ML20216B024

Proposed Tech Specs,Revising Section 3.11.2.3 to Allow Incineration of Radwaste Oil & Table 4.11-2-1 to Require Grab Sample Analysis of Each Batch Prior to Incineration Per 10CFR50,App I

ML20216B024
Person / Time
Site:	Brunswick
Issue date:	06/23/1987
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20216A997	List: L-87-033, Application for Amends to Licenses DPR-71 & DPR-62,revising Tech Spec Section 3.11.2.3 to Allow Incineration of Radwaste Oil & Table 4.11.2-1 to Require Grab Sample Analysis of Each Batch Per 10CFR50,App I.Fee Paid ML20216B024
References
85TSB19, NUDOCS 8706290032
Download: ML20216B024 (16)

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e ENCLOSURE 1 TO NLS-87-033

. PROPOSED TECHNICAL SPECIFICATION PAGES BRUNSWICK Radioactive Waste' Oil Incineration '

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SUMMARY

1 IST OF REVISIONS-i

. PAGE NO.

DESCRIPTION OF CHANGE l

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'3/4'11-12

' Included Gaseous Release Type C, " Incinerated 011" '

D

- 3/4 Il-14a --

New Page. Included Notes (i) and (j).~

3/4 11-15 Included LCO 3.ll.2.3.c, which limits ' amount of radioactivity' i

allowed to be released by burning of contaminated oil,

. B 3/411-3 '

Included a reference to incineration of waste oil.

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B3/4'11-5 Included a reference to incineration of waste oil.

6-24 Included reporting requirements 6.9.1.9.e, associated with incineration of waste oil.

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' TABLE ~4.ll.2-1-(Continued)

RADI0 ACTIVE GASEOUS WASTE-SAMPLING AND ANALYSIS PROGRAM-TABLE NOTATION

'(i) Incinerated oil may be' discharged'via points other than the. main

' vent l(e.g.,yincinerator).. Release.shall be a'ecounted for based on pre-releaseigrab; sample' data.

'(j). Samples'for. incinerated oil releases.shall be collected'from and

representative ofl oil in liquid form.

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l SBRUNSWICK.- UNIT-1 3/4 11-14a Amendment No.

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RADIOACTIVE EFFLUENTS k

i DOSE'- 10 DINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM LIMITINC CONDITION FOR OPERATION I

'3.11.2.3 The dose to a HEMBER OF THE PUBLIC from iodine-131, iodine-133, 1

tritium,'and~all radionuclides in. particulate form with half-lives. greater-than 8 days:in gaseous effluents released'from the site to areas at and beyond

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the SITE BOUNDARY (see' Figure.5.1.3-1) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 15 mrems to any organ; and-j b.

During any calendar years Less than or equal to 30 mrems to any i

organ.

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Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result of f

burning contaminated oil, a

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APPLICABILITY: At all times.

ACTION:

a.

With the calculated' dose from the release of iodine-131,. iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8' days, in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the i

Commission within~30 days, pursuant to Specification 6.9.2, a Special l

Report that identifies the cause(s) for exceeding the limit and defines the corrective actions-that have.been taken to reduce the releases and the proposed corrective actions to be taken to assure.

that subsequent releases will be in compliance with the above limits.

i b.

The provisions of Specifications 3.0.3 and'3.0.4'are not applicable.

A i

SURVEILLANCE REQUIREMENTS

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4.11.2.3 Dose Calculations - Cumulative dose contributions for the current

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calendar quarter and current cclendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than

.8 days shall be determined in accordance with the 0DCM at least once per 31 days.

I NOTES. See Bases 3/4.11.2.3 BRUNSWICK - UNIT 1 3/4 11-16 Amendment No.

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-RADIOACTIVE EFFLUENTS-IBASES

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3/4.11.1.40 LIQUID HOLDUP TANKS 4The tank's listed in this specification include all those outdoor. tanks that.

are'notlsurroundedLby' liners,l dikes, or' walls. capable of holding"the tank' contents and do"not have tank overflows and. surrounding area drains connected.

,, (to the liquid radwaste treatment system with the exception of the auxiliary surge tank.i The auxiliary surge tank is excluded:from this specification q

_. 'becau'se the tank.and.its. associated piping are all' Seismic Class-I.

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a since theLeondensate storage tanks have continuous influent and effluent, j

' stratification should~not' occur. Samples taken from the operating condensate

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, transfer pump (s); vent or drain shall be deemed representative of'this system.

s "Without' delay"' implies thatlthe' operator, upon determining the limiting 1

condition for operation is'being exceeded, takes the next appropriate action-Lto. comply with the specification.-

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-3/4.11.2 CASE 00S. EFFLUENTS

'3 /4.11'. 2.1 DOSE RATE I

This1 specification is provided to ensure that the' dose rate at and,beyond'the:

SITE BOUNDARY.from gaseous effluents from all. units on the site will be'within the annual dose' rate limits of 10 CFR Part 20 for UNRESTRICTED AREAS. 'The

.' annual dose limits are the.. doses associated with the concentration of 10 CFR-i '

Part 20,' Appendix'B, Table'II, Column'1. These limits provide reasonable' assurance:thatiradioactive material discharged in gaseous effluents will not result in the. exposure.of a.HEMBER OF THE PUBLIC in an UNRESTRICTED AREA, x

either within or=outside the SITE BOUNDARY,'toLannual average concentrations

exceeding the limits specified in Appendix-B,' Table.II, of 10 CFR Part 20t

'(10 CFR Part 20.106'(b)].For MEMBERS 0F THE PUBLIC who may at times be a

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within the. SITE

BOUNDARYfthe occupancy of.that MEMBER OF THE'PUBLIC will be sufficiently 1owlco' compensate forLany increase in the atmospheric diffusion

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factor'above that'for the~ SITE BOUNDARY. The specified release rate limits.

restrict,1st all times, the corresponding" gamma and beta dose rates'above.

. background to a HEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or: equal to'500 mrems/ year to the total' body or to less than or equal.to 3000 mrems/ year to:the skin. These release rate limits also restrict, at all-e times,'the corresponding thyroid dose rate above background to a child via the

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inhalation' pathway to less than or equal to:1500 meems/ year.

This. specification applies to the release of gaseous effluents from all 1

reactors lst the' site-and'from the incineration of waste oil.

7 With regard to footnotes (c) ard (g) of Table 4.11.2-1, (1) to determine whether the' DOSE EQUIVALENT I-131 concentration in the' primary coolant has increased by more than a factor of 3, the iodine-131 analysis performed after

-the' transient willlbe compared to the most recent routine analysis for DOSE

EQUIVALENT.I-131 concentration performed before the transient; and (2) to

~ determine whether'the main condenser air ejector noble gas monitor has increased by'more than a factor of 3, the activity indicated on the monitors' l BRUNSWICK'- UNIT 1 B 3/4 11-3 Amendment No.

L 9

l (BSEP-1-102) i RADIOACTIVE EFFLUENTS BASES 1

3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM i

i This specification is provided to implement the requirements of Section II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

The ACTION i

statements provide the required operating flexibility and, at the same time, implements the guides set forth in Section IV.A of Appendix I to assure that l

the releases of radioactive materials in gaseous effluents'to UNRESTRICTED j

AREAS will be kept "as low as is reasonably achievable." The ODCM j

calculational methods specified in the surveillance requirements implement the l

requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data

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such that the actual exposure of a MEMBER'0F THE PUBLIC through appropriate i

pathways is unlikely to be substantially underestimated. The ODCH f

calculational methods for calculating the doses due to the actual release j

rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, "Cciculating of Annual Doses 1

}

to Man from Routine Releases of Reactor Effluents for the Purpose of Evalu-1 l

ating Compliance'with 10 CFR Part 50, Appendix I," Revision 1, October 1977

(

and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and j

Dispersion of Gaseous Effluents in Routine Releases from Light-Water-cooled Reactors," Revision 1, July 1977. These equations also provide for deter-mining the actual doses based upon the historical average atmospheric condi-l tions. The release rate specification for iodine-131, iodine-133, tritium, l

and radioactive material in particulate form with half-lives gerater than 4

8 days are dependent on the existing radionuclide pathways to man in the areas I

at and beyond the SITE BOUNDARY. The pathways which are examined in the l

development of these calculations aret (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where l

milk animals and meat producing animals graze, with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man. The limits of this specification are twice the 10 CFR 50 Appendix I per reactor guidelines because they are written for a two unit site.

Doses due to the incineration of waste oil will be determined in accordance l

with the ODCH.

l l

l 3/4.11.2.4 CASEOUS RADWASTE TREATMENT SYSTEM l

l This requirement provides reasonable assurance that the releases of o

' radioactive materiale in gaseous effluents will be kept "as low as reasonably I

l achievable." This specification implements the requirements of 10 CFR l

Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.

The CASEOUS RADWASTE TREATMENT SYSTEM refers to the 30-minute offgas holdup line, stack filter house filtration, and the Augmented Off-Cas-Treatment System.

I BRUNSWICK - UNIT 1 B 3/4 11-5 Amendment No.

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iSEMIANNUAC RADI0 ACTIVE-EFFLUENT RELEASE REPORT 1.(Continued)'

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. ;6i Solidificationagentorab' sorbent-(e.g.,feement,. urea j

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c.c LA list'of descriptio'n;of unplanned releases from the ' site to; d

j l UNRESTRICTED AREAS'of radioactive materials'in gaseous and liquid t

a effluents.made duringlthe reporting. period.

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d.'. LAny. changes madeLduring the reporting period.to-the PROCESS CONTROL-a sa

PROGRAM' (PCP); or. the 0FFSITE DOSE CALCULATION MANUAL (ODCM), ' as well; j

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b' as a: Listing:of?new locations for. dose calculations and/or environmental monitoring.' identified by the land use census pursuant-J

,w to' Specification3.12.2.:

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Alsucanary of radioactivity released from the site by'incinaration of y

radioactive waste oil.

6.9.1.10 The portion of the Semiannual Radioactive' Effluent Release Report'to..

'be' submitted within 90 days after January 1-of each year.shall include'the F

1 followingiL a.:

An' annual summary of hourly metorological: data collected.over the previous calendariyear. This annual: sunsnary;may be either'.in the H

form of.an. hour-by-hour listing.on magnetic tape (ofLwind speed, wind

. direction,Latmospheric stability, and precipitation.(if measured),.or 7

.intheformof?jointfrequencydistriguti'ons'_of. wind'apeed, wind

. direction, andfatmospheric stability. /.-

q b.

An: assessment'.of'the. radiation dos'es.due-to'the. radioactive liquid

.and, gaseous.. effluents released from the' station during the previous

.calendarLyear..

MONTHLY OPERATINC REPORTS.

a 6 9.1.11 Routine reports of operating -statistics -and ' shutdown-expertence,.

including documentation'of'all challenges to main steam'sys' tem safety / relief l

valves,'sha11Ebe submitted'on a monthly basis to the Director, Office of i

Resource Management, U. S. Nuclear Regulatory Commission, Washington, D.C.

l 20555,.with a copy to the Regional Administrator of the Regional Office-no later than the 15th of each month following the calendar, month covered by the

. report; I

l 6/: In lieu of submission with the Semiannual Radioactive Effluent Release Report, the. licensee has the' option of retaining this summary of required meteorological data.in a file that shall be provided to the NRC upon.

l request.-

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' BRUNSWICK - UNIT l' 6-24 Amendment No.

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ENCLOSURE 2 TO NLS-87-033 l

PROPOSED TECHNICAL SPECIFICATION PAGES BRUNSWICK-2'

- i Radioactive Waste Oil Incineration (85TSB19)-

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SUMMARY

LIST OF REVISIONS r.

PAGE NO.

DESCRIPTION OF CHANGE

'3/4 11-121 included Gaseous Release Type C, " Incinerated Oil"'

3/411-14a'-

New Page. Included Notes (i)'and (j).

3/411-16' Included LCO 3.11.2.3.c, which limits amount of radioactivity allowed to be released by burning of contaminated oil.

j

. B 3/411-3

~ Included a reference to incineration of waste oil..

l

B 3/411-5 Included a reference to incineration of waste oil.

i 6-24 Included reporting requirements _6.9.1.9.e, associated with

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incineration of waste oil.-

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[ TABLE.4.11.2-1 (Continued)

' RADIOACTIVE CASEOUS WASTE SAMPLING AND' ANALYSIS PROGRAM

'I

TABLE NOTATION.

'\\

-(i) Incinerated oil may;be discharged via points other,than theLmain vent'

(e.g.,iincinerator).,-Release shall be accounted for' based on pre-release grab. sample data.

i'

'(j) Simples.for incinerated oil. releases shall be collected'from and

' representative of oil in liquid form.

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'(BSEP-2-103) 9 RADIOACTIV'E EFFLUENTS

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DOSE IODINE-131, IODINE-133, TRITIUM',- AND RADIONUCLIDES IN PARTICULATE FORM l

l-1 LIMITINC CONDITION FOR OPERATION

~

3.11.2.3

)

b

. The dose to a HEMBER OF THE PUBLIC from iodine-131, iodine-133,.

tritium,?and all radionuclides in. particulate form with half-lives greater

-f than 8 days in-gaseous effluents released from the site to areas at and_beyond

~

the SITE BOUNDARY:(see Figure 5.1.3-1) shall be limited'to the following:

.a.:

During.any calendar quarter:

Less than or equal to 15 meems to any organ; and

~

b.

-During any calendar year: -Less than or equal to 30.mrems to any.

organ.

c.

Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result of burning contaminated oil.

APPLICABILITY: At all times.

l ACTION:

j L.

a.

With.the calculated dose from the release ofLiodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding anyLof the above.

]

' limits, in lieu of a Licensee Event Report, prepare and submit to the

~

Commission within.30 days, pursuant to Specification 6.9.2, a special Report that' identifies the cause(s) for. exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

i SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose calculations - Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater.than 8 days shall be determined in accordance'with the ODCM at least once per 31 days.

NOTE: See Bases 3/4.11.2.3 BRUNSWICK - UNIT 2 3/4 11-16 Amendment No.

m

.4

r-

.~

t (BSEP-2-103)

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system with the exception of the auxiliary surge tank.

The audiliary surge tank is excluded.from this specification because the tank and its associated piping are all Seismic Clans I.

Since the condensate storage tanks have continuous influent and effluent, stratification should not occur.

Samples taken from the operat.ing co"densate transfer pump (s) vent or drain shall be deemed representative of this system.

"Without delay" implies that the operator, upon determining the limiting condition.for operation is being exceeded, takes the next appropriate action to comply with the specification.

3/4.11.2 CASEOUS EFFLUENTS 1

3/4.11.2.1 DOSE RATE 1

Th!

specification is provided to ensure that the dose rate at and beyond the SI?t,BLUNDARY from gaseous effluents from all units on the site will be within tl.e annual dose rate limits of 10 CFR Part 20 for UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF Td2 PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average cancentrations exceeding the limits specified in Appendix B, Table 22, of 10 CFR Part 20 (10 CFR Part 20.106 (b)]. For MEMBERS OF THE PUBLIC who may at nimes be within j

the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will be j

sufficiently low to compensate for any increase in the atmospheric diffusion i

factor above that for the SITE BOUNDARY. The specified release rate limits

{

restrict, at all times, the corresponding gamma sud bets dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total body or te less than or equal to 3000 mrems/ year to the skin.

These release viite limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year.

This specification applies to the release of gaseous effluents from all reactors at the site and from the incineration of uaste oil.

With regard to footnotes (c) and (g) of Table 4.11.2-1, (1) to determine whether the DOSE EQUIVALENT I-131 concentration in the primary coolant has increased by more than a factor of 3, the iodin'e-131 analysis performed after the transient will be compared to the most recent routine analysis for DOSE EQUIVALENT I-131 concentration performed before the transient; and (2) to determine whether the main condenser air ejectar nchie gas monitor has increased by more than a factor of 3, the accivity indicated on the monitor's i

)

BRUNSWICK - UNIT 2 B 3/4 11-3 Amendment No.

1 1

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t (BSEP-2-103) 4 RADICACTIVE EFFLUENTS

"^"*"

3& ll.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN Pp TICULATE FORM This specification is provided to implement the requirements of Section II.C, IILA, and IV. A of Appendix I,10 C/R Part 50.

The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix.I. The ACTION ata.tements provide ths required cperating flexibility and, at the same time,

'j implements the guides' set forth in Section IV.A of Appendix I to assure that l

che releases of radioactive matericis in gaseous effluents'to UNRESTRICTED ARfAS will be kept "aa low as'la reasont.bly Juhievable." 'The ODCM calculational methods specified.In the surveillance requirements implement the i

requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be chown by calculational procedures basad on models and data sue,h that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pat ways is unlikely to be substantially underestimated. The ODCM l

calculational methods for calculating the doses due to the actual release i

rates of the subject materials are required to be consistent with the i

j.

muchodology provided in Regulatory Guide 1.109, " Calculating of Annual Doses to Man from Routine Releases of Peactor Effluents for the Purpose of Evalu-l

[

ating Compliance with 10 CFR Part 50, Appendix I," Eevision 1, October 1977

)

and Regulatory Guido 1.111, "Mechods for Estimating Atmospheric Transport and e

l Dispersion of Gaseous Effluents in. Routine Releases from Light-Water-Cooled L

Reactors," Revision 1, July 1977 These equations also provide for deter-mining the actual doses based upon the historical average atmospheric condi-tions. The release rate specification for iodine-131, iodine-133, tritium, and radioactive material in particulate form with half-lives greater than 8 l

days are. dependent on the existirg radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. Tite pathways which are examined in the development of these calculations are:

(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) enposition onto grassy areas where j

milk animals and meat producing animals graze, with consumption of the milk i

and meat by man, and (4) deposition on the geound with subsequent exposure of man. The limits of this specification are twice the 10 CFR 50 Appendix I per reactor guidelines because they Jrc written for a two unit site.

Doses due to the incineration of vaste oil will be determined in accordance with the ODCh.

3/4.11.2.4 - CASEOUS R10 WASTE TREATMENT SYSTEM This requirement provides reasonable assurance that the releases of s

radioactive materiala in gaseous effluents will be kept "as low as reasonably i

achievable." This specification implements the requirements of 10 CFR Part l

50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the

[

design objectives given in Section II.D of Appendix I to 10 CFR Part 50.

j Until auch time as the Augmented Off-Cas Treatment System becomes operational f

at the Brunswick Steam Electric Plant, the CASEOUS RADWASTE TREATMENT SYSTEM shall refer to the 30-minute offgas holdup line and stack filter house l

i BRUNSWICK - UNIT 2 B 3/4 11-5 Amendment No.

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'(BSEP-2-103)

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n ADMINISTRATIVE CONTROLS N

' SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continue'd) r W

.6..

' Solidification agent'or absorbent-(e.g., cement,' urea.

Lformaldehyde).

i

~

c.

A list'of description lof unplanned releases'from the site to Eg* '

i

' UNRESTRICTED AREAS of radioactive: materials in' gaseous and liquid effluents'made during'the reporting period.

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d.

~Any, changes made during the reporting period:to the PROCESS CONTROL PROCRAM.(PCP) or the'OFFSITE DOSE CALCULATION MANDAL-(ODCM), as well as a listing of'new' locations for~ dose' calculations and/or environmental monitoring identified by the land use census pursuant' to Specification 3.12.2.

~

[h e n

'A summary.of' radioactivity.: released froc the site by incineration'of Y-radioactive waste oil.-

V 6.9.1210 The portion.of-the Semiannual. Radioactive Effluent Release Report to be sudmitted within'90tdays after January 1 of each ydar shall include the

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'following u

g

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a.'

.An.annualisummary of hourly metorological data collected over the previous calendar. year. This annual summary may.be.either in the.

form'of an hour-by-hour listing.on magnetic tap'e of wind speed, wind

[L_

direction, atmospheric stability,_and precipitation (if measured), or

'.l s

direction',and:atmosphericstability.gutionsofwind' speed,' wind-in'the form of joint frequency distri m

i

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l

?

b.

l q

An_ assessment of the radiation doses due to the radioactive liquid 1

and gaseous' effluents released from the station during the previous

'j

. calendar year, q

Lic

[ MONTHLY OPERATINC REPORTS' l

L6-6 9.i.~11 Routine reports of operating statistics and shutdown experience, d(s JL

.. including' documentation of all challenges to main' steam system safety / relief l

'visives, shall be submitted on a monthly basis to the Director, Office of

(

4 Resourcei Management, U. S. Nuclear Regulatory Commission, Washington, D.C.

1 4. Q '-205 %, with a copy to the Regional Administrator of the Regional Office no (later,thanthe15thof'eachmonthfollowingthecalendarmonthcoveredbythe V

y r:s port.

j t

l 4

6/ In lieu of_ submission with the Semiannual Radioactive Effluent Release

~

N

' Repo c't, the licensee has the option of retaining this summary of required h'

meteo'rological_ data in a file that shall be provided to the NRC upon s

re ques t.

.x 4

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q. W. / @RU(SWICK - UNIT 2 6-24 Amendment No.

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.