.

2.

Operation with Inoperable Components-With one LPCI pump inoperable or one LPCI subsystem inoperable,fadequate core flooding is assured by the demonstrated _ operability of the redundant-LPCI pumps and LPCI subsystem,' and the Core Spray system. 'The. reduced redundancy justifies the specified 7 day out-of-service period.

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LIMITING--CONDITIONS'FOR OPERATION v

SURVEILLANCE. REQUIREMENTS:

4 1 9 7 UXIblARY ELECTRICAL?SYSTEMSc.

'4. 9 VAUXILIARYhLECTRICALSYSTEMS'~

LApplic'abilityJ Npplicability:

1The - Liniitinig' Conditions"for1 The'Surveillancelkequirementsapply-IOperationappik;to thesauxilia'ryi

? to?the: periodic' testing requires 1 electrical.powerfsys'tems.

J ments.oflthe; auxiliary electrical-

power systems.,

afbbjecthe Objective-4

.. 2..

m a.

(The objective offthe; Limiting

-The dbjectivejof the'. Surveillance (Conditions for Operation;is toL

,Requirementsfis:to verify the-

~

~ :assureTan_adeq'uate supplyJof'

' operability of thelauxiliary

electricalEpower for(operation of.

electricalcsystems.

.those'. systems required for safety.

~

. Specifications

~ Specifications --

s u.

.A-lRe'quirements For Reactor-

A. IAuxiliary Electrical Systems Startup

Equipment-

-The reactor shall:not be made Tests shall be performed at!schSd-critical from.the Cold' Shutdown

~ uled. intervals as follows.to'de--

-Condition unless-alliof the fol-

~tect' deterioration of equipment lowing conditions are satisfied:

and to: demonstrate that auxiliary electrical =systemsiequipment and; components.are operable.

1. Offsite Power Sources

1. Offsite Power Sources At least two 230 kV:offsite-trans-Verify correct breaker mission lines shall be available alignments and indicated. power and each shall be capable'of availability at least once supplying auxiliary power to the per-7 days.

emergency 4160 volt buses (lE, IF,-and.lG) and each shall be capable of_ supplying power to both startup auxiliary trans-formers (IC and ID).

2. Standby AC Power Supply (Diesel 2.-Standby AC Power Supply-(Diesel Generators IA, IB, and lC)

Generators lA, IB, and IC)

Three diesel: generators 1A, IB The following periodic tests and

~

and IC) shall be operable and-surveillance of the standby AC l capable of supplying power to power supply _- (Diesel Generators -

,the emergency 4160 volt buses lA, IB, and IC) shall be per-(lE, 1F,'and 1G).

formed:

J For each diesel generator to be -

operable and capable of.sup-plying power,-the.following conditionstmust be met:

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SURVEILLANCE REQUIREMENTS-oLIMITING CONDITIONS FOR OPERATION c-

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gi3.9fA.22Standb[ACPower'SupplyU(Diese12

?439.A.2i Standby'ACiPower Supply'(DieselE.

J. Generators :(1A,11B,- and IC) =

Generators IA,c 1B, and IC) -

s l(Continued);

-(Continued) 1 4'e ea.' Operability; la.10perability The: diesel generatorLitselfJand' JEach diesel generator sh'll:

a

-its auxiliaries are operable.:

The; manually. started and.

loaded.to: demonstrate'operationali b'.lDiesel' Battery (125 Volt)

! frequency.specified;in1 able.

Jreadiness-in'accordance'with ths 4

Leach 125 volt diesel battery T

s cis' operable and capable of:

'4.9-1 on"a-staggered. test' basis.

~ supplying the required load.-

Verify that each' diesel. starts ifrom ambient' condition and lc. Battery Charger

-accelerates to' synchronous speed

.An operable battery charger is

in < 12_ seconds,lis. loaded >;

.available. Each: battery, charger.

1710.kw;in i 5 minutes,;and-

~

.shall have adequate capacity to operates for 3 60 minutes.

~

. restore its battery to full-1During the~ generator test,xthe

~

charge.within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from~a starting air. compressor _shall:

-discharged condition while~

be checked for' operation'and

carrying ths DC load.

^for its ability to recharge the:

. air, system.

Ed.- Diesel Fuelf There shall be a minimum of

b. Diesel ~Batteryt(125-Volt)'

E

'80,000 gallons of. acceptable-Each 125 volt diesel battery _

diesel fuel inLthe diesel shall be' subjected to 'the -

fuel storage tanks.

same periodic surveillance as -

theiplant-batteries in Speci-fication 4.9.A.3..

c. Battery Charger

' Indicators shall be provided.

~

to monitor the status of thA battery charger supply.

.This instrumentation shall' include indication ~of. output.

-current'and output. voltage.

d. Diesel. Fuel:

Each month the quantity'of diesel fuel available in each fuel storage. tank shall be measured and recorded.

At least once per 92 days by verifying that-a sample of.

diesel fuel from the-fuel-storage tank,_obtained;in i-accordance.with ASTM-D-270-65, is within the' acceptable' limits specified in Table-1 of ASTM D975-74 wh'en checked.

for viscosity,' water and >

sediment..

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-LIMITING CONDITIONS IM OPERATION

--SURVEILLANCE REQUIREMENTS-24.9.A.20 Standby:AC Power ~ Supply-(Dieseli

' Generators IA,-IB -~and IC).

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T-1(Continued)-

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.4 ie ! Fuel Oil Transfer Pumps ~

~

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4^

-: The. operation ' o f the. diesel 1

ifuel oil transfer pumps shall;

.be demonstrated once each month.'

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e LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS' L 3. 9.B.1~.

-One Startup--Auxiliary' Transformer.

4.9.B.1.

_One'Startup Auxiliary Transformer

-(IC'or 1D) Inoperable or Only One (lC or 1D) Inoperable or Only One Offsite Power Source Available Offsite Power Source Available (230 kV Transmission Line)

(230 kV Transmission Line)

Reactor operation'is permissible When it is-established that one for seven days from the date that startup auxiliary transformer one-startup auxiliary transformer-

.(IC or ID) is inoperable or in-(IC cnr ID) is inoperable or in-coming power is available from

coming power is 'available :from only one 230 kV offsite trans-only one'230 kV offsite trans-

mission line, verify correct breaker mission line provided tha in-alignments and indicated power creased' Surveillance Require-availability within one hour.and ments as stated in Specification at least once per eight hours there-4.9.B.1 are implemented, after, and perform Surveillance Requirements 4.9.A.2.a within 24 2.

One Diesel Generator (IA, IB, hours unless surveillance has been or IC) Inoperable performed within the previous seven days.

From and after the date that one of_the diesel. generators is made 2.-

One Diesel Generator (IA, IB,

.or found-to be inoperable, continued or IC)-Inoperable reactor operation is permissible in accordance with Specification 3.5.G When it is established that one for a period-not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

• l diesel generator (IA, IB, or lC) provided that two 230 kV offsite is inoperable,' verify correct breaker transmission lines are available, alignments and indicated power both remaining diesel generators availability within one hour and and-associated emergency _ buses are at least once per eight hours there-operable, and the increased af ter, and perform Surve'111ance Surveillance Requirements as stated Requirement 4.9.A.2.a'within-24 in Specification 4.9.B.2 are hours.

implemented.

3.

One 125/250 Volt DC Power System 3.

One 125/250 Volt DC Power System (Plant Battery 1A or IB) Inoper-(Plant Battery 1A or IB) Inoper-able able When it is established that one of From and after the date that one the 125/250 volt DC power systems of the two 125/250 volt plant bat-(plant battery 1A or IB) is made reries is made or found to be in-or found to be inoperable, the operable, continued reactor oper-pilot cell voltage and specific action is permissible during the gravity and the overall battery succeeding seven (7) days within voltage of the operable plant bat-electrical safety considerations, tery shall be tested daily and de-provided repair work is initiated termined to be satisfactory.

immediately to return the failed component to an operable state, Specification 3.5.G is satisfied,

.*Each diesel is allowed to be out ofoservice for 7 days once per year for preventive l

maintenance. In addition a total of two 13-day out-of-service intervals are allow-ed per year for major repairs of the Plant Hatch ~ emergency diesel generators.

3.9-5 m

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t Table 4.9-1 DIESEL CENERATOR TEST SCHEDULE Number of Failures In Last 100 Valid Tests

• Test Frequency

.<2 At least once'per 14 days

>3 At least once per 7 days

• Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Re'rision 1, August 1977, except that the last 100 tests are determine.d on a per diesel basis.

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' ADMINISTRATIVE CONTROLS-u ANNUAL' REPORTS (Continued)~-

= 6.9.1.5 : Reports' required on an annual basis shall include:

a..

-A tabulation on' an annual basis of the number of -atation, utility-and other personnel, including. contractors, receiving exposures greater than 100. mrem /yr and their associated man rem exposure 1

.according to work and job functions,2 e.g.,

reactor operations and surveillance,' ins'rvice' inspection' routine maintenance, special e

maintenance-(describe maintenance),' waste processing,;,and refueling.

The dose assignment to.various' duty functions may be estimates

'ba' sed on pocketidosimeter, TLD, or film badge measurements.. Seall exposures totalling less than 20% of the individual total" dose need L

not be. accounted for..In the aggregate,' at-least 80% of the' total.

whole body dose received.from externa 1' sources shall be assigned-to specific; major work ~ functions.

b.' ' Documentation of all' challenges to safety / relief valves.

- c.

A diesel generator data report which provides the number of. valid '

tests and the number of failures _to start on demand (upon a valid start signal) for each diesel generator.

d.

Any.other unit unique reports required on an annual basis.-

i MONTHLY OPERATING REPORT

(

6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the Regional Office, of Inspection and Enforcement no-l later than the 15th of each month following the calendar month covered by the report.

l REPORTABLE OCCURENCES 1

6. 9.1. 7.

The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9-below, including corrective actions and measures to prevent recurrence.-

shall be reported to the NRC. Supplemental. reports shall be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

2This tabulation supplements the requirements of 8 20.407 of 10 CFR Part 20.

l l

j HATCH - UNIT.1 6-15

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NRC DOCKET 50-366 0PERATING LICENSE NPF-5 s

EDWIN I. HATCH NUCLEAR PLANT-UNIT 2-PROPOSED CHANGES TO' TECHNICAL-SPECIFICATIONS The proposed changes ~to the Technical Specifications:(Appen' dix A.to

Operating License NPF-5)'would be incorporated.as follows:

-Re'ove Page Insert Page m

3/4 8-1.

3/4 8-1 3/4 8-2.

.3/4 8-2 3/4 843 3/4.8-3 3/4 8-3a 3/4'8-5 3/4 8-5 3/4.8-7 3/4 8-7 3/4 8-8.

3/4 8-8 6-14 6-14 9

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3/4.8' ELECTRICAL. POWER SYSTEMS-3/4!8.'1 A.C. SOURCES A.C.-SOURCES-OPERATING 1

' LIMITING CONDITION-FOR OPERATION I

~

3.8.1.1 As a minimum, the follow' ng A.C. electrical. power sources shall i

be OPERABLE:

a.'

Two physically' independent circu'its between the offsite trans-mission network and the onsite Class 1E distribution' system,.

and' b.

Three separate and independent diesel generators, each with:

1.

A separate' day tank containing a minimum of 900 gallons of fuel,

2. =A separate fuel storage tank containing a minimum of 32,000 gallons of = fuel, and 3.- A separate fuel transfer pump.

APPLICABILITY: CONDITIONS 1, 2, and 3.

ACTION:

a.

With one offsite circuit of the above required A.C. electrical-power sources inoperable,- demonstrate the OPERABILITY of the remaining offsite A.C. source by performing Surveillance Require-ment 4.8.1.1.1.a within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, and performing Surveillance Requirement 4.8.1.1.2.a.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless surveillance has been performed within the previous 7 days. -Restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

With one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> there-after, and by performing Surveillance Requirement 4.8.1.1.2.a.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Restore at least three diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

• or be in at'least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• Each diesel is allowed to be out of service for 7 days once per year for

~

preventive maintenance.

In addition a total of two 18-day out-of-service intervals are allowed per year for major repairs of the Plant Hatch emer-1 gency-diesel generators.

j HATCH ' UNIT 2 3/4 8-1 o

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ELECTRICAL ~ POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued) c.

With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate

.the OPERABILITY of the remaining A.C. sources by performing-Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, and by performing Surveillance Requirement 4.8.1.1.2.a.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Restore at least one of the in-operable sources to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Restore the other AC power source (offsite circuit or diesel generator set) to operable status in accordance with the provisions of Section 3.8.1.1 Action State-ments a or b, as appropriate from the time of initial loss.

d.

With two of the above required offsite A.C. circuits inoper-able, demonstrate the OPERABILITY of three diesel generators by perfonning Surveillance Requirement 4.8.1.1.2.a.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, unless the diesel generators are already operating; restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN with the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. With only one offsite source re-stored, restore the remaining offsite circuit to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the time of initial loss or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

e.

With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by perfonning ~ Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, and by perfonn-ing Surveillance Requirement 4.8.1.1.2.a.4 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Restore at least one of the inoperable diesel generators to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore three diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

• from time of initial loss or be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• Each diesel is allowed to be out of service for 7 days once per year for preventive maintenance.

In addition a total of two 18-day out-of-service intervals are allowed per year for major repairs of the Plant Hatch emer-gency diesel generators.

i l

HATCH - Unit 2 3/4 8-2

. ~.,

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zo ELECTRICAL: POWER -SYSTEMS 2

~

SURVEILLANCE REQUIREMENTS

~

4;8.1;1.11 Each of the above required. independent circuits: between. the-

+

1 offsite: transmission ' network and. the onsite' Class IE Ldistrib' tion.

u system shall be:

Detemine' : OPERABLE at11 east-once1perL 7 days' by verifying d

,ai correct breaker alignments and indicated power availability,;

and-b.

. Demonstrated OPERABLE at :least once:per 18 months during shutdown by. transferring, manually and automatically, unit-power supply from the nomal circuit to the alternate circuit.

r 4.8.1.1.2 = Each diesel generator shall be demonstrated-OPERABLE:

~

a.

In accordance with the frequency specified in' Table-4'.8.1.1.2-1 on a STAGGERED TEST BASIS by: '.

1.

Verifying the fuel level. in the day fuel tanks.

~

)

2.

Verifying the fuel level in the plant fuel storage tank.

3.

Verifying the fuel transfer' pump can be. started and transfers fuel from _the-storage system to the day tank.

4.

Verifying the diesel starts. from ambient condition and' accelerates to synchronous speed in < 12 seconds, is loaded.

> 2674 kw for diesel generators 2A,3 2360. kw for diesel 4

' generator IB, and 2 2742 kw for diesel generator.2C in <

5 minutes, and operates for y_60 minutes thereafter.

5.

Verifying the diesel generator is aligned to provide l

J standby power to the associated emergency busses.

i 6.

Verifying the pressure in both diesel air start receivers l

to be 2 225 psig.

I b.

.~At least once per 92 days by verifying that'a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment.

i 1

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ELECTRICAL POWER SYSTEMS =

SURVEILLANCE REQUIREMENTS (Continued) c.

- At least once per 18 months during shutdown' by:

1. _ Subjecting the ' diesel to an inspection in accordance 'with

- procedures prepared in conjunction with,its manufacturer's recommendations for this_ class ~ of standby service.

2.

Verifying that the automatic load sequence timer is OPERABLE with the interval between each load block within 110% of_-its design interval.

3.. Verifying the-generator capability to. reject a load of

> 798 kw while maintaining voltage at 4160 1 400 volts'and frequency _at 60 1 2 Hz.

1 HATCH - UNIT 2 3/4 8-3a

5 l

.l ELEC'TRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 9.

Verifying the diesel generator operates for at least'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Durir.J the first-22 hours-of this test, the diesel generator shall beLloaded > 2764 KW for diesel generator 2A, > 2360 KW for diesel generator IB and > 2742 KW for diese!- generator 2C.and during _ the remaining 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of-this test, the diesel generator shall.be. loaded > 2950 KW for diesel generator 2A, > 2547 KW for diesel generator 1B and > 2928 KW for diesel generator 2C. Within 5 minutes after completing this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test, repeat Specification 4.8.1.1.2.c.5.

'10.. Verifying that the auto-connected. loads to each diesel generator do' not exceed the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of 3135 kw.

~

~

11. Verifying the diesel generator's capability toi a) Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power,-

b) Transfer its loads to the offsite power source, and c) Proceed through its shutdown sequence.

12. Verifying that with the diesel generator operating in a test mode (connected to its bus), a simulated safety injection signal overrides the test mode by (1) returning the diesel generator to' standby operation and (2) auto-matically energizes the emergency loads with offsite -

power.

13. Verifying that the fuel transfer pump transfers fuel from each fuel storage tank to the day tank of each diesel via the installed cross connection lines.

d.

At least once per 5 years by verifying that with both air start receivers pressurized to 1 225 psig and the compressors secured, the diesel generator starts at least 5 times from ambient conditions and accelerates to synchronous speed in 1 12 seconds.

e.

At least once per 10 years or after any modifications which l

could affect diesel generator interdependence by starting both diesel generators simultaneously, during shutdown, and verifying that both diesel generators accelerate to synchronous speed in 1 12 seconds.

j HATCH - UNIT 2 3/4 8-5

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s ELECTRICAL POWER SYSTEMS

'M SURVEILLANCE REQUIREMENTS (Continued)'

2'

'4 8 1;1 4? R ports,-. SeelSpecification 6.921.5.c.-

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5 HATCH - UNIT 2 3/4 8-7

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' TABLE 4.8.1.1.2-1 DIESEL GENERATOR' TEST SCHEDULE Number of Failures In-Last 100 Valid Tests *-

Test-Frequency l

1 2 At least once per 14 days

>3 At least once per 7 days i

o I

• Criteria for determining number of failures and number of valid tests shall be-in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1, August 1977, except that the last 100 tests are determined on a per diesel basis.

HATCH - UNIT 2 3/4 8-8 N.

n ADMINISTRATIVE ~ CONTROLS ANNUAL REPORTS (Continued) 6.9.1.5. Reports required on an annual basis shall include:;

a.

A tabulation on.an annual basis of the number of station, utility.

and.other personnel,' including contractors, receiving exposures

. greater than 100 mrem /yr and their associated man rem exposure according to work and job functions,Z e.g., reactor operations and. surveillance, inservice inspection routine maintenance, special maintenance '(describe maintenance), waste processing, and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD,. or film badge ~ measurements. Small exposures totalling less than 20% of the individual total dose need.

not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b.

Documentation of all challenges to safety / relief valves.

c.-

A diesel generator data report which provides the number of valid tests and the number of failures to start on demand (upon a valid start signal) for each diesel generator.

d.

Any other unit unique reports required on an annual basis.

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U. S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the Regional Office, of Inspection and Enforcement no later than the 15th of each month following the calendar month covered by the report.

REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports shall be required to fully describe final resolution of occurrence.

In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

2This tabulation supplements the requirements of j 20.407 of 10 CFR Part 20.

HATCH - UNIT 2 6-14

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ATTAOMiNP 2 SAFETY EVAIDATION PCR PRDIOSED OIANGES 'IO 'ITE

'IEONICAL SPECIFICATIONS e

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= EDfIN I., HA3OI NUC[ EAR IGNT-UNIUS 1 AND ~2 A

SAFETY EVALUATION FOR-EMERENCY IGIER SYSTEMS y

TEGINICAL' SPECIFICATION OIANGE II. -_

fBAGGROUtO:

~

. The -Hatch 1 and 2 Technical -Specifications; contain Limiting ~ Oonditions for ; Operation 1 and Surveillance Req 11rements '. to - maintain diesel'

generator. operability._

Georgia. Power Conpany ~ 'and the ' diesel.

marufacturer : -(Colt o. Irxinstries) have determined that.some ; technical' specification regiirements are not beneficial.-to the. performance-of the-i' onsite emergency, power system. --Thereforei the proposed changes to the

' technical specifications -(Attachment 1) provide inprovements which we-believe will enhance the reliability of the diesel generators.

II.

REFERENOS:

o

' Hatch 1 Technical: Specificationsi 3.5/4.5, ~" Core. and~ Containment Cooling Systems"; 3.9/4.9i "Aixiliary Electrical Systems"; and 6.9, " Administrative (bntrols."

i-j o

Hatch 1 FSAR Section 8.4, : " Standby AC Power alpply"; 6.4.3, " Core Spray System"; 6.4.4, "Iow-Pressure Coolant Injection"; 10.6, "RHR Servi Water System"; and 10.7, " Plant Service Water System."

c' Hatch 2 Technical Specifications 3/4.8.1,_ "AC Sources-Operating,"

and 6.9, " Administrative Controls."-

+

o Hatch 2 ESAR Section 8.3, "Onsite Power System"; ' 6.3, - "Dnergency j

Core Cooling System"; 9.2, " Water System."

o Regulatory Giide 1.108, Revision 1, Aic32st 1977i " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at 4

N2 clear Ibwer Plants."

l o

NRC Generic Ietter 84-15, ally 2,1984.

o Title 10, Chapter 1, Oode of Federal Regulations, Part 50.73, j

" Licensee Event Report System," September 30, 1983.

l

-III.

BASES:~

i The Hatch 1 and 2 Technical Specifications recuire that a mininum of two offsite PC electrical power sources and three onsite diesel-l i

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.w generator] AC.electribal powerisources) be operable. ; Hatch :1l'Itchr$1 cal 7

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' Specification f 4.9. A.2.a freq1 ires - that.: each diesel; generator :. be tested

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inonthly.:, Hatch 21 Technical; Specification '4.8.1.1.2.a l implements ' the -

,o

testing sched11e given :in : Regulatory 1G11 deal.1081for routine periodic alrveillance ttesting of the diesel ~ generators. ; Regulatory : Glide. l.108

. relatesi the Lfreutency of L testing / to.. the mmber L of test failures 1 on ; a -

+

. per melear _ unit basis',' i.e. failures totaled framiall three diesels.

' 'Ite i test. intervals < vary in four - steps proceeding from ! 31E days, to 14

. days,. to 7 days,1 and ; finally as; freolent' as ' 3 days. depending on the

~

mmber of test-failures experienced.

Georgia - Ibwer Otn@any proposes a different tost - sched11e ; for - Hatchil'

~

(Refere'a e proposed alrveillance Reglirement 4.9.A.2.a) - and : Hatch 2'

(Reference proposed - Sirveillance Req 11rement 4.8.1.1.2.a).using he

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general-criteria - given inLReg21atory G2ide : 1108 with the' excepti6n.-

~

that ' routine testing' be ~ cond1cted at intervals of 14.~ days and - 7 days' only. 'Ite. diesel mamfacturer has' notified Georgia Power that. a.31 day

'4 test freglency isl too tJlong ' to - provide : reasonable : assurance 1of.' the 7 f' '

diesels capability-to ' start l and provide ' emergency power, = and '- thatr -

. reolenth p

. testing every'three days on a routine'~ basis is too freglent.

~

enhanc'e : the' b i-testing. accelerates wear. to the diesels,1 and.will, not N-thati reliability of the. diesels.. Also, it-is cur; engineering judgements al three-day test interval may generate ~ conditions adverse - to sicing-term

+

reliability of the diesels.'

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% e. proposed ' test sched11e. continues = to dapend.upon test. failure experience hit on a per diesel: basis rather than on a per mclear slait Ite test schedile shculd not reflect the idea' that--failurse basis.

i experienced on a particular diesel --would ' adversely Jaffect :;thsh, performance of the other diesels.

However, the test - schedile 'should '

4 reflect individ1al diesel : generator. reliability. - %erefore, -failures on one diesel should not force increased testirxf of _the other diesels. -

L l

%is change is also alpported by NRC Generic Ietter 84-15.

~

%e proposed changes to the Hatch 1 Technical Specifications 1_ Reference j;'

1:

ms 3:

proposed Sirveillance Reolirements 4.5.A.2,

4. 5.B. 2.',

4.5.C.3, and j

4.5.J.2) also eliminate diesel generator testing when certain emergency core cooling systems (ECOS, i.e., Core Spray, and Low Presaire Coolant i

Injection,) and essential service water systems - (Plant Service ' Nater j'

and RHR Service Water) are declared inoperable. Similar to the reasons i

discussed above, regarding the realirements of Regulatory Glide 1.108, W

failures experienced in the ECG and RHR service water systems wRl not e

adversely affect the performance of the diesel generators. Failure of b.

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~a' diisikonLof Plant Service' Water willicanse.'only1the dieseliassociated a 4 1withsitat division; to be-declared inoperable..

Therefore, ; increased.

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>Js testing 'of Ethe diesel generators under. suchicircumstances: shcx11d not be n

Mb Mrecalireddfiso,Jthis proposed changefis consistent.with the philosophy; 7

f 'of Standnd Technical; Specifications, including Hatch 2, whichi doinot.

1 R recuire / additional, testing: of the(diesel generators when other safety E

f related systegs are declared -inoperable ;and' Generic Ietter 15 which -

encourages licensees to i delete 2 thia; recazirementi to ' avoid. excessive L 7

testing of theidi~sels4 e

p mreqNcf ; the' procosed testin[ recuirements1 for ; thej diesel generators p

[

desciibed above represent a more frecalent routine; testing interval than -

I

' carrentlyL.~ exists 1 :in J the JHatch 1 - Technical Specifications. '(14/7.-day l, 4,

'versus gonthly),7and conseniently,; justifies the ramoval' of the diesel:

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generat d testihg 4reazirements : associated with ;EOCS and; essentialf

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.servim water inoperability. -

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gitch 2 Techtlical Specification 3.8.1.1, Action : Statement : a., - recalires -

~ ' cthat every - dilesel bei tested within ' one : hour ' and every eight hours ~-

(

"f tEEreafter in the event-an. emergency AC source or offsite power source

~

, i is ' declared _ -inoperable..

To be consistent : with" the' philosophy of 4-C recticing excessive testing and '.thereby enhancing the reliability of the

- diesel lgeneratoff, Georgia Power proposes that! when ;an. emergency. AC

- sairce is declared inoperziale, the remaining diesels: be -demonstrated operable within L 24_ bcurs.

Any additional testing shouldnnot be reglired.

Diesel testing iwithin the 'first 24 ' hours will provide assurance that no starting problems-exist - with 1 the Ediesels and will

/

A provide ;additichalutime for, inspection ' prior to' the test. - A L 24 bcur v interval wi31 also eliminate abusive niick diesel-startups and-stops that 'are pgesnntly recazired to test all of - them within one hour. Such testing is atusive tof the diesel generators since they should each be operated for at least one hair when started.. For tte specific case when one of the offsite emergency scurces is declared ; inoperable, diesel-fa'ilure is not -involved.

7terefore,. demonstration of their s q operability should not be req 11 red.if they -have been successfully

- () tested within. the past.seven days under. routine airveillance.- This again will rech ce the potential for excessive testing.- Moreover,

, In.tle or ao addi' clonal reliability assurance is gained from, increasing

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testing Gjond?that realired for routine surveillance.-

Also this

's proposed change is consistent with the Technical-Specifications given in Generic Ietter 84-15.

i 1

To acc w.adate ithe reccamendations described above, the proposed changeT (o Hatch 2 Technical Specification 3.8.1.1 separate existing j

Actpn Statement a. into two new Action Statements, a. and b.

Also, i

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existing ; Action

• Statementsf b.,y c.,1 and yd. : are 1 changed ' to,7 Statements c., d.,(andje. ' in :the proposed ' changes, "and are modified ; toj; lbeJ consistenttwith ithe : reelirements ;of ? proposed ! Action -Statements ' aJDr t;a

and b.. LIn = addition,c proposed ? Action { Statement e. changed the; allowable 4

?

@"V dieselsf to operable : status.yTwo hairs doesinot allow enough; time ~ to;

. ;)I time ?- frczn 72 z hours : to /24 rars yto a restorek one of :the-two i inoperable s

~

. troubleshoot a problem to determinee thei causie.of inoperability.r A two 2

hour ? limiting condition for ! operation may - resultiin.: emergency repairs :

~

~

which1may Knot i restore 9 full J reliability to i tha. diesel'.1 In ) addition,;

. existing - Action ^Statementl c. - ~ allows 24 ; bcurs ^: to 1 restore L:one of J twoD

. inoperable offsite power circuitsL (preferred : source of: emergency power)!

y to L operable' status. - 1herefore,: the; diesels should :have the f same IID realir'ement'as allowed for offsite power.

-7te: Hatch li Technical-(Specifications similarly: contain ~ additional.

diese11 generator testing; realirements;when an: offsite' power source or t

. diesel:. generator.isn declared,' inoperable.-

l(Reference Surveillance.

2 b

- Paglirements ~4.9.B.1 and "4.9.B;2.L 17herefore,. Georgia LIbwer reatests :

~

s

' thatt the 1regairements v contained in; the' = prW. changes J to J Hatch 2 -

Technicals: Specifications 1(

Reference:

Jproposed Specification?3.8.1.1,

' Action Statements a a. - D and c b.) for ': these conditions be J adopted for-

^

l Hatch 1 airveillance Realirements 4.9.B.1 and4.9;B.2, respectively, -in

' to -eliminate! ' excessive. testing :. of: - the. - diesel generators.

cn order Similarly,- the ;. ' additional _ ' diesel testing;E regiired :by, Hatch 1-i r.

0 airveillance - Beg 11rement '4.5.G should. also be deleted ' to eliminate p

i-excessive L testing when a-diesel.. generator-is1 declaredJ-inoperable.

- airveillance ' req 11rements x have - been fincorporated e for "offsite. ~ power D

sources (Reference. proposed Hatch 1 alrveillance J Req 11rements.'4.9.A.1)

{

to verify offsite power -- availability, and E breaker alignments.- alch r

-realirements. are'. presently' included : ' in' the-Hatch-2 Technical Specifications (Reference Hatch 2.

airveillance Realirement i

4.8.1.1.1.a).

Georgia Ibwer proposes to revise the, Limiting Conditions of OperationL (ICD) ' for' Hatch 1 and 2 with one diesels inoperable.

Hatch.1 ' currently has a 7-day period (reference, specifications 3.5.G and -'3.9.B. 2). to restore operability while Hatch 2 has a 3-day ' period ' (reference specification '3.8.1.1).

It is proposed ' that both units have.72 hairs g

to restore operability of the diesels with a 7-day once/ year / diesel exception to allow:for preventive maintenance and two 18-day exceptions per year. for the entire plant -(i.e., all fite emergency ' diesels) - for major repairs. ' Experience has shown that seven days:are regiired to 60 l

preventive maintenance and with the current Unit 2 3-day'IOD (with; no l

exceptions) the plant would need to be shitdown for at least sesen days -

per diesel per. year in order to'do maintenance. The proposed I4D a

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$. change. wmld ' preventi? any E forced i outages f in [orderI 'to [do) preventive l s

7bsirpintenance. 02rrently,;tmit 1 has a 7-day. IID j and does o not. have _ this :-

apgnh1 M.

HOWever, ? since tit ' iS. proposed that :both Units > have the same

~

EICO's ' the 17-day exception - for (preventive maintenance _ would ibe recuired ~

foriUnitj1 J also.1. It.~is : also proposed to i allow i two.:18-day exceptions

per year for.all

emergency diesels.1 An 18-day LI4D was -recomended by g-ithe die'sel;marufacturer to fallowKtime: to repair the diesels in case?of.

i x

,T 1a Jmajor R failure. JA ' shorter.: time : period - could i reallt ini inadecalate -

invest' h

l problem

-s and Tre@pations and. cuick / repairs that do not~ correct t e. actua lt sin a2bsecalent-failures. f Failure - experience 4 at LPlantE Hatch -

Won diesel 2C has shownithat: an 18' day IID.would allow adecuate time to.

accomodate aimajorf; repair.. In Jaddition " a study. was < performed..using ;

. probatiilistic, risk [o' assessment methodology iin order ' to assess the - effect

~

7

.upon plant 'ssfety f the l proposed IID scheme., %is ' study l assessed the.

change in the:frecuency of core damage as a reaalt of the proposed IID-

~

from,,the T IID. scheme currently: _in - use.-

The? studyE concluded : that

[bI ' adopt { ort,of the proposed ILD scheme-decreases the estimated core' damage frecuencf for; Uniti1, thereby increasing. the margin of plant safety. -

9, @@f A

' The, estimated core damage frecuency for Unit 2 increases by less than;6'

~

3 7A b / ~. percent.1 However. this.. slight increase..in the' frecuency -of core-damage i

.is of. alch 'small magnitude that it clearly: lies within the acceptable uncertaintyf bounds.of the coreJdamage-frecuency of 'a = ruclear.. power 3

E

. plant 3given the current. state-of-the-art knowledge about the ' PRA a

.}

models, failures data,. and. the 1 design. and operationE of the plants.

1 Therefore it can be concluded that the effect on Unit 2 plant safety Q

,/*

die to, the proposed, I00 scheme is insignificant.

<>V.5 3

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1To redace wear ogithe diesel generators, it has been recomended by the i-narufacturer that, testing recuired by Hatch 2 alrveillance Recuirements

A 4.8.1.1.2.a~.4 and

4.8.1.1.2.a.5.be modified in addition to ' the changes.

to the action ' statements. contained in Specification ' 3.8.1.1' discussed.

"above.

Recniring the -diesels ~ to reach synchronous speed in.less than or. ecual to'12 seconds (Specification 4.8.1.1.2.a.4) results in 'atusive e

02ick starts and: stops of the: diesels -when additional airveillance is recnired by the Action ~ Statements for. Specification '3.8.1.1.

Recuiring' the ' diesels to -accept rated loads in less than or ecanal' to 120 seconds (Specification 4.8.1.1.2.a.5)Lrepresents a strerucus ~ routine test.. Ite' diesel; manufacturer recomends that 5, mirutes be allowed for the diesels-to accept rated loads, trus providing more time for engine preconditioning' prior to loading. %erefore, it. is proposed that ' these two test recalirements be ccxnbined to form one test regardless if..it ~

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is t rout-ine' or - reo.lired by an Action Statement. -

(Reference-proposed.-

Specification

'4. 8.1.1. 2. a. 4. )

As a.: point of clarification,. the existing realirement to load' the' diesel generators in 120 seconds does not represent a' licensing basis for the plant.. _ Therefore, -increasing

. the time. to 5 mimtes will not compromise plant safety. Moreover, the 18 month - mrveillance testing reatirement for the diesel generators:

L(Reference-alrveillance.

Beolirement 4.8.1.1.2.C) verifies the

capability' of--the -diesels to function 'in accordance with ~ design _

reasirements.

Regarding load ' testing of-the _ diesel generators, the diesel mamfacturer reconmends that the diesels always be loaded to a mininum of 60%

of rated loads when started.

The ' Hatch 2 Technical Specifications meet this mininum test reglirement since they req 11re the diesel generators to.be tested at rated loads.

However, _the Hatch 1 Technical Specifications.(alrveillance aeglirement 4.9.A.2.a) realire the diesel' generators to be tested at 50% or greater of rated load when demonstrating operability. 'Iterefore, it is proposed that' the Hatch 1 diesel generators be tested ) 60% '(1710 kW) of the ~contimous rating (2850 kW)_ to agree with the diesel mamfacturer's reconmendations.- It is also' proposed (Reference Hatch 1 S2rveillance Realirement 4.9.A.2.a) to similarly incorporate the testing regiirements that were discussed above for Hatch 2 (Reference proposed Hatch 2 alrveillance Renairement 4.8.1.1.2.a.4) into the Hatch 1_ 'Iechnical Specifications. Again, there is no ' licensing basis for a 120 second loading reo2irement for Hatch 1, and at each schediled refueling cutage.

alrveillance-testing recuirements (Reference Hatch 1 Specification

4. 9. A. 7) verifies the diesels capability to function in accordance with design ren11rements.

As another. effort to redice the mnter.of unnecessary or atusive tests of the diesel generators, and thereby increase reliability, it has been reconmended-by the diesel mamfacturer that Hatch 2 Surveillance Req 2irement

4. 8.1.1. 2.c.14 be modified.

Q1rrently, this 18-month-surveillance recuirement reglires five alecessive starts of the diesels to verify the capability of the air start receivers.

It is proposed (Referenced proposed Specification 4.8.1.1.2.d) that this test be done only once per five years since 'the primary reason is to' demonstrate adentate ecuignent sizing of the air start system.

Reverification of the performance of the air start receivers will be maintained, hit on a red 1ced time frealency (every five years).

As a reallt, the diesels will be subjected to a significantly rediced mmber of atusive tests which recuire glick engine starts and stops.

Page 6 p

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g-j Overload 1 testing of the dieselL generators does not' contribute to the or the -longevity of' the ecpipnent, tut instead-

. dependability._

It may also impede seating or reseating of engine accelerates: wear..

power-parts, whether L they are new or have. been albjected 1 to' ' prior distress... Hatch 2 Surveillance Reglirement 4.8.1.1.2.c.9.. presently-

~recuires a 24-hcur test'.of the diesel generators.

naring the first two

' bcurs _of-the test, the diesel is placed in an overload condition. The loading -on the diesel is then.recliced to its rated: loads-the. following 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />. This represents an atusive test recuirement for the diesels that needs to be changed.

Therefore, it.is proposed (Reference proposed -Specification 4.8.1.1.2.c.9) - per the diesel marufacturer's -

reconnendation that the 24-hour-test be modified to req 1 ire rated load testing of the diesels c11 ring' the first 22 hcurs to allow engine

- preconditioning, and that the diesels then be subjected to overload operation claring the last two hours of the test.

It is proposed that recnirements.section

4. 8.1.1. 4

" Reporting Recuirements" of the Unit 2 Technical Specifications be deleted, since the Reportable Occurrences section of the Technical Specifications has -

been ' alperseded by 10 GR 50.73.

However to keep the NRC. Informed of the diesel generators' reliabilities an anrual report recnirement has been added to section ' 6.9.1.5 of the Unit 1 and Unit - 2 Technical.

-Specifications in ~accordance with' Generic Letter 84-15.

Section 4.8.1.1.4 of the Unit 2 Technical Specifications will reference section

6. 9.1. 5..

IV. CONCHBION The proposed changes to the Hatch 1 and 2 Technical Specifications are consistent. with the. reconnendations made by the diesel generator marufacturer and are compatible with the - reconnendations of Generic Ietter 84-15.

They represent an optimization of the current. testing recuirenents and will provide positive improvements. to diesel generator reliability.

For these reasons, the Plant Review Board and Safety Review Board have concluded tlat the probability of occurrence or consecuences of a previously, analyzed accident or malfunction of eculptent important to safety is not increased, nor has the possibility of a previously unanalyzed accident or malfunction of ecuipnent been created. Margins of plant safety have not been decreased.

Therefore, the proposed changes to the technical specifications do'not constitute an unreviewed safety cuestion.

I Page 7 O

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ATDONENT 3

- SIGNIFICANT HAZARDS EVAWATION '

4 EUR PROPOSED CHANGES'10 TfE' TECHNICAL SIECIFICATIONS l.-

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' OPERATING LI NSE DRP-54 EDWIN I. ' IRTOI NUCLEAR ?IANT UNIT -

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REQUEST TO AMEBO 1ECIMICAL SPECIFICATIONS

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R1ralant.: to 10i GR D 50.92,. : Georgia' 1 Power has evaluated theI proposed-amendment and 'has = determined that :.its = adoption J waald notM involve a

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- significant hazard. The: basis for!this determinationtis as follows:

a. iPROIOSED OiANGE l-Change 'the Oore -: Sprayj system Limiting ' Conditions 1 ifor. Operation E(3.5.A.2), Sirveillance Realirements (4.5.A.2), : and Bases :- (3.5.A.2). to delete the reglirement for demonstrating ~ diesel generator 1 operability -

when Core Spray system components _are inoperable Gange tre :LPCI system ' Limiting - Oonditions : for ' Operation '(3;5.B.2.a and

3. 5.B. 2.b), alrveillance - Bentirements - (4.5.B.2.a. and 4.5.B.2.b), ; and -

Bases -(3.5.B.2) to - delete : the reglirement for demonstrating diesel

. generator operability when LPCI system couponents are inoperable.

Change the RHR service water ' system alrveillance Realirements c(4.5.C.3) to-delete : the realirement for demonstrating ~ diesel. generator:

operability when two RHR service water p1mps are ' inoperable.

f BASIS These proposed changes are consistent with tre philosophy.of Standard -

Technical. Specifications- (including Hatch 2) which do not ' realire additional testing of the diesel generators when other safety' related systems are declared inoperable. and' Generic Istter 84-15 thich encourages licensees to delete this realirement to avoid' excessive testing of the diesels.

In addition, the proposed testing realirements -

2 for the diesel generators described -in item d. below represent a more

}.

freglent routine test interval than currently exists in. the Hatch' 1 Technical Specifications.

Also,I a failure of core spray, LPCI, or RHR service water ~ system components will not adversely effect tre perforstance of the diesel generators.

GPC has reviewed the proposed changes and considers them-not to involve a significant hazards consideration for 'the following reasons:

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(1)l ' %e_ - proposed. changes will not. significantly. increase 'the probability.. or 'conseg2ences of an accident previously evaluated,

.-because they will eliminate a practice of unnecessary and ahlsive diesel. generator testing contained in the technical specifications.

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< alch testing. contrih2tes - to accelerated diesel generator, wear,

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which conseglently degrades their reliability and availability.

(2) Se proposed changes will not create the possibility of a new or different accident fran any accident previcasly evaluated, because

.j no physical modifications are regiired to be made to the plant in conjunction with these proposed changes.

Derefore, performance '

of the onsite emergency power system. as described in the FSAR remains unchanged..

(3) %e proposed changes will not involve a significant rediction in a margin.of safety, becaise a failute of the 1 core spray, LPCI, or RHR service water system components will not adversely effect the performance of the diesel generators.

b.

PROPOSED CHANGE Change the Plant' Service Water System-Limiting Conditions for Operation (3. 5.J. 2) and airveillance Peq2irements (4. 5. J. 2) to delete the realirement-for demonstrating diesel generator operability when Plant Service Water System cmponents are inoperable.

BASIS

%ese changes are consistent with the philosopby of Standard Technical Specifications (including Hatch 2)' nich do not reauire additional testing of the diesel generators when other safety related systems are declared inoperable and Generic Ietter 84-15 which enco2 rages licensees to delete this req 11rement to avoid excessive testing of the diesels.

In addition, the proposed testing reexirements for the diesel generators described in item d. below represent a nore freq2ent routine test interval than c2rrently exists in the Hatch 1 Technical i

Specifications.

Also, a failure of a division of Plant Service Water will cause only the diesel generator associated with that division to be inoperable.

GIC has reviewed the proposed changes and considers them not to involte a significant hazards consideration for the following reasons:

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(1). W e proposed.-changes ?will

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.-.~. not: isignificantly :increaseL :the^.

probability. or 4 consegaences : of an' accident previously evaluated, i

because 1it1will' eliminate :a practice - of unnecessary and -atusive diesel 1 -generator

testing:

contained -

in- -the

.. technical (specifications.; asch testing contritutes to J accelerated diesel.

generator. wear,l which conseglently. degrades: their reliability 'and availability.

r(2) '%e' proposed changes lwill;.not create the possibility of a' new orL different accident. from any accident; previously evaluated,- because ~

. no physical modifications are : restired to be made to the plant ~ in'-

conjunction with these proposed changes.

'Iterefore, performance

- of - the onsite emergency; power. system -as described - in1 the '.FSAR remains unchanged.1 (3)' %e proposed changes will not involve a significant redaction in a margin of safety, because a failure' of a division of Plant Service Water. will cause = only - the L diesel generator. associated - with that division to be inoperable.-

c.

PRO 10 SED CI9NGE

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Change the' A2xi1iary -~ Electrical Systems --Sirveillance ' Req 11rements' (4.9.A.1, 4.9.B.1, and ' 4.9.B.2) by adding' a reo2irement to verify offsite power availability and breaker. alignments.-

BASIS

%ese changes constitute additional ~ surveillance reazirements' not i.

presently.. included in the Hatch 1 Technical Specifications.

'alch realirements are included in the Hatch 2 Technica1' Specifications..

- %erefore, these changes are being made to make both units technical-specifications consistent.

I GPC has reviewed these proposed. changes and considers them not ' to '

involve a significant hazards consideration, because they represent.

more conservative and restrictis - technical specification restirements than that which are airrently in place.

Conseglently,. these changes '

i

.are consistent with Item (ii) of the~ " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the - April 6,

1983, issue of the ~ Federal Register, and will not reallt in a significant hazards consideration.

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d.-'Pf0 POSED CHANCE i

Change Ltbe Standby 1AC Power. Supply. airveillance-Recuirements (4.9.A.2.a) to be - E consistent - with the' -diesel mamfacturers recomendations regarding routine testing of the diese1~ generators.

. BASIS

%e diesellmarufacturer :has stated that the current. monthly testing recuirement' -is too -long to provide -- reasonableiassurance Tof: the diesels

. capability to start and provide emergency power..The general criteria given in Regulatory Glide 1.108 has been. recomended - with the

' exceptions' discussed below.

. Rec 311atory Glide -1.108 relates the

- frecuency of testing to the rumber of test failures on a per mclear unit basis, i.e. failures totaled from all.three diesels..The test intervals vary in four steps proceeding from 31 days, to 14 days, to.7 days, and finally as frecpent as 3 days ciepending on the rumber of test failures experienced.

%e diesel marufacturer. has 1 recomended. that routine. testing be concheted at intervals of 14 and 7 days only.

The regulatory guide testing recuirement of every 31 days is as discussed. above. too infrecuent, and the testing recuirement of every 3 days is too frecuent for routine testing.

Frecuent testing accelerates wear to the diesels and will not enhance their reliability.

'Ibe proposed test schechle for rcutine testing will depend on test failure experience as discussed in Recplatory Glide 1.108 with.the exception that failure experience will be determined on a per diesel basis rather than on a per ruclear unit basis.

'Ibe test schechle sta11d not reflect the idea that failures' experienced on a particular diesel would adversely affect the performance of the other ~ diesels.

However, the test schechle should reflect indivicbal diesel generator reliability.

%erefore, failures on one diesel should not force increase testing of thr. other diesels.

This is consistent with the recomendations of Generic Iattet 84-15.

We diesel marufacturer has also stated that the current mininum load testing recuirement of 50% to demonstrate operability sta11d be increased to 60%, and that the diesels be allowed 5 mirutes to accept loads to allow more time for engine preconditioning prior to loading. %e diesels capability to function in accordance with design recuirements will contirue to be verified per Specification 4.9.A.7.

GPC has reviewed these proposed changes and considers them not to involve a significant hazards consideration, because they represent more conservative and restrictive technical specification recuirements Page 4

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?thani that which: are carrently in place.

1 Conseo2ently,: these changes d

.are consistent with1 Item ;(ii); of the ' " Examples of' Amendments that :are'.

Considered :.Not: Likely L to ) Involve f Significant Hazards' Considerations" E

? listed on' pageE14,870 ; of - the s April ~ 6, 1983, isaie of tre.Federali-Register, and will not rea11t in a significant hazards consideration.-

e.1 PROIOSED OIANGE diange, the ~ : A1xiliary L ElectricalE Systems - S.irveillance ; Realirements (4.9.B.1) to eliminate excessive testing irealirements from Ediesel

generator altveillance when certain offsite power seurce components are =

inoperable.-

BASIS-

'Ite proposed ch'anges to the diesel generator testing reatirements are a'

consistent with the - diesel mamfacturers 1 reconmendations. to. redice-excessive testingL and' accelerated wear and thereby enhance the

. reliability of tre diesel generators.

In lieu of verifying-that all of the diesels are operable imediately:after declaring an offsite source component ino tested within perable -(existing reatirement), tre diesels would. be is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Bis is consistent.with Generic. Ietter 84-15.

This.will provide asairance that no diesel starting problems exist, and will provide additional time 'for diesel inspection prior ~ to a test.

A 24 hair interval will-also eliminate ahasive glick diesel startups and -

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stops that are presently restired to test all of them imediately and will allow the diesels. to be operated for at least - one ~ hour when -

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. started per the diesel manufacturer's recomendations.

Any additional testing should not be req 11 red as an effort to eliminate accelerated wear of the ~ diesel generators.

Therefore, the.existin ren11rement which specifies diesel ~ testing on a rotating basisL every g24 hours such that all diesels are tested in three days, has been deleted.

Morecter, since diesel failure is not involved when an offsite source is declared e

inoperable, demonstration of their operability should not te realired if they have been successfully tested within the past seven days under routine airveillance.

nis again will reduce the potential for-accelerated wear clie to excessive testing of the diesels.

GIC has reviewed the proposed changes and considers ' them not to int olve a significant hazards consideration for tre following reasons:

4 5

(1) We proposed changes will not significantly. increase 'the probability or consentences of an accident previously evaluated, becalse it~ will eliminate a practice of unnecessary and ab2sive -

diesel generator testing contained in the technical specifications.

Sach testing contrihates to accelerated diesel generator wear, which conseg2ently degrades their reliability and availability.

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Fdifferent1 accident: frcan any accident previously evaluated, becauset no physical modifications:are remired~ to be' made to theJplant.-in iconjunction '.with t these. prW - changes. J %erefore,1 performance ! -

, of < the onsite emergency power 7 system J as described in ithe FSAR{

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_ remains unchanged.a j;

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(3) _ %e proposed changes will _ not involve a significant rediction 'in a

. margin ~ of-: safety, becazse demonstration ' of -diesel; generator:

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1 operability willi be maintained,1and willibe : condicted' on.a more

. optinum test schedsle that:will-inproveL the overall, performance of ~

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the onsite' emergency power system.

f..

PROPOSED CHANGE Change, the ~ Aixiliary~ - Electrical-' System J airveillance. Recuirements =

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l (4.9.B.2) - to J eliminate excessive testing recuirements from' diesel

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- generator-airveillance. when -one dieseli generator - is declared 1

inoperable.

BASIS:

. %e proposed changes - to the testing rewirements are consistent with the diesel marufacturer's recommendations to' redice excessive testing g

- and accelerated wear of-the diesel generators and therebyLenhance their

-reliability.

In lieu 'of-' verifying that the ' remaining diesels are operable inmediately after declaring one of ~the diesel-generators inoperable- (existing recuirement), - the remaining - diesels: would be

. tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. _ %is will provide asairance that no starting

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problems exist, and will provide additional. time for inspection prior to a test. A 24 bcur interval will also eliminate atusive cuick diesel startups and stops that are needed to -test all: of -them inmediately and

. will allow ' the diesels to be operated for at least one hour when started per the diesel marufacturer's reconmendations.- L Any additional testing. shculd not be recuired as an effort to eliminate accelerated wear of the' diesel generators., %erefore, the existing recuirement, which specifies diesel testing on a rotating basis every 24 bcurs such that both operable diesels;: are tested in two days, has been deleted.

i, All these changes are consistent with Generic Intter 84-15.

GIC has reviewed the proposed changes and considers them not to involve

.a significant hazards consideration for the following reasons:

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'(1) : 'the - proposed changes Ewill; ~ not c significantly - increase : -the probability or ' consealences Lof -anf accident previously~ evaluated, because 'it will eliminate: a practice of unnecessary and. atusive

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diesel generator.

testing ' contained.

in-the'

. technical

> specifications.-

alch ; testing ~ contritutes-.to accelerated diesel' generator wear, whichiconseaiently degrades their reliability and

. availability.

(2) %e proposed changes will not create; the ' possibility of-a new for different accident from any accident previously evahlated, because-no physical: modifications are~ regaired to be.made. to.the plant:in conjunction with these proposed changes.

%erefore, :. performara of the~ onsite emergency - power system 'as ' described. in the : ESAR remains unchanged.

(3)' We proposed changes'will not involve a significant re&ction in 'a -

margin ' of -safety, because demonstration of diesel generator operability will be -maintained, and ' will be conducted on L a more 1optim1m test schedile that will inprove thel overall performance of the onsite emergency power system.

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PROPOSED CHANGE 4

Change the ' Core and Containment Systems alrveillance Beouirerients (4.5.G) - to eliminate excessive - testing regairements when one diesel generator is declared inoperable.

BASIS

'Ite existing testing realirement is red 2ndant to that : contained in Specification 4.9.B.2' and should therefore be deleted considering the reg 11rements proposed in item f. above.- %e proposed changes to the i

testing reolirements are in compliance with the diesel marufccturer's' reconmendations to redice excessive testing and accelerated wear, and thereby enhance the-rellaoility of the diesel generators.

GPC has reviewed the proposed ch'anges and considers them not to involve a significant hazards consideration for the following reasons:

-- (1) 'Ite proposed changes will not significantly increase the probability or conseq1ences ' of an accident previously evaluated,

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because it will eliminate a practice of unnecessary and atusive diesel generator testing contained

.in the technical specifications.

Such testing contritutes to accelerated diesel generator wear, which consentently degrades their reliability and availability.

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~.ldifferent accident framlany accident previously evaluated, tocause -

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, no physical modifications t are rewired. to ' be made to the~ plant--in y"

y-o conjunction 1with-these proposed changes.

9erefore,1 performance 1of 1thei onsite : emergency power system 4 as' described; in ^ thej FSAR h j, remains unchanged.-

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(3) ; We proposed changes will

not involve a significant re&ction in a -

l margin l of E safety,- because demonstration-of diesel. generator'

= operability. will be maintained, and willt be conducted on ~a more

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optinum test schedule that: will. improve ' the overall. performance of.--

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the onsite, emergency power system.

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PEOPOSED CH9KE j

Change: the - A2xiliary' LElectrical. -Systems _ Limiting ' Conditions for Operation (3.9.B.2) to ' allow' only. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to : restore operability to I:

the diesel with a 7-day exception once/ year / diesel for preventive-maintenance andi tm 18-day exceptions per year. for the : entire plant.

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(i.e., all five emergency diesels).for major repairs..

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- We 1 aarrent technical specifications allow 7-days to restore operability, ;therefore -. changing to a 3-day IID with a 7-day exception i

once/ year / diesel / and ' two 18-day exceptions is more conservative.

A probabilistic risk assessment study showed that the freasency of core 4-melt was decreased.with the proposed I4D.

An 18 day IID ~ was reconmended by the : diesel generator marufacturer to allow time to 4

repair : the emergency diesels in case of a major failure.

A-shorter -

time period. could rea21t Lin inademate investigations and 02ick repairs.

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~that do not - correct the actual problem - and - rem 21t in a2bseasent failures. Repair experience on diesel 2C aspports that reconmendation.

i GPC has. reviewed the proposed change and considers it not to involve a j

significant hazards consideratior) for the following reasons:

(1) %e proposed change will not significantly-increase the probability or consealences of an accident previously evaluated L

because a probabilistic risk assessment study has shown that the j

proposed 100 decreases the fremency of core melt.

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(2) :2e' proposed change 'willinot create the possibility of a new or different accident from any accident ^ previously evaluated, becaase no physical modifications" are being. made to ' the plant in -

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conjunction :with this change.

Serefore the performance of; th

onsite emergency power system. as. described in the

• ISAR remains unchanged.

(3) - %e proposed change will 'not insolve a significant rediction.in.

~ the rargin of plant safety becanse a probabilistic risk assessment L study showed that the proposed IID decreases the freasency of core melt, thereby increasing plant safety.

i. PROPOSED OBNGE Oange the' Administrative controls section (6.9.1. 5) to include reatiring an anmal report of the mober of valid tests and the mnber of failures to start on demand for each diesel generator.

BASIS-t is-change constitutes. an additional reonirement not presently included in the Hatch 1 hchnical Specifications.

GPC has reviewed this proposed change and considers it not to involte a significant hazards consideration,-

becaase it represents an additional regiirement. o>nsemiently, this change is consistent with Item (ii) of the " Examples of Amendments that are Considered Not Likely to Intelse Significant Hazards Oonsiderations" listed on page 14870 of the - April

-6, 1983, Ismae of the Federal Register, and will not result in a significant hazards consideration.

t 9

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leC DOOTT 50-366

- OPERATING LICENSE NPF-5 EDWIN I. HA'IGI NUCLEAR PLANT UNIT'2 REQUEST 'IO AMEM) 'IEONICAL SPECIFICATIONS Purasant to 10 ' CFR 50.92, Georgia Power has evaluated the -proposed amendment ~ and 1has determined that its adoption.would not involve a significant hazard. %e basis for this determination'is as follows:

a.

PRDIOSED CHANGE:

Change the Electrical Power Systems Limiting Oondition for Cperation (Action Statement 3.8.1.1) to reflect the diesel - : marufacturer's reconnendations for eliminating excessive testing recuirerrents that currently exist with offsite and/or onsite emergency AC power sources inoperable.

BASIS Hatch 2 Technical Specification 3.8.1.1, Action Statement a.,

regiires that every diesel be tested within one hcur and every eight hours thereafter in the event an emergency AC source or offsite power source is declared inoperable. To redace excess testing and thereby enhancing the reliability of the diesel generators, it is proposed that when an emergency AC scurce is declared inoperable, the remaining diesels be demonstrated operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Diesel testing within tre first 24 tairs will provide assurance that no starting problems exist with the diesels and-will provide additional time for inspection prior to the test. A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval will also eliminate abusite cpick diesel startups and stops that are presently regtired to test all of them within one hcur.

Such testing is alusive to tiw diesel generators l

since -they should each be operated for at least one hour when started f

per the diesel marufacturer's recomendations.

Any additional testing l

staald not be recuired as an effort to eliminate accelerated wear of l

the diesel generators.

Therefore, the existing recpirement which i

recuires testing every eight hours has been deleted.

%is is consistent with Generic Ietter 84-15.

Ebr the specific case when one of the offsite emergency sources is declared inoperable, diesel failure is not involved.

Trerefore, demonstration of their operability should not be recpired if they have i

been successfully tested within the past seven days under routine surveillance.

'Ihis again will redice the potet.tial for excessive testing.

Moreover, little or no additional reliability asa2rance is gained from increasing testing beyond that required for tcutine airveillance.

l To accommodate the recomendations described above, the proposed changes to Hatch 2 'Ibchnical Specification 3.8.1.1 separate existing Page 1 i

I i

F-4 Action Statement a. into two new Action l Statements, a. - and. b.

.Also, existing. Action Statements ' b.,

c., - and. d. ' are changed nto Action Statensnts

c., - d., and e.,

respectively,- and are modified ~ to be consistent with the ~ reazirements of proposed Action. Statements a. 'and

b. l In ' addition, proposed Action. Statement e.

changed the allowable time--from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore one of the two inoperable diesels to operable status..Two hours-does not allow enough = time to troubleshoot a problem to determine' the canse of inoperability.

A two bcur limiting condition for operation' may result in emergency repairs which may not restore full reliability to the diesel.

In addition, existing Action Statement c. allows 2,4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore one of two inoperable offsite power cira11ts -(preferred source of emergency power) to operable status.. Therefore, the diesels shculd have the same IID realirement as allowed for offsite power.

GPC has reviewed the proposed changes and considers them not to involve a significant hazards consideration for the following reasons:

(1) 7te proposed changes.will. not significantly increase. the prchability or conseaiences of an accident previa 2 sly evaluated, because it will eliminate a practice of unnecessary and atusive -

diesel generator' testing contained in tre technical specifications, ' alch testing contritutes to accelerated diesel generator wear, which cx>nseglently degrades their reliability and availability.

(2) ite proposed changes will not create the possibility of a new or different accident from any accident previously evaluated, because no physical modifications are reesired to be made to the plant in conjunction with these proposed changes.

7terefore, performance of the onsite emergency power system as described in tre FSAR remains unchanged.

(3) 7te proposed changes will not involve a significant rediction in a margin of safety, because demonstration of diesel generator operability will be maintained, and will be cond2cted on a. more optim2m test schedile that Will ~ improve tre overall perforirance 'of the onsite emergency power system.

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'b; _ PSD50 SED O W G dange : the' Electrical' Power L Systems aarteillance Req 11rementsf(Table '

- l c-1 4.8.1.1. 2-1)

-to; be, consistent twith1 the : diesel mamfacturer's N

- recomunendations i regarding J the :

3 0 ::

. diesel generators.:

sche &le ifor routine'stesting ;of, tre t

.' BASIS-

' Hatch

2. Technical-Specification.~4.8.1.1.2.a inplements.~ the testing -

sche &le given _. in : Rec 3 latory G2ide.11;108 ' ; for routine periodic

.marveillance testing of the diesel generators.- Regulatory Gilde 1.108

. relates the fremiency of testing to the mmber = of test failurer:on a.

per mclear unit basis,,i.e. failures totaled from = all three diesels. -

The test -intervals vary in four steps proceeding from. 31 days, to 14 days,1 to 7-days, : and finally : as ' fregtent aso 3 days _ depending on the mmber of test failures experienced.

A different test ' sche &le is proposed using-the general criteria given..

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.in Regulatory-Gilde 1.108 L with the exception that routine testing be

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con &cted at. intervals of 14 : days 'and 7 ' days only.

Tre diesel mamfacturer has notifled GPC that:a" 31 day test freq2ency :is -too.long -

to. provide reasonable asairance of-the ' diesels capability to' start and provide emergency power, and that testing esery three. days on a routine -

basis is too. freasent.

Frecalent- - testing accelerates-wear to the diesels, and will not enhance their reliability.

D e proposed test schedule - contimes to depend ~ upon test failure experience hat on a per diesel basis rather than on a per mclear unit.

basis.

%e test. sche &le should not reflect the idea that failures experienced on-a-particular diesel would adversely affect the performance of the other dierels.

However, the test. screc111e stat 1d reflect indivicinal diesel generator reliability.

Therefore, failures on one diesel shculd not force increased testing of the other diesels.

%is is consistent with Generic Istter 84-15.

GPC has reviewed the proposed changes and considers them not to-intelse a significant hazards consideration for the following' reasons:

(1) 'Ite proposed changes will not significantly increase the probability or conseglences of an accident previously evaluated, beca2se It will eliminate a practice of unnecessary and ahasite diesel generator-testing contained in the technical.

specifications.

a ch testing contrihites to accelerated diesel generator wear, which consentently degrades their reliability and availability.

(2) %e proposed changes will not create the possibility of a new or I

different accident from any accident P69e 3 9

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previously evaluated, becaise no ' physica1I modifications.-are i

realired -to be made to the _ plant in _ conjunction with these j

proposed changes. 'Iterefore, ^ performance of the onsite emergency

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power. system as ' described in the ESAR remains unchanged.

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s(3) The proposed langes.will not involve a significant rediction in a margin. of -safety, becaise. demonstration of. diesel generator operability will be maintained, and will be cond cted on a more optinum test schedile ' that will improve.the overall. performance of the onsite emergency power system.

c.

PPO10 SED CHANGE Change the. Electrical Ibwer Systems alrveillance Feq2irements (Ctxtbine 4.8.1.1.2.a. 4 ' and 4.8.1.1.2.a.5 to create proposed Specification

- 4. 8.1.1. 2. a. 4) to eliminate excessive test req 2irements when demonstrating diesel operability.

BASIS The proposed changes to the test realirements are consistent with.the diesel marufacturers recomendations to red 2ce excessive testing and 4

accelerated wear of the diesel generators, and thereby enhance their reliability.

Beoliring the diesels to reach ' synchronous speed in less than or egial-to 12 seconds (existing Specification 4.8.1.1.2.a.4) results in ahlsive niick starts and stops of the diesels when additional airveillance is req 1; red by :the Action Statements for Specification 3.8.1.1.

Req 2 iring the diesels to accept rated loads in less than or egial to 120 seconds (eyisting Specification

4. 8.1.1. 2.a. 5) also represents a strerua m raitine test.

The diesel marufacturer recomends that 5 mirutes be allowed for tre diesels to accept rated loads, trus providing more time for engine preconditioning prior to loading. 7terefore, it is proposed

~that these two test reg 2irements be combined to form one test

+

regardless if it is routine or realired by an Action Statement.

(Proposed Specificaticn

4. 8.1.1. 2.a. 4. ) 7te existing realirement to load the diesel generators in 120 seconds does not represent a licensing basis for the plant.

Therefore, increasing the time to 5 mirutes will not compromise plant safety.

Moreover, the 16 month surveillance testing regiirement for the diesel generators

. (Specification 4.8.1.1.2.C) verifies the capability of the diesels to function in accordance with design reazirements.

GEC has reviewed the proposed changes and considers them not to involve a significant hazards consideration for the following reasons:

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C (1) '%e proposed changes will not significantly increase the probability or conseglences of an : accident previously. evaluated,.

because ;it ~ will ' eliminate a practice of unnecessary._ and atusive 111esel

= generator.

testing contained

.in the technical

. specifications. - a:ch testing contritutes to accelerated diesel generator wear, which conseglently degrades-their reliability and ~

availability.

(2) 7te proposed changes will not create the' possibility of 'a new -or

- different-accident from any accident-previously evaluated, lbeca2se no physical modifications are reasired to be made to the plant in

- conjunction with these proposed changes.- %erefore, performance of - the onsite emergency power ' system as described. in the ' ESAR remains unchanged.

(3) The proposed changes will not involve a significant're&ction in a margin of safet.y, because demonstration of diesel generator operability will be maintained, and will be con &cted in a.more optimam manner and on a ' more optinum test ' sche &le that will

improve the. overall performance of the onsite emergency powr system.

d.

PROPOSED CHANGE Change.

the Electrical Power Systems alrveillance Recalirements (4. 8.1.1. 2.c. 9) to cortply with the diesel marufactirer's reconnendations regarding overload testing of ' the diesel generators

& ring the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 18 month surveillance test.

BASIS Overload testing of the diesel generators does not contritute to the dependability or the longevity of the ecalipnent, tut instead accelerates wear and thereby re&ces diesel generator reliability.

It may also impede seating or reseating of engine power parts, whether they are new or have been albjected to prior distress.

The 24-hcur test of the diesel generators currently reg 2 ires each diesel to be placed in 'an overload condition Wring the first two hours and then re&ced to its rated loads the following 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />. This represents an atusive test requirement for the diesels.

The diesel marufacturer has reconmended and it is proposed ' that the 24-hour test be modified to recalire rated load testing of the diesels Wring the first 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> to allow engine preconditioning, and that the diesels then be albjected to overload operation W ring the last two hours of the test.

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,, GEC has reviewed the proposed. changes' and considers them not tolinvolve -

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- ca significant hazards consideration for the followingl reasons:'

(1):. Se : proposed changes <. will ~ not = significantly increase : the-probability of consemences: of Ean accident previously evaluated, because iit will; eliminate a practice of-unnecessary and atusive

. diesel.

' generator.. testing.. contaiwd ~. in -

the technical

. specifications.

asch 1 testing.contritutes to accelerated - diesel

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generator wear, which consemently. degrades their reliabilityL and

. availability.1

~(2)- %e proposed changes will, not create the - possibility of a new or different accident from any accident previously evaluated, because no pt:ysica1 modifications are rewired to be made to the plant in

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conjunction with. these proposed changes.

%erefore,. performance

> of the onsite emergency - power _ system as - described in the J ESAR remains unchanged.

.(3) %e proposed changes.will not involve a significant rediction in a margin of safety, because demonstration of diesel generator operability will-be maintained, and will be ' condacted in a more optinum manner that will improve the overall performance of the onsite emergency power system.

e.

PRDPOSED OmNGE Change the Electrical Power Systems aarteillance Reazirements

( 4.8.1.1. 2.c.14) to redice the fremency of verifying operability of' the diesel air start receivers.

BASIS O2rrently, this 18-month surveillance recalirement rew ires five maccessive starts of the diesels -to verify the capability of the air start receivers.

It is proposed (Specification 4.8.1.1.2.d) per the diesel marufacturer's reconmendation that this test be done only once per five years since the primary reason is to demonstrate adecasate ewipnent sizing of ~ the air start system.

Reverification of the performance of the air start receivers will be maintained, tut. on a redaced time fremency (every five years).

As a res21t, the diesels will be albjected to a significantly redaced runber of - atusive tests which reesire mick engine starts and stops, thereby decreasing wear and increasing their reliability.

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- _GBC has reviewedithe proposed danges and considers; them not to involve g'

- ma significant hasards consideration for-the following reasons:

w f(1)MSe proposed changes will ' not 'sipificantly ' increase; the probability or conssenences.of an accident..previously evaluated, 4

e because it will eliminate a practice' of unnecessary -- and atusive :

P diesel; -generatorL testing-contained in-the-technical:

- specifications.18uch'. testing contributes. to accelerated diesel' generator wear, which concessently. degrades,their: reliability and Lavailability.

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~(2) te proposed changes willL not create the possibility =of a new or(

~difforent accident from any accident previously evaluated, because no physical. modifications.are resaired to be made.to the plant in.

• conjunction with these proposed danges.

Berefore, performance J

of : the, onsite energency power systan as described in the ISAR remains unchanged.'

(3) %e proposed changes will not involve a significant reduction in 'a

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margin of safety,: because demonstration of. diesel generator operabilit.y will be maintained, and. will be condacted on a note optinum test schedile that will improve the overall performance of

~the onsite emergency pow r system.

i f.

PRDPOSED O W G Gange the A.C. Sources I.imiting conditions for Operation (3.8.1.1.b) to add a 7-day exception once/ year / diesel for preventite maintenance

)

and two 18-day exceptions per year for' the entire plant (i.e., all five emergency diesels) to the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> reetirement to return the diesel to

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operable status.

1 BASIS i

te 7-day proposed exceptions will allow preventive maintenance to be done to a diesel without having.to stutdown the plant. %e 18-day 100 was recommended by the diesel marufacturer to allow time to repair the i

emergency ' diesels in case of a major fallare.

A shorter time period

.'could result in inadecuate investigations and etick repairs that do not

. i correct the actual problem and result in aabasesent failures.

Repair

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experience on diesel 2C supports that recommendation.

In addition a L

- study using probabilistic risk assessment methodology showed that the proposed Iro does not significantly increase the freeiency of core amit.

t GPC has reviewed the proposed change and considers it not to intelte a i

significant hazards consaderation for the following reasons:

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(1) %e proposed change will not significantly increase the probability or consecuences of an accident previously evaluated, because a probabilistic risk assessment study showed that the change in core Irelt frecuency is insignificant.

(2) The proposed change will not create the possibility of a new or different accident from any accident previcusly evaluated, because no physical rnodifications are being mxle to the plant in conjunction with this change.

7terefore, the performance of the onsite emergency power system as descrited in the FSAR renains unchanged.

(3) The proposed change will not involve a significant rechetion in the margin of cafety, because a probabilistic risk assessment study showed that the change in core melt frecuency is insignificant.

g.

PROFOSED CIWr;E Change the Electrical Tower Systemn - AC Sources Peporting Becuircrents (4. 8.1.1. 4) by eliminating the recuirements, referencing the Administrative (bntrols section on anrual reports (6.9.1.5) and adding a recuirement that an anrual diesel reliability data report be tutuitted to the NRC anrually.

BASIS

%is change is proposed because Reportable Occurrences section of the Technical Specifications has been ruperseded by 10 CER 50.73.

In lieu of the current reporting recuirement an anrual diesel generator reliability data report will be tutmitted to the NRC in accordance with Generic Intter P4-15.

This will allow diesel reliability to be monitored.

Georgia Ibwer this proposed change and considers it not to involte a significant hazards consideration because it represents a change made to conform to changes in the regulations.

Consecuently, these chwjes are consistent with Item (vii) of the Exartples of Amendments that are (bnsidered Not Likely to Involve Si'Jnificant !!azards Cbnsiderations" listed on page 14,870 of the April 6,

1983, istue of the Federal Register, and will not result in a significant hazards conditions.

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