ML19210A312

Amend 41 to License DPR-50,revising Tech Specs to Add Surveillance Requirements & Limiting Conditions for Operations W/Respect to Average Air Temp Inside Containment

ML19210A312
Person / Time
Site:	Crane  (DPR-50-A-041, DPR-50-A-41)
Issue date:	05/24/1978
From:	Reid R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19210A309	List: ML19210A308 ML19210A312 ML19210A314
References
NUDOCS 7910290547
Download: ML19210A312 (8)

Text

f UNITED STATES NUCLEAR REGULATORY COMMISSION y*

• g WASHING TON, D. C. 20555

[

METROPOLITAN EDISON COMPANY j

JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 41 License No. DPR-50 1.

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

A.

The application for amendment by Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (the licensees), dated July 22, 1977, 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; 8.

The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the cormo, 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 Comission's regulations and all applicable requiremen;s have been satisfied.

1488 150 7 910290 69'7 Accordingly, the license is amended by changes to the Technical 2.

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License Ho. DPR-50 is hereby amended to read as follows:

i (2) lachnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.41, are The licensee hereby incorporated in the license.

shall oparate the facility in accordance with the I

Technict.1 Specifications.

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

issuanc.

FOR THE NUCLEAR REGULATORY COMMISSION

.ks/l j.

R6Iert W. Reid, Chief Operating Reactors Branch 44 Division of Operating Reactors

Attachment:

Changes to tiie Technical Specifications Date of Issuance: May 24, 1978 9

1488 151 4

ATTACHMENT TO LICENSE AMENDMENT NO. 41 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Revise the Appendix A Technical Specifications as follows:

Remove Paaes Insert Pages 11 & iii ii & iii 3-80 & 3-81 4-72 The changed areas on the r tised pages are shown by marginal lines.

1488 152 O

TABLE OF CONTENTS Pare Sectien 3 1.3 MIN'.?ct CC:Q:T!CNS FCR CRIT:CALr;t 3-6 R.:... c.R Cn~n e.A..e y e.,. :,. av../v.Y 3-o-3.

a.

nw 3 1.5 C:CCS"'RY 3-10 3-12 3 1.6 LIKGCI

.,-l6 vr p ro.a"."CR ". " *~r a".""v. ? C 0777I". *~.~.' F,.

"...r.n* ",.~. '.V'. ~. v.

.u u

3.,.7 i_.

3 1.8 SINGLI LCC? RES R:CT:CUS 3-17

, e,.. v r...e.

3-18 LC,a, u,,a.e..

3.rf a-. e TT-...eo...s

3..9 r.

3 1.10 CCIT"i.CL RCD CPI?.ATIC:i 3-13a 3-19 MAF'E", ? A'O 7'Jo*? CA :Cir A'o CEr':CAi, n'.D:-'CN SysTD's 32 1....y

::s 2.n.~.... ra....a

..:ns:..v.

Ce. :. v v...,

- ~...

3.3

..v

.e.,. s...=..

,-2,

-.,.,...e

. : n.~.. ~.. ~. =.,. w.. a CCa,, r.,..

u..s o,.

3.h TL'REINI CYC'.E 3-25 19.. e '.".D.,.,..rT.*. *. a*. *.

n*

e.v. e a _a.s.e_

3-27 35 4

qs *:

. -yf

.we. g.

c. ret.. m..t m..e.,

3. e;.1 C?.p ~.a.. Ca.. e, A...

... -.. 4 m.

3 5.2 CCUTECL RCD GRCUP x D ?C'a"Io. DISTS.3UT:CN LD!ITS 3-33 r.,,- n..

. n~. D.e r..:.etv. o n..e

.en..C,.-rc.,.v-i Sv..e.r 4 o.-. mn.. ~.

32.3

- wi

.s a.

SET?CI:r:S 3-37 7

C",*n,

T."aS~.m.."v..r'". A a..,J 3 18 3 5.h r

a 3.6 REACTCR EU I.DI"G 3 h1

s'.'T.

e v. e.". ?"i 3 h2 37 IP.IT.". 7' 7 "". S. ' "n' '

r u

-.:...... :... s n.a... s n...

,....., _..s 3

0 3 h6 3.?

RADICACT:'!I v.ATI.:A'3 3.10 MISCE'.Lle:ICus :.AD:CA:Trtz

/0 ra g

'Ud lll"l:ll@n 3 h6 MA.:.n.n a EC': CES I-3-55 H ly'4

f. j/

~ " '.,

-e C " ~...m~.. n. "

3 11 EX.~o -". 'w.s a

a-o t

J 3-57 3 12 PEACT"R SUII. DIN", PCI_t3 CF;Ji?

W 3-58 3 13 SECC:o.RY SYSTI't AcTrt:TY

3. Ih FLCCD 3-59 3.IL.1 IIRICDIC INS?EC"'!CN CF TE DIES ARCU:D "':C 3-59 3 1h.2

LCCD CCNDIT:C:i FCR ? LACING TE UNIT IN HCT STK:DBY 3-60 3 15 (RES* ?VID) 3-61 c'.3.P..

3-63 R..

_,St .':. ", r c e o.. s f c'.." ''.. "

• I 3 16 3-80 n.R.:

.r 3 17

. n v..,. =v.-..a

,.. n :.

3.18 FIRE PROTECTION 3-86 3.18.1 FIRE DETECTION INSTRD'ENTATION 3-86 3.18.2 FIRE SUPPRESSION 'a*ATER SYSTDt 3-88 3.18.3 Dell'CE/SPEINKLER SYSTDis 3-89 3.18.4 CO2 sysT15 3-90 g

g.g tyr T..e

...F r

.e 's,. ".

n. ;m e g_1

m......

.~~

h- ',

h.1 C P U.n' '.' u~ . n.', = ~' ~:..v.

~ "/ '. ~:.,'

a a,

• L,

i. -

-. -.cR % w G. n.

L.. : : :..

.4.

...:: n d.G 5:sv se. d J

a, 2,,

i ac-.. -....a w

w... ~.=....a u:__ 5.,a-. : ~,

,r.._....

,,-.....c a.3 h.h REAC"C?

EU!'."~,

h-29 h.'.

1 C ^ a"~."s."..'..~:.."..' ".:,* :.",a~ ~: ~a~:~ ~. S h-29 a

a,-:5

....a,-...,

i e

.,~.r.

s..,

a.a.2 n.

.n

.. ~.

c v. "'.~.". t h-m--

h.h.3 n"v. '"n' *w G ".. "w.."a ?

a

. ; era..s-..y e g..ee.p o.,.

r t --n. a ; ~.5 r. ev :.;

l e

p erne-e.

v.

.e.=...a 45

..n..

-a

. ~ ~

...a e.

v

~~'.n*.". "c".'."..'s~

~ ' '.'..'a' C " ~~ ~:. C " v' L "..s c "1 :. ~.

n.".'.

~ -

nr

--or

'SY-..,.

r_-,C,,c.

. r_ e.... -

h-39 s _.i

e..

k.5 1 D'.ERGINCY LOADING SE;'JrNCE h-39

". . r. C C '. a" a~

.Ov. e ~" '.

k h1 ia. c:. 2 "4IO. G'.'s' v~ v..:.

h.5 3 REACTCR EUI'. DING CCCL-5G xa ISCLAT:CN SYSTDi h k3 k.5.h DECAY EIAT RD'C7AL SYSTDi LE!JACE k h5 1488 153 11

.m No. x. u

TABLE OF CU:n:.;en Pere Section h h6 e v.

-.. ~r _.e...r. D... r_... a E

e.r

.,.y

r. e_ -,..

h.6 v

k h8 u..

~.~:~.-a k.7 fr: n' ~. .. C^'.~~:-'~^.-'a'.:'.'.

h-k8 h.7 1 CO::TRCL RCD LR-'iE SYSTF*4 P. CTIC:TAL TESTS k-50 h.7 2 Corr"ROL RCD FR30Fa'.4 ',t RIFICAT'CN h-5

<,.....,s. :a MA..T e....

h.8 A c m......

k-2 1.

s

.--~..,..:_=.. : r. oc_ c. r_o. '.r'IC. rs. '. "..o b.9 E m_.c e_ ". ~. '.

h-52 h.9 1 TEST h-52 ACC :. w:CE CRI ERIA h-53 k.9 2 r

k.10 REACTl!?v

"'"A*:

S k.11 SITE E.~l:FC7 "T a '. of "IC ACTI'1 Tv cVRVEY_

h-Sh h-55 k.12 CO "..'."..G L '. ~^ '..

T*.*...To..~."..,

.C.'<'".'.'.'.

h_55 w r.- m. 7..---.,,...,.- -,

h-55 L.12.1 4.12.2 FILTER TE3TS k-56 L.13 RADIC ACTP/I tTi'! ES SCUWCES 5":'1EIL l*:CE k-57 SYCTE!

h.1's REACTC?. 3LO::.G FCFGF EG.Ad:

.i,. c*)Ge

)

L.4 c.,.

...e.,...,

s.,~.-...

n.. ye M...

Os.e.s

-.a.:.

..-..,,.J.~...'.:. :-. ~.,i.. s. C :.

h-59

..eL%.

.l:

k.16 R :.s.,e,,. e.

h-60 h.17 SHCC': S" Fai q~15 e:.tr:SE3S) 4 72 4.18 FIRE PROTECTION SYRTEMS 4-72 4.18.1 FIRE PROTECTION INSTRCENTS 4-73 4.18.2 FIRE SUPPRESSION ' ATER SYSTO!

4-74 4.18.3 DELUCE/SPRU5:LER SYSTE'!S 4-74 4.18.4 CO2 SYSTC!

4-75 4.18.5 HALON SYSTE: S l.-76 4.18.6 HOSE STATIONS h-72 l

h.19 REACTOR EUIDI:iC AIR TE2Fr?A':UDE 5

I'ERTM Fer t":7S n

P< i i th,U.d i

4 Dj } i { q M;M

. m 5-1 51 SITE

> s' 5-2 52 Cc:: TAI-E"?

s 5-2 5 2.3 REACTOR EU CI::G

,a02.m In.,

,y-

,s-3 r.,.

5.o 2

9. eACe.r.o. nJ, r n,i.

t v.. a.a..

'k 53 RFACTCR i.- h 531 REACICR CCRE

', h 5.3.2 RFACTOR CCCLA::7 SYSTEf i

,. k,.. D. en.-, 21..,.,..., o. AcJ.

r. r.

.,. r..--

J D 12.

u wL.

>a w

s.u.

.a h

5-6 5.h.1 NE's FUEL 2:e.'aCs 5-6 5.h.2 SPE::" FJT.*, STC? AGE

. =.. Cm. -.~., c.I cye. :,. 2 5-8 ATR I.m.. v.r.,-.... r.. :. q :,

55

~....

r.

a 6

Ap:.gT. c.. -.2n..".:-

c-...-e m. a-.

g_1 a

6-1 6.1 R TS ?T" ~ ~ ~ ~ ' ~'"

6-2 6.2 QBGA:R AL:_3.

6-2 6.2.1 0FFSIT r.

6-2 6.2.2 FACILITY STAF2 6-3 S.... C..

e.

..-,,,....- I c A.,w,,..a 6.3

.m1

.. c. ~_-

.,s.

6-3 6.L TRA::lISG 6-3 6.5 R EVI D A' 0 A' ~' T 6.5 1 FLA'i? CE. cat:C;:3 RE' LIE 4 CC:"!IT"'IE (? CRC) 6-3

. v. e,,.,.

c..m. r r.

e, - 5

..r....

6.e.2.A

v. m:.,.,,. D C o. -. r..,.. _., m. C m..,

.2 7

..o

!.' ~.~..n \\

fa-7 6.c.m.S Gru-n. \\?..,.' - : ~. r. s..*.

? zm.

.a

> ~.s... s sc b-10 r~....m_-~..~-._

.- L,. r.

6. 6,

p. r_o. cw.e g _.,..

u

,....,....,.1.r,..,c.

6-11 o'.va m.

6.

C,,,,, w....,,

s 6.8 F ECC:54 3

,m.-

m. ; c ;<. # "

1488 154 m

REACTOR EUILDING AIR TEGERAWRE 3 17 Apolicability_

This specificatien applies to the average air te=perature of the pri=ary contain=ent during power operations.

Objeelive the temperatures assumed in the structural analysis of To assure that the Reactor Building are not exceeded.

Scecification_

320 shall Pri-a-y centair.nent average air te=perature above Elev.

3 17 1.

320 shall not exceed 130 F and average air te=perature belov Elev.

0 not exceed 1200F.

If, while the reactor is critical, the above stated tc perature 3 17.2 li=1ts are exceeded,the average temperature shall be reduced to the above limits within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, er be in at least EOT 5T MD3Y vithin the next six (6) hours and in COLD Shv"00'...! vi-hin the following thirty (30) houts.

The pri=ary centair.=ent average air temperature shall be calculated 3 17 3 e.s follows:

l a)

The average temperature above elevation 320 will o calculared i

l by taking the arithmetic average of the temperatures from ar l

1 east 15 locatiens above elevation 320. A list of locationn is given below.

l b)

The average temperatures below o'.evation 320 will be calculated by taking the arithr. etic avere of the temperatures from at j

least three locations below elt stion 320. A list of locations is given below.

e PT Locatien F1 Locatien_

1 SE Dome Elev h5h 13 NE Wall Elev 326 2

NW Deze Elev L5h 14 S Wall Ele. 326 3

N Wall Elev k5h 15 NW Wall Elev 326 h

E Wall Elev h5h 16 E See Shield Ziev 326 5

S Wall Elev h5h 17 S Rx Vall Elev 321 6

W Wall Elev k?L 18 NE Wall E'ev 29h*

T NE Wall Elev 39h 19 S Wall Elev 29h*

l 8

S Wall Elev 39h 20 NW Wall Elev 29h*

i i

21 E See Shield Elev 29h*

9 NW Wall Elev 39h NW Sec Shield Elev 29L*

22 10 NE Wall Elev 36h 11 S Wall Elev 36h 23 NE See Shield Elev 26h 2h N See Shie:2 Ele. ;ea 12 NW Wall Elev 3dh

• locatiens below elevation 320 3-so 1488 155 Amendment Mo. 41

Bases The specified temperature limits assure that the containment design temperature and pressure will not be exceeded in the event of a design basis loss of coolant accident. The limits also assure the maintenance of acceptable ambient environe. ental conditions for safety-related components located inside the containment.

4 1488 156 Amendment No. 41 3-81

h.'19 P. FACTOR EUIDI':G AIR JD?EFAn.?E Aeolicabilitf This specificaticn applies to the average air te=perature of the pri=ary con;ainment during pcVer cperations.

Obieetive To escure that the te=peratures used in the safety analysis of the reactor buildin6 are not exc +eded.

Specificatien h.19.1 When the reactor is critical, the reactor Luilding te=perature vill be checked once each tventy-fcur (2h) hours.

If any detector exceeds 1300F (1200? belev elevation 320) the arithmetic average vill be cc=puted to assure ec=pliance with Specification 3 17.1.

1488 157

(

Amerdirent No. 41 h-72

?

i, 9