ML20212A943

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Proposed Tech Specs,Incorporating Two Radioactive Liquid Effluent Monitoring Instruments & Associated Surveillance & Sampling Requirements.Evaluation of Significant Hazards Considerations Encl
ML20212A943
Person / Time
Site: Byron  Constellation icon.png
Issue date: 02/18/1987
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20212A894 List:
References
NUDOCS 8703030445
Download: ML20212A943 (8)
v • d • e


Text

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t ATTACHMENT 1 PROPOSED CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS OF FACILITY OPERATING LICENSES NPF-37 AND NPF-66 Revised Pages: 3/4 3-66 3/4 3-67 3/4 3-68 3/4 11-3 3/4 11-5 i

G703030445 870218 PDR ADOCK 05000454 P PDR i

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TABLE 3.3-12 E RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRtMENTATION 1 .

i c MININUM CHANNELS INSTRUNENT OPERA 8tE ACTION r 1. Radioactivity Monitors Providing Alare and 1 e. Automatic Termination of Release a w.

Liquid Radwaste Effluent Line (GRE-PR001) 1

b. F.re 33 C- and Oil Sump Disdor3e. ( ORE - PMooS)

Condens<de. Polisher Sune D.schors<. a g

2. . Radioactivity Monitors Providing Alare( ORE - pro *1#)

5- 1

.Ilut Not Providing Automatic Termination 31

-af Release

a. Essentia) Service Water

! Re 1) Unit 1 T

j 'J: a) RCfC 1A and IC Outlet (IRE-PR002) 1 32 b) ."CfC 18 and 1D Outlet (IRE-PR003) 1 32 1

2) Unit 2 1

a) RCFC 2A and 2C Outlet (2RE-PR002) 1 32 b) PCFC 28 and 20 Outlet (2RE-PR003) 1 32 b.

Station Slowdown Line (GRE-PR010) 1 32

3. Flow Rate Measurement Devices
a. Liquid Radwaste Effluent'Line (Loop-WX001) 1 33
h. Station Blowdown Line (toop-CWO32) 1 33 i 1 1

l l

l _

TABLE 3.3-12 (Centinued)

ACTION STATEMENTS ACTION 31 ' With tne number of channels OPERA 8LE less than required by the Minimus Channels OPERA 8LE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:

a. At least t.wo independent samples ire analyzed in accordance aith Specification 4.11.1.1.1, and-
b. At least two technically qualified ,wmoers of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway., ,

ACTION 32 - With the ntaber of channels CPERA8LE less -Jun. required by the Minimum Channels OPERA 8LE requirement, eff.luent releases via tDis pathway may continue for up to 30 days provided that, at least-once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab-anspies are collected and analy:ed for -

radioactivity at a lower ifmit of detection of no more than 10 7 microcurie /al.

ACTION 33 - With the number of' channels OPERA 8LE less than required by the Minimum Channels OPERA 8LE requirement,. effluent releases via this

'- pathway may continue for up to 30 days provided the flow cate is-estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actwil releans. : Pump.

performance curves generated in place may be used to estimate flow.

f Ac.TicN3'l - Wim 4he. number- of channels CPWABLE lea 5 %dn (Tguireri by th e-Minimum C hannels OPER.A6LE reguirtyne@, e ff foci,g Twlceses via %e5 prkway ma conHna*. fet up ts 30 day s provided Arcy sa@s for- radiocchv; li%f. of cielYchcw cLs are, analyspeci R ed in Table. 'i . il - I :g 44- a leur

.a. AF leq5F cnce per 12. heves whew he Specik ochvih of +44

. secevidag ccelant- is greal+ - %4% 0.01 microCuree./c$mn, Dose EQUIVALErr I - 131 j of

b. A v leq5 p cnce. per 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> tahew h SpedA<. OcHvi of %e.

Secondor coelow i3 )<SJ iban or eguhl to 0.01 micro Curie./3ram

Dose E Ut vA LE1\TT" I - 13 ) .

3 1

'-~

  • 3YRON - UNITS 1 & Z 3/4 3-67

\ s ,

i TA8tE 4.3-8 ,

I 4 3

! E RADIGACTIVE LIQUID EFFLUENT NONITORING INSTRUNENTATION SURVfitLANCE RE0ulRE l c DIGITAL ANALOG g Cil4NNEL CHANNEL CHANNEL d INSTRUNENT CHECK SOURCE CHECK CHAUML OPERATIONAL OPERATIONAL Call 8AATION TEST TEST

[ 1. Radioactivity Monitors Providing '

] m Alars and Automatic Termination

,' of Release n.

Liquid Radwaste Effluent Line (ORE-PR001) 8 P

) b. F;re. und 0;t .3 ump tischer3e. (CRE - PRooS) R(3) Q(1) N.A.

D M R(3) q (s)

! c. (.ondensc k. Pol; sher Sump Discherse (dRE-PR011) D N.A.

! 2. Radioactivity Monitors Providing Alare But ti R(3) Q(i) N. A .

Not Providlng Automatic Terslaation of Release 1

i y a. Essential Service Water i y 1) Unit 1

\

1 C

I a) RCFC 1A and 1C Outlet (1RE-PR002) 0 M R(3) 0 Q(2) N.A.

b) RCFC 18 and 10 Outlet (1RE-PR003) M R(3) Q(2) N.A.

2) Unit 2

) a) RCFC 2A and 2C Outlet (2RE-PR002) O M

! R(3) Q(2) N.A.

1 b) RCFC 2R and 20 Outlet (2RE-PR003) O M R(3) Q(2)

N.A.

j b.

Station Blowdown Line (ORE-PR010) 8 M R(3) Q(2) N.A.

3. Flow Rate Measurement Devices
d. Liquid Radwaste Effluent'line (Loop-WX001) 0(4) N.A. R N.A. Q
b. Station Blowdown Line (Loop-CWo32) 0(4) N.A. R N.A. Q r

l i

n TABLE 4.11-1 (Continued)

RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAN LOWER LIMIT MINIMUM OF D UECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE TYPE OF ACTIVITY (LLD){ )

FREQUENCY FREQUENCY ANALYSIS (pCf/ml)

3. Continuous W C7) W C7) Principal Gamma 5x10 7 Release (5) Grab Sample EmittersC3) o.. Essential i Service Water Reactor Coolant Fan ' '

Cooler (RCFC)

Outlet Line (RE.- PAcol )

and RE.PR005 r

b. p;ce, and Oil

- I-131 1x10.s s ep Dack<wf. *

( CRE -PR005) Dissolved and C. C & s ale. Entrained Gases Po hsher 1x10.s (Gamma Emitters)

Jwy Duckdry:.

CORJE - Pf 091) g.3 1xyg.s ,

l i

O O 1

9 4 6 BYRON - UNITS 1 &'2' ' '

3/4 11-3 l_ _ _ _ _ _ _ , . - - _ - - - -- - - _ - - - - - - - - - - --- - - - - - - - - - - - " - ~ ~ - ~ ~ - ~ ~ - ~ ~

TA8LE 4.11-1 (Continued)

TABLE NOTATIONS (Continued)

(3) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-54, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Co-141, and Ca-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7 in the format outlined in Regulatory Guide 1.21, Appendix 8, Revision 1. June 1974.

(4) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g.,

continuous from a volume of a system that has an input flow during the release.

(6) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent releash.

(7) Not reqEi.m, ;!::=

  • Fanantial Servica We "C"C L ies saatation Monitort RE-PR002 =af Z enuus indicas.. ---= C"r d levels greater than W above background at any time during sn. d . _

Samp);= and anal 3.si.s onl PaA dnen the_ assoc.iated.y n:'huir rad; H e m e n. edrov- en on e ffluent release.in Ievefs cfeak# 4% Iy Io'" pCiImI above background unlex he Se+poinf- is exceaded due l'o a SPuncus noise. 'spk e.

BYRON - UNITS 1 & 2 3/4 11-5

l ATTACHMENT 2 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATIONS 10 CFR 50.92(c) states that a proposed amendment will involve no significant hazards considerations if the proposed amendment does not:

1. Involve a significant increase in the probability or consequences j of an accident previously evaluated; or
2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or
3. Involve a significant reduction in a margin of safety.

The discussion below addresses the proposed amendment, how each of these three criteria apply to the changes, and demonstrates that the proposed amendment involves no significant hazards considerations.

The proposed amendment adds two radiation monitors to the Technical Specifications: one on the condensate cleanup (CP) system sump and one on the fire and oil sump. Upon detection of unacceptable levels of radioacti-vity in sump effluent, the monitors are designed to alarm and automatically terminate sump discharge. Monitor setpoints are conservatively placed to ensure that 10 CFR 20.106 limits are not exceeded.

The proposed changes do not involve significant hazards considera-tions because operation of Byron Units 1 & 2 in accordance with these changes would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. Accidents previously evaluated involve an airborne release to the environment from the rupture of a spent resin storage tank or boron recycle holdup tank and; a liquid release to groundwater resulting from the rupture of the boron recycle holdup tank.

The probability of occurrence of these accidents is not affected by establishing a monitored effluent release path of potentially radioactive fluid from the CP sump or fire and oil sump.

The consequences of these previously evaluated accidents have been determined to be within 10 CFR 100 and 10 CFR 20 limits.

Establishing a monitored effluent release path from the CP sump or fire and oil sump will not affect the consequences of these previously evaluated tank ruptures.

2. Create the possibility of a new or different kind of accident from any accident previously evaluated. The additional effluent release paths and monitors do not interface with any safety related system or equipment. An evaluation of the expected activity from these two systems indicates that activity levels should be negligible.

The addition of a radiation monitor in each release path assures that discharges are properly monitored and terminated if unacceptable levels of radioactivity are detected. This function assures that releases in excess of 10 CFR 20 ILmits do not occur via these pathways during normal or accident situations. The addition of these monitors to the Technical Specifications further assures their operability to prevent releases. The addition of these monitors will minimize the possibility for a new or different kind of accident.

3. Involve a significant reduction in a margin of safety. The added radiation monitors do not interface with safety related equipment or instruments. Releases via the CP sump and the fire and oil sump are expected to be minimal and well below the limits of 10 CFR 20.

Addition of the radiation monitors to detect and prevent any radioactive release provides an additional measure of control for release paths where activity levels are expected to be minimal.

The changes therefore do not involve a significant reduction in a margin of safety.

Based on the above discussion, Commonwealth Edison concludes that the proposed amendment will involve no significant hazards considerations.

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