ML20235S429

Amend 12 to License DPR-21,revising Tech Specs to Reflect Higher Set Points for Main Steam Line & Steam Tunnel Ventilation Radiation Monitors

ML20235S429
Person / Time
Site:	Millstone
Issue date:	09/29/1987
From:	Thomas C Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235S413	List: ML20235S410 ML20235S429 ML20235S440
References
NUDOCS 8710080495
Download: ML20235S429 (17)

Text

_ _ _ ___- -

t

"'4 UNITED STATES p NUCLEAR REGULATORY COMMISSION g

y WASHINGTON, D. C,20555 NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 12 License No. DPR-21

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

l A. The application for amendment by the Northeast Nuclear Energy Company, (the licensee) dated December 16, 1986 and supplemented January 30, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

871008049S 070929 5 DR ADOCK 050 F

I

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of. Facility Operating License No. DPR-21 is hereby amended to read as follows:

(2) Technical Specifications The Technica1' Specifications contained in Appendix A, as revised through Amendment No.12, are hereby incorporated in the license.. The licensee shall operate the facility in accordance with the Technical Specifications.

3._ This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION hh, 'W Cecil 0. Thomas,' Director Integrated Safety Assessment Project Directorate Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: September 29, 1987 l- '.

e e

ATTACHMENT TO LICENSE AMENDMENT NO. 12 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET N0.'50-245 l

Revise Appendix A Technical Specifications by removing the pages'indentified below and inserting the enclosed pages. The revised pages are identified by the. captioned amendment number and contain marginal lines indicating the area.

of change. Pages marked with an asterisk (*) are overleaf pages that have been provided to maintain document completeness. No changes are contained on l these pages.

1 REMOVE INSERT 3/4 1-3 3/4 1-3* j 3/4 1-4 3/4 1-4 ..

3/4 1-5. 3/4 1-5 I 3/4 1-Sa 3/4 1-6 3/41-6*

3/4 2-1 3/4 2-1*

3/4 2-2 -3/4 2-2 ,

3/4 2-2a 3/4 2-11 3/4 2-11*

3/4 2-12 3/4 2-12 B3/4 2-5 B3/4 2-5 B3/4 2-6 B3/4 2-6* i 3/4 12-7 3/4 12-7 3/4 12-8 3/4 12-8  !

I L___-_____-_

)

0 )

1 7 N )( '

(

U X X 5 XXX X X X R (X X n

o T i O t HY )

ce/B 7 '

nl PD (

ubUN X X XX XXX X X X F aI A X rRT heAS cpT iOS h

S T

we B

)

1 N n 1 E it M s 8 E su ( ) )

R eM/

I d LN -

9 2 U o EW X

( (

X XX XXX X X Q M UO X X E FD R ET RU N H O S I

T A

T N

E M

U R

T S

1. N

1. I 3) r e

n EA LR BC M C D

et et d

i n

di e

n t n

e AS

• vt c l i go

• oo T( aognn cvu o smnn t e o e

M g h s l hi AAuRhi t E n 0 pct p T

S i

t l 8nti 2 2. nris dctt i e Y

S t

e l <Uis u

f eeSP wo 1 22MoSP 1.I awo b v

ol S gl RB

• a N f aure nnP re

• O l otdot ooLt ot g

• st I e l ot a ii it a i h e T v 5oMcr tt%ucr s c hf C e 2V ee cc0cee p g n co E L 1 Ml p T /IR eO SS ee5 rl p i i n O p ieO 5 s i R

0HIS >CS 8 p 0 P

i r

2 ee 0 6i 1 . . . ee . . 2 R

T 5ABC SSABC. 1 5 5 1t 1

2l 5

O T

C A

E R

N l W e O x e e v D u r r e .

_ n T

U l u u l l o F s s o

_ H m x s s r V a

S i

t r hu e e e c n c gl r r t e n S iF P P a g u

i H W r h r l a F h l e dg o l w hl p

c a v eie t e o ce t u xi sHl c w l sv i i n ut a b a y

_ r w a l a l da e r r l

Ol T S M F r Ber R D o e  : ce t m e

Mwup

h p h h c ag d Mgo R odo g g a ri

. o Ri n Pl en i i e cH M IHI AFRI H H R S

_^

r s

_ e l )

- bee 1

_ ml n(

_ ubn Naapm

_ rhi e

_ meC rt up

_ s 1 1 33 222

_ mO .T y 2 2 2 2 i trS nf se ionp M I

/ iI I. l ,

) )

4 4 m ( (

t X X X R X X n

o T i O t HY ce/8 ) ) ) )

nl PD 3 3 4 4 ubUN ( ( ( (

F aI A X rRT X X X X heAS c pI ioS h

S T

we B

)

1 N n 1, E I t M - s .8 E se (

R eM/ ) ) ) )

I d LI 3 3 4 4 U

Q M o EW UO

( ( ( (

E FD X N X X X R ET RU s R H d 0 _ $

m n

. l i t e o p

A s s T y e

)N dE eM nn

.s r r

o uU oo . c nR ,

iih .

- iT tS tt c h) nN cct ce oI nei iW C ut w hM

() f os w r 7 M hpe t0 1A c d a3

.R ) aro h 1C r2 e1 eomt t y l

3( w o( r c 'n ne F oao at EM g n

n a P e e f et ha LE n d r 2 r rca t fm BT i i l n u u s AS TY t

t c

e l u uo s

o 1 s o

mre eor sx so S e V F r l. 2 l tf er s a C C s e l p N . l h n y ,h p O l g ac e o e skt sa I

T e

v H ma rB l v f t l v

pof g c .I t

C e . o a c a il ot eu E l n N V e V rb srp T f S t sput O p x  %  % dn su R

P i

r 3 0 e 0 doo0so 2 7 1 e 1 eri0e T 4 $ $ S 5 p t6rr R pli ( po O ios t T

C r rrosea ttpinr A n f e E roNebn R n n e o cWOuug r r e o

k ., i t ehOst(

w t a

t e

e l tT s

_ o v biUeew

_ l i l l awHrgo n d* o ae e r e ,S pal

_ o r a se Vr v tf

_ i e R I r u l psdrs

_ t s u l s a osno m c

n nm e n

es no oo V aatta eu rl op cse u du l ll tC p w yL a r t nc n F l iC o tbE eis p

oa e s

m ot t Urf

_ cV ae Cs S eof d i e ev a btEnne

_ r e t tl eF e Reet T n $ sa n n l e hha nV nwwr i i i ll

_ b n b br abi

_ r i i r hI dd%

_ u a a u u sstee5 T M M T T sess4 eiss s rmeaao e r r p pt h e TP yy BB

_ . r i e l) ~

, ee1 . . . .

dl t b n n(

)

~

12 34 N aa pn 6 rhi e (

aeC t p rtT s 2 2 4 2 2  :

eO . y s l t rS e nf se t ionp o M I N

ll lI!{l i J

l

". l a

m m-r r 2 a r n o 1 D l a o u m n h y l e

g p e l o . h 1 u i l l c s t

. o r a a r .

e r t c c t u f o l

a h

t g s

n i s r o o N r h l c n w t i l s A i o c f t 0 t a w o

d e e

h g 5 n

• . hl 1 " l e e sl u

2 6

l M

h t

l n m l

o . e a d lf 1 R r s h n e S

- f P e f rn t e

n5 A h I i t i n2 P e t eh s m a1 h d i ht s A h/ f t e e . i e s

c3 o y t

a d d

e rw u

l t Mt m l i n p on e n Rs a r

n o

c o a p fo r e I a i i a m e c s , r: nt e s , s d e~

r l e l. F a e t n ii e hs r i bt r

• t ek to e u aa o 2 n r ba i p . h q r f 1 a e t w s t .

e eg 2 s l Yr l R pn e . s n l e s6u r e oi v n d e i ab d0o o u n

o ha t

. a l

h a e r i r

y h

sl oNh rA l f

i cc d v t i u l l Tt e e t

a ai ed t

e. n s u

q e q l u ma eh l eSh g v e i v

t n e o s e r

r f ts bTi l t

) n rI t i e s aOe c _

de o t t l o er yw rM r a em fd i n

a t s sol e/n e uu nr ra n I l

o i s o n a l a pe pPi o0h p

h e -

i t o s s ib 1t s t

% ts te g i e s n d r lRi t nn cl n r i o o . td law u f oI eb i t u i e aT p o $

C t a e n t y t r D. tt Ss n -

()

m de er b e m

a r i t c n

l1 o

as hI f

oev e i p o

1 _

a p m u e r u r4 tI hl M t

1. r eo a r p g f t nta R 4

/ -

p oo nn c h r t m e ,s s v P e 3

1. S Ts c s . e t sn  ! n L h 3( i s ng in t

i n i r

ci t

mo ei tin r o o t

Em .l a i r t l a tt ehi w e e

te 8t As Mne t

Rn t

u lt ar ue t

a t

n e

e v

l c sc ai f

ya s

sct ata lil t

n b v

o Ty S nh h a o nn al w m n

i t

fi ic pt e

ess wo h a a n

ic i

t med r o i a

a r ep e ia ri t

ee I t s e

o dM w e t c

t n

e ls t r p pon lde s h i eR hr p b s c t cP e to a o o ah eo mmi le n c aA v gg r e c n rt hr o l i e l l I ei t p ce t

o pd e

a v ii e nn y r n pw o fa p

daa cm e r

7 2

r st e

st h or l

e a a e o nl e a 1 P ia t m ec e a pt i n l e v i n bn eh s e s r hc o cni d n

e r o a nt r i t

o co ts y y a L p i t

od t r o, i d..in .

h e

n c is wa n bt  : h n i o rs om

.s t o yen a a l e g e s dc i e s al i h o ec fe 4 ., f t R e f rm cb H w p ra t . ne i a eh o an ia tr W I i tsey bas t _

dt si ex e Nl mu un aro e n

. . i* o mit e

r sa et t e rp D O

ul b U

R e qI ms r l l e m

eMc b u cn eo f lF a rd ep pR a . u nt s eo b f l o r n e bi oId rM r en o nc ue H Vh g e I p tm r n eR t hu l sb $ or tt f oa pP s w c nr ei o h nas o ot oA n d eo soit n gH c nh d n I de s hf I Mr e t ei nt nl a I n et t w g rd mrad b i r dyd). acbo oeo a.lev _

sr i se haIhe cc o w s

a ivl d eo m dneioe cr te as pn r

e sg cn t e tcxsu t e sl enr r l. e n

rt e

e iSuld nlhmouf e l yi b y n p sr a au es w

$lF lOe R

d e

d o oa ic cl sri neb ds r

el g pp rn y o a

euhaM e i r m tia ot cl tce I wr ou isnR'M t e

rl i bg n

ei dngrR u e nut m ept oP a auf s ht o ai c P q h uaat se t cL w e ei tc MMHSA e t f r aee .

s d br n r d e rb icc ef e e u nu h py i t uu bo h

'M b e a yd ef t t iheft idd t R h h ... . . o i r S o nee lt I T M W abcde N W T ( en h n iRR l n i e n

o 1

e .t a wm h t

m 2 c i c

i n

. . . . 0 1 f . . . Ml

- 5 6 7 8 9 1 1 1I ABC R -p n i t

P n I A o e

c e n _

n n n o _

o A O t _

s i s e t l _

t c

• l _

o A *

• i N " *

• M _

l 1

"#' Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal i full power radiation backgrouted level and ecsociated tdp setpoints may be changed based on a calculated value of the radiation level expected during the test. 'Ite background radiation level and associated trip' setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from 4 hydrogen injection. The backgrcund radiation level shall be determined and associated trip setpoints shall be set: within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reestablishing normal radiation levels after completion of the test 4 program, or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% rated power. If, due to a recirculation pump trip or other power  ;

reduction event, the reactor power drops below 20% rated power with the i MSLRM setpoints at their test value, control rod withdrawal will be j prohibited until the necessary setpoint readjustment can be made.

i I

l

\

I I

l Amendment No.12 3/4 1-Sa '

e-

c n h5 h( l e c( c e u ) ) ) ) ) ) ) )

a ap u q 1 1 1

) ) ep eu ) f e 1 1 1 1 1 1 1 u t eg e ( ( ( ( ( ( ( ( (

1 r ( et er ( ra F rr ra t S oa ot h u T m ft f s co I u es e a U m B B E C i R

I i n

C M L ) ) ) )

O 8 8 8 8 N R ( ( ( ( W T ) ) ) ) )

O N 2 8 ) D O ( (

6 7 5 2 T C ( ( ( ( U m m m m m m H D r r r r r r m m ) ) m m S N a a a r r 6 8 r r A l a a a a a ( ( a a n l l l l l l l

_ S A A A A A A A l l i TT A s s A A SN d d d y y h EE d d d d d a a d d c t n n n n n n n n TM s a a a a a a a l l n n t U e a e e a a i LR T l l l l l l R R w l l AT e e e e e e e e l l S NS l n n n n n n m n n t t e e ON a n n n n n n r u u n n e

_ II T

n o h a

h a

h a

h a

h a a a n

a n

a t p

t p n a

n a

d o

CY i C C C C h l h h u u h h M 1NT t C C A C C O O C C

.UE c p p p p p p p p p p p p p e

1FF n i i i i i i i c

. A u r r r r r r r i

r i

r i

r i

r i

r i

r a

4NS F T T T T T T T T T T T l

O T T P EIR LTO BAF AT TNS EE )

MI 3 UC (

RN A A A A A A A A A B B TE p C B A SU u NQ o I E r R G MF A e RT r CS u SE s T e g

o L r l

e A C r a u N h e s O c v o I s l l T i a C C D V e N r t M U m n u s R F a o s a n P o l r i o F A N M e c t M i

U e e v S a l

C e x R t

a W

O M r r e m l v u P I u u l n u o s i

D N s s u l l A d T l

e s s r i s e a F a U I

n c I v V x R H M e e e l a l h u S n r r t e V e a l g l e a P P a v n V o i F n n h

C r W l e w o

i L p r H i i o

l r m t h L t

l e o r l o a n d g h n

t m t r o e i m c c w t e r a S c C s H a e a y c t e e S a e t

m e r a a s t e e d i

u R D e W n S n l n i

B e t

S S w

r R e i a i c t h h h d n b u b w u s g g w g n r n r o h e n o o i

a u d M g d i

H i

H i

a u l e R i o I L H C M T M T F R I H M

?

LIMITING CONDITION FOR OPERATION 3.2 PROTECTIVE INSTRUMENTATION Applicability:

Applies to the plant instrumentation which performs a protective function.

Objective:

l To assure the operability of protective instrumentation.

Specification:

A. Primary Containment Isolation Functions '

When primary containment integrity is required, the limiting conditions of operation for the instrumentation that initiates ' primary containment

, isolation are given in Table 3.2.1.

B. Emergency Core Coolino subsystems Actuation -l The limiting conditions for operation for the instrumentation which initiates the emergency core cooling subsystems are given in Table 3.2.2 except as noted in Specification 3.5.F.6.

j C. Control Rod Block Actuation j

\

1. The limiting conditions of operation for the instrumentation that initiates control rod block are given in Table 3.2.3.

I SURVEILLANCE REQUIREMENT 4.2 PROTECTIVE INSTRUMENTATION Applicability:

Applies to the surveillance requirements of the instrumentation that performs '

a protective function.

Objective:

To specify the type and frequency of surveillance to be applied to protective instrumentation.

Specification:  !

The instrumentation to be functionally tested and calibrated as indicated in Table 4.2.1.

l l

Millstone Unit 1 3/4 2-1 o' _ _ _ _ -___________-_ _ __

o t o sp r u f i

y tl o t l r t c sN ea h e A U bh t m l pR s a l i l A e

. i a re l w b

_ t i th ao ,

l n t t hl 1 o e e n d se 2 t u r e en b . 6 f d e r pi m s 1 e n f e p ed r - v l e u f f ie t e u . S a ev o i f rl st os P h S ui r d i tb ys hr N ft g d a si u r t O c k r rl l 4 o o o I ea c e r oi p 2h f n T v a t e a i s C if b a t a

ev rn n8 e s N to w l a t o i v e U c ap r ( . w b i n l o F e ge s( . ae tt ni a d o w w s rb ac oh v N ft o o nh ge e ha it t O o l p icnh pd t ti n n I

pv e f tnic oe e iw o e T d tit n e ,t d i m

A oo m e e ti on sa nY t e .

L

• tb a t s0e w mi oB a rd O g a e a 5s5 ty er cD l i e S n e t r p1 3 l t p N o us I i vs s i 2 p2 r

en so yr nA s qo t oe l a

i

b. o wT i el T t e

bh ac d

e t) r) sp p

oS rc N m et e lh d t E

M S

si n t a

r o

2n i2i d l c ai i pa tT uO n

e me er N l e r n sl s hh re hH m t a I

A -

e v

h) c0 f si g e h mer s sw th t

s n

u r

s ye T e n- go es mp cah e ee e di . t sn N L i4i F nect rn h , l m s i 1 O p

_ + s%

• i it na el t s ore n pl

. C 7( p0 0 t5 siw hi m cot I .i gre 2 i 2 2 0 2 4 t m f e t s Y r 1921 2 78 6 n4n a ot ncy l nth 3 R T 27$5 $ 52 1 o4o ,e s ias ai t A dt ey e utr E M es ns rrr nren L I r o p o e aepi B

A R

P i n ui ri t es cvn mn i ss T qa or aae eel e S e n

em r

ft ehd r

hdev E n t nl T l e th do rna I

A rein ermi )

. sr iu et mo enc va goav n h T t uaa n6 n s b a n i gcn I aseM i(

a n o ys e hno sn o N rWst i t e br oi oiti I e eSel Mli t i r o dit l t nt t wr re ea a rp tf nta crea T aoPnunnnM l e g o acl eml A

H WL 1 aauiueit non on ew t o nt ne uo ynuo si nds birs T

t s ww1 MrTtTr ooe e a us IL i

nl am c

wei or yt s ti N n ll wwpeiesewr r e d n rnnt O e yomndnsnoe to nb tdi aein I m rrrl el aiel l s nf m ua sm e

, iA T u r

ooDFTiRl riFn tt m mP m e e

mt ut l o hos sl e snem eil n T t cchhhaha aagggegewegn ahd np on v cabi N

E s

n eeiiitit oti o i e ac cn a yyl et aa ll a nnrt M

U I RRHHHSHsLSHC t x ne tc s

rrv ee ncpo oen R o .rn ddn e oc T

S c ,eim rro hr nnf u ooi wofh N yoi l t f ot I

t _

ril eo nna d o .

at mhc aal egrb fnp mcat -

o sne oei )f i ne t ees sibf

. mr 5o

( s rutf s tti agmih pru rut pf sI r aa er )

)) ce hl i iie yune a bt r1 rhh f tts bp n t mse( 42an

(( en ecc: iio mi t unP a

vaane nnl egul a NI m eeeoh n IIC bnmm se 2222nh2 2 2 it iia mel t i c errt yrne e

. ul es b h oecf . . . auit s

, mb ny ' 4 u WfPAI ABC M d M s ~

, i anS s nra - f

)'

i eh o2 )) ) )

M pC 1 23 4 5 O 2 ( (( ( (

4

" ' Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor powr at greater than 20% rated pwer, the nomal

. full powr radiation background level and associated trip setpoints my be changed based on a calculated value of the radiation level expected during the test. We background radiation level and associated trip

• setpoints m y be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. We background radiation level shall be determined and associated trip setpoints shall be set: within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reestablishing normi radiation levels after completion of the test prognim, or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor powr levels below 20% rated power. If, due to a recirculation pump trip or other power reduction event, the reactor power drops below 20% rated power with the MSLRM setpoints at their test value, control rod withdrawal will be prohibited until the necessary setpoint readjustment can be m de.

I i

Amendment No.12 3/4 2-2a

s l y . ne b

_. S ce obs a N nb c ner O e l obe I ul lli p . -

T ql l atl o A ei ihal L

O f rw wsrae bhb S s tsis I ee stl o hv esast D ti t eCk N s t cd A t s l ee t ai al .hr S m nakci K dr one u C ee ioet q O t p tiwne L s ct er B ee th ncrm uneue D t f uprr O y F t a R l f e es N

l o h cns a T . nI t O nn l o n oo I

T A

ii tt

.nd nneeu e

.em T ca oaegr

- N nu ihcat .

E ut tcxt s M f c i eun U a nt oi

)

R e ino T b e f et ge d

e S

N l t h em detit nh

. u I l rol n i g tunen i

t G

N wn i ss eayfh ue n I sd t ecew o L yu mnr C O al l e s

~ ( O C

l c en aeuhd nhqco 1 ri oteai

. E i rer 2 R st t of e

. O us ct gp 4 C be nnd n t uieie E R y f rrs L O cl li uo B F na eaudh A en hnq t T Y go t ged C ri ireg N

E et mc ms o ari mn U en rl or Q u f ahf u E nf . ct rd R olge diie F erwpy el a tt a N l ut pcped O bf u eeub I a o cl t r T l A xerl e A i g e al p R a n dti B

I v .i ael seswe c it L ve ahsn A rou nl cro C ebf ouao D

wae r o imest N p) ti ns aseea A 1 y t rse 1( r a

nao l T e e f e S 0yv mgeht E db e unbt a T i ri vdd t t d gd M iee scene U dim nemim M nf r ij rdr I

N iio cf sifl f nouo I eer i rcr M hpe hf ene Tsp T o pi p

) )

5 6

)

s LIMITI!G COCITION IVR OPERATIOJ 3.2 PROIECTIVE INSTEMNIATIOi C.2. De minimum number of operable instrument channels specified in Table 3.2.3 for the Rod Block Monitor may be reduced by one for maintenance and/or testing for periods not in excess of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 30-day period.

D. Ait Ejector Off-Gas System

1. Except as specified in 3.2.D.2 below, both air ejector off-gas syster radiation monitors shall be operable during reactor power operation.

Se trip settings for the monitors shall be set at a value not to exceed the equivalent of the instantaneous stack release limit specified in Specification 3.8. We time delay setting for closure of the steam jet tair ejector off-gas isolation valve shall not exceed 15 minutes.

- 2. From and after the date that one of the two air ejector off-gas system radiation monitors is made or found to be inoperable, reactor power operation is permissible only during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided the inoperable motor is tripped, unless such system is sooner made operable.

E. Reactor Buildino Ventilation Isolation, Steam Tunnel Ventilation Isolation and Standby Gas Treatment System Initiation

1. Except as specified in 3.2.E.2 below, six radiation monitors shall be operable at all times.

2. One of the two radiation monitors in the reactor building ventilation duct, one of the two radiation monitors on the refueling floor and one of the two radiation monitors in the steam tunnel ventilation may be inoperable for 24 hrs. If it is not restored to service in this time, the reactor building ventilation system and steam tunnel ventilation system shall be isolated and the standby gas treatment

,, operated until repairs are complete.

3. Se radiation sonitors shall be set to trip as follows:

a. Ventilation duct - 11 arAr. a

- b. Refueling floor - 100 ar/hr.

c. Steam tunnel ventilation - 50 mrAr.8 2 8

.-~ w .. .. .,v-  : .. ,

(*8 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pr'ior' to the planned start 'o'f the hydrogen injection test, the setpoint may be increased as necessary, up to 100 mr/hr, provided that the difference between the increased setpoint and the calculated value of '

the backgrourx$ radiation level expected during the test does not exceed 50 mr/hr. Se setpoint shall be returned to normal within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reestablishing normal ,

radiation levels af ter co=pletion of the test program.

MILLS 7t2E tNIT - 1 3/4 2-12 Amen 6mert No. J, 12 r

3.2 Hvi.nucaVE INSTM.cnATION BASES Two air ejector off-gas monitors are provided and when their trip point is reached, cause an isolation of the air ejector off-gas line. Isolation is initiated when both instruments reach their high trip point or one has an upscale trip and the other a downscale trip. nere is a 15-minute delay before, the air ejector off-gas isolation valve is closed. mis delay is accounted for by the 30-einute holdup time of the off-gas before it is released to the stack.

Both instruments are required for trip but the instruments are so designed that any instrument failure gives a downscale trip. Se trip settings of the instruments are set so that any instrument failure gives a downscale. trip. We trip settings of the instruments are set so that the instantaneous stack release rate limit given in specification 3.8 is not '

exceeded. *

'Ihree sets of two radiation monitors are provided which initiate isolation of the reactor building and steam tunnel ventilation and operation of the standby gas treatment system. One set of monitors is located in the reactor building ventilation exhaust duct, one set is located in the vicinity of the fuel pool, and the other set is located adjacent to the steam tunnel ventilation exhaust duct. A high level trip on any one of the six monitors or two downscale trips on any one set of monitors will initiate the standby gas treatment system and isolate the ventilation system. Trip settings of 100 ar/hr on the fuel pool monitor,11 ar/hr on the ventilation duct monitor, and 50 mr/hr on the steam tunnel ventilation monitor are based on initiating normal ventilation isolation and standby gas treatment system operation.

F Amendment No. 12 MILLS' IGE UNIT - 1 B 3/4 2-5

4.2 PROTECTIVE INSTRUMENTATION l l

BASES I l

The instrumentation listed in Table 4.2.1 will be functionally tested and calibrated at regularly scheduled intervals. Although this instrumentation is not generally considered to be as important to plant safety as the Reactor Protection System, the same design reliability goal of 0.99999 is guierally applied for all applications of (1 out of 2) X (2) logic. Therefore, on-off sensors are tested once/3 months, and bi-stable trips associated with analog sensors and amplifiers are tested once/ week. i Those instruments which, when tripped, result in a rod block have their contacts arranged in a 1 out of n logic, and all are capable of being bypassed.

For such a tripping arrangement with bypass capability provided, there is an optimum test interval that should be maintained in order to maximize the reliability of a given channel.(1) This takes account of the fact that testing degrades reliability and the optimum interval between tests is approximately given by:

i = r2t 3

! 'r where i = the optimum interval between tests t = the time the trip contacts are disabled from performing their function while the test is in progress r = the expected failure rate of the relays.

)

To test the trip relays requires that the channel be bypassed, the test made, and the system returned to its initial state. It is assumed this task requires an estimated 30 minutes to complete in a thorough and workmanlike manner and that the relays have a failure rate of 10-6 failures per hour.

Using this data and the above operation, the optimum test interval is:

I *

[2(0.5)] b = 1 x 103 hours0.00119 days <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br /> = 40 days 10-6 The sensors and electronic apparatus have not been included here as these are analog devices with readouts in the control room and the sensors and electronic apparatus can be checked by comparison with other like instruments.

The checks which are made on a daily basis are adequate to assure operability of the sensors and electronic apparatus, and the test interval given above provides for optimum testing of the relay circuits.

The above calculated test interval optimizes each individual channel, considering it to be independent of all others. As an example, assume that {

there are two channels with an individual technician assigned to each. Each (1) UCRL-50451 Improving Availability and Readiness of Field Equipment Through

! Periodic Inspection, Benjamin Epstein, Albert Shiff, July 16, 1968, Pg. 10, Equation (24), Lawrence Radiation Laboratory.

Millstone Unit 1 B 3/4 2-6

- _______---_-____A

LIMITING CONDITION FOR OPERATION 3.12 FIRE PROTECTION SYSTEMS C. Carbon Dioxide and Halon 1301 Systems

1. The following high pressure C0 systems 7

shall be OPERABLE with the storage tanks at least 90% of full charge weight whenever equipment in the high pressure C07 protected areas is required to be OPERABLE.

a. Gas Turbine Enclosure

2. With one or more of the above required high pressure C07systems inopt rable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission, pursuant to Specification 6.9.2, within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

3. The following Halon 1301 systems shall be operable, with the minimum number of storage containers shown each a having a net weight of not less than 95% of full charge weight.

a. Fire Pump House - I container ,

b. Cable Vault - 2 containers t

4. With one or more of the above required Halon 1301 Systems inoperable, within one (1) hour establish a continuous fire watch with backup fire i suppression equipment for those areas in which systems or equipment )

could be damaged; for other areas establish an hourly fire watch patrol. I Restore the system to OPERABLE status within 14 days or, in lieu of any  !

other report required by Specification 6.9.1, prepare and submit a j Special Report to the Commission, pursuant to Specification 6.9.2, within the next 30 days outlining the action taken, the cause of the inoper-ability and the plans and schedule for restoring the system to OPERABLE status.

SURVEILLANCE REQUIREMENT l

4.12 FIRE PROTECTION SYSTEMS C. Carbon Dioxide and Halon 1301 Systems

1. Each of the high pressure CO 2 systems in 3.12.C.1 shall be demonstrated OPERABLE:

a. At least once per 6 months, by verifying C02 storage tank weight.

b. At least once per 18 months, by:

l Millstone Unit 1 3/4 12-7 AmendmentNo.1,/,12

R. .: ..

7 SURVEILLANCE REQUIREMENT (Continued)

(

4.12 FIRE PROTECTION SYSTEMS 4.12.C.I.b.(1) Verifying the system, including associated ventilation dampers, actuates automatically upon receipt of a simulated test signal and manually through operator action, and-(2)~ Performance of a visual inspection of th'e discharge nozzles to assure no blockage.

2. The Halon '1301 Systems referenced in 3.12.C.3 shall be demonstrated OPERABLE:

a. At least once per 6 months the weight and pressure of the  !

refillable container shall be checked. If the container shows a loss in net weight of more than 5% or the pressure (corrected to 70*F) drops to 325 psig it shall be refilled or replaced.

b. At least once per 18 months, by:

(1) Verifying the system, including associated ventilation dampers, actuates automatically upon receipt of a simulated test signal and manually through operator action, and ,

f

-(2) Performance of a visual inspection of the discharge nozzles to assure no blockage.

I e

I

. Mill s t'nne .nni t i .,,..

3/,4 12-8 Amendment No. I I 12

- - - -