ML20081A609

From kanterella
Jump to navigation Jump to search
Amend 88 to License DPR-50,revising Tech Spec to Ref New Liquid Effluent Discharge Monitor RM-112,in Lieu of Presently Referenced Monitor RM-L7
ML20081A609
Person / Time
Site: Crane Constellation icon.png
Issue date: 10/14/1983
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp
Shared Package
ML20081A612 List:
References
DPR-50-A-088 NUDOCS 8310260339
Download: ML20081A609 (8)


Text

_.

l'ga tacqIo UNITED STATES

[ ;,* _,.. g,}

NUCLEAR REGULATORY COMMISSION

-1,[g pv ji E

WASHING TON. O. C. 20555 METROPOLITAN EDISON COMPANY JEP.SEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. l'

. AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-50 1.

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

A.

The. application for amendment by GPU Nuclear Corporation, et al (the licensees), dated June 24, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the

. Act), and the Comission's rules and regulations set forth in 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 activi. ties 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 connon 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.

8310260339 831014 hM ADOCK 05000289 PDR 4

,c n-,

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-50 is hereby amended to read as follows:

Technical Specifications t

The Technical Specifications contained in Appendix A, as revised through Amendment No.88, are he'reby incorporated in the. license.

GPU Nuclear Corporation -

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 F. Stolz, 'C.kief ratin'g Reactors Branch-#4 vision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: October 14, 1983 l >

ATTACHMENT TO LICENSE AMENDMENT NO.88 FACILITY OPERATING LICENSE NO. DPR-50 DOCKFT NO. 50-289 Replace the following-pages of the Appendix "A" Technical. Specifications

~

with the enclosed pages. The r.evised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Pages Insert Pages 3-96 96 3-97 3-97 3-99 3-99 4-88 4-88

-4.99 4-99 S

e g.

,,w

--w

---aw w9--*

~*-vm w-i-ww---m-w wr w

w oo - w-w p'--'w-t S

M-*--wy-n---w-----

-www


v-

  • ~---w'-

=-

^'.

~

INSTRUMINTATION RADICAC*IVE LIOUID EFFLUENT INSTRDIEX*ATION

~

LIMITINC-CONSITION FOR OPERATION 3.21.1 The radioactive-liquid effluent monitoring instru=entation channels shown in Table 3.21-1 shall be OPERABLE with their alarm / trip setpoin:s se:

to ensure tha: the limits of Specificacica 3.22.1.1 are no:

exceeded.

The l

ALARM / TRIP setpoints of these channels shall be determined in accordance with :he Offsite Dose Calculation Manual (ODCM).

l A?PLICASILITY:

At all times

  • ACTION:

W[th a' radioactive liquid effluent monitoring ' nstruments: ion a.

i channel alarm / trip setpoint less conservative than. req'uired by the above specification, immediately suspend the release of radio-active liquid e'ffluents monitored by the affected channel ~cr declare the channellinoperable.-

~

4 b.

Withless-thantheminimumnumberofradioachiveliquideffiuent monitoring instrumentation channels operable, ' ake the ACTION shown t

in Table 3.21.1.

  • For'FT-84 and RM-L6, operability is not gon: rolled through the closure of "JDL-V 237. required when discharges are pesi:ively
  • For RM-L12 and associated IRTS/IWFS flow interlocks, operabillty is' not gequi 4.-i gd_yhen, d,4segyges.y;e positively controlled through the closure of '

i.,/3 anc Av.-

ou,

  • ?or ?!-li6, cperabill:y.is not required when discharges are pesi:ively centrolled :hrough.che closure of ~4DL-V-257, IW-V-72, 75' and IN-V-2SO.23.

IASES:

i The radioactive liquid effluent instrumentation is provided to' monitor and control, as applicable, the releases of radioactive caterials in liqu d effluents during. actual or potential releases.

The alarm /: rip setpoin:s for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure 'the alar =/ trip will occur prior to exceeding the limits.of 10 CFR 20.

3-96 Amendment No. 77, 38

- - _.. ~ -

O O

e.

)

9 8

e T..

-dO l

. ~.

N w<*

Z.

a n.

W ese Eeal

,I ar E

M '.

M M, j -

.zl

.Z.:*2=,

3 u,

- Z zl g.ZZ<

b

-Z < %s'.

E g

. = -

4~*

e e

P""* l da.s We 1

z l

.s. e O

I X

-hii N

3 [,

9s

-1,

. W) e

-. 8

(

m,I n

90e N

Gg N

me

~*

e

>a-.

W

=.=e ep G

-l W

v 6..

emn* p u

A N E h

g On L =

=

O ew C

's

-=C; a 5 a

~

""= b

)

  • Q Q

C

'OP

_3 M

  • k w

w U

N h===

uu

  • O "3 ^

lf,

> 5 m C

~

0 0:

=

u u 0

G :

-s 2"

  • /.

C<

0 L

0

n v

"E i

==e OC e

i 7 E U 0

r-C -= =

u =

"./:

X; O

==

O

  • H N.

2 tr. >

O

. 3 W,

  • n u

Z' C 6 0

=,

w*

F,-

"O C

.3 M

LS,t 2,

e m.

. emme 0

Amendment No.

U, 88 3-97 O

I 3-,,

,,,-,---or,w mS-r*-

w

TABLE'3.21-1 (Continued)

ACTION 18

.With the number of channels OPERABLE less than recuired b> the

- Minimum Channels OPERABLE requirement, effluent releases ma: be resumed for up to 14 days, provided the: prit: to initiatin; a.

release:

1.

At least two independent sanples are analyzed in 'accordance with Specification.4'22.1.1, and:

2.

At least two. technica11y' qual'ified members of the Unit staff independently verify'the. release rate calculations and. verify the discharge valve lineup.

3.

Manager Unit 1 shall approve each relea.se.

Dtherwise, suspend' release of radioactive affluents via this

- patnway.

ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via

~

~

this pathway may continue for up to 30 days-provided th'at grab samples are collected'and analvzed for gross radioactivity (beta and gan=a) at a ' limit of detection of at least 10 '

microcuries/ml, prior to initiating'a release and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during release.

f i

ACTION 121 With the number of channels.0PERABLE less than required by the Minimum Channels OPERABLE requirement, radioactive effluent releases via this pathway may continue for up.to 30~ days pre-

.vided the flow rate is estimated at least onte'per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> l

during act'ual releases.

Pump curves may be. sed to estimate flou.

I t

f I'

i f

3-99 l

Amendment 12, 88 i

.c

..... -,,,,,~

-,,m-

.,ww-r-~-..n-:-~,,-_-_,...,,._,

-,_,-,,-y

,,,-r,,,

,,v f---

k g

- Tali 1.E 4. 2 l-1 H.A.D.I9.A.Cf.l.VlS l'Iil.II.I D. El'l'l.llE, tit _ titINl'lfOlt,l_NG 1 NSTRllelENTATION SURVElI L

- - j(- - - -1NST llflENT I.

H E t HANNI.l.

CHANNEL.

.Clif._CK;,

CalECK

("Al.I lil:Nr1 UN

,Tl?!s,T Ny g

1.

Itailloartivity tioni tors l'rovidins; Alarm and Automatic Isolation a.

Ifnit i 1.ly n t ti Itadwant e Ef flui'nt s 1.ine (ItH-l.6) g 3

g (.g )

g)( g )

12 IWTS/lWFS discliarl:e. Iine (ltti-l 12)

D l'.

It( 1)

()(g) 2.

Flow Rate lionitorn

{

a.

Unit i 1.lquid Itatlwante Ef Ilneiit I.I ne - (1'r-Il4 )

D(4)

N/A

,R

)

m s

12 Stat ion Efl inent. Dincharne (FT-146) g3(4)

N/A R

)

f i

l 1

g

_T.a_l> l _e_4. _._2. _2_ _1 (Cont'd) a E,

llA,II,10Aql'l V,E, l. l till_II(, WASTE,,S Af t,l'I.I N(i AND,,A,N AI.YS_l S_ l'It0Cl(Att g

a

<T

....._..c.___.

l.I <g u i ti itelease Type Sampling Frerguency flinimum Analysis

' Type of Activity'

l. owe r I.imi t of y

Frenguency Analysis Detectton (1.1.D) w (pCi/ml) a 3

g A2 Continuons "

Continuous #

Cornpos i t e" Princ ipal Car mut '

5x 10-7 lleleases 4-Emi t t e r'sK i

_ c, i

I-131 1 x 10 il

?!

Dissolved and I x 10~

CRAll b.ampic En t ralined. Ca:ics

( anmia emit t ers) t!

s-

.Continuonti-Composite 11 - 3 1x 10 i

e c

-5 e

so i

_Mross jriplia 1x 10~

1 c

Continuous' Q

S r-89, S r-90 5x 10-8 Composite"

-6 l.e-55 1 x 10 2

___P__3_2 ___..._. _

1 x 10..-

~

I e

i e

a f

1 i

4

.