Text

Proposed Tech Specs,Adopting Guidance of RG 1.9,GL 93-05 & GL 94-01 to Achieve Overall Improvement in EDG Reliability & Availability
	ML20092J414
Person / Time
Site:	Wolf Creek
Issue date:	09/15/1995
From:	; WOLF CREEK NUCLEAR OPERATING CORP.
To:	;
Shared Package
ML20092J408	List: ML20092J407; ML20092J414;
References
	RTR-REGGD-01.009, RTR-REGGD-1.009 GL-93-05, GL-93-5, GL-94-01, GL-94-1, NUDOCS 9509220124
	Download: ML20092J414 (23)
	v • d • e

-

'Attcchm:nt IV to ET. 95-0099 Piga 1 of'23 T

?

+:

1 4

)

i ATTACHMENT IV PROPOSED TECHNICAL SPECIFICATION CHANGES-l J

f 4

i 4

1 i

9509220124 950915 r

PDR. ADOCK 05000482 P

_.,PDR,,

Attschment IV to ET 95-0099 Piga 2 of 23 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE PLANT SYSTEMS (Continued) 3/4.7.10 DELETED TABLE 3.7-3 DELETED 3/4.7.11 DELETED 3/4.7.12 AREATEMPERATURE MONITORING.

3/4 7-29 TABLE 3.7-4 AREA TEMPERATURE MONITORING..

3/4 7-30 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating....

3/4 8-1 TABLE 4.8-1 O!ESEL GENERATOR TEST SCHEDULE..

3/4 9-7 DELETED I

Shutdown..

3/4 8-8 3/4.8.2. D.C. SOURCES Operating..

. 3/4 8-9 TABLE 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS..

3/4 8-11 Shutdown...

3/4 8-12 3/4.8.3 ONSITE POWER DISTRIBUTION Operating..

3/4 8-13 Shutdown..

3/4 8-15 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices..

3/4 8-16 WOLF CREEK - UNIT 1 XI Amendment No. 45,39,44

,.nx,.

.a

=

.>+t w.

v.

a

-.~.r a

a s+.. + p n

+

s AttschmentTIV to ET 95-0099.

Paga 3 of 23 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.11 A. C. SOURCES -

OPERATING j

LIMlTING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. Two physically independent circuits between the offsite transmission network and the Onsite Class 1E Distribution System, end

b. Two separate and independent diesel generators, each with:

1) A separate day tank containing a minimum volume of 510 gallons of fuel,

- 2) A separate fuel Oil Storage System containing a minimum volume

- of 85,300 gallons of fuel, and

3) A separate fuel transfer pump.

c

. APPLICABILITY: MODES 1,2,3, and 4.

ACTION

s. With an offsite circuit of the above required A.C. electrical power -

sources inoperable, demonstrate the OPERABILITY of the remaining off-i site A.C. source by' performing Specification 4.8.1.1.1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. 'f :lther frr' ;=:reter of the Mr :-';e! :d A.C. c'Md=! gr:r rere: he net Men rrrr'u!!y treted tJ'" the per! 24 heure, dem=:trete OPER ^.S!L!"

bypederming S;MHrM= 4.S.* 1.2- '* tepr'2':!y f0 'h:t fr- '

g=: ret ^' within.24-hours, Restore at least two offsite circuits to OPERABLE st:tus within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within -

the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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

sources by performing Specification 4.8.1.1.1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. Demonstrate the OPERABILITY of the remaining OPERABLE diesel generator by performin S cifica-tion 4.8.1.1.2a.4 within24_ hours";(uriiess tho'a~tisenc o any potential co'mmon m' ode failure for the remaining diesel generator is demonstrated, or if the diesel generator became Inoperable due to any cause other than an inoperable support system, an Independently testable component, proplanned preventive maintenance or testing, or maintenance to correct a condition which, if left uncorrected, wohotaffect the _ _.

OPERABILI Y of the die noneratoc{ restore the' int >perable ~

sei generator o O ERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least i

HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

'TM rutem:tb :::'t =d te;urnee !re$ng cf : frr! ;=:::ter rtMr the t::n; rr;u!r:m:nt: Of Sperfeten 4.9M

22.' fer thic Adhn St:t::: '

- Thb te!!! rr;r!-- t0 h em;!d:d !!;rrfer O'"'h= 'he !^^p rrb'r frd

--...-- 1....,gg.gpgmg 99... u g.9 $gy...=.ag.:.,

inopesable#^ prep'en=d-proverdotive-maaot===, 'r-Mg, Or meint=ence

'O =~d

=rften -tbh, W 58tanoorrede, wer'd net crt tM r^---5""y Of 'M fr-! generator, 4

t WOLF CREEK - UNIT 1 '

3/4 8-1 Amendment No. 8

Attechm:nt IV to ET 95-0099 Pr.go 4 of 23 3/4 B ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES LIMITING CONDITION FOR OPERATION 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 offsite A.C. source by performing Specification 4.8.1.1.1 within i hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter and Specification 4.8.1.1.2a 4* within hours ** on th redundant diesel en rato un ess the absence of any potential common m allure or the remaining diesel generator is demonstrated, or if the diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, proplanned preventive maintenance or testing, or maintenance to correct a condition which, if left uncorrected, would not _ affect the_OPERABI ITY

~_of the diesel enerato es o a 1 east one of the inoperable sources to O RA status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Restore the remaining A.C. electrical power 4

source (offsite circuit or diesel generator) to OPERABLE in accord-ance with Specification 3.8.1.1. ACTION a. or ACTION b. as applicable with 'he time requirement for the ACTION based on the time of the initlt oss of the remaining inoperable A C. electrical power ll source A successful test of diesel generator OPERABILITY performed in accordance with Specification 4 8.1.1.2a.4* under this ACTION for an OPERABLE diesel generator or a diesel generator that was restored to OPERABLE, satisfies the subsequent testing requirement of Spec-ification 3.8.1.1 ACT!ON :. cr ACTION b. for an OPERABLE diesel generator.

d. With one diesel generator inoperable in addition to ACTION b. or c.

above, verify that:

}

1. All required systems, subsystems, treins, components, and devices that depend on the remaining OPERABLE diesel genera'.or as a source of emergency power are also OPERABLE, and I

4

The automatic start and sequence loading of a diesel generator satisfies the testing requirements of Specification 4.8.1.1.2a.4 for this Action Statement.

- Th!: te t !: re';9ed te S =mp! ted : g-d'er: ch-hen 'he ineperd!e 9ere!

generater !: rettered to OPERA 9LE stater unle:s4t4 dere! re dec!ered inoperablete d0 prepienned pr:v:nte!!ve m intenanc^ tetting, Or maintenanc^

to4orrecta cond!!!cn whic5 if 4ehncorrected, e;~.:!d act " :t the

^p r9!!!!y Of t%4esetgener:ter.

WOLF CREEK - UNIT 1 3/4 8-ia Amendment No. 8 I

Attachment IV to ET 95-0099 Pigg 5.of 23 j

l ELECTRICAL POWER SYSTEMS i

LIMITING CONDITION FOR OPERATION ACTION (Continued)

2. When in MODE 1,2, or 3, the steam-driven auxiliary feedwater pump is OPERABLE.

l If these conditions are not satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months be in at least 4

HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

e. With two of the above required offsite A.C. circuits inoperable, demen:tr:te the OPEP ^S!L!N ef % dere' gener ter: by requent!:!!y p-dermin;

teMee'^^ ' B.4 1.30.' M'M S heur en'er! the ferc' ge=95: ere ! reedy ^^^' !!n;; restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be

' in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Following restoration of one offsite A.C. electrical power source, follow ACTION a. above with the time requirement of ACTION a. based on the time of the initialloss of the remaining inoperable offsite A.C. electrical power source. A e eerr'u! teet of fcre! generator-OPERASIL4TV t

peermed !n - ee-de : "!!' e crMcetien ' ".4 1.2:.4* under th!:

ACT!ON for the OPERABLE.er ' gener&re, ret!9: the &c';uen!

ecting requirement cf c e$cet:en 3 9.* 4 ^CT!ON.

p i.

. f. With two of the above required diesel generators inoperable, demon-strate the OPERABILITY of two offsite A.C. circuits by performing Specification 4.8.1.1.1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Following restoration of one diesel generator follow ACTION b. with the time requirement of the ACTION based on the time of initialloss of the remaining inoperable diesel generator. A successful test of diesel generator operability performed in accordance with Specification 4.8.1.1.2a.4 under this ACTION for the OPERABLE diesel generators, satisfies the subsequent testing requirement of Specification 3.8.1.1 ACTION b.

g. With one or more diesel generators with new fuel oil properties outside the required Diesel Fuel Oil Testing Program limits, following

+

the addition of new fuel oll* to the Diesel Fuel Oil Storage Tanks, restore the stored fuel oil properties to within the required limits within 30 days.

i

h. With one or more diesel generators with stored fuel oil total particulates outside the required Diesel Fuel Oil Testing Program limits, restore the

+

fuel oil total particulates within the required limits within 7 days.

s SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the Onsite Class 1E Distribution System shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability.

Th^ et--'t $d 2nd requena- !? reg ef : ere' ger:1^r - ".W_..e the

...c__

m_..:m _ __.. m, e--an:,..c_ 2 a 4 4 % a sm,.w.

a,.u_ e..

The g[roiie ihcific previty; kinematic viscosity; water and sediment content; and flash point shall be confirmed to be within the Diesel Fuel Oil Testing Program limits, rior to the addition of new fuel oil to the Diesel Fuel Oil Storage Tanks.-

WOLF CREEK-UNIT 1 3/4 8-2 Amendrnent No. 8 I

z Attcchment IV to ET 95-0099 Paga 6.of 23

' Ft FCTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l 4.8.1.1.

d' sel enerator shall be demonstrated OPERABLE:

Atless once r 31' days 7

a..c _rrr_:nr

. N:rWn~/ rper*?d in T9'r i.8-4 on a STAGGERED TEST BASIS by:

1) Verifying the fuellevelin the day tank,

2) Verifying the fuellevelin the fuel storage tank,

3) Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day tank,

4) Vedt;!n; the fr:r' :! d: nd re?'?'r'r-10 et 'cret 51' rpm Wrt: tMn r r;" '1012 crende." 75 ;:nr:tr r!!!;-

nd fre;" ncy the'! h '190 ^ 1*^

120 "^": :nd ^^ ^

2 Hz wdhm42-:-^end:" cr 'he Sted :!;ne!. The f 0:r' gener ter the!! be steded !c' th*4est 6/ =!n; en ef 'he !?!!rtz:n;

signals,

0) '.'enu:!,er kWu'eted !ct: of c":!t: pc::= b" t !! rov S:'et !njetten !::t :!gne!.

c) j

4) Verifying the diesel starts" and obtains a voltage of 4160

+ 160 - 420 volts, and a frequency of 60i1.2 Hz. The diesel generator can be slow started and allowed to reach rated speed at a rate that is selected to minimize stress and wear,

5) Verifying the generator is synchronized, gradually loaded to

^^^ te S204 kW*" for at least 60 minutes, and until an indicated ^Nto $201 k

temperature equillDrIDm is attained. The rate of loading and unbading of the generator during this test should be gradual, based upon minimizing stress and wear on the diesel generator, and

6) Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

b. At least once per 31 days andefter e ch rperrtien cf the fr: '

ch::: the p-d^d of rperrt:en r r grer'er the er r;ur' te

hour by checking for and removing accumulated water from the day tanks;

c. At least once per 31 days by checking for and removing accumulated water from the fuel oil storage tanks; "This test shall be preceded by an engine prelube period and/or other warmup procedures recommended by the manufacturer so that the mechanical stress and wear on the diesel engine is minimized.

"*This band is mea idance to avoid routine overloading of the engine.

Loads in f this band for special testing under direct monitoring or momentary vari ons e to changing bus loads shall not invalidate this test.

WOLF CREEK - UNIT 1 3/4 8-3 Amendment No. 8

d Attachmsnt IV to.ET 95-0099 P:ga 7 of 23 El ECTRICAL POWER SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued) l g.

Du,_.-..,8*.,-.....- s. a.a.) n.al

.u.

.k A cTU nAnK, n,u,.a 1

.aaa u.......

e,.. n m om, m..a.,..,.:, i.~_ _..a_._,.....au.u.... --. ma 1 a cru nove a 4 pry -......._ _...-..

r-a prier-toodddien40th etere r !:nh: th t the emp!e has; j

/

\\,

A D i f**,. m. a..m,.

a.. u. Mki. n. 82 a..._..

A.ne t* a,....elC,.

Aa

. _-..., a.. au. n..n.n. e. n.

. a_n.u_n.c e.,... -. __..., _.."_ *_a the x.

... ~

=.n.=._._.u....._m___.a.

,, a.n..m.n. e r..,..,..- -.--.u...,,......., n.. n. ' '.*..less4han

_..i

n.. o n,,,,,g. x. a.,. -. - -.u..,.

...i 10,37.d ;-- but !n: then O'- er' te 39 de;rrr:

Swy.a u. - _.a m. r.._ ~. _ _..,. _ e,n. e a... _ _ -.u._..._.....

zu y.

a.

4.. o -.

I..mL.., k., er'...___.___.._...A,....a...

.. J4.,...l..eL.._._,

.k

.A l';r:r"'; rr not d ^-- :ned by xmp~; ten w"' 'he cup

, u..a_.,, a. c...u i,a, i.. u. -,.a.

......, m., _. -. -.u..

4. _o.c o e,.. a_

s.

.._ r...

(d) ^ 'r-d br!;ht r-- rr:n= w"' p----' e^ ^r "then 'e d

u.~.

..a au a cru n' *76 82, (2',._.u"".-'.,:..-"'-'..'^._'_-".d._'"_:"..'."..*_-..,'._'.".'.'.."..

u.._,.:ma i v.w. 4 a a cru nove a 4. _.

4 r..'..r - - 'r'...,.~r - - ' '.- ~. '...'a u a cr' u- ' ' '

v.' e 'a 4.

'.,~_ _ '..u. Tw...u..

....'u.'.'W.

a...___..a.

..... no.. _

.T T

_-W W.

nt;& 'cr uur :; b p 'erm-

l- ---~ den = ""' ^ STu l'

9er-ASTu 93933 go, d.' By verifying fue o 1 p ope es of new fuel oil are tested in accordanc6 with, and maintained within the limits of, the Diesel Fuel Oil Testing Program.

e.

_ __. nc :T:n; E d ; by ^" ":rg : : mp!: Oue! O!! !n

^*

.~.,.--....au a eTMD32?S ", ed ' 'y!.; '"' ''M p: "' '

-^ntem"r"?- te !rr then 10 m;!'!!:r e'h:n ch--k- !n ~~rerdance

..au ieru no2'c ' " -' " d ^

e.' By ve oil progi ~ es of stored fuel oil are tested in accordance with, and maintained within the limits of, the Diesel INel OilJesting P

,.. i.<-.~.

_,4. F.ronram..

._...._.u..a:..,_......_~_...un.u.....a..

the. :~.._.'i.._

a_.c. _.a_ i

2.. a. 4 4.. o.

2. _~..e._.~_ _.u.._._a_

.m _.. u..'-^. 2

r-! ^^~'":en: (u&; the Err; we-rymm) u6; On: c' 614 p- " 'er th:n er -^ur' to 12 :-^cn&. The ;:nereter 'fe!!:;0 and *-- ren' / h:!! b-41cn

190 '20 "c": nd SO 21.2 H: =!!hin 42-soeendeafter4he-sta4:!;ne!. c b-- ren!!y "er!/ the gener:ter u

isleaded te en !ndH * '.400040-6304 u.^?* "!ce then O,',e >r'.te A.n._._ea..a.. -.'a am,=.*

. la.a Annn.a coni MAf** ' - ' - = ---

r-----'----

a im..

an ""'-

f. At least once per 184 days verify each diesel generator starts from standby conditions

and achieves in less than or equal to 12 seconds, a voltage of 4160 + 160 -420 volts, and a frequency of 60 1.2 Hz using one of the following signals:

1) Manual,or

2) Simulated loss-of-offsite power by itself, or

3) ' Safety injection test signal

~ *This test shall be preceded by an engine prelube period so that the mechanical stress and wear on the diesel engine is minimized.

"TNe Send 1-nt et ; uW.= te eve!d -^"".ne eu-deP.; c' *a e en;!ne.

h i_ a. u._

.. s.w. u_.a. <'~-' -. us....: m---s---'""--'-'"'-',-,

i

..a_ a:..

a v

r----"

_ _ _ _. ~, m..u.c_.a...'....,=..., bus"'d_.-".."...*.".-"__'.'."..-.

test. -

WOLF CREEK - UNIT 1'

' 3/4 8-4 Amendment No. 8 t

t'l.

C

e

Attachmunt IV to ET 95-0099 Piga 8 of'23 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

g. At least once per 18 months, during shutdown, by:

4)' *"bj-^'!n; the <isese%4n '^rpr-'!rn L-r---d=0 Y "'

precede :: perpr d in ^^njun^'ir r"' ": ran"'r**r e ':

.cc.:n"x 10e Hi: ^'-- Of :t;ndr; : r;!:e,

' 2) V -!? !n; t'- fer r';= re'^r - prs""y te rejr** t'- ESW

/

pump --te- '^rd (th: !:r---? !n;!: emergency-loadFwhile m:!n'i. 'n;"^" ;r et41*^ ^ 190 120 re!!! :nd 5';rency et

^^ 2 $? H:,

3) V: */ ~; t'- frir'; n reter ' 7 '""y ! rrjrd 'crd Of 6301

' e "hert4 ripping--The ;= r:ter "r" ;r ' '!mt osed4784-welto<iur!

nd 'r!!=99-t'^ '--d r-lr? ^+

1)- e ac go r pera ng a a power ctor between 0.8 and 0.9 does not trip on overspeed and voltage does not exceed 4784 volts and frequency does not exceed 65.4 Hz following a load rejection of 5580 to 6201 kW,"

i) S!re! ';ng a !ce: Of Ot" pc::r b" " ", =d:

) V:df;!n; drencry--'en Of!" :- r;rcy br:ir: =d !Ord che fng frem the emer;ene/ errer, =d d

b b) Ved'ying the 4leeset:tede"* = 'he rut ^ clasteegnal, energia": the em:r;=0y but ?! w!!' permanent!y

^^n^^'ed

'^rdt w"':^ 12 er^ade, 0 erf--- !he cr'^ ^^ n

^'^d ch 'd--n !rrer '"rcr;5 the Shut-"

te';"--- r =d ^^^' ales fe'; : !: the er e-" '10 5 -: nut

rh!!:it:;= reter isleaded-wetMhe4hutd.--'^rde

^** r = rf--'^,

the 'r 9; c'r'-"^!!r:0 = d h -" n ej ef

O m er;.v.y br:rr-2:!! b^ m:!nt:!ned :! 4190 ^ 1SO - 420 70" =d

,. u am,t_,.w:........ - -..

i 4,.

2) VerTfyFng on an actual or s mulated loss-of-offsite power signal (LOOP)";

a) De-energization of emergency buses; b) Load shedding of emergency buses; c) The diesel generator auto-starts from standby conditions *" and:

e

1) energizes permanently connected loads within 12 seconds, l_.

2) energizes the auto-connected shutdown loads through the shutdown sequencer,

3) maintains steady state voltage at 4160 + 160 - 420 volts,

4) maintains steady state frequency at 6011.2 Hz, and

5) operatas for greater than or equal to 5 minutes while the nerator is loaded with the shutdown loads.

"This suWeillance shall not be performed in Modes 1 or 2 and credit may be taken f

np_lanned events _that satisfy this regul_roment,

' *"TMsTest'ishall De priceTed by an engine prilube period and/or other warmup

- procedures recommended by the manufacturer so that the mechanical stress and wear on the diesel engine is minimized.

WOLF CREEK UNIT 1 3/4 8-4a Amendment No. 8. 59 4

d a

-n s-u

.u

_. _ _ _ _ _. _ =

Attachmsnt IV to ET 95-0099 Pags 9'of 23' I

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4 i

u.,. u..u...,

. c. _.,. wa_.a.....,. u

.e....uu...,

u..

o.

n f

..g...,i

.....y..

offsetopower, 'k" f r ' g= retr :te'*:* 0^ the-outo4 tad signoLandeper:'r en c' ndby f0';r- '--'h= r e-"9 to 64nmutes; e^.d the c8't"a ; :. ::-^".r= =r;be tM rr'.e-

_____e._-.__......,~.,i.___-_mm.f.___u a.,u.,~_

u..u. i t.v.u..

g__

The ;;; ::^*r v^'tr e =d f'e'"^n'y the!! b^ '1*^ ^ 1M 120 J

ve" =d "O i 1.2 H: wit'2-12 seconde cr 'he r"'^ ete't

!;n:!, the ;=, ret ^' 'ert; Pete ;enrete v^".rge =d fre-u..__u..:

a...au:_. u _ n_.a. a.,u

.u:....

3) Ve ing on an actual or s mulated SaEtyYnhcNtuEtiori Signal (SlAS)" that each diesel generator auto 4 tarts from the standby condition

and:

i a) achieves a voltage of 4160 + 160 420 volts in less than or equal to 12 seconds after the auto-start signal; b) achieves a frequency of 6011.2 Hz in less than or equal 4

to 12 seconds after.the auto-start signal; c) operates on standby for greater than er equal to 5 minutes; t

1 d) the offsite power source energizes the tuto-connected I

cident) loads through the LOCA sequencer.

_~

6) "!me!: ting e !^ ! Of 0 'd'^ pc:fr in /^njun"*!^^ Y'"h44afety 8

'njef:^^ tett :!gne!, end f

e) Vrif !ng drenr?-'en Of the*mergency br--^ =d !^rd

/

the '"ng !=m the emerg=0y br-er; d

l b) Vrif !ng the dre!:tet* On the ru'^ etartsignair

/

=rg!:r the e- ^.'g=0y burr e'"5 p^r' c=t!y c^^.nef^d

'cet w"h!n 12 e--^^de, energber the ^r'^ en r^d errg=cy (redd^^t) !^29 'heu;5 the LOCA n'; rec ^r =d Op^ retr for gre?r' *h= = e-" ' to 5 "ne'-!while4ts generatcr !: !cetd with the emerg=cy '^rt ^ *er =rgba-

!!=, 'he eter+/ -tete v^"rg- =d 're';recy Of the emeg-ency berr the!' bemamtained e641*^ ^ 1SO 420 voltsend 6011.2 H: during th!: te:!; =d c) Vrif !ng that :!! rr'^-' etic '"er! greetr 'd?:, ere^'

/

h%h jrMet c^^'en' tempretum, rg!ne cerep^^d, kw4ube onpressure, h!gh r=' cree pere'e, eted f-"u'e re!:y, and gn ::t^' C"';:=t!:!, re ='^mrt!r! y by;cerd up^n 4-los: Of "^"r;-^ es4he emr;= y but conceren* w!!h e4efety A"*ert!^^ :! =!,

4). Verifymg on a s mula loss-of-offsite power in conjunction with a simulated Safety injection Actuation Signal (SIAS)"

t that each diesel generator auto-starts from the standby condition

and:

4 a). achieves a voltage of 4160 + 160 - 420 volts in less than i.

or equal to 12 seconds after the auto-start signal; i

4 b) achieves a frequency of 6011.2 Hz in less than or equal to 12 seconds after the auto-start signal; c) de-energization of the emergency busses and load shedding from the emergency busses; 4

Attachment IV to ET 95-0099 Page 10 of 23 v

d) energizes the emergency busses with permanently connected loads within 12 seconds, energizes the auto-connected emergency (accident) loads through the LOCA sequencer; e) operates for greater than or equal to 5 minutes while its generator is loaded with emergency loads.

7)-Verifying the f t:r' gener:ter ^^^rrtre for et leer,t44-hours, During the fret 2 heer: c!4his tet, the derr! generator shallbe4oaded10 en -* ?'^d46004aS821 kW** end during 2

the-rem-!n:ng 22 ' cur: Of th!: te:t, 'he dere! genereter the!!

b^ !^rded 10 en infr-'ed4000404201-kW." The gener:ter i

Wand 4requency the!! b= 41C# ^ *SO 420 ve!!! and444 4,244a, - 2 H: r*^ 12 e^-^^d:4 'er the :!:'t :!gne', 'he 8

c'erdy itete gener:ter v^'teg-Ond freguency the!! 5e meinte!ned

" tith!n 41C# ^ *SO - 420 ve!!: and C* i

2 H: during !".!: te:!.

WithidHnute: *.:: ccmp'eting thi: 24 50er tect, p-derm e

r..:

aa4 4 % ew..

5) Verifying eaN5Ni soihnerator's automatic trips are bypassed upon the simulated SIAS and LOOP combined test" except:

f a) High Jacket coolant temperature; b) Engine overspeed; c) Low lube oil pressure; d) High crankcase pressure; e) Start failure relay; f) Generator differential current.

This test shall be preceded by an engine prelube period and/or other warmup procedures recommended by the manufacturer so that the mechanical stress and wear on the diesel engine is minimized.

"This surveillance shall not be performed in Modes 1 or 2 and credit may be taken for unplanned events that satisfy this requirement.

4 J

"Th!: band !: me:n! : ge!d2nce !: eve!d r^ut!ne ever!^rfng cf *he engine.

L^2de in excer: Of th!: bend for ep-c! !4esting under direct monitoringer momentary + anal +ons-due4e c"Onging but !Oede she!! not inv2'!d2te th!:

test, 4

WOLF CREEK-UNIT 1 3/4 8-5 Amendment No. 8 4

1 Attachment IV to ET 95-0099 Pcg; 11 of 23 s

FI FCTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

I I

I I I

8) V:r!'y!n; the!'M rute enn~d-d !r:H te r~h feseigenerator JA4

,______s

6) Verifying ~ full-load carry ng capabilityof the diesel generator at a power factor between 0.8 and 0.9 for an interval of not less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at 5580 to 8201 kW (Indicated)*, The generator voltage and frequency shall be maintained within 4160 + 160

- 420 volts and 6011.2 Hz during this test;

7) Verifying the diesel generator's hot restart capability by operating the diesel generator for greater than or equal to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at an indicated load of 5580 to 6201 kW, shutting down the diesel generator and restarting it within 5 minutes. On restart, the diesel generator voltage and frequency shall be 4160 + 160 - 420 volts and 6011.2 Hz within 12 seconds after the start signal;

9) Verifying the diesel generator's capabilit

to:

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) Be restored to its standby status.

9) 40) Verifying that with the diesel generator operating in a test 4

mode, connected to its bus, a simulated Safety injection signal overrides the test mode by: (1) retuming the diesel generator to standby operation and (2) automatically energizing the i

emergency loads with offsite power; 10)

) 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; and

11) 2) Verifying that the automatic LOCA and Shutdown sequence timer i

is OPERABLE with the interval between each load block within 110% of its design interval.

" !r d = = p ~ 10 y =r: Or :'ter =y =$f::M!0 = r hie e r'd affect fer' ;=:re!~ !nterdepender by :teing" Mth fre!

generator: !=" n-^=!y, during detdem, =d verifying th t Mth

+r-! gecret~e ecc': te te et !rd 51' rpm !n !r: th= Or C

h. At least once per 10 years verify that when started simultaneously from standby conditions," each diesel generator achieves in less I

than or equal to 12 seconds, a voltage of 4160 + 160 420 volts and a frequency of 6011.2 Hz.

!! e---*rt5 4.8.L t.2geb !: ^^t rt!9^'~!!y =m;!:t:d, " !: net

--^--- / !0 repet the prrefn; 24 h=r !=t, '-W d, 'M fer! ;=0r:

ter my M ^per9d eta 201 kW !0:

h=r er ="! rpe'eting ! mperature he q'f!" ?

This surveillance shal not be performed in Modes 1, or 2 and credit ay_be taken_f_or unplanneyd eventhat satisfy this.

utrement.

"This test shall be pre ~ ceded Dy an engirie preIube perio) an or o er warmup procedures recommended by the manufacturer so that the mechanical stress and r on the diesel ngine is m' imized.

"This surve 11 nee e 11 not be pe ormed in Modes 1,2,3, or 4 and credit a be taken for unplanned events that satisfy this requirement.

WOLF CREEK - UNIT 1 3/4 8-6 Amendment No 8

~.

Attechment IV to ET 95-0099 Pega 12 of 23 2

FLECTRICAL POWER SYSTEMS SURVElLLANCE REQUIREMENTS (Continued)

1. At least once per 10 years by:

1) Draining each fuel oil storage tank, re Ov:ng th-r~2 u!:!:d sedunentend c'erntng !.'- !:nk eeing a r^d!u-hyp^^h! '"e

.__i,._:_~.__,._....i...

2) Removing the accumulated sediment,

3) Cleaning the tank to remove microbiological growth.

m.4...e _o.,.._.. a n. a_ :..,._.,..~.. e. m a..._...,.._.n..a_,. ~......c..a.,. u..n.

..... u.ai,.. c

.i o _ ~... u r,._ _:,..:........

..m w

e ~.:,u..:m. e' =o o...aw : on,....'. o'._-.'..,., a:..

'......', s n.....

..r-----'

r-----

-r

-r-w- --' -' '. c.. o.. w,,

...w, n. i m_a_._.a_._.w'. i.a..~.. _....' :~_.. _ ~_ _ __r - - 'a_ i. o.._.,.._... _ ~. y r - - - - - - - - - - - -

--- i-

o. ~_ _. a:....

o. _.i. ~., n_._.u_ _._ < 4. n..o, o...: : ~.

4.,.a._..... 4..av. v is.u.....

u_.,.,,,., a.... :

the !::t 1aa u !!d tr& (en a per nuc'e?' u 't bre:r) !c ;rrete hen ~

.._.. i., u.. ~.. un u.. i_

.a.,. i, i..,a

.u. a,aa :~.

-._.o'--'-'.c..o..,--------'~,

i.a.. m.. _.. im....~_ _m_

. a' m_ _e' g o..._.,....

m, r----

rr--

..o.,...i..._.

. ~_ a :~.. w n_..ia.

4. n. o., o...:

i.m_. 4, a.._.,.._.._. 4. o. v.,

WOLF CREEK UNIT 1 3/4 8-6a Amendment No. 8,60 1

_~ n.

~

Attachment IV to ET 95-0099

'PIgt 13 of 23-t htCCCf t"icklCD ATr\\D TCCT C/'t.JCMI 11 C 6

.LAST-2GVAL40-TESTSt TEST.AEQUENCY 4

ggm _.. 2 4. A

.,.a.

^^OO "U 3

r i.

t t

I a

1 -_m,as.s.a..L

.- a.f. s.a mt.id. s. _a:I.m_ise...an.,4.as.m...L - - n.i. s.m.a l' A Ga_ m am Of. ene.m.e.l.m. I.a.n _J -_ _. _..........

.a

.I.rs. n_ e_e_^rA nn.a_n m.a.dek O.=,na ntaenn,e.O^m:a:an. (.% $... af. Dan, alnean,, f*, alA_m.

4. 4. M. O,D.-..:-:a. n.. 4.. A.a_a,.a_im_ e 4 077, km a.t..J

'..- '...- A. a.n...a esn.,.A._ :. n. af, a n.a.,.ma,a. r 7

g..

aI M ^ A-=segEnlam Shn ram,s aarad Sam e Iraan earant,e Aka Cap tha na nestam am h em am- - - - - - ' -' ' ' ' - r -' r - - - - '.wa m-s-l.a. _g ara. II.a a_n=.=.malaea _ _ _ _

N'-

t-A"am al es ma.nla_ n_ie_ e.m_m e. f. _al.l.a_s em. c_a_ n_in.s.t..,.

r.u.sa.rk. _m a al G.a. laL.a.

a.m.a.n. man. A_l.e.ma_ n. s.a la e.n.m. el.a m d

,s,as,tdad th at Ska as sark an nt r-----sr'------*----"-'

I..MO. 3%J.%m.0. WW.h.m!n..d.a.n...an. 'An anar melan ad &amaannle'-

. 7 r-------'"'"'---'sa m a, m.e.l.C..e..nM..a,s a nns. a.s a. A ki,, e,,k..n.

en...an. id. me.t.a. ara.,,.an.A is. se_emsst. akin sali nk:t.6.,,

k. a m ka_ m_ e.4 N.a.swt.a.n...m 0.r e0 A_. Th.a. emIIakIta&.s,i ArEO.a.N.A.n.,.s k..a.ll. lsa. e,h.n. c_ a_nn_ e_ mm e 8. al e.am.e.s.elmal4,s af 4 J ennm an, nah an gang, in M'

- - ' - - ' Tan af akm. one em m a,1mm r-----'-'

.a. a8_ OnE..m.EI._Nm i.&.d.aI..., h8_ g.. O_ n.aJ%n.m.

..._a.. O n..

..........O..,

n I.n.a.lf.Omm0m, In.

Spec $.E.aA_ a&anst J..O.4 4..D8.. 18 Ok.am n_N.4.a.ria.n..

la. n.#.e.

A. A.kN.s%.M, h.k.a. E. arm.$. a m.a. lam. n.8. O.a. m 0m_,.ma.t,a m U ^ ms.t..m.0.m. M_r50.A.N.a.n..

la. km a.am.m. A l.a t.r.an.sm.anin am e.h.m. In:li s,m. e_ n_ n_an..e l.a..m asa..em.m,an.alna.m..k.lD./.4 anarammal rr---="

$g S.a.m.8. f.r. aan_aan..m.a,s a.k..al.f k.m.

a=.s..a lm..e..nla..n.d,.s.n.6l.l s. -..- -=. enam ana_. Ah = =

k..m* sa ka. nn.. esacE.n.esm..a.M..an.A 40.%.a n.a.me.n..$sa.r.a.l. E. aIla.tra.m.

d. el. l.a.er. m. S.ea.n....

Omm0m 7

l.ame. S. A. i al.:A. a.m. m.a.m. k...an.

4 i

E f.% D.C C.l/.1.Ik..t tT. 4,

.A_nn..a. n. A -m..m s.e L.la.. O, M..

I i

i i

l 1

I

Attcchment IV to ET 95-0099 P ga 14 of.23

. El_ECTRICAL POVER SYSTEMS A.C. SOURCES SHUTDOWN 4

LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C, electrical power sources shall be 10PERABLE:

a. One circuit between the offsite transmission network and the Onsite Class 1E Distribution System, and

b. One diesel generator with:

1) A day tank containing a minimum volume of 510 gallons of fuel,

2) A fuel storage system containing a minimum volume of 85,300 gallons of fuel, and

3) A fuel transfer pump.

APPLICABILITY: MODES 5 and 6.

ACTION With less than the above minimum required A.C. electrical power sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, positive reactiv-ity changes, movement of irradiated fuel, or crane operation with loads over the spent fuel pool. In addition, when in MODE 5 with the reactor coolant loops not filled, or in MODE 6 with the water level less than 23 feet above the reactor vessel flange, irnmediately initiate corrective action to restore the required sources to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE the performance of each of the requirements of Specifications 4.8.1.1.1. n 4.8.1.1.2 (except for Specification 4.8.1.1.2a.5)g =d 4.9.4A%

+

WOLF CREEK UNIT 1 3/4 8-8 Amendment No. 8 h

, ~.

1 AttOchment IV to ET 95-0099 Paga 15 of 23 i

3/4 8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.1. 3/4.8.2 and 3/4 8.3 A.C. SOURCES. D.C. SOURCES AND ONSITE POWER DISTRIBUTION The OPERABILITY of the A.C. and D.C. power sources and associated distri-bution systems during operation ensures that sufficient power will be avail-

)

able to supply the safety-related equipment required for: (1) the safe shut-down of the facility, and (2) the mitigation and control of accident condi-tions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criterion 17 of Appendix A to 10 CFR Part 50.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commen-surate with the level of degradation. The OPERABILITY of the power sources are consistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during acci-

= dent conditions coincident with an assumed loss-of-offsite power and single failure of the other onsite A.C. source. The A.C. source and D.C. source

' allowable out-of-service times are based on Regulatory Guide 1.93,

" Availability of Electrical Power Sources", December 1974. When one diesel generator is inoperable, there is an additional ACTION requirement to verify that all required systems, subsystems, trains, compcaents and devices, that depend on the remaining OPERABLE diesel gercrator as a source of emergency power, are also OPERABLE, and that the steam-driven auxiliary feedwater pump is OPERABLE. This requirement is inter.ded to provide assurance that a loss-of-offsite power event will not result in a complete loss of safety function of critical cystems during the period one of the diesel generators is inoperable. The term verify as used in this context means to administratively check by examining logs or other information to determine if certain components are out-of service for maintenance or other reasons. It does not mean to perform the Surveillance Requirements needed to demonstrate the OPERABILITY of the component.

The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that:

(1) the facility can be maintained in the shutdown or refueling condition for extended time periods, and (2) sufficient instrumentation and control

. capabikty are available for monitoring and maintaining the unit status.

When determining compliance with action statement requirements, addition to the RCS of borated water with a concentration greater than or equal to the minimum required RWST concentration shall not be considered to be a positive reactivity change.

The Surzf'ene-Pc';u! :m:nt: Sr demen:treting the OPEP ^.9!'JTV-of4he d:rr e! ;en-rM' ere !n re-~dence r" 'he r--r m:ndMen: O! - u' ten; Ou!d:: 1.9,"90'r9^^ Of O!rre' Generebr Set CepMty Sr Stendby PC:::: Sep 1979,

199, "o ' rdt --'5g Of O! ::'

0 ::," 906!rn *, 'hver'^r 9

e Generst^' Un!!: U rd e: Onfr Eleed Pr r Sy: tem: :t Me?' Perr P'..te," 909b- *, A r rrt 197' e: : -: f': d by.^ r.dnn' '6. 9 4 "^d en "cy 29,1997, end * !??, "Fue! d! Sy:!:m: f^' Shndby O!r:r' Gener tere,"

9: i! n*,0 *rber1979.

INSERT "A" WOLF CREEK-UNIT 1 -

B 3/4 8-1 Amendment No. 59 November 22,1993 t

Attachment IV to ET 95-0099 P:gs 16 of 23 ELECTRIC POWER SYSTEMS BASES A,C. SOURCES. D C. SOURCES. AND ONSITE POWER DISTRIBUTION (Continued)

E d d!0:0! gener ter (OG) i: prev!ded w!!h en engine Over: peed trip to pr:v:n! d mege to the engine. Recovery frem the tr:nde^' ceuted by the !cee O! O ! rge !ced ceu!d reute d!ere! engine everspeed, "h! h, if exceer!ve, m!gh' retu!!!n a trip ef'he engine. The DG !ced rerpence c'ere-+et!:ce end crp9!!!!y !O reject 'he !:r;ee! :!n;!e !c2d w"hout exc-^d!n; predeter-Ined v^!!cge end frequency are dement! ret ^d wh!!e m2!ntain:ng a sp^^!'^d merg!n te the ever peed trip as requ! red by Pege!et~y Guide 1.9, o dt:en C.'

For mer!!n; Sur; !" enc ^ Pequ remente, 'he !:r;e-! :!ng!e !ced i

r

!: denned ee e !ced equ've!cn* !O the ESW pump -^ter '!!e under 'he fe!!

post-LOCA m^deof-operation, The Surveillance Requirement for demonstrating the OPERABILITY of the Station batteries are based on the recommendations of Regulatory Guide 1.129,

" Maintenance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978, and IEEE Std 450-1980, "lEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Bat-teries for Generating Stations and Substations."

Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle high discharge rates and compares the battery capacity at that time with the rated capacity.

Table 4.8-2 specifies the normallimits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity. The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and 0.015 below the manufacturers full charge specific gravity or a battery charger current that had stabilized at a low value,is characteristic of a charged cell with adequate capacity. The normal limits for each connected cell for float voltage and specific gravity, greater than 2.13 volts and not more than 0.020 below the manufacturers full charge specific gravity with an average specific gravity of all the connected cells not more than 0.010 below the manufacturers full charge specific gravity, ensures the OPERABILITY and capability of the battery.

Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 4.8-2 is permitted for up to 7 days. During this 7-day period: (1) the allowable values for electrolyte level ensures no physical damage to the plates with an adequate electron transfer capability; (2) the allowable value for the average specific gravity of all the cells, not more than 0.020 below the manufacturers recommended

~ full charge specific gravity, ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the allowable value for an individual celfs specific grevity, ensures that an individual cell's specific gravity will not be more than 0.040 below the manufacturers full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual ceirs float voltage, greater than 2.07 volts, ensures the battery's capability to perform its design function.

INSERT B" WOLF CREEK - UNIT 1 B 3/4 8-2 Amendment No. 59

Attcchment IV to ET 95-0099 Pcga 17 of 23

)

-ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The PSRC shall meet at least once per calendar month and as convened by the PSRC Chairman or his designated attemate.

- QUORUM 6.5.1.5 The quorum of the PSRC necessary for the performance of the PSRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated altemate and four mernbers including attemates.

BESPONSIBILITIES -

6.5.1.6 The PSRC shall be responsible for;

a. Review of:(1) Administrative Control Procedures and changes thereto, and (2) procedures and changes thereto required by Specification 6.8.1 and requiring a 10 CFR 50.59 safety evaluation.

b. Review of all proposed changes, tests and experiments which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR;

c. Review of all proposed changes to Technical Specifications or the Operating License;

d. Review of all safety evaluations performed under the provision of Section 50.59(a)(1),10 CFR, for changes, tests and experiments;

e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation end recommendations to prevent recurrence to the Vice President Plant Operations, and to the Nuclear Safety Review Committee (NSRC);

f. Review of all REPORTABLE EVENTS;

g. Review of reports of operating abncrmalities, deviations from expected performance of plant equipment and of unanticipated deficiencies in the design or operation of structures, systems or components that affect nuclear safety;

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman, NSRC; g, p...w eview of the Diesel Fuel Oil Testing Program;

j. Not used.

WOLF CREEK UNIT 1 6-8 Amendment No. 4A&,-68,73 1

6

Attachment IV to ET 95-0099 P:ga 18 of 23 ADMINISTRATIVE CONTROLS AUDjlS (Continued)

d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B,10 CFR Part 50, at least once per 24 months;

e. The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA or ISEG personnel;

f. - The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year;

g. The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months;

h. The ODCM and implementing procedures at least once per,24 months;

i. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months; J. The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months;

k. The Emergency Plan and implementing procedures at least once per 12 months;

1. The Security Plan and implementing procedures at least once per 12 months;-and

m. The Diesel Fuel Oil Testing Program and implementing procedures; and hm-Any other area of Unit operation considered appropriate by the NSRC or the President and Chief Executive Officer;.

RECORDS 6.5.2.9 Records of NSRC activities shall be prepared, approved, and distributed as indicated below:

a. Minutes of each NSRC meeting shall be prepared, reviewed by partici-pating members and forwarded to the President and Chief Executive Officer within 14 days following each meeting;

b. Reports of reviews encompassed by Specification 6.5.2.7 above, shall be prepared, reviewed by participating members and forwarded to the President and Chief Executive Officer within 14 days following com-pletion of the review; and WOLF CREEK UNIT 1 6-12 Amendment No. 4 v

=_

m Attachment IV to ET 95-0099 Piga 19'of 23 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

e. Process Control Program implementation;

f. ODCM implementation;4nd g Quality Assurance Program implementation for effluent and environ-mental monitoring; h

ire eti P ram i lementatio and

1. Diesel Fuel Oi Testing Progranilmplementation.

4 6.8.2 Each procedure of Specification 6.8.1 and changes thereto; and any 1

other procedure or procedure change that the Vice President Plant Operations determines to affect nuclear safety, shall be reviewed and approved as described below, prior to implementation.

a. Each procedure, or change thereto shall be reviewed by a Qualified Reviewer who is knowledgeable in the functional area affected, but is not the individual who prepared the procedure or procedure

. change. All required cross-disciplinary reviews of new procedures, procedure revisions or change thereto shall be completed prior to approval.

b. Procedures other than Administrative Control Procedures shall be approved by the responsible Manager or his designee as specified in

' Administrative Control Procedures. The Vice President Plant i

Operations shall approve Administrative Control Procedures. The Manager responsible for the Security Plan shall approve the Security Plan and implementing procedures. The Manager responsible for Emergency Planning shall approve the Radiological Emergency Response Plan and implementing procedures.

c. The responsible Manager or his designee shall ensure each review includes a determination of whether a procedure, or change thereto, requires a 10 CFR 50.59 safety evaluation, if a procedure, or change thereto, requires a 10 CFR 50.59 safety evaluation, the responsible Manager or his designee shall forward the procedure, or change thereto with the associated 10 CFR 50.59 safety evaluation to the PSRC for review in accordance with Specification 6.5.1.6.a.

Pursuant to Section 50.59,10 CFR, NRC approval of items involving unreviewed safety questions shall be obtained prior to approval for implementation.

d. Qualified Reviewers shall beet the applicable quahfications of ANSI /ANS 3.1-1978. Personnel recommended to be Qualified Reviewers shall be reviewed by the PSRC and approved and documented by the PSRC Chairman. The responsible Manager shall ensure that a sufficient complement of Qualified Reviewers for their functional area is maintained in accordance with Administrative Control Procedures.

e. Records documenting the activities performed under Specification 6.8.2.a. through 6.8.2.d shall be maintained in accordance with Specification 6.10.

i WOLF CREEK - UNIT 1 6-14 Amendment No. 4,15,45,55,73 l

l

h Attcchment'IV to ET 95-0099 Piga 20 of-23 ADMINISTRATIVE CONTROLS f-nSCEDURES AND PRQGBBdS (Continued)

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to Appendix 1 to 10 CFR Part 50,

9) ' Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from lodine-131, lodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas beyond the SITE BOUNDARY conforming to Appendix i to 10 CFR Part 50,

10) Limitations on the annual dose or dose commitment to any MEMBER' OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f. Radioloaical Environmental Monitorina Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) repre-sentative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix i to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and the modifications to the monitoring program are made if required by the results of this census, and

3) Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program r environmental monitoring.

I SERT "C" 654EPORTjNG REQUIREMENTS ROUTINE REPORTS 6.9.1 in addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the NRC Regional Office unless otherwise noted.

WOLF CREEK UNIT 1 6-18 Amendment No. 42

Attachment IV to ET 95-0099 Page 21 of 23 INSERT "A" The surveillance requirements of Technical Specification 3/4.8.1 are based upon, in part, the guidance of Generic Letter 94-01, " Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators From Plant Technical Specifications" Generic Letter 93-05, "Line-item Technical Specifications improvements to Reduce Surveillance Requirements for Testing During Power Operation," Regulatory Guide 1.9, " Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1E Onsite Electrical Power Systems at Nuclear Power Plants," Revision 3, and NUREG-1431, " Standard Technical Specifications - Westinghouse Plants." Also, the guidance of NUMARC 87-00, " Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors," Revision 1, and Regulatory Guide 1.160 has been adopted to formulate a comprehensive Emergency Diesel 4

Generator Reliability Program.

Technical Specification 3.8.1.1, Action b and c, require, in part, the demonstration of the operabikty of the remaining operable emergency diesel generator by performing Technical Specification 4.8.1.1.2a.4. This test is required to be completed regardless of when the inoperable emergency diesel generator is restored to operable status unless the emergency diesel generator was declared inoperable to do preplanned preventative maintenance, testing, or maintenance to correct a condition which, if left uncorrected, would not affect the operability of the emergency diesel generator. The requirement to test the remaining operable emergency diesel generator when one emergency diesel generator is inoperable is limited to those situations where the cause for inoperability can not be conclusively demonstrated in order to preclude the potential for common mode failures. The test is not required to be accomplished if the emergency diesel generator was declared inoperable due to an inoperable support system or an independently testable component. When such a test is required, it is required to Le performed within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of having determined that the emergency diesel generator is inoperable.

Technical Specification 4.8.1.1.2a.4 is considered to be a " Start Test" as described in Regulatory Guide 1.9, Revision 3.

A " Start Test" is performed to demonstrate proper startup from standby conditions and to verify that the required design voltage and frequency is attained. For these tests, Regulatory Guide 1.9, Revision 3, recommends that the emergency diesel generators be slow started and allowed to reach rated speed on a prescribed schedule that is selected to minimize stress and wear.

Regulatory Guide 1.9, Revision 3, considers Technical Specification 4.8.1.1.2a.5 to be a " Load-Run Test". A " Load-Run Test" demonstrates 90 to 100 percent (5580 to 6201 kilowatts) of the continuous rating (6201 kilowatts) of the emergency diesel generator for an interval of not less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and until temperature equilibrium has been attained. This test may be accomplished by synchronizing the generator with offsite power and the loading and unloading of an diesel generator during this test should be gradual and based on a prescribed schedule that is selected to minimize stress and wear on the diesel generator.

Regulatory Guide 1.9, Revision 3, considers Technical Specification 4.8.1.1.2b to be a " Fast-Start Test". A " Fast-Start Test" demonstrates that each emergency diesel generator starts from standby conditions. If a plant normally has in operation keep warm systems designed to maintain lube oil and jacket water cooling at certain temperatures or prelubrication systems or both, this would constitute normal standby conditions for that plant. Verification that the emergency diesel generator reaches required voltage and frequency within acceptable limits and time is also required.

The requirements of the " Single-Load Rejection Test" and the " Full-Load Rejection Test" as described in Regulatory Guide 1.9, Revision 3 have been combined. The " Full-Load Rejection Test"is a demonstration of the emergency diesel generator's capability to reject a load equal to 90 to 100 percent of its continuous rating (5580 to 6201 kilowatts) while operating at a power factor between 0.8 and 0.9 and that the voltage does not exceed 4784 volts and that the frequency does not exceed 65.4 Hertz following a load rejection of 5580 to 6201 kilowatts. The frequency criteria is from the

" Single-Load Rejection Test" and is based on nominal engine speed plus 75 percent of the difference between nominal speed and the over-speed trip setpoint.

The note that will not allow a surveillance requirement to be performed in Modes 1 or 2 is based on the improved Standard Technical Specifications (NUREG-1431) which recognizes that the performance of certain surveillance requirements during operation with the reactor critical could cause perturbations to the electrical distribution systems that could challenge continued steady state operation and, as a result, unit safety systems. However, this note does not preclude operating the emergency diesel generator with the reactor critical, as necessary, to support operational conditions.

t

Attcchm:nt IV to ET 95-0099 P ga 22 of 23 INSERT"B" DIESEL FUEL OIL TESTING PROGRAM in accordance with Technical Specification 6.8.4, a Diesel Fuel Oil Testing Program to implement required testing of both new fuel oil and stored fuel oil shall be established. For the intent of this specification, new fuel oil shall represent diesel fuel oil that has not been added to the Diesel Fuel Oil Storage Tanks. Once the fuel oil is added to the Diesel Fuel Oil Storage Tanks, the diesel fuel oil is considered stored fuel oil, and shall meet the Technical Specification requirements for stored fuel oil.

Tests listed below are a means of determining whether new fuel oil is of the appropriate grade and has not been contaminated with substances that would have an immediate detrimental impact on diesel engine combustion. If results from these tests are within acceptable limits, the new fuel oil may be added to the storage tanks without concern for contaminating the entire volume of fuel oil in the storage tanks. These tests are to be con (*ucted prior to adding the new fuel to the storage tanks, but in no case is the time between receipt of the new fuel oil and conducting the tests to exceed 30 days. The tests, limits, and applicable ASTM standards being used to evaluate the condition of new fuel oil are:

1.

By sampling new fuel oil based on ASTM D4057 prior to addition to storage tanks and:

2.

By verifying based on the tests specified in ASTM D975-81 prior to addition to the storage tanks that the sample has:

a)

An API Gravity of within 0.3 degrees at 60'F or a specific gravity of within 0.0016 at 60/60 'F, when compared to the supplier's certificate or an absolute specific gravity at 60/60 'F or greater than or equal to 0.83 but less than or equal to 0.89 or an API gravity of greater than or equal to 27 degrees but less than or equal to 39 degrees; b)

A kinematic viscosity at 40 'C of groater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, if gravity was not dete mined by comparison with the supplier's certification; c)

A flash point equal to or greater the1125 'F; and d)

A water and sediment content of less than or equal to 0.05% when tested based on ASTM D1796-83.

Failure to meet any of the above limits is cause for rejecting the new fuel oil, but does not represent a failure to meet the Limiting Condition for Operation of Technical Specification 3.8.1.1 since the new fuel oil has not been added to the diesel fuel oil storage tanks.

Within 30 days following the initial new fuel oil sample, the fuel oil is analyzed to establish that the other properties specified in Table 1 of ASTM D975-81 are met when tested based on ASTM D975-81 except that the analysis for sulfur may be performed based on ASTM D1552-79, ASTM D2622-82, or ASTM D4294-90. An exception to ASTM D129, which is specified in ASTM D975-81, has been taken. ASTM D129 uses a Barium precipitation method for the determination of sulfate after oxidation has occurred. The use of any wet lab sulfate analysis is acceptable since the determination is made in the aqueous rinse water for the oxidation process. In the event the correct fuel oil properties are not met, Action g provides sa additional 30 days from the time that it is determined that the correct fuel oil properties are not met to meet the Diesel h. Oil Testing Program limits. The additional 30 day period is acceptable because the fuel oil properties of interest, even if they are not within limits, would not have an immediate effect on emergency diesel generator operation. The diesel fuel oil surveillance in accordance with the Diesel Fuel Oil Testing Program will ensure the availability of high quality diesel fuel oil for the emergency diesel generators.

At lease once every 31 days, a sample of fuel oil is obtained from the storage tanks based on ASTM D2276-83. The particulate contamination is verified to be less than 10 mg/ liter when checked based on ASTM D2276-83, Method A. The filter size for the determination of particulate contamination will be 3.0 micron instead of 0.8 micron as specified by ASTM D2276-83. The filtered amount of diesel fuel oil will be approximately one liter when possible. Also, it is acceptable to obtain a field sample for subsequent laboratory testing in lieu of field testing.

Fuel oil degradation during long term storage shows up as an increase in particulate, due mostly to oxidation. The presence of particulate does not mean the fuel oli will not burn properly in a diesel engine. The particulate can cause fouling of filters and fuel oil injection equipment which can cause engine failure.

The frequency for performing surveillance on stored fuel oil is based on stored fuel oil degradation trends which indicate that particul ate concentration is unlikely to change significantly between surveillances.

~

.~

Att0chment IV to ET 95-0099 Prg3l23'of.23 INSERT "C"

. g. Danel Fuel Oil Testina Proaram i

A diesel fuel oil testing program to implement required testing of both new -

- l l

fuel oil and stored fuel oil. The program shallinclude sampling and testing requirements, and acceptance criteria, based on the applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

l

1. an API gravity or an absolute specific gravity within limits,

2. a flash point within limits for ASTM 2D fuel oil,

3. ~ a kinematic viscosity within limits for ASTM 2D fuel oil,-

4. a water and sediment content within the limits for ASTM 2D fuel oil;

' b.. Other properties for ASTM 2D fuel oil are within limits within 30 days following sampling and addition of new fuel oil to storage tanks; and -

c. : Total particulate concentration of the stored fuel oil is < 10 mg/ liter when tested

' every 31 days based on the applicable ASTM Standards.

i h.' Emeroency Diesel Generator Reliability Proaram An emergency diosel generator reliability program that establishes the requirements and guidelines for emergency diesel generator reliability, availability, and monitoring.

The program shall include the following:

a.- Emergency diesel generator reliability performance goals (target reliability) based upon the station blackout coping assessment. Target reliability goal monitoring is accomplished through monitoring methods that are based upon those described in Appendix D of NUMARC 87-00,

b. Measures to ensure detailed root cause analysis of emergency diesel generator failures is performed and effective corrective actions are taken in response to failures,

c. Implementation of an emergency diesel generator preventive maintenance program that is consistent with the Maintenance Rule, and

d. - Monitoring of emergency diesel generator availability and performance parameters to ensure the target reliability is met or exceeded.

[

b Y

9 i

s

+

1' s

a

~

m

ML20092J414

Text

Navigation menu

Search