ML20033B464

Proposed Revisions to Tech Specs 2.0 & 3.0,changing Methodology Used for Monitoring Noble Gas Releases

ML20033B464
Person / Time
Site:	Brunswick
Issue date:	11/25/1981
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20033B461	List: ML20033B460 ML20033B464
References
NUDOCS 8112010434
Download: ML20033B464 (19)

Text

BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.1 Liquid Waste Effluents (cont'd) 3.3.1 Liquid Waste Effluents (cont'd) g.

The maximum radioactivity to be con-e.

The flow rate of liquid radioactive tained in any liquid radwaste tank waste shall be continually measured and that can be discharged directly to recorded during release.

the environs shall not exceed 10 C1, f.

All liquid effluent radiation monitors excluding tritium and dissolved and shall be calibrated at least quarterly entrained fission and activation by means of a known radioactive source gases.

which has been calibrated to a National h.

If the cumulative release of Bureau of Standards source.

Each radioactive materials in liquid monitor shall also have a functional effluents excluding tritium and test monthly and an instrument check dissolved and entrained fission and prior to making a release.

cetivation gases, exceeds 2.5 Ci per reactor in a calendar quarter, the licensee shall make an investigation to identify the causes of such releases, define and initiate a program of action to reduce such 3.5.2 Specifications for Gaseous Waste releases to the design objective Sampling and Monitoring levels listed in Section 2.5, and reprt these actions to the a.

Plant records shall be maintained and Commission within 30 days from the records of the sampling and analysis end of the quarter during which the results shall be submitted in accordance release occurred.

with Section 5.4 of these Specifications.

Estimates of the 2.5.2 Specifications for Gaseous Waste sampling and analytical error associated Discharges with each reported value should be included.

a.

(1) The release rate limit of noble b.

Gaseous releases to the environment from gases from this site shall be:

the two reactor building vents, the two n

3 4

turbine building vents, and the off gas

{ [DETB (8.0 x 10 )0,1+ m (1.3 x 10 )0yg)<1 vent (stack), except as noted in g

g i+1 Specification 3.5.2.c below, shall be where 0, = release rate from main stack continuously monitored for gross in Ci/sec (elevated release) radioactivity and the flow measured and recorded. Whenever these monitors are Q = release rate from vents in Ci/see inoperable, grab samples shall be taken y

(ground release) and analyzed daily for gross gaseous th radioactivity.

If these monitors are i = the i individual nuclide.

inoperable for more than seven days, n = total number of nuclides.

these releases shall be termin.ced or the plant shall be shut down.

DETB1 = Total-body elevated release dose c.

An isotopic analysis shall be made of a factor f rom Table 3.5-5a in representative sample of gaseous mrem /Ci activity, excluding tritium, at the f

Total-body dose factor from discharge of the steam jet air ejectors DTB

=

3 Table 3.5-5a in mrem-m /pci-yr and at a point prior to dilution and discharge.

(1) at least monthly.

BRUNSWICK - UNIT 1 2-10 Amendment No.

8112010434 811125 PDR ADOCK 05000324 p

PDR

BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REOUIREMENTS 2.5.2 Gaseous Was te Effluents (cont'd) 3.5.2 Gaseous Waste Effluents (cont'd)

(2) The release rate limit of I-131 and (2) within 1 month, following each radioactive materials in particulate refueling outage.

form with half-lives greater than eight (3) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, if the gaseous days, released to the environs as part of the gaseous wastes from the site waste monf torn, indicate an increase shall be:

of greater thah 50% in the steady state fission sas release af ter 4

6 factoring out increases due to power

[3.7 x 10 ]O, + [5.8 x 10 ]Qy11 changes.-

s where 0, = release rate from the main d.

All waste gas effluent monitors shall be stack in Ci/sec (as elevat-calibrated at least quarterly by means ed release) of a known radioactive source which has been calibrated to a-National Bureau of O = release rate from the vents y

Standards source.

Each monitor shall in Ci/sce (ground release) have a functional test at least monthly and an instrument check at least daily b.

Should any of the conditions of excluding days of no discharge.

Specification. 2 5.2.b(1) or 2.5.2.b(2) listed below be exceeded, the licensee e.

Sampling and analysis of 'radioacitive'

~

shall make an investigation to identify material in gaseous waste, particulate the causes of the release rates, define form, and radioiodine shall be performed cnd initiate a program of action to in accordance with Tabic 3.5-2.

reduce the release rates to design oojective levels listed in Sections 2.5.a and 2 5.b for gaseous was tes and j

report these actions to the Commission a

within 30 days from the end of the calendar year during which the releases occurred.

(1) the average release rate of noble gases from the site during any calendar year should be:

n 2

5

[ DAB [(4.0 x 10 )0si + (1.6 x 10 )0y1)i1 f

i+1 and n

5 5

[ [DETA (1.9 x 10 )0d+DAG (3.2 x 10 )0yg]Il 1

f l

1+1 l whura 0,1 = release rate of radioisotope i from the main stack in Ci/sec.

O g = release rate ~ of radioisotope i from the y

l vants of each reactor in Ci/sec.

BRUNSWICK - UNIT 1 2-11 Amendment No.

L BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REOUIREMENTS 2.5.2 Gaseous Waste Effluents (cont'd) 3.5.2 Caseous Effluents (cont'd)

DAB

= The beta air dose factgr from f

Table 3.5-Sa in mrad-m /pci-yr DETA1 = Camma air elevated release dose factor from Table 3.5-5a in mrad /Ci DAG

=Thegammaairdosefacgorfrom g

Table 3 5-Sa in mrad-m /pci-yr (2)

The average release rate from the f.

Calculations for meeting the site of I-131 and radioactive materials requirements of Specifications in particulate form with half-lives 2.5.2.b(1) and (2) shall be performed at greater than eight days during any least once every 31 days, calendar year should be:

6 Y

(6.56 x 10 0 ) + (7.46 x 10 O ) <1 3

y (If no teen, child or-infant milk consumption) 3

' The consumption of milk.must be demon-i strated by the Radiological Environ-x

's 7 ental Monitoring Prc

'.2.7.

If the Radiological Enviror Monitoring Program determines-u.,

consumption of j ~ '

nilk by teen, ichi14, or infant the above S

1' equation lshall M modified by the

. c.ppropriate' coeffic' ient (Dose Factors) cof Regulatory Cuide 1.109.

e

-1 s,

Sh' auld any> of(the conditions of s c.

(

Specifications 2.5.2.c(1) or. 2.5.2.c(2)

' ' ' listed. below be Lexceeded,i the -licensee

~

-:shall make an in'ves tigati.on' to ' identify -

[

the causes of. the release ' rates, define L,

and ini,tiate, a program of ' action to

' reduce the release rates to design -

' objective levels listed in Sections 2.5.a and "2.'i.b for gaseous was tes and report these ' actions to the Commission within 30 days from the end of the calendar quarter during which the releases occurred.

BRUNSWICK - UNIT 1 2-12 Amendment No.

L

BSEP-1 & 2

-2.0 ENVIRONMENTAL PROTECTION CONDITEONS 3.0 SURVEILLANCE REOUIREMENTS 2.5.2 Gaseous Waste Ef fluents (cont'd) 3.5.2 Gaseous Waste Effluents (cont'd)

(1) The average release rate of noble gases during any calendar quarter from the site should be:

2 DAB [(2.0x10)0si + (8.0 x 10 )gg} 11 g

i+1 5

[DETA(9.3x10)0,1+DAG(1.6x10)0yg]i1 L

g 1

i+1 (2) The average release rate of I-131 g.

Calculations for meeting the and radicactive materials in particulate requirements of Specifications form with half-lives greater than eight 2.5.2.c(1) and (2) shall be performed at days during any calendar quarter from least once every 31 days.

the site should be:

l 6

[3.26x10 0,}+[3.74x10 O}11 y

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

The consumption of milk,must be demonstrated by the Radiological Environmental Monitoring Program 4.2.7.

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

l l

l ERUNSWICK - UNIT 1 2-12a Amendment No.

i l

l l

BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REOUIREMENTS 2.5.2 Gaseous Waste Effluents (cont'd) 3.5.2 Gascous Waste Effluents (cont'd) d.

Whenever the augmented off gas ( A0G) h.

The operability of each automatic system is out of service, at least one isolation valve in the gaseous radwaste of the condenser / air ejector off gas discharge line shall be demonstrated monitors listed in Table 3 5-4 shall be quarterly.

operating and set to alarm and capable to initiate the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in 2.5.2.a 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 systet 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 is not:

2 DAB ((2.0 x 10 )0,g + (8.0 x 10')0yg]<1 g

i+1 5

DETA [(9.3 x 10 )0gg+DAG (1.6 x 10 ) 0y1]il i+1 BRUNSWICK - UNIT 1 2-13 Amendment No.

L

.... ~

j J

1 i

i

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Table 3.5-5 i

INTENTIONALLY LEFT BLANK h

h i

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1 I

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1 1

2 b

L 4

4 1,

i BRUNSWICK - UNIT I 2-30 Amendment No.

=

Tablo 3.5-Sn DOSE FACTORS ISOTOPE DETB PTB DAB DETA DAG 3

mres/Ci mrem-m mrad-m3 mrad /Ci arad-m3 pCi-yr pCi-yr pCi-yr Kr-83m 1.0 x 10-9 7.6 x 10-8 2.9 x 10-4 6.0 x 10-8 1.9 x 10-5 Kr-85 6.0 x 10-7 1.6 x 10-5 2.0 x 10-3 7.5 x 10-7 1.7 x 10-5 Kr-85m 4.5 x 10-5 1.2 x 10-3 3

5 Kr-87 2.0 x 10-4 5.9 x 10-3 2.0 x 10 2 4.5 x 10 4 1.2 x 10-3 Kr-88 6.0 x 10-4 1.5 x 10-2 1.0 x 10 3 2.0 x 10 4 6.2 x 10-3 6.0 x 10-1.5 x 10-2 2

2.9 x 10 2 2.7 x 10-4 1.7 x 10-2 Kr-89 2.7 x 10-4 1.7 x 10 2 1.1 x 10-4 2.7 x 10 5 1.6 x 10-7.8 x 10-3 2.7 x 10-4 1.6 x 10-2 Kr-90 1.1 x 10-9.1 x 10-5 1.1 x 10-3 1.2 x 10-5 1.6 x 10-4 Xe-131m Xe-133 9.0 x 10-6 2.9 x 10-4 1.0 x 10-3 1.0 x 10-5 3.5 = 10-4 Xe-133m 8.2 x 10-6 2.5 x 10-4 1.5 x 10-3 9.5 x 10-6 3.3 x 10 3 4

5 5

Xe-135 7.0 x 10 4 1.8 x 10-3 2.5 x 10-3 8.0 x 10 4 1.9 x 10-Xe-135m 1.1 x 10-3.1 x 10-3 7.4 x 10-4 1.3 x 10-3.4 x 10 3 3

5 Xe-137 3.5 x 10 4 1.4 x 10-3 1.3 x 10-2 3.5 x 10-5 1.5 x 10-Xe-138 3.0 x 10 4 8.8 x 10-3 4.8 x 10-3 3.3 x 10-4 9.2 x 10 3 3

Ar-41 3.7 x 10-8.8 x 10-3 3.3 x 10-3 4.0 x 10-4 9.3 x 10-l b

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BRUNSWICK - UNIT 1 2-30a Amendment No.

GASEOUS WASTE EFFLUENTS - Th2 relccca cf r:diecctive matsricio in gaccius wcste effluents to unrestricted areas shall not exceed the concentration limits specified 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 individual from I-131 and particulates with half-lives greater than 8 days will not exer ed 30 mrem.

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.

I BRUNSWICK - UNIT 1 2-19 Amendment No.

For Specification 2.5.2.a(2), dose calculations have been made for the critical sectors and critical pathways for I-131 and radioactive material 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 widt half lives greater than eight days, and iodine-131 at the design objecti~e annual quantity during any calendar year.

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 no't limit the instantaneous gaseous radioactive release rate, but permits the licensee the flexibility of operation to assure that the public is provided 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 methodology 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 SSE sector distance of 1464 meters where X/0 is 6.5 x 10-6 3,cf,3 for the dose due to inhalation.

The critical location for elevated releases is the SSE eector 3

at a distance of 1464 meters where the X/0 is 3.45 x 10-8 sec/m for the dose, due to inhalation.

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

The grass-cow-milk-thyroid chain is controlling.

BRUNSWICK - UNIT 1 2-20 Amendment No.

s.

r The repsrting r quirements cf 2.5.2.b and 2.5.2.c delin1 cts that th2 c ura be identified whenever the release of gaseous effluents exceeds the annual objective during any calendar year or one-half the annual objective quantity during any calendar quarter, and describe the proposed program of action to reduce such release rates to the design objectives.

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 jof 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.

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 monitoring requirements given under Specification 3.5.2 provide assurance that radioactive materials released in gaseous wastes are 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 wastes released to the environment.

Reports on the quantities of radioactive materials released in gaseous effluents are furnished to the Commission on 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 from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.

BRUNSWICK - UNIT 1 2-21 Amendment No.

u

BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.1 Liquid Waste Effluents (cont'd) 3.5.1 Liquid Waste Effluents (cont'd) g.

The maximum radioactivity to be con-The flow rate of liquid radioactive e.

tained in any liquid.radwaste tank waste shall be continually measured and l

that can be discharged directly to recorded during release.

the environs shall not exceed 10 C1, f.

All liquid effluent radiation monitors excluding tritium and dissolved and entrained fission and activation shall be calibrated at least quarterly i

by means of a known radioactive source gases.

which has been calibrated to c National h.

If the cumulative release of Bureau of Standards source. Each radioactive materials in liquid monitor shall also have a functional effluents excluding tritium and test monthly and an instrument check i

dissolved and entrained fission and prior to making a release.

activation gases, exceeds 2.5 Ci per reactor in a calendar quarter, the licensee shall make an investigation

. bo identify the causes of such i

releases, define and initiate a I

program of action to reduce such 3.5.2 Specifications for Gaseous Waste releases b3 the design objective Sampling and Monitoring levels listed in Section 2.5, and report these actions to the a.

Plant records shall be maintained and Commission within 30 days from the records of the sampling and analysis and of the quarter during which the results shall be submitted in accordance release occurred.

with Section 5.4 of these Specifica tions.

Estimates of the 2.5.2 Specifications for Gaseous Waste sampling and analytical error associated Discharges with each reported value should be included.

c.

(1) The release rate limit of noble b.

Gaseous releases to the environment from gases-from this site shall be:

the two reactor building vents, the two n

3 4

turbine building vents, and the off gas

[ [DETB (8.0 x 10 )Q,g+ DTB (1.3 x 10 )0' g]Il vent (stack), except as noted in g

g y

i+1 Specification 3.5.2.c below, shall be where 0, = release rate from main stack continuously monitored for gross in Ci/sec (elevated r21 ease) radioactivity and the flow measured and recorded.

Whenever these monitors are Q, = release rate from vents in Ci/sec inoperable, grab samples shall be taken (ground release) and analyzed daily for gross gaseous th radioactivity.

If these monitors are i = the i individual nuclide.

inoperable for more than seven days, n = total number of nuclides.

these releases -shall be terminated or the plant shall be shut down.

DETBg = Total-body elevated release dose c.

An isotopic analysis shall be made of a factor from Table 3.5-Sa in representative sample of gaseous area /Ci' activity, excluding tritium, at the DTB

= Total-body dose factor from f

discharge of the steam jet air ejectors 3

Table 3.5-Sa in mrem-m /pci-yr and at a point prior to dilution and discharge.

(1) at least monthly.

BRUNSWICK - UNIT 2 2-10 Amendment No.

r

BSEP-1 & 2

^

2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.2 Gaseous.aste Effluents (cont'd) 3.S.2 Gaseous Waste Effluents (cont'd)

(2% The release rate limit of I-131 and radioactive materials in particulate (2) within 1 month, following each

[

form with half-lives greater. than eight refueling outage.

days, released to the environs as part (3) within 72. hours, if the gaseous j

of the gaseous wastes from the site waste monitors indicate an increase shall be:

of greater than 50% in the steady state fission gas release af ter 4

6 factoring out increases due to power

[3.7 x 10 ]Q, + [5.8 x 10 )0y f, I changes.

where Q, = release rate from the main d.

All waste gas effluent monitors shall be stack in C1/sec (as elevat-ed release) calibrated at least quarterly by means of a known radioactive source which has -

been calibrated to a National Bureau of Q, = release rate from the vents Standards source.

Each monitor shall in C1/sec (ground release) have a functional test' at least monthly b.

Should any of the conditions of and an instrument check at least daily Specifications 2.5.2.b(1) or 2.5.2.b(2) excluding days of no discharge.

listed below be exceeded, the licensee i

e.

Sampling and analysis of radioactive l

shall make an investigation to identify the causes of the release - rates, define material in gaseous waste, particulate and initiate a program of action to form, and radioiodine shall - be. performed in accordance with Table 3 5-2.

reduce the release rates to design objective levels listed in Sections 2.5.a and-2.5.b for gaseous wastes and report these actions to the Commission within 30 days from the end of the calendar year during which the releases occurred.

(1) the average release rate - of noble gases from the site during any calendar year rhould be:

n 2

5

[ DAB [(4.0 x 10 )0,1 + (1.6 x 10 )0yg]f,1 y

i+1 and n

5 5

{[DETA(1.9x10)Q g+DAG (3.2 x 10 )0 g}f,1 g

y y

i+1 whara 0,1 = release rate of radioisotope i from the main stack in Ci/sec.

O g = release rate of radioisotope i from the y

vants 'of each reactor in Ci/sec.

i 1

i

' BRUNSWICK - UNIT 2 2-11 Amendment No.

l

BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.2 Gaseous Waste Effluents (cont'd) 3.5.2 Gaseous Effluents (cont'd)

DAB

= The beta air dose factgr from f

Table 3.5-Sa in mrad-m /pci-yr DETAg = Gamma air elevated release dose factor from Table 3.5-Sa in mrad /Ci DAG

= The gamma air dose facgor from g

Table 3.5-Sa in mrad-m /pci-yr (2) The average release rate from the f.

Calculations for meeting the site of I-131 and radioactive materials requirements of Specifications in particulate form with half-lives 2.5.2.b(1) and (2) shall be performed at greater than eight days during any least once every 31 days.

calendar year should be:

6 7

(6.56 x 10 0s) + (7.46 x 10 0 ) f_1 y

(If no teen, child or infant milk consumption)

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

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

c.

Should any of the conditions of Specifications 2.5.2.c(1) or 2.5.2.c(2) listed below be exceeded, the licensee chall make an investigation to identify the causes of the release rates, define end initiate a program of action to reduce the release rates to design objective levels listed in Sections 2.5.a and 2.5.b for gaseous wastes and report these actions to the Commission within 30 days from the end of the calendar quarter during which the releases occurred.

BRUNSWICK - UNIT 2 2-12 Amendment No.

BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REQUIREMENTS 2.5.2

. Gaseous W ste Effluents (cont'd) 3.5.2 Gaseous Waste Effluents (cont'd) a (1) The average release rate of noble gases during any calendar quarter from the site should be:

2 DAB ((2.0 x 10 )0,1 + (8.0 x 10')0,1)

_<,1 g

i+1 n

[ [DETA (9.3x10 )Q,t+DAG (1.6x10 )0yg)11 g

i+1 (2) The average release rate of I-131 g.

Calculations for meeting the and radioactive materials in particulate requirements of Specifications form with half-lives greater than eight 2.5.2.c(1) and (2) shall be performed at days during any calendar quarter from least once every 31 days.

the site should be:

6 7

[3.26x10 0,')+(3.74x10 0,,) 11 (if no teen, child or infant milk consumption)

The consumption of milk must be demonstrated by the Radiological Environmental Monitoring Program 4.2.7.

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

l l

BRUNSWICK - UNIT 2 2-12a Amendment No.

BSEP-1 & 2 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 3.0 SURVEILLANCE REOUIREMENTS 2.5.2 Gaseous Waste Effluents (cont'd) 3.5.2 Gaseous Waste Effluents (cont'd) d.

Whenever the augmented off gas ( A0G) h.

The operability of each automatic system is out of service, at least one of the condenser / air ejector off gas isolation valve in the gaseous radwaste discharge line shall be demonstrated monitors listed in Table 3.5-4 shall be quarterly, operating and set to alarm and capable to initiate the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in 2.5.2.a 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 AOG 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 le not:

2 4

DAB [(2.0 x 10 )0,1 + (8.0 x 10 )0,1] 11 g

i+1 fDETA [(9.3 x 10 )0,1+DAG (1.6 x 10 )0y1]i1 1

i+1 BRUNSWICK - UNIT 2 2-13 Amendment No.

<m..

t.

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l BRUNSWICK - UNIT 2 2-30 Amendment No.

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1.,--.-v.,*-,..,.4_

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. me---

Tcblo 3.5-5:

DOSE FACTOPS ISOTOPE DETB DTB DAB DETA DAG 3

mrem /Ci mrem-m mrad-m3 mrad /Ci arcd-m3 pCi-yr pCi-yr pCi-yr Kr-83m 1.0 x 10-9 7.6 x 10-8 2.9 x 10-4 6.0 x 10-8 1.9 x 10-5 Kr-85 6.0 x 10-7 1.6 x 10-5 2.0 x 10-3 7 5 x 10-7 1.7 x 10-5 5

4.5 x 10 4 1.2 x 10-3 2.0 x 10-3 4.5 x 10-5 1.2 x 10-3 Kr-85m 2.0 x 10 0 5 9 x 10-3 1.0 x 10-2 2.0 x 10-4 6.2 x 10-3 Kr-87 6.0 x 10-1.5 x 10-2 2.9 x 10-3 6.0 x 10-4 1.5 x 10-2 Kr-88 Kr-89 2.7 x 10-4 1.7 x 10-2 1.1 x 10-2 2.7 x 10-4 1.7 x 10-2 Kr-90 2.7 x 10-4 1.6 x 10-2 7.8 x 10-3 2.7 x 10-4 1.6 x 10-2 Xe-131m 1.1 x 10-5 9.1 x 10-5 1.1 x 10-3 1.2 x 10-5 1.6 x 10-4 Xe-133 9.0 x 10-6 2.9 x 10-4 1.0 x 10-3 1.0 x 10-5 3.5 x 10-4 Xe-133m 8.2 x 10-6 2.5 x 10-0 1.5 x 10-3 9.5 x 10-6 3.3 x 10-4 5

5 Xe-135 7.0 x 10 4 1.8 x 10-3 2.5 x 10-3 Xe-135m 1.1 x 10-3.1 x 10-3 7.4 x 10-4 8.0 x 10 4 1,9 x 19-3 1.3 x 10 5 3.4 x 10-3 Xe-137 3.5 x 10-5 1.4 x 10-3 1.3 x 10-2 3.5 x 10 4 1.5 x 10-3 Xe-138 3.0 x 10-4 8.8 x 10-3 4.8 x 10-3 3.3 x 10 4 9.2 x 10-3 Ar-41 3.7 x 10-4 8.8 x 10-3 3.3 x 10-3 4.0 x 10-9.3 x 10-3 BRUNSWICK - UNIT 2 2-30a Amendment No.

GASEOUS WASTE EFFLUENTS - Th2 ralscsa cf radiocctiva mattrials in groscus wzste sfflu2nts to unr:stricted erzas shall not cxcred the cancsntratica limits specified 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 individual from I-131 and particulates with half-lives greater than 8 days will not exceed 30 mrem.

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.

BRUNSWICK - UNIT 2 2-19 Amendment No.

For Specification 2.5.2.a(2), dose calculations have been made for the critical sectors and critical pathways for I-131 and radioactive material 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 calendar year.

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 provided 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 methodology of Regulatory Guides 1.109 and 1.111, and methods provided fn 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 SSE sector distance of 1464 meters where X/O is 6.5 x 10-6 geef,3 for tha dose due to inhalation.

The critical location for elevated releases is -

sector at a distance of 1464 meters where the X/0 is 3.45 x 10-8 sec/m i dose, due to inhalation.

The assumptions for the grass-cow-milk-thyro.

.n are lis ted in Table 3.5-6.

The grass-cow-milk-thyroid chain is controlling.

BRUNSWICK - UNIT 2 2-20 Amendment No.

The reparting r;quircments cf 2.5.2.b and 2.5.2.c dalin 2sta that th2 causa be identified whenever the release of gaseous effluents exceeds the annual objective during any calendar year or one-half the annual objective quantity during any calendar quarter, and describe the proposed program of action to reduce such release rates to the design objectives.

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.

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 monitoring requirements given under Specification 3.5.2 provide assurance that radioactive materials released in gaseous wastes are 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 wastes released to the environment.

Reports on the quantities of radf-6~mive materials released in gaseous effluents are furnished to the Cc amissic a on the basis of Section 5.4 of these Technical Specifications and in conf 3cmance with Regulatory Guide 1.21.

On the basis of such reports and any additional information the Commission may obtain from the licensee or I

others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.

BRUNSWICK - UNIT 2 2-21 Amendment No.

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