ML20216J832

Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases.Change Extends LCO for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer

ML20216J832
Person / Time
Site:	FitzPatrick
Issue date:	09/29/1999
From:	James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20216J385	List: JPN-99-030, Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days ML20216J387 ML20216J832
References
NUDOCS 9910060218
Download: ML20216J832 (1)

Text

-..

Attechment i to JPN-99-030 l

• REVISED TECHNICAL SPECIFICATION PAGES ONE-TIME-ONLY CHANGE TO THE TECHNICAL SPECIFICATIONS REGARDING RHRSW ALLOWABLE OUT-OF-SERVICE TIME (JPTS-99-005) l l

l l

l l

1 l

l l

i l

i New York Power Authority JAMES A. FITZ?ATRICK NUCLEAR POWER PLANT Docket No. 50-333

' 9-59 9910060219 ADOCK O 633 P,DR ._

k.

. lE

. r t

o eey m c a

e m e hdl eeb e t r t oet s d he e ,ma s yyth sil st o e u -

t b gd l

i ebay sft in f an e mud o s duse b od t n

o s s orlim eo c y

a r

a ppom cgnsti e na he ni re f

r, e

D Y e moc n ie bi l olycn v n

• _ ui tl p moe ao . itr#

a*Y y 3 1

5 s nb ect epe r e s#

c n r e

r e

p Wiea Svnp emre ynd t

sti seepc aoll a

inmbt e a f W'

S' e p Roio a R#

u e bmmmgsehr H a e c H bt e u n R '" .

e r

c n n Ran b o simun a i pin s t h * *

• A **

F O O e 1 co o e t gt nnl eWimy a ei l h'

e' n B. h d t 5. t e liob oc arReysd Smt a t o"

)

t#

h criti r c s ha3ff i

oi r otnp eHr sd c S*5 _

a e at oi n s t n is e t nd aoRebn hua 9 DA -

ew mahdd e yle d edn t v e r en e mubno engle et s

, y 9*

n e ebe 9' t

apto ot leee beaz .

n r h n.

ir h ,uhaut la thr l

po z minuoll t f ndo nbi a iet l

t o' tla at ec o sn r qpaa ar e raoi l i t

a n urp a seini hn c #'

,s ss it sotndn eemhe t r n ed t

e hepcode i #'

f io n o t a ,

a wde seio ,p tde s a e

dst o c sh sre ohiWot c ,e t f i m do" I" cmdo efl ki n cwo t t e em mn s sn iegmt ee v r

r.ieinnm m

f N i(

f r

t ieaeoric eir t e r ri iaf o atd r

e t ni tl n ey nb l

oa ef t e nl esme o# n" I e

m ev rhl vlap et otthsr oo r na neoe in on pi yd s ia a s n rbamib el er ot aa i*

o t i avoinopcn e r e e pl

) It apch hmo mbd e sa un hon ha e cne na* '*'

d

't n

Wcr Wistbcoheop i t

s*

n o . e c e f m

( . .

g 2 3 n 5 n P u P 4 D N 6 -

F 1 A l 1

J n la e i

h t e4 g in d d sd yo c n d e

r e a a m2n in ie _

iui u

n dm s e n d 7 ei bh t iaef rr ic qt 0g mir en 3i n tept e o e t i tu rt o rap e

r och e ho l smc c ow n s s co y u ax n n t

a rps e l ne gst u c t ,t bpr s ee ao e a i el u o ct i

pm ) 2 nbn r g en sWdt i

otes(t o ai n 3. ^r per u im gSuoet o r 3 m pd run nRnn B. c o tn n 0 o nl o yd a i i Hi t

5. d ta cl n e 2 cint t loRnd o oio 3l o aoo eop 1 ed hnet oa ho c

n cecr n ,e r o c r

cm 7 1

t ul t

n o lep dr no oc f oi b de of seh edba 2. a at 3 pro iisdt mlu raro B. w gac e l 5

m mvfoe i noef ahp 5. de neb ir a 1

u er or a l

tn saie 3c a t r p appt sb sh et pe 7

de r nb fl 5 s nr o op c oii s ti Wmsiy enp e e es se sw c

on 1 a tb Rbon d o o Se id i S pe helbmim n l sen i t a o r el a yt a det0ma i r f r c e eep mh hi t l

Pva3o r opb es pm ie h t

5 e o egc s eo s r r r n bpngm o a oidn e nnmi o et ie on ir uo qt e ewv wp Fbo 9

d 1 ro eiy e n i s t si ec r a oe a 3 t

lu B. ct c a s d lu m osr y a 's. e er pb *2 B. o wll 1 a ucmb ocbey h t e a25 N

- )

d ho 5. e S3rsr s eu heupa Sbsod fhrth oh Ls<3 t

't I

n n e o . . . m c 2 3 4 5 d

(

n 5 e m

3 A

[

~

. hef ithc nr goser er ad e w#'

'o epw e n wt yt i r et ot he n e gh Ca y dnt w dt u ro l

gea nf e m#eeKyu r htes e o on sp it f l

'. i nhs nwe oa o e v t n d i a

t s p e wco ie f

ice r

t yr r

l no ht f o sl nCe s is t

cusiLoPht es I

y hs nNh s

e

'sh kt r, 8 e e n p

p o of t cyr s e s t a

d e eh ereb ot h

s a rd r e

pt e u i

f f

e pepfr d r h pee o bss *"e osb e e

r t

t t w ocq e eTur s heec t

s C" m new '" m p d u er ht w f we -

o r d o . eTf i

r e

o nto e pF h a m"*ah c

y p tcco n n a t

. y -

nw r

a e i s iw2 m 1 a t Fl e A"bp

- en eo i

a r eR r el o 2h*0s t r m sn p b H t 7 e o oe e

r y

d nl aifl R dnegww1 v d i oo e da s*ht t

s - yo s f e

d a woe totceh l ubs e cb e o*

ss*n "se cna g ed n n d s e it st o dnr n xt n rv #c v snm aoo mc oi et on o e n e

s t ee ng ne t t alaol iwee

• e t

o s/u ri gi s*.

a s pl on i ei l eh glc uni l

w d nin f ks s or e s

n i

cmo s o co bwicws nai n

l l

f r

daop rf e u

r ia m

e h

yc p~

ee t

n e

var e te haCt ivr iae t uy s m

e#nE#c dn o

n e6 n

o *" o f A r

rbmt n l

Or at a ** so cf4 s m Yaye m e wri an a sL n

o s ra spa ov t r aS e

r eyA s'r "t W t t

e s optealp po n e iti a senmrC e'u6m h

e t

n6sE s

y apo e pO t n oh a e oe n#n l

s uboct SL optr h P

e n

wict o

lca m 7

2 P o L C

• 1 N

F A t eeoe Rrfeoamsege t

. enc s gh t e al J nhht et t id Ht ee sznr e e i i t vl ahb m r eodv Ra wle htsL odnh ri aaoe i

t ar -

nmFiot aa t ueo impr e bey p t e o m cee e ql cecp heahsbn i

ao t l

baf on _

t r nf .l o f v icpt uioe er nddt a _

o t ns t

ore cgah st j i aonr ei

/c y e i e l

(

u er nl h cyes sme mpt eh se l gd e p e s h roh ust .i o Cecumri r d t f u o f sdgn oianieoo nm Pncsa L o Rtahi Hp t E gi o t nil jm eas inr e er ootn b de c

.l o eo t

e ht e t nph en r a mRwl g o swmpc ooeb t eri tr ct s a s t a el a n wfoloot pnot nmt n yiu an d Bme y t eco o hom i

S f or e l

ot pe ee R ne - c t o er o ,aon n s nq a er remhfi t i

r .ts H c s isie e s n ersy ovfogm. -

pd stamo aga amvubs yi R

e it on it oms sloi sy r

t nmn e uap roia e n.n d yi nd nt or i sc cu pe mP o s l

h r ot ,i l

p ct pt i o y- of r n

l t

l l

n r a eb Resruyonmiot r b r c em ng a

ac pu apetciepe oi n v o aeop ia f

o t Hg hh t

(

o t f mfe a nRneme il st o md to ainrel c t

e o ah t r ih r ah ect a f to syd o i

d coh c pt ,o nc _

o ee rd nt enth vao t

M t ivvo , ht ewxmeot r o gagyt nwisemml nf f eb e oc n t 1

a a oecd i il e t ae e nm e t

k m e lot e r f f 5 n c oscy ayt sr s vm f ot a reac froic 1

h peear o -

n ye on i

lo hh s sp obi a o

t ns t t ga t set ab re r t v n ab S _

mtsh at

)

d C ein id ph m et ie

,ise ei s t wdn fpseenaduge c n snh e no i

l sne yonga oRmsu n pd enTt c t h _

n n nf 8 d i

't n e id e n r o

c m taoeic nmme ni r

bscoiel t eHimrenia Rt a u o m n.heen ne N

r.

(

i n o npau i sh q u) smsu na,l agb eoce npef e o S

E t a

n cya t er ht epcrh apn a mori os c wney t t

n e

S o e ratnws e csmicc c o ere sse nyhl iLs ofon d u woa ayu ESpr e e.s x otf thh m A h poos n B C Tscf leh l t i d n

e 5 . m 3 B A

i Attachm nt 11 to JPN-99-030 SAFETY EVALUATION ONE-TIME-ONLY CHANGE TO THE TECHNICAL SPECIFICATIONS REGARDING RHRSW ALLOWABLE OUT-OF-SERVICE TIME (JPTS-99-005) I l

i l

i l

l New York Power Authority l JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59

F Attichm:nt ll t) JPN-99-030 SAFETY EVALUATION l Page 1 of 5

1. -

DESCRIPTION l l

This proposed change to the James A. FitzPatrick Nuclear Power Plant (JAF)

Technical Specifications (TS) extends the Limiting Condition for Operation (LCO) for the Residual Heat Removal (RHR) Service Water (RHRSW) system from 7 days to 11 l days with special conditions to allow for installation of a modification to the division l

"A" RHRSW strainer.

The applicability of this proposed change is limited to the one-time-only installation of this mod fication on the "A" RHRSW strainer.

The Specific changes are as follows:

1 Technical Specification 3.5.B.3 l Add the following qualifying note:

I "During the installation of modification 99-095 to the "A " RHRSW strainer, l

continued reactor operation is permissible for a period not to exceed 11 days. "

Bases for Technical Specification 3.5.B.

Add the following qualifying note:

"During the installation of modification 99-095 to the "A " RHRSW strainer, the seven day repair period may be extended to eleven days. The l

Conditional Core Damage Probability with the plant in this configuration for '

eleven days has been determined to be below the thresholdprobability of 1 E-6 for risk significance of temporary changes to the plant configuration in the EPRI PSA Applications Guide."

ll. PURPOSE OF THE PROPOSED CHANGE Each train of the JAF RHRSW system has two RHRSW pumps, configured with a i common header. The common header discharges into a duplex strainer, which then discharges to the system loads. Each duplex strainer is configured with a flow porting mechanism for directing RHRSW flow through either of the two strainer baskets to allow on-line cleaning of the other basket. The flow porting mechanism consists of two opposing crank operated piston / cylinder assemblies, which perform the flow porting function. Each piston / cylinder assembly is configured with a compression packing / stuffing box to minimize leakage between the piston ram and the strainer body.

The packing gland on the A RHRSW strainer is degrading due to corrosion. To ensure RHRSW strainer operability, the packing gland has been tack-welded in place in accordance with the FitzPatrick Ternporary Modification Program. This temporary repair effectively mitigates the effects of this degraded condition.

l l

[

T .

~

I Attichm:nt 11 ta JPN-99-030 SAFETY EVALUATION Page 2 of 5 in order to correct this degraded condition, a permanent modification has been developed which will replace the degraded packing gland with that of a new design. l This new packing gland design is a significant improvement over the existing design in terms of leak-tight peformance and reliability.

The Authority staff has estimated that the RHRSW strainer modification installation l will require approximately 7 days to complete. The current LCO allowable out of l service time for a single division of the RHRSW system is 7 days. The projected l modification installation schedule does not allow for unforeseen eventualities during modification installation, which could extend the RHRSW system outage beyond the ,

7 day LCO allowable out of service time in the current TS and would therefore result '

in a forced plant shutdown.

This proposed change to the FitzPatrick TS allows for unforeseen eventualities in the modification installation schedule described above. The applicability of this proposed change is limited to the one-time-only installation of the RHRSW strainer modification on the division "A" of RHRSW.

Ill. SAFETY IMPLICATIONS OF THE PROPOSED CHANGE This proposed change extends the Limiting Condition for Operation (LCO) for the Residual Heat Removal Service Water (RHRSW) system from 7 days to 11 days with special conditions to allow for installation of a modification to the division "A" RHRSW strainer. This modification corrects a degraded condition in the "A" RHRSW strainer and therefore results in improved safety system reliability.

The core damage frequency (CDF) impact associated with removing one division of RHRSW from service with the plant at pcwer is currently evaluated in support of the JAF Configuration Risk Management Program (CRMP) (Reference 1). The increase in CDF, over the base, for this configuration is 2.14 E-6 per year (Reference 2). For an 11-day allowable outage time, the Conditional Core Damage Probability is 6.4 E-8.

Plant risk will be managed during this proposed, extended LCO timeframe in accordance with FitzPatrick's existing Configuration Risk Management Program (CRMP) (Reference 1). This is an appropriate control because the Core Damage Frequency used to compute the Conditional Core Damage Probability due to this proposed char.ge is consistent with the existing risk assessment program Configuration Risk Management Program.

An element of this program is the development of a contingency plan for this plant configuration. For the RHRSW modification installation, the contingency plan will be l to provide an alternate means of achieving flow on the division "A" of RHRSW via a j temporary connection to the Fire Protection system header. This will provide a means of achieving limited containment cooling in the event the "B" division of RHRSW were rendered inoperable during the "A" RHRSW strainer modification.

i

Attichm:nt il to JPN 99-030 SAFETY EVALUATION )

Page 3 of 5 This temporary connection is achieved by connecting a temporary hose to cross tie connections, which are permanently installed, between the RHRSW system and the Fire Protection system. Instructions for installing this crosstie exist in current plant j procedures and the material required for crosstie installation is permanently pre- )

staged in an equipment cabinet in the RHRSW pump room. During the time the "A" RHRSW strainer pressure boundary is breached, system pressure boundary integrity will be maintained to support this contingency by the uso of a temporary plug. This plug will be located at the work site and instructions will be developed for installation and use of the plug prior to the start of the "A" RHRSW modification

' installation.

The conditional core damage probability of 6.4 E-8 falls below the threshold probability of 1 E-6 for risk significance of temporary changes to the plant '

configuration in the EPRI PSA Applications Guide (Reference 3) and is therefore not considered to be risk significant.

IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Operation of the FitzPatrick plant in accordance with the proposed amendment would not involve a significant hazards consideration as defined in 10 CFR 50.92 since it would not:

Involve an increase in the probability or consequences of an accident previously evaluated.

The Conditional Core Damage Prc bability due to this proposed change is calculated to be 6.4 E-8. This value falls below the threshold probability of 1 E-6 for risk significance of temporary changes to the plant configuration in the EPRI PSA Applications Guide (Reference 3).

This proposed change does not increase the consequences of an accident previously evaluated because all relevant accidents (LOCA) would result in the transfer of decay heat to the suppression pool. For this scenario, the same compliment of equipment will be available to achieve and maintain cold shutdown as is required by the current Technical Specification LCO.

Create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed change does not physically alter the plant. As such, no new or different types of equipment will be installed. The new design for the RHRSW strainer packing gland will be evaluated under a separate 10 CFR 50.59 uvaluation and is considered to be functionally equivalent for the purposes of this one-time-only proposed Technical Specification change. I 1

The implementation and use of the contingency plan for achieving limited )

containment heat removal in the event the B division of RHRSW is rendered i inoperable will be evaluated under the Authority's 10 CFR 50.59 program.

l

1 f

l. ~

! Att: chm:nt 11 tn JPN-99-030 SAFETY EVALUATION Page 4 of 5 Involve a significant reduction in a margin of safety.

l l Tho Conditional Core Damage Probability due to this proposed change is

! calculated to be 6.4 E-8. This value falls below the threshold probability of 1 E-l 6 for risk significance of temporary changes to the plant configuration in the EPRI PSA Applications Guide (Reference 3) .

The consequences of a postulated accident occurring during the extended allowable out-service time are bounded by existing analyses therefore there is no significant reduction in a margin of safety. 1 V. IMPLEMENTATION OF THE PROPOSED CHANGE This amendment request meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) is follows:

(i) The amendment involves no significant hazards consideration.

As described in Section IV of this evaluation, the proposed change involves no significant hazards consideration.

I (ii) There is no significant change in the types or significant increase in the i amounts of any effluents that may be released offsite.

The proposed change does not involve the installation of any new equipment, or the modification of any equipment that may affect the types or amounts of effluents that may be released offsite. Therefore, there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.

(iii) There is no significant increase in individual or cumulative occupational radiation exposure.

The proposed changes do not involve plant physical changes, or introduce any new mode of plant operation. Therefore, there is no significant increase in individual or cumulative occupational radiation exposure.

Based on the above, the Authority concludes that the proposed changes meet the criteria specified in 10 CFR 51.22 for a categorical exclusion from the requirements of 10 CFR 51.21 relative to requiring a specific environmental assessment by the Commission.

l

Att: chm:;nt 11 to JPN 99-030 SAFETY EVALUATION Page 5 of 5 i VI. - ' CONCLUSION The core damage frequency (CDF) impact associated with removing one division of RHRSW from service with the plant at power is currently evaluated in support l of the FitzPatrick CRMP. The increase in CDF, over the base, for this '

configuration is 2.14 E-6 per year. For an 11-day allowable outage time, the Conditional Core Damage Probability is 6.4 E-8. This Conditional Core Damage Probability falls below the threshold probability of 1 E-6 for risk significance of temporary changes to the plant configuration in the EPRI PSA Applications Guide j and is therefore not considered to be risk significant. In addition, Modification 99-095 corrects a degraded condition in the "A" RHRSW strainer and therefore results in improved safety system reliability. Based on the above, no question of ,

safety exists.

The Plant Operating Review Committee (PORC) and Safety Review Committee l (SRC) have reviewed this proposed change to the TS and have concluded that it  !

does not involve an unreviewed safety question or a significant hazards consideration and will not endanger the health and safety of the public. {

Vll. REFERENCES

1. New York Power Authority, Administrative Procedure AP10.02, Rev.

7, "13-Week Rollina Schedule", July 1998

2. JAF-ANAL-RHR-03422, Probabilistic Evaluation in Support of Technical Soecification Amendment to Extend RHR Service Water Looo A Outane , Rev. O, September,1999.

3. EPRI TR-105396, PSA Applications Guide, August 1995 l

1 l

)

I

f

• l Attachment til to JPN-99-030 )

l MARKED-UP TECHNICAL SPECIFICATION PAGES l ONE TIME-ONLY CHANGE TO THE TECHNICAL SPECIFICATIONS REGARDING RHRSW ALLOWABLE OUT-OF-SERVICE TIME .

l (JPTS-99 005) ,

l l 1 1

l l

l l

l l

l l i l

l l i New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59

) ) ) )

• - ( q s

( (

s eo y D

y a- s r

a hdl t o e e ,m :_ s 2,yth m

ee be N e he l e 5liy a st o

)

1 Y f t

bangM m A-dsft bo d y

c 3

r 5 orlis eo o c duse n e r e ppom cgnsti e ni f e p , p moci n binaheroycn e A ao v er,x u e e uit e l e

a c n c p s nb l

moe ect epe l e ht -

r F O O n Wiea Svnp eme r t yndimbto-sti an ol ol f o

t .s 5 n y is h,is c

i c

R oi o Hbt e R

e 1 co anobe seepce bmmmgso-u n simun a i pin s ht hr 9

0id- t 9 a1 9 e1 npd o

r o or ee a

f nnl eWimy gt a.ti e atrn oi~ s n8et a ei l i

t a oc ma e yle o.hd t 5. t e l

i ob RSmt e syd a ct ex ic t

ohdd eee.'beez ocar o f a i

deo hat,uhautrhn ha3foi r t i l

l thrz l

po f

ct eHr sd o rt mdt t

sn dt n ts vm e eo ec niWhn ndao n epRethua ebs yn ~ r iat o e t un n surpessi o t i

en f,

ind -

sot'ndn edn t

i o n,wd

,e i s s ne e e r. m u b n , gle- nt o

~

t a e .i o tde oe nt o nir it oe minbe a ir c n d o ke t. n, t te em s s ndo l p la cp l

rqu pea oll t f iet nbi l a ibef c n n o c r n ee tere mhe r ar e l a r,,

e r aoif f t i

reaeo i t

ne e d hepce rod t is m ew rhl ei tre i af otd e o sre nm a ,o viett v sr rna ds ohiWot f m r sn csh e ap o ioo ct ,i et ie l

t Evoinvpc n i neoe epch iegmt it ni t t

onss n ey t i

ee e r.i ei nbaef o

l r

v tesme nnm_

e nl s ht s e, g W ;is nS iruH, R m, N

n pi yd e as n e el rbamib pl e aa DR,

)

d h m bd r ot r m honha heop ecne

't e f

Wcrsa o e un n

5

(

o c

2

. Wistbcoa4 3

j P

P 4 N

F A

J n l

l a e i

h t g i n

dd sd e4 e e yo c n d wu a e m2n i n e un dmg s s 7 i i ei aei f qti mir n bh t r rc en 3i 0n epot d ee ue t

ro sct c oe ho l

smcc t

ti ow n ortaps r

n e,h u c t y uex s nn a t

rpe es b por e ao el gst nbn air g en u o cit pm) e 2 o

per unim sWdt et 3. dn i

o tes (t 3 gSuo r t mpdrun o nl o yd a i nRnn Hit 8. co to nen T-i l

oRnd 5. d clan eo cint tn o oop o o 3l r o cen oi

?

edoa cr hnetho t

ul c t n o,ep e

o c a

r dro cm  ?

?

fofoibde seh edba l

2. n noc at 3 prsdt ml u roar B. i gal ce 5 m

oiif mv o oe i no ef 5. d e neb ira u

pder e p trsba l ah p t s ole 3c a t she r 1 ap n rnb fl et p 5 Wmsy s enr npe o oii c s op ti swn o

• el e es i

a se ,

Rbond opeo hbmim Se cd i tb n

t a o r ela l se e

yt an '

Het0mr i rce I mh t

Rva3o a f eep hih oregcs o eo s pb es r p mit .e 5 neb o a oi pn gm oimi nn ir uo eewv rr wpFb o 9

eteon -

qt ,

dn e ec 3 d 1 o reit ns ra oe*a dmsi$. e l

u 8. t ei y l yat e pb2 ccas u osrs r l1 8 o

)

d ho 5. eu a cmb eu o cbey h heupa t e fh

• wle25 oh N _

't S3rsrs Sbsod I t Ls<3 t n

n e o m

(

c 2 3 4 5 d n

5 e 3 m A -

~

F

~

lfi!!i/iid!u!;5 3gll"'1ls,Q'I *% q l 10101 '

I[

li'jlI 5! }{0!!! /

l1lI lh!l!

!!Il!ll!ll!r,fllNf! / ,

I B

jamio dhI!!pprpgju d$

p)llkI'hf

!we lil{

ll!!;lh{ililH ll!!0!!!alhl i

lil0illllill I I