ML19274D813

Amend 19 to License DPR-71.Revises Tech Specs to Limit Annual Gaseous Release to 10CFR50 Design Objectives During Interim Period

ML19274D813
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 7902260182
Download: ML19274D813 (21)

Text

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umTro:Tavirs NUCLEAR REGULATORY COMMiss10N y

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l CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1_

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 19 License No. DPR-71 The Nuclear Regulatory Comission (the Comission) has found that:

1.

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

(thelicensee)datedOctober 16, 1978 complies with th-standards l

j 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 confomity with the application, B.

the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (1) that the activities authorized C.

by this amendment can be conducted without endangering the I

health and safety of the public, and (ii) that such ectivities will be conducted in compliance with the Comission's regulations; The issuance of this amendment will not be inimical to the D.

comon defense and security or to the health and saf2ty of the public; and The issuance of this amendment is in accordance with 10 CFR Part E.

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

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

ifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.19, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

7902260182-

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION T omas Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 9,1979

A ATTACHMENT TO LICENSE AMENDMENT NO. 19 FACILITY OPERATING LICENSE NO. OPR-71 DOCKET NO. 50-325 Replace the following page.s 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.

Remove Insert i*

1*

11 11 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.

l M ELECTRIC PLANT, UNITS 1 & 2 BRUN5VICK STEA t

INVIRONMENTAL TECHNICAL SPECIFICATIONS TA3LE OF CONTENTS PAGE N0_.

SECTION 1-1 to 1-3

~

1.0 Deffaitions 2.0 Environmental Protection Conditions 2-1 to 2-3 2.1 Thermal 2-4 to 2-5 2.2 Chemical 2-6 2.3 Bydraulic 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 Thermal 2-4 to 2-5 3.2 Chemical 2-6 2-7 3.3 Hydraulic 3.4 Meteorology 2-F to 2-14 3.5 Radioactive Discharges 2-15 to 2-23 Bases

.s 4.0 Environmental Surveillance 4-1 to 4-5 4.1 Biological Surveillance 4-5 to 4-10 Radiological Environmental Monitoring Program 4.2 5-1 to 5-7 5.0 Administrative Controls Special Surveillance and Study Activities 6-1 to 6-3 6.0 6.1 Marsh Productivity 6-4 6.2 Deleted 6-5 6.3 Deleted 6-6 to 6-7 6.4 Salt Deposition Monitoring Figures

{

f 3

i Amndments 7 & 29

LIST OF TABLES _

TABLE PAGE No.

)

3.5-1 Radioactive Liquid Sa=pling and Analysis 2-24 to 2-25 3.5-2 Radioactive Gaseous Waste Sampling and Analysis 2-26 to 2-27 2-28 3.5-3 Liquid wasta System:

Location of Process and Effluent Monitors and Samplers Raquired By Technical Specifications 2-29 3.5-4 Gaseous Waste Water Systcm:

location of Process and Effluent Monitors and 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

~4.2-1 Environmental Radiological Monitoring Program -

4-11.to 4-15 i

Brunswick Steam Electric Plant 4-16 to 4-19 4.2-2 Analysis of Samples 4.2-3 Environmental Radiological Monitoring Program 4-20 to 4-22 Sumary - Brunswick Stean Electric Plant 4.2-4a Typical Minimum Detectable Concentrations -

4-23 Ge-Li Ga==a Spectronetry 4.2-4b Minimum Detectable Concentrations 4-24 4.2-5 Control Stations for BSEP Environmental 4-25 l

Radiological Monitoring Program l

l Amendbent No. 19 11

BSEP - 1 & 2 f

2.0 ENVIRON'! ENTAL PROTECTION CONDITIONS 3.0 SURVElLLANCE REQUIRE:!ENTS 2.5 RADIOACTIVE DISCl!ARCES 3.5 RADIOACTIVE DISCHARCES Obj ective: 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 as low as eous effluents to the environs to ensure reasonably achievaole and within allowable that these releases are as low as reason-values.

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.

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

.a defined in Appendix I to 10 CFR Pr.rt 50, the following design objectives apply.

For liquid wastes:

a.

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

b.

The annual total quantity of radio-active caterials in liquid waste, exclading tritium and dissolved and entrained fission and activation gases discharged from the site should not exceed 5 Ci per reactor.

For gaseous wastes:

a." The annual total quantity of noble gases above background discharged from the site should result in an air dose due to gamma radiation of less than 20 mrad, and an air dose due to beta radiation of less than 40 mrad, at any location near ground level which could be occupied by individuals at or beyond the bound-ary of the site.

2-8 Amendment No.

19

P.S E1 - 1&2 2.0 "0/ Iso:?:E';!AL PROTELTICS CO::I)! 110::S 3.0 St'P.VEILLtd;CE RERIKEMEm 2.5 P.\\DIiACfl'!E DISJiARGLs (Cont'd)

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3.5 p _ :ol.cIIVE JIs c..A.~.CI3 Ncnt'df I

b.

The annual total quantity of 1-131 and radioactivematerialinparticulateforms{

with half-lives greater than 8 days above; background from all reactors at a site should not result in an annual dose to any organ of an in ividual in an unre-i stricted area f rom all pathways of expo-f sure la excess of 30 mrem.

i I

t 2.5.1 Specifications for Liquid Waste i 3.5.1 Sp_ecifications for Liliid Waste Samplir; and Monitorin; Effluents The concentration of radioactive materi-a.

Plant reterds shall be raintained of the

~

radioactive concentration and volume before a.

als released in liquid waste effluents from all reactors at the site after dilu !

dilution of liquid waste discharged, and the tion in the discharge canal shall not average dilut2>n ficw and length of time ove-exceed the values specified in 10 CFR which each di charge occurred. Sample analy Part 20, Appendix B, Table II, Column 2, ses results and other reports shall be sub-nitted in accordance with Secticn 5.4 of for unrestricted areas, b.

The curulative release of radioactive these specifications.

Estimc'a of the samp materials from the site in liquid waste ling and snalytical errer snall be included effluent, excluding tritium and dissolved as stated in NRC Rerulaterv Guide 1.?1 b.

Prior to re12ase of each batch of liquid and entrained fission and activation waste, a sample shall be taken t' rom that gases, shall not exceed 10 Ci per reac-batch and analyzed f or each significant tor in a calendar quarter.

gamma peak in accordance with Table 3.5-1 c.

The cumulative release of radioactive to demonstrate compliance with Specifica-materials from the site in liquid waste tion 2.5.1 using the flow rate of the ef fluents excluding tritium and dis-stream into which the vaste is discharged solved and entrained fission and activa-tion gases, shall not exceed 20 Ci per during the period of discharge.

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

c.

waste shall be performed in accordance

'd.

During release of radioactive wastes, the effluent control, monitor shall be with Table 3.5-1.

Prior to taking samples from a sample or drain tank, at least two set to alarm and to initiate the auto-tank volumes shall be recirculated.

matic closure of each waste discharge The radioactivity in liquid wastes shall d.

valve prior to exceeding the limits be continuously monitored and recorded specified in 2.5.1.a above.

during release. Whenever these nonitcr.

The operability of each automatic isola-e.

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 sar;1es cf charge line shall be demonstra d cach tank t o be dincharged shall be an s qonrterly.

f.

Ihn eqolpment installed in the ligold lyind and two plant p,rrannel shall indern radioactive wante system shall be main-dently check valvine, prior t o the died sigc If these nonitors are incperable for a tained and shall be o; crated to process radioactive liquid uastes prior to their period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no liquid

,is*r tank shall be released ar.d any release in dis:harg2 when the projected curolative release from the site could exceed 1.25 progress shall be terminated.

Ci per reactor in a calendar

23rter, s

excludir.; tritium and dissolved and entrained fi:sion and activation gases. 2-9 Amendment No. 19

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IN. * - 162 r

2.0 l';Vm."NTAL PROTECTION CONDITIONS 3.0 SURVE!LI.ANCE Pd E !hE% ST; 2.5.i E I~I~ h te Lttluenti (cont'u) 3.5.1 Liquid A' w t e I:f f luen a ( ant ' c J g.

Tae r.n i m n ra d ica c t i v i t :. to be con-e.

The llow r e. t e of :1 quid ic.dicactice tained in any liquid radwaste tank that

'easte shall be continuali, measured can be discharted directly to the and recorded during release.

environs shall not exceed 10 Ci, f.

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

by means of a known radioactive source h.

If the cumulative relear of radioactive which has been calibrated to a National naterials in liquid effluents excluding Bureau of Standards scurce. Each monitor tritiun and dissolved and entrained shall also have a functional test monthly fission and activation gasts, exceeds and an instrument check prior to taking 2.5 Ci per reactor in a calendar quarter,I a release.

the licensec shall make an investigation '

toidentifythecausesofsuchreleases,!

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

objective levels listed in Section 7. 5, and report these actions to the Commis-g

e. ion within 30 days f rom t he end of the I qunrter durinf, which the release occurred.

3.5.2 Specifications for Caseous Waste

_S ccifications for Gaseous Waste Sar.pling and Monitorine

2. 5. 2 2

Discharles-a.

Plant records shall be maintained ar.d a.

(1) The release rate limit of noble records of the samplin;t end analysis results shall be submitted in accordance gases f ron this site shall be:

with Section 5.4 of these Specifi-E 4.0E + 0.23E

+Q 35E + 92E

- 1 cations. Estir.ates of the saepling

/._,Qsi, yf 61 v.

Yi 61 and analytical error associated with i

i+n each reported value should be included.

where Qs = release rate from main stack b.

Gaseous releases to the environment in Ci/sec (elevated release).

from the two reactor building vents, the two turbine building vents, and the off-Q,,, = release rate from vents in C1/sec gas vent (stack), except as noted in (ground release)

Specification 3.5.2.c below, shall be continuously monitored for gross radio-1 = the ith individual nuclide.

activity and the flow neasured and recorde n " total number of nu. lides.

k'henever these monitors are inoperable.

grab samples shall be taken and analyzed

_E = the average gama energy per daily for gross gaseous radioactivity.

If Yi disintegration for nuclide 1.

these monitors Ore incperable for Scre than seven davs, these releases shall be E = the average beta energy per terminated or tre plant shall be snot down di disintegration for nuclide 1.

c.

An isotopic analysis shall be made of Refer to Table 3.5-5 for E_

and E_

a representativs sarple of c,asceus activity, exclucing tritium, at the

1. 1 i

values to be used.

discharge of the stean jet air ejectors and at a point prior to dilution and discharge.

(1) at least monthly, Amendment No.

19 2-10

ESEP - 1 & 2

-t'

2. 0 E:".'! F 0NP 'C AL P FM TIC il'"I C]:iDITIONS 3.0 r,UI.V EI LL.::E F.TT IF.lMNIS 2.5.2 G i..' e.,

t'-

u U ! ! m. r. t r. (cont'd) 3.5.2 Caacou, tra.t c f1 :n-(cent'd)

(2) The re

se rate limit of (2) within 1 conth, followin;; each l

I ref uelin;; outa;;c.

1-131 and radicactive caterials in particulate forn 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

t Ercater than eight days, released to vaste conitor; indicats. an intrease the environs as part of the r,aseous of greater than 50 ' in the steady vastes fron the site chall be:

state fission gas release after factoring out increases due to pcr.eer changes.

6

+

5.8 x 10 ' Q

_s 1 3.7 x 104-Q d.

All vaste gas effluant ronitors shall be 8

y where Q = release rate fron.the = sin calibrated at least <;uarterly by ceans I

stack in Ci/sec (as elevat-of a kncvn radioactive source which hss 8

ed release) been calibrated to a National Bureau of Standards source.

Ec.:h tenitor shall have l

. ate from the vents functional t est at le st conthly 4 = release i

in C1/sec (ground rele.ase) and a l m v'

'-t.. check at least daily,

'"5

^Y'

1. 1. ##E**

b.

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

Sarpling and analysis of radioactive consecutive months shall be:

r'.aterial in ca secus vas te, pa r t ictilat e E

f o rm, and radioicdine shall be perfomed

_ [2.8Q

+1160()<1 in accordance with Tchle 3.5-2.

i+n add t

i 90Q

+ 800Q 3 1 l

n L*n 'i' "I

release rate of radioisotope i where Q,g =in stack in Ci/sec from the ma Q

= release rate of radioisotope i from f

the vents of each reactor in Ci/sec.

(2) The average release rate from l

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 a

months shall be:

o 6

7 g

(6.56 x 10 Q ) + (7A6 x 10 Q ) 11 g

y n

z (If no teen, child or infant milk o

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 raodified by the appropriate coefficient (Dose Factors) of Regulatory Guide 1.109.

2-11

BS E? - 1 & 2 t

2.0 E: /IRC:0!CNT/d. PROTECTIO:: C0::DITICNS 3.0 StJP.'/EILL'J:CE REQUInD:C;!S 2.5.2 Casecu, 'Ja s t e Effluents (c on t 'd) s c.

Should any or the conditions of l

2.4.2.((l), or (2) listed below exist, the licensee shall cake as investigation to identify the causes of the release rates, define and in-itiate a progras of actica to reduce tne rele ne rates to design objective Icvels listed in Section 2.5 cad re-port these actions to the Co mission within 30 days from the end of the quarter during which the releases occurred.

~

(1) If the avera'>,e relcise rate of ncble gases during any calendar quarter fror. the site is:

E 1.50Q

+ 575 Q (1

g 5

y 1.. n i i

i Or E

45Q

+ 400 Q fl y

s v

i' i

i y

(2) If the average release rate of I-131 and radioactive ma terials

~

in particulate f o rm with half-lives greater than eight days during any calendar quarter froo the site is:

0 3.26x 10 Q

+

3.74 x 10 Q 11 3

y (if no teen, child or infant milk consumption)

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

If the Radiological Environmental Mani-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. 19 2-12 o

BSEP - 1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.2 Gaseous Waste Effluents (cont'd)

F.

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

d.

Whenever the augmented off gas (A0G) system is out of service, at least one of the condenser / air ejector of f 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 ejector off gas monitors are incapable of initiating 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 off 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 hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

f.

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

I

[E g 1.5 r

+ 575 Q

>1 Q,i y

1-n i,

i or E

' 45 Q

+ 400 Q

>1 Y

1*n i'

• i' 1'

Amendment No.

19 2-13

I BSEP - 1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.2 GASEOUS 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 activity 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 confermance with Specification 2.5.2.c(*) 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 the recombiners shall be operable during (A0G) oper-ation.

If the hydrogen concentration reaches set point of four percent 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 thesc three devices are inoperable during (A0G) operation, grab samples shall be taken and analyzed for hydrogen concentration each shift. Calibration cf 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 determina or estimate the total curie quantity and principal radio-nuclide composition of all radio-act ive 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.

Amendment No.

19 2-14

BSEP - 1 6 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.3 Specificationa for Solid Wasti-Handling and Disposal (cont'd) c.

Reports of the radioactive solid waste shipments, volumes, principal radionuclides, and total curie quantity, small be submitted in accordance with Section 5.4.

l Amendment No.

19 2-14a

CASEOUS WASTE EFFLUENTS - The release of radioactive materials in gaseous waste effluents to unrestricted 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 will not exceed 40 mrad from noble gases, and that the annual dose to any organ of an l

individual from I-131 and particulates with half-lives greater than 8 days will l

not exceed 30 mrem.

i The design objectives have been developed based on operating experience, taking j

into account a combination of system variables including defective fuel, primary j

system leakage, and the performance of the various waete treatment systems.

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

i The ganna dose contribution was determined using the equation 7.63 in Section 7-5.2.5 of "eteorolocy and Atomic Energ- - 1968. The releases from vents are consider _a to be ground 1cvel releases whici could result in a beta dose from ciaud submersion.

The beta dose contribution was deter-mined using Equation 7.21, as described in Section 7-9.1 of ifeteorology and Atonic Ener:y - 1968. The beta dose centribution was determined on the basis of an infinite cloud passage with semi-infinite geometry for l

a ground icvel release (subnersion dose). The beta and gamma components of the crosr radioactivit y in nascous effluenti vere corbined to deter-mine the allowabic continuous release rate.

Based on these calculations, a continuous release rate of gross radioactivity in the amount specified in 2.5.2.a(1) will not result in offsite annual doses above background in excess of the limits specified in 10 CFR Part 20.

T1 e average gamma and beta energy per disintegration used in the equa-i tion of Specification 2.5.2.a(1) will be based on the average composi-tion of gases determined fro'n the plant vent and ventilation exhausts, j

Amendment No.

19 2-19 4

The average energy per bet'a or gamma disintegration for those radio-isotopes determined to be present from the isotopic analyses are given in Table 3.5-5.

Where isotopes are identified that are not listed in Table 3.5-5, the gamma energy are determined from Table of Isolcpes, C. M. Lederer, J. M. Hollander, and I. Perlman, Sixth Edition, 1967 and the beta energy shall be as given in USNRDL-TR-802, II.

Spectra of Individual Negatron Emitters (Beta Spectra), O. Hogan, P. E. Zigr.an, and J. L. Mackin.

For Specification 2.5.2.a(2), dose calculations have been made for the critical sectors and critical pathways for I-131 and radio-active caterial in particulate form with half-lives greater than 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 Y

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 meteorolog! cal data and method-ology of Regulatory Guides 1.109 and 1.111, and methcis provided in Meteorology and Atomic Energy (1968).

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

-0 SSE sector distance of 1464 meters where X /Q is 6.5 z 10 sec/m for the dose due to inhalation. The critical location for elevated "cleases is

-8 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.

19 2-20 4

1

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 proposed program of action to reduce such release rates to the design objectives.

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

The 24-hour period will allow ao 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 dudden 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.

Specification 2.5.2.g requires that the primary containment atmosphere 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.

The sampling and menitoring requirements given under Specification 3.5.2 provide assurance that radioactive materials released in gaseous wastes cre properly controlled and monitored in conformance with the requirements of Design Criteria 60 and 64 These requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive vastes released to the environment. Reports on the quantitics of radioactive materials released in gaseous ef flueats are furnished to the Comnission en the basis of Section 5.4 of these Technical Specifications and in conformance with Regulatory Guide 1.21.

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

Amendment No.

19 2-21

The points of release to the environment to be monitored in Section 3.5.2 include all t he moni t ored re lease points as provided for In Tible 1.5-4.

S OL I D Wid T F !).' m.

A;.C D J I L N S ?.a - T'. e r e qu i cca.::.t s f er solid radic a

.c wasr handling ud disocsal given under Specification 2.5.3 provide assurance that solid radioactive materi.ils shipped offsite are properly contrellu,

monitorcd, and packaged in confermance with 10 CFR Far: 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 o1 the quantities aad amounts of the radio'nuclides, and volumes of the shirnents, shall be furnished to the Cornission according to Section 5.4 of.these Technical Specifications. On the basis of such reports aad any additicnal information the Conmissica may obtain from the licensee or others, the Co.rnission may from time to time requ2.re the licensee to take such action as the Cornission deems appropriate.

Amendment No.

19 2-22

INTE?TTIONALLY LEFT BLANK 2-23 Ainendnient. No. 19

TABLE 3.5-6 Assumptions for Limiting Equation for Iodine and Radioactive Particles (with Ralf Lives Greater than Eight Days)

Cow's Consumption Rate 50 Kg/ day 2

Agricultural Productivity (feed grass)

.7 kg/m 2

Agricultural Productivity (stored feed)

.'.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

.7 Fraction of the Year Cow is on Pasture Uptake Rate:

310 1/yr.

Adult Thyroid Ingestion Dose Factor (I-131):

~3 1.95 x 10 mrem /gCi Adult Meteorlogy Data (Steven's cow):

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

-9

-2 2.16 x 10 m

(D/Q elevated)

Annual Average Relative Deposition

_g 2.4 x 10 m'

(D/Q ground) 2-31 Amendment No.

19

4.2.6 Soil canoline Soil samples ar< collected from eleven locations every thrr.e yearc and beach sand is collected from three locations sentannually. Analysir of soil samples includes Sr and gamma spectrometry.

4.2.7 Milk Sampling Milk samples will be collected from either two or three locations on a weekly frequency. One sampling station is a fam!1y cow that does not produce suf ficient milk for a sanple every werk.

Within seven days of saepling, I analysis will be conpleted using an analytical an procedure similar in sensitivity to the procedure out-lined in Regulatory Guide 4.3.

Samples of individual locations will be composited monthly and analyzed for 89 40 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 Vecetation 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 ganna spectrometry.

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

Samples will be ancl'yzed by gamma spectrometry.

Amendment No. 19 4-9

4.2.10 Fodder and Feed Crops nree lccations on.i l'e eti crops will be collected at mon tli t y Irequency (luring the growing seas..a.

Samples will be.inalyzed by gamma spectrometry.

Amendment No.

19 4-9a