Text

Application for Amend to License NPF-63,consisting of line-item Improvement to TS Per Guidance Contained in Generic Ltr 89-01 Re Radiological Effluent TS & Incoporating Programmatic Controls for Solid Radwastes
	ML18010A699
Person / Time
Site:	Harris
Issue date:	07/21/1992
From:	Starkey R; CAROLINA POWER & LIGHT CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18010A700	List: ML18010A699; ML18022A897;
References
	GL-89-01, GL-89-1, NLS-92-132, NUDOCS 9207290101
	Download: ML18010A699 (115)
	v • d • e

OS2 I

9207290101 I

SHEARON HARRIS NUCLEAR POWER PLANT OPP-SITE DOSE CALCULATION MANUAL (ODCM)

Revision 3

Advance Change 3/5 Docket No. STN-50-400 CAROLINA POWER Ec LIGHT COMPAHY PNSC Chairman's Approval Effective Date

OS2 TABLE OF CONTENTS Section Tit1e Pacae TABLE OF CONTENTS LZST OF TABLES LIST OF FIGURES

1.0 INTRODUCTION

2.0 LIQUID EFFLUENTS 2.1 Monitor Alarm Set Point Determinations 2.2 Compliance with 10CFR50 2-1 2-2 2-15 3.0 GASEOUS EFFLUENTS e

3.1 Monitor Alarm Set Point Determination 3.2 Postrelease Compliance with 10CFR20-Based ODCM Specification 3.11.2 3.3 Compliance with 10CFR50 e '3-1 3-1 3-13 3-21

( Ac. i/5 4.0 RADZOLOGZCAL ENVIRONMENTAL MONZTORZNG PROGRAM 4-1 5.0 ZNTERLABORATORY COMPARISON STUDIES 5.1 Objective 5.2 Program 5-1 5-1 5-1 6.0 TOTAL DOSE (COMPLIANCE WITH 40CFR190) 6-1 6.1 Dose to the Likely Most Exposed Member of the Public 6-1 6.2 Dose to a Member of the Public due to Activities Within the Site Boundary 6-2 DCM/ODC-TOC Rev. 3.0

OS2 TABLE OF CONTENTS (continued)

Section Title Pacae 7.0 LICENSEE. INITIATED CHANGES TO THE ODCM

~

APPENDIX A - Meteorological Dispersion'actor Computations

~

7 '1 APPENDIX B - Dose Parameters for Radioiodines, Particulates, and Tritium B.l Calculation of P,

B.2 Calculation of g B-1 B-1 B-3 APPENDIX C - Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Numbers C-1 APPENDIX D - Programmatic Controls D-1 D.1 Instrumentation DT2 D.2 Radioactive Effluents

. D-16 D.3 Radiological Environmental Monitoring..

. D-30 APPENDIX E - Programmatic Control Bases

~

E-1 E.l Instrumentation Bases E.2 Radioactive Effluents Bases E-2 E-3 E.3 Radiological Environmental Monitoring Bases E-10 APPENDIX F

- Administrative Controls F.1 Reporting Requirements F-1 F-2 DCM/ODC-TOC Rev. 3.0

OS2

'IST OF TABLES No.

Title Pacae 2.1-1 Liquid Effluent Release Tanks and Pumps 2-23 2.1-2 Set Points for Cooling Tower Blowdown Dilution Flow Rate (B) 2-24

2. 1-3 Signal Processor Time Constants (Y) for GA-Technologies Effluent Monitors 2-24 2.1-4 Liquid Effluent Monitor Gamma Sensitivities (Sens g) 2-25 2.2-1 g, values for the Adult for the Shearon Harris Nuclear Power Plant 2-26 2.2-2 Decay Factors 2-28 3.1-1 Gaseous Source Terms 3-11 3.1-2 Dose Factors and Constants 3-12 3.2-1 Releases from Shearon Harris Nuclear Power Plant Normal Operation 3-17 3.2-2 Distance to the Nearest Special Locations for Shearon Harris Nuclear Power Plant (Miles) 3-18 3.2-3 Dose Factors for Noble Gases 3-19 3.2-4 PValues (Inhalation) for a Child for the Shearon Harris Nuclear Power Plant 3-20 DCM/ODC-TOC Rev.'.0

OS2 LIST OP TABLES (continued)

No Title Pacae 3.3-1 thru R Values for the Shearon Harris Nuclear Power Plant

. 3-32 3.3-19 4.1 Radiological Environmental Monitoring Program 4-2 A-1 thru X/Q and D/Q values for long-term ground-level releases at special locations A-4 A-5 thru A-12 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground-level releases for standard and segmented distance locations for long-term releases A-5 A-13 Shearon Harris Nuclear Power Plant on-site joint wind frequency distributions for 1976-1987 A-13 A-14 Shearon Harris Nuclear Power Plant site information used for ground-level calculations with NRC "XOQDOQ" Program A-16 B-1 Parameters for Cow and Goat Milk Pathways

. B-15 B-2 Parameters for the Meat Pathway B-16 B-3 Parameters for the Vegetable Pathway B-17 3.3-12 A

Radioactive Liquid Effluent Monitoring Instrumentation D-3 A

. 'sly DCM/ODC-TOC iv Rev. 3.0

OS2 LIST OP TABLES (continued)

No.

Title Pacae 4.3-8 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements D-6 3.3-13 Radioactive Gaseous Effluent Monitoring H

Instrumentation D-10 4.3-9 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements D-13 4.11-1 Radioactive Liquid Waste Sampling and Analysis Program

.D-17 4.11-2 Radioactive Gaseous Waste Sampling and Analysis h

Program

~

D-23

3. 12-1 Radiological Environmental Monitoring Program.....

D-32

3. 12-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples

~

D 38

4. 12-1 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection D-39 DCM/ODC-TOC Rev. 3. 0

OS2 LIST OF FIGURES No.

Title Pacae 2.1-1 Liquid Waste Process Flow Diagram 2-29 2.1-2 Liquid Effluent Flow Stream Diagram 2-30 2.1-3 Normal Service Water Flow Diagram 2-31 2.1-4 Other Liquid Effluent Pathways 2-32 3.1 Shearon Harris Nuclear Power Plant Gaseous Waste Streams.. 3-51 3.2 Schematic of Plant Airborne Effluent Release Points

~

. 3-52 3.3 Shearon Harris Nuclear Power Plant Condenser Off-Gas System 3-53 4.1-1 Shearon Harris Nuclear Power Plant Exclusion Boundary Plan........................

4-16 4.1-2 thru Shearon Harris Nuclear Power Plant Environmental

4. 1-5 Radiological Sampling Points 4-17 DCH/ODC-TOC Vl b'av. s.o

~ hC 3/5

OS2

1.0 INTRODUCTION

The Off-Site Dose Calculation Manual (ODCM) provides the information and methodologies to be used by Shearon Harris Nuclear Power Plant (SHNPP) to ensure compliance with Technical Specifications 6.8.4.h and 6.9.1 of the SHNPP operating License, and ODCM Specifications 3.3.3.10, 3.3.3.11, 3/4.11.1, 3/4.11.2, 3/4.11.4, 4.12.1, 4.12.2, and 4.12.3.

These specifications are those related to normal liquid and gaseous radiological effluents, environmental monitoring, and reporting.

They are intended to show compliance with 10CFR20-based requirements and 10CFR50.36a, Appendix I of 10CFR50, and 40CFR190 in terms of appropriate monitoring instrumentation and set points, dose rate, and cumulative dose limitations.

Off-site dose estimates from nonroutine releases will.

also be included in the cumulative dose estimates for the plant to comply with Appendix I of 10CFR50.

The ODCM is based on "Westinghouse Standard Technical Specifications" (NUREG 0452),

"Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG 0133),

and guidance from the United States Nuclear Regulatory Commission (NRC).

Specific plant procedures for implementation of this manual are presented in the SHNPP Plant Operating Manual.

These procedures are utilized by the operating staff of SHNPP to ensure compliance with technical specifications.

The ODCM has been prepared as generically as possible in order to minimize the need for future revisions.

However, some changes to the ODCM are expected in the future.

Any such changes will be properly reviewed and approved as indicated in the Administration Control Section I qc,3/~

Specification 6.14 of the SHNPP Technical Specifications.

DCM/ODC-I Rev.

3

~ 0

OS2

1.0 INTRODUCTION

(continued)

The assessment of annual radiation doses to members of the public from radioactive liquid and gaseous effluents from the plant is estimated using the NRC codes LADTAP II and GASPAR using concurrent meteorology for the report period.

These off-site dose estimates for each calendar year are reported in the Semiannual Radioactive Effluent Release Report submitted to the NRC by March 1 of the following year as required by Technical Specification 6.9.1.4.

NRC Generic Letter 89-01, "Guidance for implementation of Programmatic controls for RETS in the Administrative Controls Section of Technical Specifications and the Relocation of the Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program",

relocated the Radiological Effluent Technical Specifications (RETS) from the SHNPP Technical Specifications to the SHNPP ODCM.

The relocated specifications retain the same

number, but will be referred to as ODCM Specifications.

DCM/ODC-I 1-2 Rev. 3.0

OS2 2.0 LI UID EFFL NTS h

Radioactive materials released in liquid effluents from SHNPP to unrestricted areas are required to implement 10CFR50 Appendix I (ODCM Specification 3.11.1.2) and be limited to the concentrations specified in 10CFR Part 20, Appendix B, Table II, Column 2

(ODCM Specification 3.11.1.1)

For 'dissolved or entrained noble gases the concentration shall be limited to 2E-4 pCi/ml total activity.

The liquid effluent release point is at the point of discharge from the Cooling Tower Blowdown Line into Harris Lake (see Figure 2.1-3 and T/S Figure 5.1-3)

Radioactive liquids are routinely released as batches from the Waste Monitor Tank (WMT), Waste Evaporator Condensate Tank (WECT), and Treated Laundry and Hot Shower Tank (TL&HST).

Batch releases may also originate from the Secondary Waste Sample Tank (SWST).

These tanks are shown in Figures 2.1-1 and 2.1-2.

Effluent monitor identification numbers are provided in Appendix C.

Liquid effluent dilution prior to release to Harris Lake is provided by the Cooling Tower Blowdown Line.

Concurrent batch releases should not normally occur at SHNPP.

Continuous releases are routinely permitted from the SWST and the Normal Service Water (NSW) system because a low potential for radioactive contamination exists.

These releases are checked by effluent monitors on the SWST (Figure 2.1-2) and the NSW lines (Figure 2.1-3).

The turbine building floor drains and the outside tank area drains (Figure 2.1-4) are monitored effluent lines with low probability of

) <<(

/-

radioactive contamination.

The radioactive liquid waste sampling and analysis required for batch and continuous releases are found in Table 4.11-1 of the ODCM Specifica-

~

I tions.

DCM/ODC-2 2-1 Rev.

3. 0

OS2 2.1 Monitor Alarm Set Point Determination ODCM S ecification 3.3.3.10 2.1.1 Batch Releases Liquid effluent monitor set points have two set points, the high alarm and the alert alarm.

The high alarm set point (HSP) provides alarm and isolation if the tank radionuclide concentrations, when diluted, would approach the ODCM Specification limits for concentrations in unrestricted areas.

Alert alarm set points (ASP) are set at a fraction of the HSP to provide an early warning of the approach to ODCM Specification limits.

Based on analysis of the tank contents, the tank release rate is adjusted, based on the Cooling Tower Blowdown Line flow

rate, to dilute the tank activities to'0 percent of the allowable concentrations at the release point to Harris Lake.

/ <c,3IS 1.

Minimum Tank Mixing. Time pootnote 2 to ODCH Specification Table 4.11-1 reooizes that hQ, 5f the method used to mix an isolated effluent tank prior to sampling and analysis be described.

Equation 2.1-0 below provides an acceptable method for ensuring a well mixed tank so that a representative sample can be taken for radioactivity or other appropriate analyses.

R (v)

(E)

(n)

(P)

(60)

(2. 1-0) where:

Minimum allowable mixing time, hr DCM/ODC-2 2-2 Rev.

3. 0

OS2 2.1.1 Batch Releases (continued)

V

=

Actual tank liquid volume, gal E

=

Eductor factor P

=

Pump design recirculation flow rate, gpm Number of tank volumes for turnover; this will be typically two or more.

60

~

60 min/hr Table 2.1-1 lists the tank capacities, eductor factors, and pump design recirculation flow rates for individual liquid effluent release tanks.

2.

Minimum Acceptable Dilution Factor Determine D the minimum acceptable dilution factor required to meet the limits of ODCM Specification 3.11.1.1, based on prerelease and composite sample analyses.

Do

[D+D+D]

og ocomp 0't (2. 1-1)

Where Dog the mi.nimum acceptable dilution factor apportioned to the gamma emitting isotopes.

q gt 3/p 2 (pg

~)

MPH (2. 1-2)

DCM/ODC-2 2-3 Rev.

3. 0

OS2 2. 1. 1 Batch Releases (continued)

Fraction of the available dilution volume which may be assigned to a particular release to ensure discharge point limits are not exceeded by simultaneous radioactive liquid releases.

The value of T is based on assumed operational considerations for simultaneous releases but normally will be 0.8 for a batch release and 0.2 for a continuous release.

4.

Available Dilution Factor The Available Dilution Factor, D

, represents the cooling avl'ower blowdown flow rate available during the time of a batch release to dilute the tank activities to or below the ODCH Specification limits.

.-5 B + RR RR (2.1-6) where:

Davl Available dilution factor Tank release

rate, gpm The lower value between the calculated MRR and the pump discharge capacity in Table 2.1-1.

5.

Prerelease Criteria For Permitting Batch Releases Compliance with 10CFR20

- Based ODCH Specifications cncH specification 3.11.1.1 requires that the Mpc values of

~ PC ~l~

10CFR20 are not exceeded at the point of discharge for any radionuclide in a release.

Therefore, DCM/ODC-2 2-6 Rev. 3. 0

OS2 2.1.1 Batch Releases (continued) where:

~sg MDC =

Em Time constant of the signal processor, minutes.

Table 2.1-3.

Zf not, postpone the release and decontaminate or replace the sample chamber to reduce the background, then recalculate HSP and ASP using the new, lower background.

7.

Effluent Monitor Set Point Based on Z-131 (Set Point Calculation Method

Z-131)

Zf analysis of the batch sample indicates all gamma-emitting h l~

nnclides are r LLD, (as defined in ~on specification Table

~ hjp 4.11-1),

the tank gamma activity, Cg, may be assumed to consist only of Z-131.

This nuclide has the lowest MPC of any to be found in liquid effluents and provides a

conservative basis for a monitor set point.

a

~

Liquid Channel Set Point based on Z-131 MPC and the available dilution flow.

(1)

Monitor High Alarm Set Point.

HSP Z

131'pCi/ml)

DCM/ODC-2 2-10 Rev. 3.0

OS2 2.1. 1 Bat h Releases (continued)

[p C (Bene g) ]

+ Bkg

~ Davt. c Dc c m-1-131 Em where:

C 3E-07 )Ci/ml in the calculation of D, (MPC for I-131).

Sens g

1. 55E+08 cpm/pCi/ml, the monitor sensitivity for I-131 gamma energy, Table 2.1-4.

(2)

Monitor,Alert Alarm Set Point, ASP (pCi/ml).

ASP

=

((HSP

- Bkg )

Fx]

+ Bkg (2.1.11)

(3)

Check for Excessive Monitor Background Verify that:

Bkg 0.2 ((HSP i ln-.Bkgm)

F) )

2 (2. 1-12)

Postrelease Compliance With 10CFR20--Based ODCM Specification a.

Postrelease Compliance Check To show final compliance with ODCM Specification

3. 11. 1.1 the following relationship must hold:

DCM/ODC-2 2-11 Rev.

3. 0

OS2 2.1.2 Continuous Releases The continuous releases from the SWST and the NSW return lines are monitored as shown in Figures 2.1-2 and 2.1-3.

The function of these monitors, in contrast to the isolation function of batch release tank monitors, is to provide an indication of low levels of radioactivity in the effluent.

1.

Effluent Monitor Set Point based on an assumed FSAR nuclide mix for the SWST (Set Point Calculation Method CRP)

Liquid channel set point (1)

Monitor high alarm set point, HSP (pCi/ml) i HSP 0.1 MPCGgg (Sens,ff)

+ Bk9 Bl E

, pCi/mZ (2.1-15) m where:

MPC Weighted MPC for the SWST outlet nuclides listed in Table 11.2.1-14 of the FSAR.

Sens eff E,

(Sens g x 4 abundance) for the SWST nuclide mix, cpm/pCi/ml.

(2)

Monitor Alert Alarm Set Point, ASP (pCi/ml)

ASPm

[(HSP

- Bkg )

F,]

+ Bkg (2. 1-16)

When the monitor is operable and not in alarm, analysis of weekly composite samples is not required by

~OD Specification Table 4.11-1.

DCM/ODC-2 2-13 Rev.'.0

OS2 2.1.2 Continuous Releases (continued)

If the monitor is in alarm or the presence of non-naturally occurring radioactivity )LLD is confirmed, the releases may continue provided the sampling and analysis required by ODCM I ~.i/5 Specification Table 4.11-1 are performed.

The results of the sample analysis will be evaluated for compliance with ODCM Specification 3.11.1.1.

The monitor alarm set points may be recalculated using Equations 2.1-7 and 2.1-8 with the results of the gamma analysis and analyses of the composite sample.

(3)

Check for Excessive Monitor Background Monitor background is considered excessive when the minimum detectable concentration (MDC) for the monitor., is )0.01 MPC Therefore, eff background is acceptable if:

~sg

0. 01 MPC,rr (Sens rr) 2T Em Em (2. 1-17) 2.1.3 N nroutin Li lease Outdoor Tank Area Drain Effluent Line The outdoor tank area drain effluent line routes rain water collected in the outdoor tank area to the storm drain system and from there directly to the lake.

The line is monitored for radioactivity and is capable of automatic termination of effluent release.

Because no radioactivity is normally expected in this line, the monitor high alarm and. alert alarm set points are DCM/ODC-2 2-14 Rev. 3.0

OS2 2.2.1 Cumulation of Doses (continued)

BF)

Bioaccumulation factor for radionuclide "i" in fish (from Table A-1 of Regulatory Guide 1. 109, Rev. 1), pCi/kg per pCi/l DF;,

=

Dose conversion factor for radionuclide

~'i" for adults for a particular organ t (from Table E-11 of Regulatory Guide 1.109, Rev. 1), mrem/pCi Table 2.2-1 presents the A.

values for an adult receptor.

Values of lT exp

(-1, t,) are presented in Table 2.2-2 for each radionuclide "i.>>

The sum of the cumulative dose from all batch and any continuous

'releases for a quarter is compared to one-half the design objectives for total body and any organ.

The sum of the cumulative doses from all relea'ses for a calendar year is compared to the design objective doses.

The following relationships should hold for the SHNPP to show compliance with ODCH Specification 3.11.1.2.

For the calendar quarter:

D s

1.5 mrem total body 7

(2.2-4)

D c

5 mrem any organ T

(2.2-5)

DCM/ODC-2 2-19 Rev. 3.0

OS2 2.2.1 Cumulation of Doses (continued)

For the calendar year:

D T

3 mrem total body (2. 2-6)

D7 10 mrem any organ (2. 2-7) where:

Cumulative.total dose to any. organ t or the total body from all releases, mrem:

The quarterly limits given above represent one-half the annual design objective of 10CFR50, Appendix Z, Section ZZ.A.

1f any of the limits in Expressions 2.2-4 through 2.2-7 are exceeded, a special report pursuant to SHNPP Technical Specification 6.9.2 must be filed with the'RC.

This report complies with Section ZV.A of Appendix Z, 10CFRSO.

2 2

2 Pro'e i n f Do s

Dose projections for this section are required at least once per 31 days A

(monthly) in ODCM Specification 4.11.1.3.1 whenever the liquid radwaste A

r

>IS treatment systems are not being fully utilized.

DCH/ODC-2 2-20 Rev. 3.0

OS2 2.2.2 Pro'ection of Doses (continued)

The doses will be projected using Equation 2.2-1.

When the operational conditions for the projected month are to be the same as for the current

month, the source-term inputs into the equation for the projection can be taken directly from the current month's data.

Where possible, expected operational evolutions (i.e., outages, increased power levels, major planned liquid releases, etc.)

should be accounted for in the dose projections.

This may be accomplished by using the source-term data from similar historical operating experiences where practical.

This may also be accomplished by using the projected Percent Power-Reactor Days

'or the unit as in the following expression:

D~

D2, D)P~

i.e.,

D~ =

Pi Pa Pi (2.2-8) where:

D,

=

Past month's dose to total body or any organ, mrem Dg Projected month's dose to total body or any organ, mrem P)

For past month:

(Average

% power) x (Reactor days of operation)

Pg For projected month:

(Estimated average 0 power) x (Estimated reactor days of operation)

To show compliance with ODCH Specification 3.11. 1.3, the projected month's dose should be compared as in the following:

DCM/ODC-2 2-21 Rev. 3.0

OS2 3.0 GASEOUS EFFLUENTS At SHNPP there are four gaseous effluent release points:

Plant Vent Stack 1, Turbine Building Vent Stack 3A, and the Waste Processing Building Vent Stacks 5 and 5A.

These are shown in Figures 3.1, 3.2, and 3.3 along with their tributaries.

All gaseous effluent releases at the plant are considered ground releases.

3.1 Monitor Alarm Set Point Determination (ODCH Specification 3.3.3. 11)

This section provides the methodology for stack effluent monitor set points to ensure that the dose rates from noble gases at the site boundary do not exceed the limits of 500 mrem/year to the whole body or 3000 mrems/year to the skin as specified in ODCH Specification 3.11.2.1

~ AC r'nd 10CFR20.105.

Thus, the stack monitor set points effectively provide pre rele-ase compliance with 10CSR20-hased ODCH specifications for noble

~,5C gases.

The radioactivity effluent monitors for each stack and for specific effluent streams are shown in Figures 3.1 and 3.3 and are listed in Appendix C.

ln Stacks 1 and 5, the potential exists for batch releases concurrent with the normal continuous ventilation flow of effluents.

The sources of batch releases for the Plant Vent Stack 1 include containment normal and preentry purge and pressure relief.

Batch release sources for Vent Stack 5 include releases from the waste gas decay tanks (WGDT).

Zn these

cases, the monitor set point must reflect the contribution of both the continuous and batch sources.

DCM/ODC-3 3;,1 Rev. 3.0

OS2 3.1.1 Effluent Monit r Set Point Based On Known Or Assumed Stack Effluent Co osition (Set Point Calculation Method GALE)

The following set point calculation is applicable to the 4 vent stack monitors for all conditions, e.g.

~

Continuous release via Plant Vent Stack 1.

~

Batch mode release of containment normal purge, preentry

purge, or pressure relief via Plant Vent Stack 1 concurrent with the continuous release.

~

Continuous release through Vent Stack 3A.

~

Continuous release via Vent Stack 5.

~

Batch release of a waste gas decay tank via Stack 5

concurrent with the continuous release.

Continuous release via Vent Stack 5A.

The general approach to gas monitor set point determination begins with the ODChl Specification limits on noble gas dose rates (mrem/year) to the ~l'~

whole body and skin at the site boundary.

These site limits are apportionated to each of the four stacks on the basis of respective design flow rate.

Individual stack release rates (pCi/sec) are calculated which are functions of the known or assumed (GALE code) noble gas composition of the effluent.

Based on stack flow rate (acfm) the release rate can be converted to an allowable noble gas concentration (pCi/cc).

The monitor high alarm set point is then established to provide alarm when the concentration reaches 50 percent of the allowable level.

DCM/ODC-3 3-2 Rev. 3. 0

OS2 3.2 Postrelease Com liance with 10CFR20-Based ODCM S ecification 3.11.2

)

grail~

3.2.1 Noble Gases The gaseous effluent monitors set points are utilized to show prerelease

,(.~l>

compliance with ODCH Specification 3..11.2.1.

However, because they may be based upon a conservative (GALE code) mix of radionuclides, when using Table 3.1-1, the possibility exists that the set points could be exceeded and yet 10CFR20-based limits may actually be met.

Therefore, the following methodology has been provided in the event that if the high alarm set points are exceeded, a determination may be made as to whether the actual releases have exceeded the dose rate limits of ODCH Specification 3.11.2.1.

~ pe~i>

The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem/year to the total body and 3000 mrem/year to the skin.

Based upon NUREG-0133, the following equations are used to show compliance:

K (~XQ)

Q 3.

V s 500 mrem/yr (3.2-1)

(L

+ 1. 1 M )(F75)

Q c 3000 mzem/yz 1

(3.2-2) where:

(XTQ) v

~

The highest calculated annual average relative concentration for long-term vent stack releases for areas at or beyond the

'xclusion boundary sec/m'.

6.1E-06 sec/m'rom Table A-1, Appendix A, for ground-level releases in the S sector at the exclusion boundary.

DCM/ODC-3 3-13 Rev. 3.0

OS2 3.2.1 Noble Gases (continued)

The X/Q value utilized in the equations is the highest long-term annual average relative concentration

(~X Q) V in the unrestricted area for the period 1976

- 1987.

Long-term annual average

(~XQ) V values at other locations shown in Table 3.2-2 are presented in Appendix A.

A description of their derivation is also provided in this'ppendix.

To select the limiting location for ground-level releases, long-term annual average

(~XQ)v values were calculated assuming no decay, undepleted transport to the exclusion boundary.

These values are given in Table A-l, Appendix A The maximum exclusion boundary

(~XQ) V for ground-level releases occurs in the S sector.

Therefore, the limiting location for implementation of the dose rate limits for noble'ases is considered to be the exclusion boundary (1.36 miles) in the S sector.

Values for Q, L;, and g which 'are to be used by SHNPP in Equations 3.2-1

)I>

and 3.2-2 to show compliance with ODCH Specification 3.11.2 are presented in Table 3.2-3.

These values were taken from Table B-1 of NRC Regulatory Guide 1.109, Revision 1.

The values have been multiplied by 1 AL OE+06 to convert mrad/pCi to mrad/pCi for use in Equations 3.2-1 and 3.2-2.

3.2.2 Rad 'nes and Parti lates

, qj9 The bases for ODCH Specification 3/4.11.2.1 states that the dose rate to the thyroid of a child in an unrestricted area resulting from the inhalation of radioiodines, tritium, and particulates with half-lives i 8 days is limited to 1500 mrem/yr to any organ.

Based upon NUREG-0133, the following is. used to show compliance:

DCM/ODC-3 3-15 Rev. 3.0

OS2 3.2.2 Radioiodines and Particulates (continued)

P p,

[ (~xg), g,

]

e 1500 mzemiyz (3. 2-3) where:

Pi The dose parameter for radionuclides other than noble gases for the inhalation pathway, mrem/yr per pCi/m'.

Zn the calculation to show compliance with ODCH Specification 3.11.2.1.b, only the inhalation pathway is considered.

The radionuclide mix is again based upon the normal operational source terms calculated using the GALE Code and presented in Table 3.2-1 as a

function of release point.

The determination of the controlling exclusion boundary location was based upon the highest exclusion boundary

(~XQ) > value.

Values for Pi in Eq. 3.2-3 were calculated for. a child for various radionuclides for the inhalation pathway using the methodology of NUREG-0133.

The Pi values are presented in Table 3.2-4.

A description of the Xy methodology used in calculating the P< values is presented in Appendix B.

The values of P~ reflect, for each radionuclide, the maximum P< value f'r any organ.

The

(~X Q) > value utilized in Equation 3.2-3 is obtained from the tables presented in Appendix A.

A description of the derivation of the X/Q values, is provided in Appendix A.

"DCM/ODC-3 3-16 Rev. 3.0

052 3.3.1 Noble Gases (continued)

Values for M, and N which are utilized in the calculation of the gamma air and beta air doses in Equation 3.3-1 to show compliance with 10CFR50, are presented in Table 3.2-3.

These values originate from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1.

The values have been multiplied by 1.0E+06 to convert from mrad/pCi to mrad/pCi.

The following relationships should hold for SHNPP to show compliance with ODCH Specification 3.11.2.2.

For the calendar quarter:

Dy s 5 mrad (3.3-3)

Dp i 10 mrad (3.3-4)

For the calendar year:

Dy s 10 mrad (3.3-5)

DP i 20 mrad (3.3-6)

The quarterly limits given above represent one-half of the annual design objectives of Section II.B.1 of Appendix I of 10CFRSO.

If any of the limits of Equations 3.3-3 through 3.3-6 are exceeded, a

Special Report pursuant to Technical Specification 6.9.2 must be filed with the NRC.

This report complies with Section IV.A of Appendix I of 10CFR50.

DCM/ODC-3 3-23 Rev. 3.0

OS2 3.3.1 Noble Gases (continued)

Projection of Doses Doses resulting from the release'f gaseous effluents will be projected once every 31 days (monthly).

The doses will be projected utilizing Equations 3.3-1 and 3.3-2.

When the operational conditions are expected to be the same as for the current month, the source-tean inputs into the equation for the projection can be taken directly from the current month's data.

Where possible, credit for expected operational evolutions (i.e.,

outages, increased power levels, major planned batch gas releases, etc.)

should be integrated into the dose projections by using source-term data from historical operating experiences.

This may also be accomplished by using the projected Percent Power-Reactor Days for the unit as in the following expression:

Dq D2, D~ P2 i,e.,

D, =

P1 P2 P~

(3.3-7)

To show compliance with ODCH Specification 3.11.2.4, the projected

>'>li C,

month's dose should be compared as in the following:

Dy i 0.2 mrad to air for gamma radiation, (3.3-8)

DP s 0.4 mrad to air for beta radiation (3. 3-9)

Zf the projections exceed either Expressions 3.3-8 or 3.3-9, then the appropriate portions of the gaseous radwaste treatment system shall be used to reduce releases of radioactivity.

DCM/ODC-3 3-24 Rev.

S. 0

OS2 3.3.2 Radioiodine and Particulates (continued)

Zn the determination of the limiting sector, all age groups and all of the exposure pathways are initially evaluated using the GASPAR code.

These include cow milk, beef and vegetable ingestion, inhalation, and ground.plane exposure.

Goat milk is not currently an exposure pathway at SHNPP.

A 1 SHNPP ODCM Specification 3.12.2 requires that a land-use census Is> r h

)

survey be conducted on an annual basis.

The age groupings at the various receptor locations are also determined during this survey.

Thus, depending on the results of the survey, a new limiting location and receptor age group could result.

To avoid possible annual revisions to the ODCM software which'valuates effluent releases for compliance with 10CFR50, the limiting sector location has been fixed at the exclusion boundary in the S sector where the highest historical annual average

(~X Q) and

(~D Q) values occur (Appendix A).

With all of the exposure pathways identified in the land use census (Table 3 '-2) available to a hypothetical receptor, the critical organ is a child's bone.

This approach avoids a substantial underestimate of the dose to a real member of the public.

Long-term

(~X Q) >

and (DjQ) >

values for ground-level releases are provided in tables in Appendix A.

They may be utilized if an additional special location arises different from those presented in the special locations of Table 3.2-2.

A description of the derivation of the various X/Q and D/Q values is presented in Appendix A.

DCM/ODC-3 3-29 Rev. 3.0

OS2 3.3.2 Radioiodine and Particulates (continued)

Tables 3.3-1 through 3.3-19 pre'sent R; values for the total body, GI-tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow,milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways.

These values were calculated using the methodology described in NUREG-0133 assuming a grazing period of eight months.

A description of the methodology is presented in Appendix B.

The following relationship should hold for SHNPP to show compliance with SHNPP ODCH Specification 3.11.2.3.

i"e For the calendar quarter:

Dv s 7.5 mrem For the calendar year:

Dr s 15 mrem (3.3-12)

The quarterly limits given above represent one-half the annual design objectives of Section II.C of Appendix I of 10CFR50.

If any of the limits of Equations 3.3-11 or 3.3-12 are exceeded, a

Special Report pursuant to Technical Specification 6.9.2 must be filed with the NRC.

,This report complies with Section IV.A of Appendix I of 10CFR50.

DCM/ODC-3 3-30 Rev,. 3. 0

OS2 3.3.2 Radioiodine and Particulates (continued) 2.

Projection of Doses Doses resulting from release of radioiodines and particulates will be projected once every 31 days (monthly) utilizing Equation 3.3-10.

When the operational conditions for the projected month are expected to be the same as for the current

month, the source-term inputs into the equation for the projection can be taken directly from the current month's data.

Where

possible, credit for expected operational evolutions (i.e.,

outages, increased power levels, major batch gas releases, etc.)

should be integrated into the dose projections by using source term data from historical operating experiences.

This may also be accomplished by the using projected Percent Power-Reactor Days for the unit as in the following expression:

D1 D2, D1 P2

= i.e.,

D2 =

P1 P2 1 (3. 3-13)

A To show compliance with ODCH Specification 3.11.2.4, the projected

!5(-

month's dose should be compared as in the following:

D s 0.3 mrem to any organ (3. 3-14)

Zf the projections exceed Expression 3.3-14, then the appropriate portions of the gaseous radwaste treatment system shall be used to reduce releases of radioactivity.

DCM/ODC-3 3-31 Rev. 3.0

OS2 5. 0 INTERLABORATORY COMPARISON STUDIES 5.1 O~b'ectiv The objective of this program is to evaluate the total laboratory analysis process by comparing results for an equivalent sample with those obtained by an independent laboratory or laboratories.

5.2

~erc rem 5.2.1 Environment l S le Anal ses Com arison Pro ram Environmental samples from the SHNPP environs are to be analyzed by the 4

Harris Energy

& Environmental Center (HE&EC) or by a qualified contracting laboratory.

These laboratories will participate at least annually in a nationally recognized interlaboratory comparison study.

The results of the laboratories.'erformances in the study will be provided to SHNPP Environmental

& Radiation Control (E&RC).

The results will be included in the Annual Radiological Environmental Operating C

Report (see SHNPP QDCH Specification 4.12.3) 5.2.2 Effluen Rel a e Anal ses Pr ram SHNPP E&RC will perform sample analyses for gamma-emitting radionuclides in effluent releases.

The E&RC radiochemistry laboratory will participate annually in a corporate interlaboratory comparison study or an equivalent study.

Radiochemical analyses of composite samples required by ODCM Specifications Tables 4.11-1 and 4.11-2 will be performed by the HE&EC.

DCM/ODC-5 5-1 Rev.

3. 0

OS2 6.0 TOTAL DOSE COMPLIANCE WITH 40 CFR 1

0 ODCM Specification 3.11.4 requires that the. annual dose or dos'e commitment to a member of the public from uranium fuel cycle sources be limited to 25 mrem for the whole body and any organ except the thyroid which is limited. to 75 mrem.

In addition, assessment of radiation doses to the likely most exposed member of the public from primary effluent pathways, direct radiation, and any other nearby uranium fuel cycle sources are required by Technical Specifications 6.9.1 to show conformance with 40 CFR 190 limits.

The results of the dose assessments are to be submitted with the Semiannual Radioactive Effluent Release Report after January 1 of each year.

6.1 Dose to the Likel Most E

osed Member of the Public 6.1.1 Effluent Pathwa s

The ODCM dose equations for noble gases, iodines, particulates, and tritium provide conservative estimates because the X/Q and D/Q are historical values for the exclusion boundary distances.

Because these distances are fixed and represents the closest points in the unrestricted areas to the plant, it assures that 10 CFR 50 Appendix I doses to a member of the public are unlikely to be substantially underestimated.

More realistic qstimates of the actual doses from the gas and liquid effluent pathways to the likely most exposed member of the public can be obtained by. using the Regulatory Guide 1.109-and WASH 1258-based NRC codes LADTAP II and GASPAR.

These permit use of current annual average meteorology X/Q and D/Q values derived from the NRC XOQDOQ (NUREG/CR-2919)

Code appropriate for the specific location of the receptor and the applicable exposure pathways.

DCM/ODC-6 6-1 Rev. 3.0

OS2 7.0 LECENSEE-XNETIATED CHANGES TO THE ODCM Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Technical Specification 6.10.3.p.

This documentation shall contain:

1) 'ufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 2)

A determination that the change will maintain the level of radioactive effluent control required by.10 CFR Part 20.106, 40 CFR Part 190, 10 CFR Part 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent,

dose, or set point calculations.

b.

Shall become effective after review and acceptance by the Plant Nuclear Safety Committee (PNSC) and the approval of the Plant Manager.

35 c.

Shall be submitted to the Commission in the form of a

complete, legible copy of the entire ODCM as a part of, or concurrent with, the Semiannual Radioactive, Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating. the area of the page that was changed, and shall indicate the date (e.g.,

month/year) the change was implemented.

DCM/ODC-7 7-1 Rev. 3.0

OS2 APPENDIX A (continued)

Sheet 2

of 3

A twelve-year record of meteorological data was used from the on-site meteorological program at the Shearon Harris Plant.

These data consisted of a3:1 collected parameters from the normal 10.0 meter tower level for the years

" 1976-1987.

The description of the model used and the computations are presented in NUREG/CRC-2919.

The following tables provide the meteorological dilution factors (i.e.,

the X/Q and D/Q values) utilized to show compliance with ODCM Specifications 3/4.11.2 for noble gases and radioiodines and particulates.

l <~(g Tables A-1 through A-4 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground level releases for special locations for long-term releases.

Tables A-5 through A-12 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground level releases for standard and segmented distance locations for long-term releases.

Table A-13 SHNPP on-site joint wind frequency distributions for 1976-1987.

1 The X/Q and D/Q values which are utilized in the appendices are,all assumed to be ground level releases.

DCM/ODC-AA A-2 Rev. 3.0

OS2 Sheet 1

of APPENDIX B DOSE PARAMETERS FOR RADIOIODINES PARTICULATESf AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radioiodines, particulates, and tritium to show compliance with ODC33 Specification 3.11.2.1.h and Appendix 1 of 10CFR50 for gaseous effiuents.

~ QC r

These dose parameters, P, and Q, were calculated using the methodology outlined in NUREG 0133 along with Regulatory Guide 1.109, Revision 1.

The following sections provide the specific methodology which was utilized in calculating the P, and Q values for the various exposure pathways (Tables 3.2-4 and 3.3-1 through 3.3-19, respectively)

B.l Calculation of P<

The dose parameter, P contained in the radioiodine and particulates portion of Section 3.2 includes only the inhalation pathway transport parameter of the "i" radionuclide, the'receptor's usage of the pathway media, and the dosimetry of the exposure.

Inhalation rates and the internal dosimetry are functions of the receptor's age; however unde,r the exposure conditions for ODDLY gpecifi-

~

Ai'ation 3.11.2.1b the child is considered to receive the highest dose.

The s

values for P.

presents the highest dose to any organ including the whole body i) resulting from inhalation of radionuclide "i" by a child.

The following sec-tions provide. in detail the methodology which was used in calculating the P,

values for inclusion into this ODCM.

B.'l.l Inhal tion P

hw The evaluation of this pathway consists of estimating the maximum dose to the most critical organ received by a child through inhalation by:

P.

K'BR) DFQ-DCM/ODC-AB B-1 Rev. 3.0

OS2 Sheet 2

of 14 APPENDIX B (continued)

B.1.1 Inhalation Pathwa (continued) where:

P.

=

Dose parameter foi radionuclide "i" for the inhalation 1)

pathway, mrem/yr per pCi/m';

K' constant of unit conversion; 106 pCi/pCi; BR The breathing rate of the children's age group, m'/yr; DFg The maximum organ inhalation dose factor for the children' age group for radionuclide "i," mrem/pCi The age group 'considered is the child because the bases for the ODCH Specification 3.11.2.1.b is to restrict the dose to the child's thyroid via inhalation to c 1500 mrem/yr.

The child's breathing rate is taken as 3700 m'/yr from Table E-5 of Regulatory Guide 1.109, Revision 1.

The inhalation dose factors for the child, DFg, are presented in Table E-9 of Regulatory Guide 1.109 in units of mrem/pCi.

The total body is considered as an organ in the selection of DFQ.

The incorporation of breathing'rate of a child (3700 m'/yr) and the unit conversion factor results in the following equation:

P,

~

3.7 x 10~ DFQ 1)

(B. 1-2)

DCM/ODC-AB B-2 Rev. 3. 0

OS2 Sheet 3

of le APPENDIX B (continued)

B.2 Calculation of Q The bases for ODCH Specification 3.11.2.3 state that conformance with the guidance in Appendix I should be shown by calculational procedures based on models and data such that, the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated.

Underestimation of the dose can be avoided by assigning a theoretical

. individual to the exclusion boundary in the sector with the highest X/Q and D/Q values and employing all of the likely exposure

pathways, e.g.,

inhalation, cow milk, meat, vegetation, and ground plane.

g values have been calculated for the adult, teen, child, and infant age groups for the inhalation, ground plane, cow milk, goat milk, vegetable, and beef ingestion pathways.

The methodology which was'tilized to calculate these values is presented below.

B:2.1 Inhalation Pathwa The dose factor from the inhalation pathway is calculated by:

R.

=

K'BR),

(DFA;),

(B. 2-1) where:

R,

~

Dose factor for each identified radionuclide "i" of L) the organ of interest, mrem/yr per 5 pCi/m';

K' constant of unit conversion; 10~ pCi/pCi; (BR),

a Breathing rate of the receptor of age group "a," m/yr; DCM/ODC-AB B-3 Rev. 3.0

OS2 APPENDIX D PROGRAMMATIC CONTROLS The surveillance requirements and limiting conditions for oPerations Pertaining to instrumentation, radioactive effluents, and radiological environmental monitoring are detailed in Sections D.1, D.2, and D.3, respectively.

ODC-AD D-1

OS2 D.l INSTRUMENTATZON RADXOACTXVE LI UID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDZTZON FOR OPERATION 3.3.3.10 The radi'oactive liquid effluent monitoring instrumentation channels shown in Table 3.3-3.2 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSZTE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTXON:

With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the

'bove specification, immediately (1) suspend the release of radioactive liquid effluents monitored by the affected channel or (2) declare the channel inoperable and take ACTION as directed by

b. below.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Exert best effort to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.4 why this inoperability was not corrected in a timely manner.

C.

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

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE

CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3'-8.

ODC-AD D-2 pc Rev. 3.0

0anI TABLE 3.3-12 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE ACTION 2

~

3.

Radioactivity Monitors Providing Alarm and Automatic Termination of Release a.

Liquid Radwaste Effluent Lines 1)

Treated Laundry and Hot Shower Tanks Discharge Monitor 2)

Waste Monitor Tanks and Waste Evaporator Condensate Tanks Discharge Monitor 3)

Secondary Waste Sample Tank Discharge Monitor b.

Turbine Building Floor Drains Effluent Line c.

Outdoor Tank Area Drain Transfer Pump Monitor Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a.

Normal Service Water System Return From Waste Processing Building to the Circulating Water System b.

Normal Service Water System Return From the Reactor Auxiliary Building to the Circulating Water System Flow Rate Measurement Devices a.

Liquid Radwaste Effluent Lines 1)

Treated Laundry and Hot Shower Tanks Discharge 2)

Waste Monitor Tanks and Waste Evaporator Condensate Tanks Discharge 35 35 35, 36*

36 37 39 38 38

0an TABLE 3.3-12 Continued RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT 3.

Flow Rate Measurement Devices (Continued) 3)

Secondary Waste Sample Tank b.

Cooling Tower Blowdown MINIMUM CHANNELS OPERABLE ACTION 38 38

When the Secondary Waste System is being used in the continuous release mode, Action 36 shall be taken when the monitor is inoperable.

In the batch release mode, Action 35 is applicable.

OS2 TABLE 3 3-12 Continued ACTION STATEMENTS ACTION 35

- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36

- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at, a lower limit of detection of no more than 10~ microCurie/ml:

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microCurie/gram DOSE EQUIVALENT I-131 or, At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microCurie/gram DOSE EQUIVALENT I-131.

ACTION 37

- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for radioactivity at a lower limit of detection of no more than 10~ microCurie/ml.

ACTZON 38

- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

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

ACTZON 39

- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the weekly Cooling Tower Blowdown weir surveillance is performed as required by Specification 4.11.1.1.1.

Otherwise, follow the ACTION specified in ACTION 37 above.

ODC-AD D-5 gC R

. 30

~ g/g

TABLE 4.3-8 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 1.

Radioactivity Monitors Providing Alarm and Automatic Termination of Release a.

Liquid Radwaste Effluent Lines 1)

Treated Laundry and Hot Shower Tanks Discharge Monitor 2)

Waste Monitor Tanks and Waste Evaporator Condensate Tanks Discharge Monitor 3)

Secondary Waste Sample Tank Discharge Monitor b.'urbine Building Floor Drains Effluent Line c.

Outdoor Tank Area Drain Transfer Pump Monitor CHANNEL CHECK D

D D

SOURCE CHECK P,

M(5)

CHANNEL CALIBRATION R (3)

R(3)

R (3)

DIGITAL CHANNEL OPERATIONAL TEST Q (1)

Q (1)

Q(1)

Q(1) 2.

Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a.

Normal Service Water System Return Prom Waste Processing Building to the Circulating Water System D

R(3)

Q (2)

0Un I

TABLE 4.3-8 Continued RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT CHANNEL CHECK SOURCE CHANNEL CHECK CALIBRATION DIGITAL CHANNEL OPERATIONAL TEST 2.

3.

Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release (Continued) b.

Normal Service Water System Return From the Reactor Auxiliary Building to the Circulating Water System Flow Rate Measurement Devices a.

Liquid Radwaste Effluent Lines 1)

Treated Laundry and Hot Shower Tanks Discharge 2)

Waste Monitor Tanks and Waste Evaporator Condensate Tanks Discharge 3)

Secondary Waste Sample Tank D

D (4)

M N.A.

N.A.

R (3)

Q (2)

N.A.

b.

Cooling Tower Blowdown D (4)

N.A.

OS2 TABLE 4.3-8 Continued TABLE NOTATIONS (1)

The D1GZTAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation

'ccur if any of the following conditions exists:

Instrument indicates measured levels above the Alarm/Trip

Setpoint, or Circuit failure (monitor loss of communications (alarm only),

detector loss of counts (Alarm only) or monitor loss of power), or C.

Detector check source test failure (alarm only), or Detector channel out of service (alarm only), or

'e.

Monitor loss, of sample flow (alarm only).

(2)

The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation. occurs if any of the following conditions exists:

a.

Instrument indicates measured levels above the Alarm Setpoint, or Circuit, failure (monitor loss of communications (alarm only),

detector loss of counts, or monitor loss of power), or c.

Detector check source test failure, or d.

Detector channel out of service, or e.

Monitor loss of sample flow.

(3)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

(5)

When the Secondary Waste System is being used in the batch release

mode, the source check shall be prior to release.

When the system is being used in the continuous release

mode, the source check shall be monthly.

ODC-AD D-8

OS2 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION

'I 3.3.3.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.5 are not exceeded.

The Alarm/Trip Setpoints of these channels meeting Specification 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3-13 ACTION:

~

a With a radioactive gaseous effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than, required by the above specification, immediately (1) suspend the release of radioactive gaseous effluents monitored by the affected channel or (2) declare the channel inoperable and take ACTION as directed by

b. below.

b.

With the number of OPERABLE radioactive gaseous effluent monitoring instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13.

Exert best efforts to return the instrument to OPERABLE status within 30 days.

Zf unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.4 why this inoperability was not corrected in a timely manner.

C ~

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

h SURVEILLANCE REQUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE

CHECK, CHANNEL CALIBRATION and a DIGITAL CHANNEL OPERATIONAL TEST or an ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-9.

ODC-AD D-9

OUnI TABLE 3 3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT GASEOUS HASTE PROCESSING SYSTEM--HYDROGEN AND OXYGEN ANALYZERS a.

Recombiner Outlet Hydrogen Monitor b.

Recombiner Outlet Oxygen Monitor c.

Compressor Discharge Oxygen Monitor MINIMUMCHANNELS OPERABLE 1/recombiner 1/recombiner APPLICABILITY ACTION 50 48 48 U

ICI 2.

3.

TURBINE BUILDING VENT STACK a.

Noble Gas ActivityMonitor b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Monitor PLANT VENT STACK a.

Noble Gas ActivityMonitor b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e'.

Sampler Flow Rate Monitor 47 46 46 49 49 46 46 S

0UnI TABLE 3.3-13 Continued RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUMCHANNELS OPERABLE APPLICABILITY ACTION 4

WASTE PROCESSING BUILDING VENT STACK 5 a.l Noble 'Gas ActivityMonitor (PZG) a.2 Noble Gas ActivityMonitor (WRGM) b.,Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor MODES 1, 2, 3

45, 51 52 49 49 46 e.

Sampler Flow Rate Monitor 5.

WASTE PROCESSING BUZLDZNG STACK SA a.

Noble Gas ActivityMonitor b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Monitor 47 49 46 46

OS2 TABLE 3 3-13 Continued TABLE NOTATIONS At all times.

During GASEOUS RADWASTE TREATMENT operation.

ACTION'STATEMENTS ACTION 45

- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the waste gas decay tank(s) may be released to the environment provided that prior to initiating the release:

a At least two independent samples of the tank's contents are

analyzed, and b.

At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 46

- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 47

- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 48

- With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement, operation may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing operations and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations.

ACTION 49

- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.

ACTION 50

- With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the iecombiner.

ACTION 51

- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement for both the PZG and

WRGM, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioacta.vasty within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 52

- Take the ACTION as required by Specification 3.3.3.6 ACTION c.

ODC-AD D-12 pc Rev. 3.0

TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT GASEOUS WASTE PROCESSING SYSTEM--

HYDROGEN AND OXYGEN ANALYZERS a.

Recombiner Outlet Hydrogen Monitor b.

Recombiner Outlet Oxygen Monitor c.

Compressor Discharge Oxygen Monitor CHANNEL CHECK D

D D

SOURCE CHECK N.A.

N.A.

CHANNEL CALIBRATION Q(4)

Q (5)

DIGITAL CHANNEL OPERATIONAL TEST M.

M'ODES FOR WHICH SURVEILLANCE IS RE UIRED 2.

3.

TURBINE BUILDING VENT STACK a.

Noble Gas Activity b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Monitor PLANT VENT STACK a.

Noble Gas ActivityMonitor b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Monitor D

N.A.

D D

D N.A.

D D

N.A.

R(3)

N.A.

R(3)

N.A.

Q(2)

N.A.

Q (2)

N.A.

0UnI TABLE 4.3-Continued

'ADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT WASTE PROCESSING BUILDING VENT STACK 5 a.l Noble Gas ActivityMonitor (PIG) a.2 Noble Gas ActivityMonitor (WRGM)

CHANNEL CHECK D

D SOURCE CHANNEL CHECK CALIBRATION R (3)

R(3)

DIGITAL CHANNEL OPERATIONAL TEST Q(l)

Q(2)

MODES FOR WHICH SURVEILLANCE IS RE UIRED 5.

b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Monitor WASTE PROCESSING BUILDING VENT STACK 5A a.

Noble Gas ActivityMonitor b.

Iodine Sampler c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Monitor N.A.

N.A.

D D

N.A.

D D

N.A.

N.A.'.A.

N.A.

R(3)

N.A.

Q(2)

N.A.

Q Q

OS2 TABLE 4.3-9 Continued TABLE NOTATION At all times,.

~*

During GASEOUS RADWASTE TREATMENT SYSTEM operation.

~ANALOG CHANNEL OPERATIONAL TEST (1)

The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation occur if any of the following conditions exists:

Instrument indicates measured levels above the Alarm/Trip

Setpoint, or Circuit failure (monitor loss of communications (alarm only),

detector loss of counts (alarm only) or monitor loss of power), or c.

Detector check source test failure (alarm only), or d.

Detector channel out of service (alarm only), or e.

Monitor loss of sample flow (alarm only).

(2)

The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

a ~

Znstrument indicates measured levels above the Alarm Setpoint, or b.

Circuit failure (monitor loss of communications (alarm only),

detector loss of counts, or monitor loss of power), or c,

Detector check source test failure, or Detector channel out of service, or e.

Monitor loss of sample flow.

(3)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing hydrogen and nitrogen.

(5)

The CHANNEL CALZBRATZON shall include the use of standard gas samples containing oxygen and nitrogen.

ODC-AD D-15 Rev. s.o

~ gC s/s

OS2 D.2 3 4.11 RADIOACTIVE EFFLUENTS 3 4.11.1 LI UID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1-3) shall, be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10~ microCurie/ml total activity.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRZCTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according

~

to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.

ODC-AD D-16

OS2 TABLE 4. 11-1 RADIOACTIVE LI UZD WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE.

TYPE SAMPLING FREQUENCY MINIMUM ANALYSIS FREQUENCY TYPES OF ACTIVITY ANALYSIS LOWER LIMIT OF DETECTION (LLD)0)

(pCi/ml) 1.

Batch Waste P

P Release Tanks+

Each Batch Each Batch Principal Gamma Emitters"~

Sx10 ~

a.

Waste Monitor Tanks b.

Waste Evaporator Condensate Tank c.

Secondary Waste Sample Tank~

d.

Treated Laundry and Hot Shower Tanks P

One Batch/M P

Each Batch P

Each Batch M

Composite~+

Q Composite'+

I-131 Dissolved and Entrained Gases (Gamma Emitters)

H-3 Gross Alpha Sr-89, Sr-90 Fe-55 lxlo~

lx10~

1x10 ~

5x10~

1x10~

2.

Continuous Releases'~

Continuous'"

W Composite'~

Principal Gamma Sx10 ~

Emitters+

a.

Cooling M(7)

Tower Weir Grab Sample b.

Secondary Waste Sample Tank@

Continuous~"

Continuous'"

M(7)

M Composite<~

Q Composite'~

Dissolved and Entrained Gases (Gamma Emitters)

I-131 H-3 Gross Alpha Sr-89, Sr-90 Fe-55 1x10~

1x10~

1x10 ~

Sx10~

1xl0~

ODC-AD D-17

OS2 TABLE 4.11-1 Continued TABLE NOTATIONS (1)

The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement

system, which may include radiochemical separation:

4.66 sb E

V 2.22 x 10' exp (-A,h,t)

Where:

LLD = the "a priori" lower limit of detection (microCurie per unit mass or volume),

sb the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E

= the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 x 10' the number of disintegrations per minute per microCurie, Y = the fractional radiochemical yield, when applicable, X = the radioactive decay constant for the particular radionuclide (sec'),

and 4t

= the elapsed time between the midpoint of sample collection and the time of counting (sec)

Typical values of E, V, Y, and ht should be used in the calculation.

Zt should be recognised that the ZLD is defined as an a priori (before the fact) =limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit Sor a particular measurement.

(2)

A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

ODC-AD D-18 I uk <

Rev. 3. 0

OS2 TABLE 4. 11-1 Continued TABLE NOTATIONS Continued (3)

The principal gamma emitters for which the LLD specification applies include the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141.-

Ce-144 shall also be measured but with a LLD of 5 x 10~.

This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.4 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(4)

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

(5)

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

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

(6)

To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream.

Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release..

(7)

These points monitor potential release pathways only and not actual release pathways.

The potential contamination points are in the Normal Service Water (NSW) and Secondary Waste (SW)

Systems.

Action under this specification is as follows:

a)

If the applicable (NSW or SW) monitors in Table 3.3-12 are OPERABLE and not in alarm, then no analysis under this specification is required but weekly composites will be collected.

b)

If the applicable monitor is out of service, then the weekly analysis for principal gamma emitters will be performed.

c)

If the applicable monitor is in alarm or if the principal gamma emitter analysis indicates the presence of radioactivity as defined in the ODCM, then all other analyses of this specification shall be performed at the indicated frequency as long as the initiating conditions exist.

(8)

The Secondary Waste System releases can be either batch or continuous.

The type of sample required is determined by the mode of operation being used.

ODC-AD D-19 iA<

Rev.

3. 0

OS2 RADZOACTZVE EFFLUENTS LZMZTZNG CONDZTZON FOR OPERATZON 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLZC from radioactive materials in liquid effluents released to UNRESTRZCTED AREAS (see Figure 5.1-3) shall be limited:

a.

During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and b.

During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

APPLZCABZLZTY: At all times.

ACTZON:

a With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, 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(s) 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.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEZLLANCE REQUZREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

ODC-AD D-20 Ac Rev. 3.0 3/y

OS2 RADIOACTIVE EFFLUENTS LI UID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall be OPBRABLB and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, to UNRESTRICTED ARES'see Figure 5.1-3) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION:

With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a

Special Report that includes the following information:

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.

Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action(s) taken to prevent a

recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

ODC-AD D-21

OS2 RADIOACTIVE EFFLUENTS 3 4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3. 11. 2. 1 The dose rate due to radioactive materials released in gaseous effluent's from the site to areas at and beyond the SITE BOUNDARY (see Figure 5. 1-1) shall be limited to the following:

For noble gases:

Less than or equal to 500 mrems/yr to the whole body and'less than or equal to 3000 mrems/yr to the skin, and For Zodine-131, for Zodine-133, for tritium, and for all radionuclides in particular form with half-lives greater than 8 days:

Less than or equal to 1500 mrems/yr,to any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).

SURVEILLANCE REQUIREMENTS

~

4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

4.11.2.1.2 The dose rate due to Iodine-131, Zodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

ODC-AD D-22 Rev. 3.0 S/j

0an TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS RELEASE TYPE 1.

Waste Gas Storage Tank 2.

Containment Purge or Vent 3.

a.

Plant Vent Stack b.

Turbine Bldg Vent Stack, Waste Proc.

Bldg. Vent Stacks 5

& 5A SAMPLING FREQUENCY P

Each Tank Grab Sample P

Each PURGE"'rab Sample Ms>.w.e Grab Sample M

Grab Sample MINIMUM ANALYSIS FREQUENCY P

Each Tank P

Each PURGE"'YPE OF ACTIVITYANALYSIS Principal Gamma Emitters"'rincipal Gamma Emitters+

H-3 (oxide)

Principal Gamma Emitters"'-3 (oxide)

Principal Gamma Emitters+

H-3 (oxide)

(Turbine Bldg.

Vent Stack)

LOWER LIMIT OF DETECTION (LLD)a~

(pCi/ml) 1x10~

1x10 Ix10~

1x10~

1x10 1x10~

1x10~

4.

All Release Types

- Continuous'"

as listed in 1.,2.,

and 3. above Continuous+

Continuous" Continuous'"

Charcoal Sample W

Particulate Sample M

Composite Particulate Sample Q

Composite Particulate Sample I-131 I-133 Principal Gamma Emitters Gross Alpha Sr-89, Sr-90 1x10'~

1x10'x10" 1x10 "

1x10"

OS2 TABLE 4 11-2 Continued TABLE NOTATIONS (1)

The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement

system, which may include radiochemical separation:

4.66 sb E

~ V 2.22 x 10' exp (-A,ht)

Where:

LLD = the "a priori" lower limit of detection (microCurie per unit mass or volume),

sb the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 x 106

= the number of disintegrations per minute per microCurie, Y = the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide (sec'),

and ht

= the elapsed time between the midpoint of sample collection and the time of counting (sec).

Typical values of E, V, Y, and ht should be used in the calculation.

It should be recognized that the Lan is defined as an h priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (aster the fact) limit for a particular measurement.

ODC-AD D-24

OS2 TABLE 4 11-2 Continued TABLE NOTATIONS Continued (2)

The principal gamma emitters for which the LLD specification applies include the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Ce-144 in Iodine and particulate releases.

This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.4. in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3)

Sampling and analysis shall also be performed following shutdown,

startup, or.a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.

(4)

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

(5)

Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool.area, whenever spent fuel is in the spent fuel pool.

(6)

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation-made in accordance with Specifications 3.11.2.1, 3.11.2.2, and 3. 11.2.3.

(7)

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after'removal from sampler.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each

shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10.

This requirement does not apply if:

(1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

ODC-AD D-25 Rev.

3 0

~/

3/$

OS2 RADIOACTIVE EFFLUENT DOSE NOBLE GASES LIMITING CONDITION FOR OPERATZON 3.11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

During any calendar quarter:

Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and b.

During any calendar year:

Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

/BUTTIN:

a.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, 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(s) 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.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

ODC-AD D-26

OS2 RADIOACTIVE EFFLUENTS DOSE

- IODINE-131 IODINE-133 TRITIUM AND RADIOACTIVE MATERIAL IN PARTICULATE FORM J

LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Zodine-131, Zodine-133, tritium, and all radionuclides in particulate form with half-lives, greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 7.5 mrems to any organ~

and During any calendar year:

Less than or equal to 15 mrems to any

'r gcul APPLICABILITYl At all times.

ACT1ON:

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, 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(s) 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.

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

ODC-AD D-27 Rev.

3. 0 3/s

OS2 RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the GASEOUS RADWASTE TREATMENT SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) would exceed:

a.

0.2 mrad to air. from gamma radiation, or b.

0.4 mrad to air from beta radiation, or c.

0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

a.

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a

Special Report that includes the following information:

Identification of any inoperable equipment or subsystems, and the reason for the inoperability, Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action(s) taken to prevent a

recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when the GASEOUS RADWASTE TREATMENT SYSTEM is not being fully utilized.

4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and GASEOUS RADWASTE TREATMENT SYSTEM shall be considered OPERABLE by meeting Specifications 3.11.2,1 and 3.11.2.2, or 3.11.2.3.

ODC-AD D-28

OS2 RADIOACTIVE EFFLUENTS 3 4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.11.1.2a.,

3.11.1.2b.,

3.11.2.2a.,

3.11.2.2b.,

3.11.2.3a.,

or 3.11.2.3b.,

calculations shall be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits.of Specification 3.11.4 have been exceeded.

If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.

This Special

Report, as defined in 10 CFR 20.405(c),

shall include an analysis that estimates the radiation exposure (dose) to a MEMBER QF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report.

Zt shall also describe levels of radiation and concentrations of radioactive material

involved, and the cause of the exposure levels or concentrations.

Zf the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.11.4.1

~

Cumulative dose contiibutions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.

4.11.4.2 Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM.

This requirement is applicable only under conditions set forth in ACTION a. of Specification 3.11.4.

ODC-AD D-29

OS2 D.3 3

4 12 RADIOLOGICAL ENVIRONMENTAL MONZTORZNG 3

4 12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The Radiological Environment Monitoring Program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

With the Radiological Environmental Monitoring Program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.3, a description of the reasons for not conducting the program as required and the plans

~

for preventing a recurrence.

b.

With the level.of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, 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(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2.

3 '1.2.2, or 3.11.2.3.

When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1)

+

concentration (2)

+

~ 1, 0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Specification 3.11.1.2, 3.11.2.2, or 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.3.

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

ODC-AD D-30

OS2 RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM LlMZTZNG CONDITION FOR OPERATION ACTION Continued With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 3.12-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

d.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.

ODC-AD D-31 Rev. 3.0 A

TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM*

EXPOSURE PATHWAY AND OR SAMPLE 1.

Direct Radiation+

NUMBER OF REPRESENTATIVE AMPLBS AND SAMPLE LOCATIONSai Forty routine monitoring stations either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; SAMPLING AND COLLECTION FRB UENCY Quarterly.

TYPE AND FREQUENCY OF ANALYSIS Gamma dose quarterly.

An outer ring of stations, one in each meteorological sector in the 6-to 8-km range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences,

schools, and in one or two areas to serve as control stations.

OUn I

TABLE 3.12-1 Continued RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND OR SAMPLE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONSsi SAMPLING AND COLLECTION FRE UENCY TYPE AND FREQUENCY OF-ANALYSIS 0

I 4J 4J 2.

Airborne Radioiodine and Particulates Samples from five locations:

Three samples from close to the three SITE BOUNDARY locations, in different

sectors, of the highest calculated annual average ground-level D/Q; One sample from the vicinity of a community having the highest calculated annual average ground-level D/Q; and Continuous sampler Radioiodine Cannister:

operation with sample '-131 analysis weekly.

collection weekly, or more frequently if required by dust loading.

Particulate Sam ler:

Gross beta radioactivity analysis following filter change;"'nd gamma isotopic analysis~"

of composite (by location) quarterly.

3.

Waterborne One sample from a control

location, as for example 15 to 30 km distant and in the least prevalent wind direction.

a.

Surface'"

One sample upstream.

One sample downstream.

Composite sample over 1-month period.+

Gamma isotopic analysis"'.

monthly.

Composite for tritium analysis quarterly.

b.

Ground Samples from one or two sources only if likely to be affected+.

Quarterly.

Gamma isotopic'" and tritium analysis quarterly.

4J O

0anI TABLE 3.12-1 Continued RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND OR SAMPLE 3.

Waterborne (Continued)

NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS'AMPLINGAND COLLECTION FRB UENCY TYPE AND FREQUENCY OF ANALYSIS c.

Drinking One sample in the vicinity of the nearest downstream municipal water supply intake from the Cape Fear River.

One sample from a control location.

Composite sample over 2-week period'" when I-131 analysis is performed; monthly composite otherwise.

I-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year.@

Composite for gross beta and gamma isotopic analyses'+

monthly.

Composite for tritium analysis quarterly.

a I4l d.

Sediment from Shoreline 4.

Ingestion One sample in the vicinity of the

- 'Semiannually.

cooling tower blowdown discharge in an area with existing or potential recreational value.

Gamma isotopic analysis~+ semiannually.

s ~

O a.

Milk Samples from milking animals in three locations within 5 km distance having the highest dose potential. If there are none, then one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr.@

One sample from milking animals at a control location 15 to 30 km distant and in the least prevalent wind direction.

Semimonthly when animals are on pasture; monthly at other times.

Gamma isotopic'+ and I-131 analysis semimonthly when animals are on pasture; monthly at other times.

TABLB 3.12-1 Continued RADIOLOGICAL ENVIRONMENTAL MONITORING ROGRAM EXPOSURE PATHWAY AND OR SAMPLE 4.

Ingestion (Continued)

NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS'AMPLINGAND COLLECTION FRB UBNCY TYPE AND FREQUENCY OF ANALYSIS b.

Fish and Invertebrates One sample of Sunfish, Catfish, and Large-Mouth Bass species in vicinity of plant discharge area.

Sample in season, or semiannually if they are not seasonal.

Gamma isotopic analysis'"

on edible portions.

c.

Food Products One sample of same species in areas not influenced by plant discharge.

Samples of three different kinds of broad leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed.

One sample of each of the similar broad leaf vegetation grown 15 to 30 km distant in the least prevalent wind direction if milk sampling is not performed.

Monthly during growing season.

Gamma isotopic"'nd I-131 analysis.

Gamma isotopic'" and I-131 analysis.

OS2 TABLE 3 12-1 Continued TABLE NOTATIONS Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure(s) in the ODCM.

Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October

1978, and to Radiological Assessment Branch Technical

Position, Revision 1, November 1979.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment.

If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period.

All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.3.

It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.

In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program.

Pursuant to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location(s) for obtaining samples.

(2)

One or more instruments,'uch as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.

For the purposes of this

table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation.

(The 40 stations are not an absolute number.

The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly.

The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information within minimal fading.)

(3)

Airborne particulate sample filters shall be analyzed for gross beta radioactivi.ty 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay.

If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

ODC-AD D-36

OS2 TABLE 3.12-1 Continued TABLE NOTATIONS Continued (5)

The "upstream sample" shall be taken at a distance beyond significant influence of the discharge.

The "downstream" sample shall be taken in an area beyond but near the mixing zone.

"Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence.

Salt water shall be sampled only when the receiving water is utilized for recreational activities.

(6)

A composite sample is one -in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow.

In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g.,

monthly) in order to assure obtaining a representative sample.

(7)

Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(8)

The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

ODC-AD D-37

0an I

TABLE 3,12-2 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES ANALYSIS H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 WATER (pCi/l) 20,000*

1,000 400 1,000 300 300 AIRBORNE PARTICULATE FISH OR GASES (pCi/m~)

(pCi/kg, wet) 30, 000 10,000 30,000 10,000 20,000 MILK (pCi/l)

FOOD PRODUCTS (pCi/kg, wet)

Zr-Nb-95 400 I-131 0.9 100 Cs-134 Cs-137 30 50 10 20 1, 000 2,000 60 70 1, 000 2, 000 Ba-La-140 200 300

For drinking water-samples.

This is 40 CFR Part 141 value.

If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

- Ifno drinking water pathway exists, a value of 20 pCi/1 may be used.

Oan I

TABLE 4.12-1 DETECTION CAPABIIITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS~'>>

LOWER LIMIT OF DETECTION LLD ANALYSIS Gross Beta WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT (pCi/l)

=

OR GASES (pCi/m')

(pCi/kg, wet)

(pCi/l)

(pCi/kg, wet)

(pCi/kg, dry) 0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 I-131 15 0.07'0 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15

Zf no drinking water pathway exists, a value of 3000 pCi/1 may be used.

- Ifno drinking water pathway exists, a value of 15 pCi/1 may be used.

Q

OS2 TABLE 4.12-1 Continued TABLE NOTATIONS (1)

This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, together with those of the above

nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.3.

(2)

Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3)

The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For 'a particular measurement

system, which may include radiochemical separation:

Lz,D

'4.66 s E

~ V ~ 2.22

~ Y ~ exp (-Ah,t)

Where:

LLD = the "a priori" lower limit of detection (picoCurie per unit mass or volume),

sb the standard deviation of the background counting rate or of the counting rate of a blank sampl'e as appropriate (counts per minute),

E =

the counting efficiency (counts per disintegration);

V =

the sample size (units of mass or volume),

2.22

the number of disintegrations per minute per picoCurie, Y

the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide (sec'),

and 4t =

the elapsed time between environmental collection, or end of the sample collection period, and the time of counting (sec)

Typical values of E, V, Y, and 4t should be used in the calculation.

ODC-AD D-40 pc Rev. 3.0

OS2 TABLE 4 12-1 Continued TABLE NOTATIONS Continued It should he recognized that the LLn is defined as an a Rriori Ihefore the fact) limit representing the capability of a measurement system and measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.

Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.3.

ODC-AD D-41 Rey. 3.0

OS2 RADIOLOGICAL ENVIRONMENTAL MONITORING 3 4.12.2 LAND USE CENSUS LIMITING CONDITZON

'FOR OPERATION 3.12.2 A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden* of greater than 50 m'500 ft'-) producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

a.

With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, pursuant to Specification 6.9.1.4, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report.

b.

With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.

The sampling location(s),

excluding the control station location, having the lowest calculated dose or dose commitment(s),'ia the same exposure

pathway, may be deleted from this monitoring program after

'October 31 of the year in which this Land Use Census was conducted.

Pursuant to Specification 6.9.1.4, submit in the next Semi. annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

C.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEZLLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best

results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.3

~

<<Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SZTE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.

Specifications for broad leaf vegetation sampling in Table 3.12-1, Part 4.c., shall be followed, including analysis of control samples.

ODC-AD D-42 vga.

Rev.

3.0

)

OS2 RADIOLOGICAL ENVIRONMENTAL MONITORING 3

4. 12. 3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Znterlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.3.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEZLLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM.

A summary of the results obtained as part of the above required Znterlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.3.

ODC-AD D-43 Rev.

R.O

OS2 APPENDZX E PROGRAMMATZC CONTROL BASES The instrumentation, radioactive effluents, and radiological environmental monitoring bases are described in Sections E.l, E.2, and E.3, respectively.

ODC-AE E-l QC Rev.

3. 0

OS2 E.l INSTRUMENTATION BASES 3/4.3.3 Instrumentation 3/4.3.3.10 Radioactive Li id Effluent Monitorina Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and

control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The Alarm/Trip Set Points for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.11 Radioactive Gaseous Effluent Monitorin Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and

control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The Alarm/Trip Set Points for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The sensitivity of any noble gas activity monitors used to show compliance with the gaseous effluent release requirements of Specification 3.11.2.2 shall be such that concentrations as low as 1 x 10-'Ci/ml are measurable.

ODC-AE E-2 QC, Rev.

3. 0 g]5

OS2 E.2 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 Li id Effluents 3/4.11.1.1 Concentr tion This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2

~

This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within:

(1) the Section ZI.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to the population.

The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs).

Detailed discussion of the LLD, and other detection limits, can be found in HHSL Procedures

Manual, H~HSL-3 0 (revised annually),

Currie, L. n., "Limits for Qualitative Detection and Quantitative Determination

- Application to Radiochemistry," Anal.

Chem.

40, 586-93 (1968),

and Hartwell, J.

K-.,

"Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

ODC-AE E-3

OS2 E.2 RADIOACTIVE EFFLUENTS BASES (continued) 3/4. 11. 1. 2 Dose This specification is provided to implement the requirements of Sections II.A, ZIZ.A, and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Condition for Operation implements the guides set forth in Section ZZ.A of Appendix Z.

The ACTION statements provide the required operating flexibilityand at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

The dose calculation methodology and parameters in the ODCM implement the requirements in Section ZZI.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

3/4.11.1.3 Li i R

w Tr m n S

m The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.,

The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as.

is reasonably achievable."

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

,the design objective given in Section ZZ.D of Appendix I to 10 CFR part 50.

The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR part 50 for liquid effluents.

ODC-AE 4

gC 3.0

~

g($

OS2 E.2 RADIOACTIVE EFFLUENTS BASES (continued) 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 Dose Rate This specification is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units'on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS.

The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table ZI, Column Z.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table ZZ of 10 CFR Part 20

[10 CFR Part 20.106(b)]

For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM.

The specified release rate limits restrict, at all times, the corresponding gamma and beta 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 whole body or to less than or equal to 3000 mrems/year to the skin.

These release rate 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.

The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs).

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, H~L-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination

- Application to Radiochemistry,

" An 1 h

4, 586-93 (1968),

and Hartwell, J. K.,

"Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-A-21 (June 1975).

ODC-AE E-5 Rev. 3.0 ['/$

OS2 E.2 RADIOACTIVE EFFLUENTS BASES (continued) 3/4.11.2.2 Dose N ble Gase This specification is provided to implement the requirements of Section II.B, IXX.A, and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Condition for Operation implements the guides set forth in Section Z.B of Appendix Z.

The ACTION statements provide the required operating flexibilityand at the same time implement the guides set forth in Section ZV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

The Surveillance Requirements implement the requirements in Section ZZZ.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, "Methods foi Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"

Revision 1, July 1977.

The ODCM equations provided for determining the air doses at and beyond the SXTE BOUNDARY are based upon the historical average atmospheric conditions.

ODC-AE E-6

OS2 E.2 RADIOACTIVE EFFLUENTS BASES (continued) f 3/4.11.2.3 Dose

- Zodine-131 Zodine-133 Tritium and Radioactive Material in Particulate Form This specification is provided to implement the requirements of Sections ZZ.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 statements provide the required operating flexibilityand at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

The'DCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.Aof Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 1977.

These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for Zodine-131, Zodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.

The pathways that were examined in the development of the calculations were:

(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 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.

ODC-AE E-7 j}c.

R

. 3.0

~ yg

OS2 E.2 RADIOACTIVE EFFLUENTS BASES (continued) 3/4.11.2.4 Gaseous Radwaste Treatment S stem The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTZLATZQN EXHAUST TREATMENT SYSTEM ensure that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

This specification implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of'ppendix A to 10 CFR Part 50 and the design objectives given in Section ZZ.D of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections ZZ.B and ZZ.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

3/4.11.4 Total Dose This specification is provided to meet the dose limitations of 10 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525.

The specification requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to'he whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units and from outside storage tanks are kept small.

The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.

For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.

Zf ODC -AE E-8 QC Rev. 3.0

~c

OS2 E.2 RADIOACTIVE EFFLUENTS BASES (continued) the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part

190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected),

in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to he a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed.

The variance only relates to the limits of 40 CFR Part

190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1.1 and 3.11.2.1.

An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

ODC-AE E-9 Rev.

3.O

0

OS2

E.3 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4. 12 Radiolo ical Environmental Monitorin 3/4.12.1 Monitorin Pro ram The Radiological Environmental Monitoring Program required by this specification provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant operation.

This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.

The initially specified monitoring program will be effective for at least the first 3 years of commercial operation.

Following this period, program changes may be initiated based on operational experience.

The, required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs).

The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories.

It should be recognized that the LLD,is defined as'n ~ariori (before the fact) limit representing the capability of a measurement system and not as an osteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures

Manual, HASL-300 (revised annually), Currie, L'. A., "Limits I

for Qualitative Detection and Quantitative Determination

- Application to Radiochemistry," Anal Chem.

40, 586-93 (1968),

and Hartwell, J. K.,

"Detection Limits for Radioanalytical Counting Techniques" Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

ODC-AE E-10

~

[ gQ Rev.

3. 0

OS2 E.3 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES (continued) 3/4.12.2 Land e -Censu This specification is provided to ensure that changes in the use of areas at

/

and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program are made, if required, by the results of this census.

The best information from the door-to-door survey, from aerial survey, or from consulting with local agricultural authorities shall be used.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 50 m~ provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.

To determine this minimum garden size, the following assumptions were made:

(1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage),

and (2) a vegetation yield of 2 kg/~.

3/4. 12. 3 In rl ora o

ari n Pro r The requirement for participation in an approved 1'nterlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section ZV.B.2 of Appendix I to 10 CFR Part 50.

ODC-AE E-11

OS2 APPENDEX F

~

ADMXNXSTRATIVE CONTROLS Reporting requirements pertaining to the Annual Radiological Environmental Operating Report, Semiannual Radioactive Effluent Release

Report, as well as major changes to the Radwaste Treatment System (liquid and gaseous) are described in Section F.l.

ODC-AF F-1 Re~.

3.0

) '15 4i'

OS2 F.1 REPORTING RE UIREMENTS Annual Radiolo ical Environmental eratin Re ort (Formerly part of

~

Specification 6.9.1.3)

Routine Annual Radiological Environmental Operating Reports, covering the operation of the unit during the previous calendar year, shall be submitted prior to May 1 of each year.

The initial report shall be submitted prior to May 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Reports shall include

. summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational

studies, with operational controls, as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of the Land Use Census required by Specification 3.12.2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the OFFSITE DOSE CALCULATION MANUAL, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor; the results of licensee One map shall cover stations near the EXCLUSION AREA BOUNDARY; a second shall include th'e more distant station.

ODC-AF F-2 QC.

Rev. 3.0 f $/9

OS2 F.1 REPORTING RE UIREMENTS (continued) participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Specification 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Specification 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12-1; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12-2 but are not the result of plant effluents, pUrsuant to ACTION b. of Specification 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

ODC-AF F-3 J

($ C Rev. 3.0

(

>/$

OS2 F.l REPORTZNG RE UIREMENTS continued Semiannual Radioactive Effluent Release Re ort (Formerly part of Specification 6.9.1.4)

Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

The period of the first report shall begin with the date of initial criticality.

The Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,"

Revision 1, June 1974, with data summarized on a quarterly basis" following the format of Appendix B thereof.

The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year.

This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind

speed, wind direction, atmospheric stability, and precipitation (if measured),

or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.** This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Specification Figure 5.1-3) during the report period.

Zn lieu of submission with the Semiannual Radioactive Effluent Release

Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

ODC-AF F-4 R8.. 3.0 l~g/$

OS2 F.1 REPORTZNG RE UIREMENTS (continued)

All assumptions used in making these assessments; i.e., specific activity, exposure

time, and location, shall be included in these reports.

The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses.

The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSZTE DOSE CALCULATZON MANUAL (ODCM).

The Semiannual Radioactive Effluent Release Report to be submitted within

'0 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLZC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1, October 1977.

The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases, from the site to UNRESTRZCTED AREAS, of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Semiannual Radioactive Effluent Release Report shall include any changes made during the reporting period to the ODCM, pursuant to Specification 6.14, as well as any major change to. Liquid and Gaseous Radwaste Treatment Systems pursuant to Specification 6.15.

Zt shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Specification 3.12.2.

ODC-AF F-5

)h('-

Rev.. 3.0

OS2 F.1 REPORTING RE UIREMENTS (continued)

The Semiannual Radioactive Effluent Release Reports shall also include the following:

an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Specification 3.3.3.10 or 3.3.3.11, respectively; and a description of the 'events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Specification 3.11.1.4 or 3.11.2.6, respectively.

ODC-AF F-6

OS2 F. 1 REPORTING RE UIREMENTS (continued)

Ma'or Chan es to Li id and Gaseous Radwaste Treatment S

s ems (Formerly part of Specification 6.15)

Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous) a

~

Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed in accordance with Specification 6.5.

The discussion of each change shall contain:

A summar'y of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.

2.

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information.

'3.

A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.

An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto.

,*Licensees may choose to submit the information called for in the Specification as part of the annual FSAR update.

ODC-AF F-7

OS2 F. 1 REPORTING RE UIREMENT (continued) 5.

An evaluation of the change, which shows the expected maximum exposures, to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population, that differ from those previously estimated in the License application and amendments thereto.

C 6.

A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents to the actual releases for the. period prior to when the change is to be made.

An estimate of the exposure to plant operating personnel as a result of the change.

8.

Documentation of the fact that the change was reviewed and found acceptable in accordance with Specification 6.5.

b.

Shall become effective upon review and acceptance in accordance with Specification 6.5 ODC-AF F-8 R

. 3.0

.gG

ENCLOSURE TO SERIAL'LS-92-132 ENCLOSURE 7

SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (GENERIC LETTER 89-01)

PROCESS CONTROL PROGRAM CHANGES

TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE

2.0 REFERENCES

3.0 DEFINITIONS 4.0 GENERAL 4.1 Review, Approval and Changes 4.2 Use of Solidification Vendor Service 5.0 IMPLEMENTATION 5.1 Waste Streams 5.2 Cement Solidification 5.2.1 Solidification Formulas 5.2.2 Control of Process Parameters 5.2.3 Pre-Solidification Sampling and Testing 5.3 Polymer Solidification 5.3.1 Solidification Formulas 5.3.2 Control of Process Parameters 5.3.3 Pre-Solidification Sampling and Testing 5.4 10 CFR61 ImpLementation 5.4.1 Waste Classification 5.4.2 Waste Charateristics 5.4.3 Labeling 5.5 10 CFR20.311 implementation 5.5.1 Shipment Manifest 5.5.2 Quality Control Program 6.0

FIGURES, TABLES, ATTACHMENTS 6.1 Process Control Program Implementing Procedures 6.2 SHNPP Radioactive Waste Streams 6.3 Waste Stream Sample Points Attachment 1 Solid Radwaste Programmatic Controls 1.34 Definitions Solidification 3.11.3 Solid Radioactive Waste LCO 4.11.3 Surveillance Requirements 3/4.4.11.3 Bases 6.9.14 Semiannual Radioactive Effluent Release Report 6.15 Major Changes to Liquid Gaseous, and Solid Radwaste Treatment Systems 4

4 5

5 5

6 6

7 7

7 9

11ll 12 14 15 15 16 17 17 17 17 18 19 20 21 21a 2la 21b 21b 21c 21c 2ld PLP-300, Rev.

0 Page 2 of 21

LIST OF EFFECTIVE PAGES

~Pa e

12-4 5 "21 2la - 21d Revision 0

AC-0/1 0

AC-0/1 PLP-300, Rev.

0 Page 3 of 21

1.0 PURPOSE The purpose of the Process Control Program (PCP) is to establish a

set of process parameters which provide reasonable assurance of com-plete solidification of variou's radioactive waste and compliance with 10 CFR 20, 10 CFR 61, Federal and State regulations, burial site requirements, and other requirements governing the disposal of R

radioactive waste.

The Process Control Program is a requirement of Technical Specification 6.8.

The Solid Radwaste Programmatic Controls are given in Attachment 1.

2.0 REFERENCES

2.1 Code of Federal Regulations, Title 10 Part 61, "Licensing Requirements for Land DisposaL of Radioactive Waste."

2.2 Code of Federal Regulations, Title 10 Part 20.311, "Transfer for Disposal and Manifests.-

2.3 NUREG-0472, "Radiological Effluent Technical Specification for PWR" July 1979.

2.4 NUREG-0133, "Preparation of Radiological Effluent Technical Specification for Nuclear Power Plants."

2.5 General Process Control Program, "Cement Solidification of Low Level Liquid Waste at Pressurized Water Reactors",

Stock Equipment Company RPA 8.3.1.2-A.

2.6 General Process Control Program, "Polymer Solidification of Dry Products,"

Stock Equipment Company RPA 8.3.2.1-0.

2.7 Technical Specification, "Shearon Harris Nuclear Power Plant Technical Specifications."

2.8 NRC Generic Letter 89-01 Programmatic Controls for RETS in the Administrative Control Section of t'e Technical Specifications."

2.9 Regulatory Guide 1.21, June 1974 "Measuring, Evaluating, and Reporting Radioactivity in Solid Radwaste."

2.10 Code of Federal Regulations, "Title 10 Part 50, "Licensing of Production and Utilization Facilities."

3.0 DEFINITIONS 3.1 Batch A specified quantity of waste material requiring solidi-fication which can be isolated from further inputs.

3.2 Exothermic Period For polymer solidification, the point at which t e rate o

temperature increase is equal to 1'F per min.

3.3. Solidification - The conversion of radioactive waste into a form 3.4 Waste Classification The determination of a waste class as outline xn y radionuclide isotopic analysis and/or corre-lation with other measured nuclides.

PLP-300, Rev.

0 Page 4 of 21

ML18010A699

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1.0 INTRODUCTION

1.0 INTRODUCTION

1.0 INTRODUCTION

the number of disintegrations per minute per picoCurie, Y

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