ML19274D819

Amend 43 to License DPR-62,revising Tech Specs to Limit Annual Gaseous Release to 10CFR50 Design Objectives During Interim Period

ML19274D819
Person / Time
Site:	Brunswick
Issue date:	02/09/1979
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML19274D814	List: ML19274D813 ML19274D819 ML19274D824
References
NUDOCS 7902260187
Download: ML19274D819 (21)

Text

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/

UNITE D STATES NUCLEAR REGULATORY COMMisslON c'

• e vv ASHINGTON,0. C. 20666 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING L? CENSE Amendment No. 43 License No. DPR-62 1.

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

The application for amendment by Carolina Power & Light Company A.

(the licensee) dated October 16, 1978 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 10 CFR Chapter I; The facility will operate in conformity with the application, B.

the provisions of the Act, and the rules and regulations of the Comission; There is reasonable assurance (i) that the activities authorized C.

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; The issuance of this amendment will not be inimical to the D.

common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part E.

51 of the Commission's regulations and all applicable requirements have been satisfied.

Accordingly, the license is amended by changes to the Technical Spec-2.

ification as indicated in the attachn'ent to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 43, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

790226018'i

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

3.

FOR THE NUCLEAR REGULATORY C0tVilSSION Th p

hief Operating Reactors Branch #3 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 9,1979

ATTACHMLNT 10 LICENSE AMENDMENT N0. 43 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following pages of the Appendix "B" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Renove Insert i*

i*

11 ii 2-8 2-8 2-9 2-9 2-10 2-10 2-11 2-11 2-12 2-12 2-13 2-13 2-14 2-14 2-14a 2-19 2-19 2-20 2-20 2-21 2-21 2-22 2-22 2-23 2-23 2-31 4-9 4-9 4-9(a)

• 0verleaf page provided for convenience.

~

BRUNSWICK STIAM ELECTRIC PLANT,1/ NITS 1 & 2 ENVIRONMENTAL TECHNICAL SPECITICATIONS TABLE OF CONTENTS PAGE No.

SECTION_

1-1 to 1-3 1.0 Definitions l

2.0 Environmental Protection Conditions 2-1 to 2-3 2.1 Thermal 2-4 to 2-5 2.2 Che=1 cal 2-6 2.3 Hydraulic 2-7 2.4 Meteorology 2-8 to 2-14 2.5 Radioactive Discharges 3.0 Surveillance Requirements 2-1 to 2-3 3.1 Ther=al 2-4 to 2-5 3.2 Chemical 2-6 3.3 Hydraulic 2-7 3.4 Meteorology 2-8 to 2-14 3.5 Radioactive Discharges 2-15 to 2-23 Bases

_=&

4.0 Environmental Surveillance 4-1 to 4-5 4.1 Biological Surveillance 4-5 to 4-10 4.2 Radiological Enviroc= ental Monitoring Progra=

5-1 to 5-7 5.0 Administrative controls Special Surveillance and Study Activities 6-1 to 6-3 6.0 6.1 Harsh Productivity 6-4 6.2 Deleted 6-5 6.3 Deleted 6-6 to 6-7 6.4 Salt Deposition Monitoring j

f 71gures I

i i

l 1

Amendments 7 & 29

LIST OF TABLES PACE NO.

j TABLE _

2-24 to 2-25 3.5-1 Radioactive Liquid Sa=pling and Analysis 2-26 to 2-27 3.5-2 Radioactive Caseous Waste Sa=pling and /.nalysis 2-28 3.5-3 Liquid Waste system:

Location of Process and Effluent Monitors and Samplers Required By Technical Specifications I.

2-29 l

3.5-4 Gaseous Waste Water System:

Location of Process and Effluent Monitors and i

Samplers Required by Technical Specifications 2-30 3.5-5 Average Energy Per Disintegration 2-31 3.5-6 Assumptions for Limiting Equation for Iodine and Radioactive Particles 4-11 to 4-15 4.2-1 Environ = ental Radiological Monitoring Program -

Brunswick Stea= Electric Plant i

4-16 to 4-19 4.2-2 Analysis of Sa=ples 4-20 to 4-22 l

4.2-3 E=vironmental Rac'iological Monitoring Progra=

Su==ary - Brunsvick Steam Electric Plant i

4-23

{~

4.2-4a Typical Mini =um Detectable Concentrations -

Ge-Li Ga==a Spectro =etry 4-24 l

4.2-4b Mini =uu Detectable Concentrations 4-25 4.2-5 Control Stations for BSEP Environ = ental Radiological Monitoring Program t

11 Amendbent No. 43

c I

j BSEP - 1 6 2 f,

l 2.0 LNVic r m;TAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIRE C;TS t

2.5 RADIOACTIVE DIScilARGES 3.5 RADIOACTIVT DISCHARCES e

Obj ect ive : To define the limits and Objective: The purpose of these specifica-conditions for the controlled release of

~ tions is to ensure that the releases of radioactive materials in liquid and gas-radioactive materials are ar. low as cous effluents to the environs to ensure reasonably achievable and within allowable that these releases are as low as reason-values.

3 ably achievable. These releases should not result in radiation exposures in unre-stricted areas greater than a few percent of natural backg'round exposures. All effluents shall be within the limits specified in 10 CFR Part 20.

To ensure that tnu release of radioactive material above background to unrestricted areas will be as low as reasonably

.I achievable as defined in Appendix I to 10 CFR Part 50, the following design objectives apply.

l.

For liquid wastes:

a.

The annual dose above background to the total body er any organ of an individual from all reactors at a site should not exceed 5 nrca in an unrestricted area, b.

The annual total quantity of radio-I active =aterials in liquid waste, excluding tritium and dissolved and entrained fission and activation gases discharged f rom the site should not exceed 5 Ci per reactor.

i For gaseous wastes:

a.' The annual total quantity of noble ga;cs above background discharged from the site should result in an air dose due to ganas radiation of less than 20 mrad, and an air dose j

due to beta radi tion of less than 40 nrad, at any locat ion near ground Icvel which could be occupied by individuals at or beyond the bound-ary of the site.

2-8 Amendment No.

43 i

PS fl -1L2 2.0

!!;V150::':E';!AL PROTECT 10:; CO::DIT10::S 3.0 St'EVEILLMCC RT.:;;KE?n S 2.5 F.\\DI c cT1'!E DI5 21.iRGE5 (Cont'd) i 3.5 LW101.CTirL Disc lace 3. ment'dj

~

l b.

The annual total quantity of 1-131 and radioactive material in particulate f orms g with half-lives greater than 8 days abcve; background from all reactors at a site should not result in an annual dose to any organ of an individual in an unre-stricted area from all pathways of expo-sure in excess of 30 mrem.

[

i i

?

S _ecific ations f er, Liq :id vas t e 2.5.1 Specifications for Liquid '4aste 3.5.1 E

Effluents l

Sampling and Moniterin; a.

The concentration of radioactive materi-I a..

Plant records shall ce maintained of the l

radioactive concentration rnd volutt before als released in liquid waste cffluents from all reactors at the site after dilu-dilution of liquid waste discharged, and the tion in the discharge canal shall not average dilution flow and length of time nye-excced the 'ealues specified in 10 C?R which each discharge occurred. Sample anal;.

Part 20, Appendix B, Table II, Column 2, ses results and cther re;crts shall be sub-nitted in accordance with Section 5.4 of for unrestricted areas.

(

b.

The cumulative release of radioactive these specifications.

Est. nates of tbc s ar.p materials fron the site in liquid waste ling and analytical errer shc11 be included effluent, excluding tritium and dissolved as stated in NRC Reculater" Guide 1.?1 und entrained fission and activation b.

Prior to relc ase of each batch of liquid gases,~shall not exceed 10 Ci per reat.

waste, a sample shall be taken from that batch and analyted f or each signi ficant tor in a calendar quarter.

gamma peak in accord 2nce with Table 3.5-1 c.

ihe curulative release of radioactive to demonstrate compliance with Specifica-materials f rom the site in liquid waste effluents excludiag tritium and dis-tion 2.5.1 using thc flew rate of the stream into which the vaste is discharged g

solved and entrained fission and activa-tien gases, shall not exceed 20 Ci.)er during the period of dis:harge.

Sampling and analysis of liquid radioactiva reactor in any 12 consecutive months.

c.

waste shall be performed in accordance

'd.

During release of radioactive vastes, with Table 3.5-1.

Prior to taking sampics the effluent control aonitor shall.be f rom a sample or drain tank, at least two set to alarm and to initiate the auto-tank volumes shall be recirculated.

..S matic closure of each vaste discharge d.

The radioactivity in liquid wastes shall valve prior to exceeding the limits be continuously monitored and recorded speci led in 2.5.1.a above.

. e '.. The o>erability of each automatic isola-during release. Whcnever these ronitors are inoperable for a period not to tion valve in the liquid radwaste dis-exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent s amp i m o.

charge line shall be demonstrated cach tank i o be discharged shall te ana-quarterly.

f.

The equip:acnt installed in the liqufd lyred and two plant persranel shall inden,-

radioactive waste system shall be main-dent ly chec k valvine, prict to the discharge if these monitors are inepercole for a tained and shall be operated t? process radioactive liquid vastes prior to thcir period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no liquid wast <

tank shall be released ar.d any release in a

discharge when the projected cumulat ive release from the site could exceed 1,25 progress shall be terminated.

}

Ci per reactor in a calendar quarter.

excladir.; tritium and disselved and entrained fission and activatien gases.

2

,1 Amendment No.

43

BSE' 1 62 e

2.0 1 I E.." INTAL TF.0TT.CTICS NSDITIONS 3.0 S UR'.'E I LLiu CE RE T

• LE".E:C i 2.;.1

..q...

4 ;j e _. :1uants (cont'u) 3.5.1 L:nuid..i s t e

_ en e :::nt':)

~'

n.

'm us i.un radicactivity to be con-e.

The llow rate of.: quid r..cica:; ice tained in any liquid radvaste tank that waste shall be contir.uall ceasured can be discharcod directly to the and recorded dur ng release.

environs shall not exceed 10 C1, f.

All liquid effluent radiation ronitors excluding tritium and dissolved and shall be calibrated at least quarterly ent rained fission and activation gases.

by means of a known radioactive source h.

If the cumulative release of radioactive ;

which has been calibrated to a National naterials in liquid effluents excluding Bureau of Standards source. Each monitor tritium and dissolved and entrained shall aleo have a functional test monthly fission and activation gases, exceeds and an instrument check prior to naking 2.5 Ci per reactor in a calendar quarter,,

a release.

~

the licensee shall make an investigation,

to identify the causes of such releases, I I

define and initiate a progran of action to reduce such releases to the design i

objective levels listed in Section 2.5, and report these actions to the Cor. mis-sior. within 30 days f rom the end of the !

quarter during which the release l

m curred.

3.5. 2 Spec i fica t ions fer case'us waste

'or Q wne L'a r t e pa_rylig and "c

erin.-

2. 5. 2 ations ~

~

I

~

0

',:.r.e I

a.

I'lant recerds shal: be.aintained and a.

II) ine release rate limit of neble records of the samplinz nd analysis results shall be e ^

d-ed in accordance gases f ron this site shall be:

with Section 3.*, or these Specifi-cations.

Estinates of the sarpling Q

4.OE t 0. 2 3E.

+ Q 35E + 92E

< 1 v.

Yi 6i and analytical errcr associated with sg,

. y1 D) i 1+n each report (d value should be included.

release rate from main stack b.

Gascous releases to the environment where Qs

=

in C1/sec (elevated release).

from the two reactor building vents, the two turbine builoing ver.ts, and the off-Qy = release rate from vents in Ci/sec gas vent (stack), except as noted in (ground release)

Specification 3.5.2.c below, shall be continuously monitored for gross radio-i= the ith individual nuclide.

activity and the flow nessured and recorde n " total number of nuclides.

Whenever these monitors are inoperable, grab samples shall be taken and analyzed the average gamma energy per daily for gross gaseous radioactivity, If E-Yi disintegration f or ~uclide 1.

these monitors cre ineperable for more than seven days, these releases shall be

-E=

the average beta energy per terminated or t' e plant shall be snoi dcwn r

di disintegration for nuclide 1.

c.

An isotopic analysis shall be made of a representativc sample of gaseous Refer to Tabic 3.5-5 for E_

and E.1 activity, exclucinC tritium, at the Ti 0

values to be used.

discharge of the stear jet air ejectore and at a point prior to dilution and discharge.

(1) at least conthly, Amendment No. 43 2-10

BSE? - 1 & 2 2.0 EK.'I F.0:RIE:.TC PROTECT

• 0N CO::DITICNS 3.0 StTR','EILL* :2E RE2UIT.D:E';TS 2.5.2 C seca Vaste Effluents (cont'd) c.

Should any or the conditions cf l

2.4. 2.c"(1), or (2) listed below exist, the licensee. shall take an investigation to identify the causes of the release rates, define and in-itiate a progrc of cetica to reduce t' e release rates to design objective n

levels listed in Section 2.5 cad re-port these actions to the Consission within 30 days frca the end of the quarter durin2 which the releases etcurred.

(1) If th. average release rate of noble gases during any calendar quarter from the site is:

1 E

1.50Q

+ 575 Q

-<fl 8

s v.

n..n i,

i i

Or 45Q

+ 400 Q f1 E y s

v i'

i i

.a (2) If the average release rate of I-131 and radioactive materials in p' articulate form with half-lives greater than cight days during any calendar quarter f rom the site is; 0

3.26x 10 Q,_ +

3.74 x 10 Q Il v,

(if no teen, child or infant milk consumption)

The consumption of milk must be demon-strated by the Radiological Environ-mental Monitoring Program 4.2.7.

If the Radiological Environmental Moni-toring Program determines the consump-tion of milk by teen, child, or infant, the above equation shall be modified by the appropriate coefficients (Dose Factors) of Regulatory Guide 1.109.

Amendment No. 43

ESEP - 1 & 2

-/

~'2.0 D

F.0'." ~ A T F.0!ECT IO: CJSDITICNS 3.0 S D " U L' /12 E El ' C h!;IS

-': e t f f it.c n:c_ (cont 'd) 3.5.2 C a, c e.m '. a. t c

-t.: '

(Ornt'd) 2.5.2 cnce r s

(2) Tnc re. :se rate limit of

(

(2) within 1 conth, folicwing cach

{

1-131 and radicactive caterials refueling outege,

~

in particulan form with half-lives (3) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, if the r,aseous l

greater tnan eight days, released to vaste conitoro indicate an increase the cavirons as part of the gaseous of greater than 50.; in the steady vastes frer. the site chall be:

state fission gas relcase af ter factoring out increases due to power changes.

6

+

5.8 x 10 Q 3 1 3.7 x 10 Q,

d.

All vaste a: effluant nonitors shall be where Q = release _ rate fros.the main calibrated ac lesst quarterly by means stack in Ci/sec (as elevat-of a knevn radios:tive source which has ed release) been calibrated to a National Bureau of Standards source.

? :h cenitor shall have release rate fro: the vents functional t est et least renthly Q

=

in Ci/sec (ground release) g u s 2,... --. check at least daily, excluding days of no discharge.

b.

(1) the average release rate of noble, gases from the site during any 12 c.

Sanpling :nd.inalysis of r:dioactive consecutive months shall be:

n.:cri 1 :n ga ;;c.:3._ ; 3 t c, 73 7 t ;c., t c.,

fore, and radioicdine chall le perferned i

e- --

+ ll60Q ] $1 l

in accordcnce with Ta5le 3.5-2.

g [2.8Q E

i+n and 90Q

+ 8000 3 1 qt

'A 1*n L'

where Q

= release rate of radioisotope i si from the main stack in Ci/sec Q

= release rate of radioisotope i from f

the vents of each reactor in Ci/sec.

(2) The average release rate from the site of I-131 and radioactive materials in particulate form with half-lives greater than eight days g

during any period of 12 consecutive m

months shall be:

u D.

u 6

7 (6.56 x 10 Q ) + (7.46 x 10 Q )

o S

V

-<1 m

n z

(If no teen, child or iifant milk o

consumption) n The consumption of milk must be demon-w strated by the Radiological Environ-mental Monitoring Program 4.2.7.

If the Radiological Environmental Moni-toring Program determines the consump-tion of milk by teen, child, or infant the above equation shall be modified by the appropriate coefficient (Dose Factors) of Regulatory Guide 1.109.

2-11

BSEP - 1 & 2 t

2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.2 Gaseous Waste Effluents (cont'd)

F.

The operability of each automatic isolation valve in the gaseous rad-waste discharge line shall be demon-strated quarterly.

l f',

Whenever the augmented off gas (A0G) d.

system is out of service, at least one of the condenser / air ejector off gas monitors listed in Table 3.5-4 shall be operating and set to alarm and cap-able to initiate the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in 2.5.2 above.

e.

If both condenser / air elector off gas monitors are incapable of initiao!"e automatic closure of the waste gas discharge valves, a shutdown shall be initiated so that the reactor will be in the hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The augmented of f gas (A0G) process monitor shall be operable whenever a release is being made from the A0G system storage tanks.

If the augmented off gas system is out of service and the air ejector off gas monitors are inoperative, a reactor shutdown shall be initiated so that the reactor will be in the he t shutdown condition within 24 houra.

f.

If the release rate from the site of noble gases from the main condenser vacuum system is:

E g

1. 5 Q

+ 575 Q

>1 1-n l'

i l'

I or E

• 400 Q

>1 45 Q*i "i

Y 1*n i

Amendment No. 43 2-13

BSEP - 1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.2 CASEOU$ WASTE EFFLUENTS (cont'd) for a period of greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, notify the Commission in writing with-in 10 days, identifying the causes of activity.

The report should include the flow rate of the off gas from the main condenser vacuum system and the act'ivity measured at the off gas steam jet air ejector (SJAE). monitor.

g.

The drywell shall be purged through the standby gas treatment system, or released'to the environment at a rate in conformance with Specification 2.5.2.c(2) based on a containment sample analysis as defined in Table 3.5-2.

h.

Either the hydrogen monitor and one of the two temperature switches or both temperature switches in the off gas line downstream of.:he recombiners shall be operable during (A0G) oper-ation.

If the hydrogen concentration reaches set point of four pt cent by volume or the temperature reaches the setpoint of 900*F, the off gas flow shall be stopped by automatically closing the valves downstream of the recombiners.

Whenever any two of these three devices are inoperable during (A0G) operation, grab samples shall be taken and analyzed for hydrogen concentration each shift.

Calibration of the monitoring system shall be per-formed quarterly and checked weekly by comparison to grab-sample analysis.

2.5.3 Specifications for Solid Waste Handling and Disposal a.

Measurements shall be made to determine or estimate the total curie quantity and principal radio-nuclide composition of all radio-active solid waste shipped

offsite, b.

Solid wastes preparatory to ship-ment shall be monitored and pack-aged to assure compliance with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 171-178.

e k>. 43 2-14

BSEP - 1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.3 Specifications for Solid Waste Handling and Disposal (cont'd)

Reports of the radioactive solid c.

waste shipments, volumes, principal radionuclidas, and total curie quantity, small be submitted in accordance with Section 5.4.

Amendment No.

43 2-14a

GASEOUS WASTE EFFLUENTS - The release of radioactive materials in gaseous waste effluents to anrestricted areas shall not exceed the concentration limits spec-ified in 10 CFR Part 20, and should be as low as reasonably achievable in accordance with the requirements of 10 CFR Part 50.36.

These specifications provide reasonable assurance that the resulting annual air dose from this site due to gamma radiation will not exceed 20 mrad, and an annual air dose due to beta radiation vill not exceed 40 mrad from noble gases, and that the annual dose to any organ of an individual from I-131 and particulates with half-lives greater than 8 days will l

not exceed 30 mrem.

I j '

The design objectives have been developed based on operating experience, taking into account a combidation of system variables including defective fuel, primary system leakage, and the performance of the various waste treatment systems.

For Specification 2.5.2.a(1) dose calculations have been made for the critical These calculations consider site meteorology, buoyancy characteristics, sector.

and radionuclide content of the effluent of each unit.

Meteorological calcula-tions for offsite locations were performed, and the most critical one was selected to set the release rate. The controlling distance is 914 meters to the south-southeast.

The gamma dose contribution was determined using the equation 7.63 in Sectien 7-5.2.5 of Meteorolcev and Atonic Enerr. - 1968.

The releases l

fica vents are considered to be ground level releases whica ceuld result 1

in a beta dose icom cloud submersion.

The beta dose contribution was deter-mined us.ing Equation 7.21, as desc~ribed in Section 7-4.1 of 'teteorolocy and Atonic Ener y - 1968.

The beta dose centribution was deterrined on the basis of an infinite cloud passage with semi-infinite geocetry for a ground level release (subnersion dose).

The beta and gamna components of the gross radioactivity in gaseous effluents were corbined te de:er-mine the allowable continuous release rate.

Based on these caltulations, a continuous release rate of gross radioactivit, in the amount specified in 2.3.2.a(1) will -no t result in offsite annual doses above backgrcund in excess of the linits specified in 10 CFR Part 20.

The average gamra and beta energy per disintegration used in the equa-tion of Specificction 2. 5.2.a (1) will be based en the averace conposi-tion of gases determined frem the plant vent and ventilation exhaus:s.

Amendment No.

43 2-19

L'

, The average energy per beta or gamma disintegration for those radio-isotopes determined to be present fron the isotopic analyses are given 17 Table 3.5-5.

'Jhere isotopes are identified that are not listed in Table 3.5-5, the gamma energy are determined f rom Table of Isotcoes, O. M. Lederer, J.'M.

Hollander, and I. Perlman, Sixth Edition, 1967 and.

'he beta energy shall be as given in USNRDL-TR-802, II.

Spectra of Individual Necatron Emitters (Beta Spectra), O. Hogan, p. E. Zigman, and J. L. Mackin.

For Specification 2.5.2.a(2), dose calculations have been made for the critical sectors ano critical pathways for I-131 and radio-active =aterial in particulate form with half-lives greater then eight days.

The calculations consider site meteorology for these releases.

. Specification 2.5.2.b establishes upper site levels for the releases of

' noble gases, iodines and particulates with half lives greater than eight days, and iodine-131 at the design objective annual quantity during any period of 12 consecutive months.

Since BSEP does not have an A0G that has been demonstrated to be continuously operable, the content of these limiting conditions for operation assumes that the design objectives of 2.5a and b for gaseous wastes can be met.

This specification does not limit the instantaneous gaseous radioactive release rate, but permits the licensee the flexibility of operation to assure that the public is pro-vided a dependable source of power under unusual operating conditions which may temporarily result in higher releases than the objectives and yet remain below annual design objective releases. The equation limiting radioactivity releases was established based on on-site meteorological data and method-ology of Regulatory Guides 1.109 and 1.111, and methods provided in Meteorology and Atomic Energy (1968).

For iodine-131 and radioactive material in particulate form with half-lives greater than eight days, the critical location for ground releases is the

-6 SSE sector distance of 1464 meters where X /Q is 6.5 x 10 sec/m for the dose due to inhalation.

The critical location for elevated releases is the SSE sector at a distance of 1464 meters where the X/Q is 3.45 x 10~

sec/m for the dose, due to inhalation.

The assumptions for the grass-cow-milk-thyroid chain are listed in Table 3.5-6.

The grass-cow-milk thyroid chain is controlling.

Amendment No. 43 2-20 i

in addition to the protection conditions of Specifications 2.5.2.a and 2.5.2.b, the reporting requirements of 2.5.2.c delineate that the cause be identified whenever the release of gaseous effluents exceeds one-half the objective annual quantity during any calendar quarter, and describe the propose'd program of action to reduce such release rates to the design obj ectives.

Specifications 2.5.2.d and 2.5.2.e assure compliance with NRC general design criterion 64.

The 24-hour period will allow an investigation of several hours to determine the cause of the monitor inoperability and possible repair prior to initiating-the hot-shutdown.

Specification 2.5.2.f is to monitor the performance of the core. A sudden increase in the activity levels of gaseous releases may be the result of defective fuel.

Since core performance is of utmost importance in the resulting doses, a report must be filed within 10 days following the specified increase in gaseous radioactive releases.

I I

Specification 2.5.2.g requires that the primary containment atmosphere 6

receive treatment for the removal of gaseous iodine and particulates prior to its release.

Specification 2.5.2.h requires that hydrogen concentration in the system shall be monitored at all times during A0G operation to prevent buildup of combustible concentrations.

I l

The sampling and menitoring require =ents given under Specification 3.5.2 provide assurance that radioactive materials released in gaseous wastes are properly controlled and monitored in conforcance with the requirements of Design Criteria 63 and 64 These requirements provide the data for the licensee and the Cennission to evaluate the plant's performance relative to

~

radioactive vastes released to the environment.

Reports on the quantir.ies of radicactive n2:erials released in gaseous effluents are furnished to the Connission en the basis of Section 5.4 of these Technical Spe cif t:a:icn cnd in conforuance with ?.egulatory Guide 1.21.

On the basis of such reports and any additional information the Commission may obtain fran the licensee er others, the C._.tssier may frem ti=e to time require the licensee to tar such action as :he Cc=nission deems appropriate.

Amendment No.

43 2-21

The points of release to the environment to be monitored in Section 3.5.2 include all the monitored release points as provided for in Table 3.5-4.

SOLID k'ASTE RANDLING AND DISPOSAL - The requiremdnts f or solid radicactive waste handling and disposal given under Specification 2.5.3 provide assurance that solid radioactive materials shipped offsite are properly controlled, monitored, and packaged in conformance with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 171-178.

These requirements provide the data for the licensee and the Commission to evaluate the handling and storage facilities for solid radwaste, and to evaluate the environmental impact of offsite ship-ment and storage.

Reports on the quantities and amounts of the radic'nuclides, and volumes of the shipments, shall be furnished to the Commission according to Section 5.4 of these Technical Specifications.

On the basis of such reports and any additional information the Commissica may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.

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Amendment No.

43 2-22

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I 2-23 Amendment No. 43 i

TABLE 3.5-6 Assumptions for Limiting Equation for Iodine and Ra'dioactive Particles (with Half Lives Greater than Eight Da'vs)

Cov's Consumption Rate 50 Kg/ day 2

Agricultural Productivity (feed grass)

.7 kg/m 2

Agricultural Productivity (stored feed) 2.0 kg/m

-3

. Stable Element Transfer coefficient 6.0 x 10 day /1 Fraction of Activity Retained on Feed Grass 1

Transport Time from Cow to Receptor (feed grass)

. 2 days Transport Time from Cow to Receptor (stored feed) 90 days Fraction of the Year Cow is on Pasture

.7 i

Uptake Rate:

t 310 1/yr.

Adult Thyroid Ingestion Dose Factor (I-131):

~3 1.95 x 10 mrem /pci Adult l

Meteorlogy Data (Steven's cow):

Critical Sector SSE width 22.5 Critical Distance 1464m Annual Average Relative Deposition

-9 m' (D/Q elevatef 2.16 x 10 Annual Average Relative Deposition

~D

-4 (D/Q ground) 2.4 x 10 m

2-31 icendment No. 43

4.2.6 Soil Samoling Soil samples are. collected from eleven locations every l

three years and beach sand is collected from three locations semiannually.

Analysis of soil samples includes ' Sr and gammn spectrometry.

4.2.7 Milk Sanoling Milk samples will be col-lected from either two or three locations on a weekly frequency.

One sampling station is a family cow that does not produce sufficient milk for a sample every week. Within seven days of sampling, 131I analysis will be completed using an analytical an procedure similar in sensitivity to the procedure out-lined in Regulttory Guide 4.3.

Samples of individual locations will be composited monthly and analyzed for

'Sr, Sr, and by gamma spectrometry. To determine the presence of an infant, child or teen consuming the milk from the cow (s) at sample station 35 (Steven's Farm), a survey on the usage of the milk should be conducted at least once per calendar quarter.

The result of this survey should be included in the semiannual Radiation Effluent Release Report.

4.2.8 Terrestrial Veeetation Samples of the leafy portions of natural terrestrial vegetation will be collected quarterly from four loca-tions in the vicinity of the plant.

Samples will be analyzed by gamma spectrocetry.

i 4.2.9 Food Crops Edible portions of food crops will be collected from two locations three tines during the growing season.

Samples will be analyzed by gamma spectrometry.

Amendment No.43 4-9

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