ML20203J269

Rev 0 to Radiological Effluent Monitoring & Offsite Dose Calculation Manual & Process Control Program

ML20203J269
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	01/01/1986
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20203J178	List: ML20203J174 ML20203J199 ML20203J211 ML20203J233 ML20203J269 ML20203J316
References
PROC-860101, NUDOCS 8604300157
Download: ML20203J269 (100)

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{{#Wiki_filter:.x. ? n a. :97gc;,9?%W%2yiwmW FM". .s ~ Policy No 18 [4f "g }, 5 Rev 0 I b I' Date 3-10-82 ~ r [f 1 ll Page 1 of 2 i ] NEO POLICY STATEMENT NUCLEAR WASTE MANAGEMENT PROGRAM Northeast Utilities recognizes the need to maintain environmen-tal quality and to provide for.public. health and safety in all To provide this quality, Northeast Utili-of its activities. ties is committed to the long-term management of both high-level and low-level nuclear waste material. Policy Number 8 addresses the issue of high-level waste generation and Northeast Utili-ties' policy on the handling of this waste. This policy pro-vides focus on the management of low-level. wastes which are generated as a consequence of routine power reactor operation, gjh maintenance and' modifications. Northeast Utilities is committed to the minimization and envi-ronmentally safe processing of low-level nuclear waste material utilizing cost effective and efficient methods. Implementation of this policy is accomplished by: Including systems in the plant design to treat solid, ( ) () 1) liquid, and gaseous nuclear wastes such that all app 11-cable release limits prescribed by regulation are met. r 2) Plant operations, modifications, maintenance, and routine refueling operations are planned and implemen-ted to control and limit the generation of nuclear waste material. 3) A minimum of one year's worth of waste storage space is always available so that the plant may safely continue to operate if normal offsite shipment and ' disposal of waste is not possible. 4 4) Existing plant nuclear waste processing methods and systems are periodically reviewed to assess their~per-formance and any need for modification or replacement. 5) Strategic alternates to existinC waste disposal sites are re-evaluated on a continuing basis to provide a contingency to Northeast Utilities to prevent any significant unplanned accumulation of nuclear waste on-site or adverse impact on safe plant operations. 6) New or innovative waste processing methods which pro-vide benefits to the safe, cost-ef.fective, or efficient {T operation of Northeast Utilities' nuclear gener,ating t s,) facilities are evaluated on a continuing basis. 8604300157 860421 PDR ADOCK 05000213 P PDR

c.;: y. .:m, ,- m x,c,cs.y.g;>.a. y.sw.x. v.n> u m,-,.;.. x.:s ~ :. Po!fcy No 18 Rev o Date '-10-82 ~~ Page 2 of 2 O ~ 7) NE&O will actively participate in the development of was te mana gement s tanda rds and legislation.. Overall responsibility for compliance with this nuclear waste management program policy rests with the Senior Vice President, Nuclear Engineering and Operations. Specific responsibility for implementation of programs to assess compliance with Items 1, 4 and 6 lies with the Vice President, Generation Engineer-ing and Construction; responsibility for Items 2 and 3 lies with the Vice President, Nuclear Operations; and responsibility for Items 5 and 7 lies with the Vice President, Nuclear and Environmental Engineering. Draft revisions, additions to, and audits of this policy, with' the approval of the affected Divisions, are the responsibility of the Vice President, Nuclear and Environmental Engineering. Final approval of all revisions or additions of policy state-ments rests with the Senior Vice President of Nuclear Engin-eering and Operations. i i O 1 i '). M*M W. G. Counsil Senior Vice President Nuclear Engineering & Operations w b l d e a v, - -. - + 4

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Docket Nos. 50-245 S* l' nf8 50-336 50-423 License Nos. DP R-21 DPR-65 NPF-44 RADIOLOGICAL EFFLUENT, MONITORING AND . OFFSITE DOSE CALCULATION MANUAL AND PROCESS CONTROL PROGRAM .l MilI' stone Unit Nos.1,2, & 3 o) t t v y Northeast Nuclear E6ergy Company "~ d

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- ~ - - ' s- . s...c.9;m s. ..,- g, s . ~~. ;' j l. 1 l .l b SECTION I .ch 9 t l RADIOLOGICAL EFFLUENT 1 i-MONITORING MANUAL 6 FOR THE MILLSTONE NUCLEAR POWER STATION. UNIT NOS,1,2, & 3 DOCKET NOS. 50-245 50-336 50-4237 i e ~- . v. i 3., January 1986 Revision 0

r . n, _..,y,.;_n,.. 3 l 1 1/1/86 f] Rev. O ,eh RADIOLOGICAL EFFLUENT MONITORING MANUAL

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.c }l TABLE OF CONTENTS ~ .,' j 'i SECTION PAGE NO. REV.NO. ~ yy ') A. INTRODUCTION A-1 0 B. RESPONSIBILITIES. B-1 0 C. 1. LIQUID EFFL UENTS SAMPLING C-1 0 ~~ AND ANALYSIS PROGRAM 2. LIQUID WASTE TREATMENT C-11* 0 D. 1. GASEOUS EFFL UENTS SAMPLING D-1 0 AND ANALYSIS PROGRAM 2. GASEOUS WASTE TREATMENT D-9 0 E. RADIOLOGICAL ENVIRONMENTAL MONITORING-1. SAMPLING AND ANALYSIS E-1 0. 2. LAND USE CENSUS E-3 0 3. INTERLABORATORY COMPARISON PROGRAM E-4 0 F. REPORT CONTENT 1. ANNUAL RADIOLOGICAL j ENVIRONMENTAL OPERATING F-1 0 ,cx REPORT ( ) 2. SEMI ANNUAL RADIOACTIVE T EFFLUENT RELEASE REPORT F-2 0 3., 's 8 b, m 'x..f .e 9

( ~ ;,,,. ms p,:. y;g_c-n g.-- + z. ~ m m,,;... s 3.mg,; g... I h't 1/1/86 Rev.0 h A. INTRODUCTION ,n,a 'j The purpose of this manual is to provide the sampling and analysis programs' which provide input to the ODCM for calculating liquid and gaseous effluent concentrations and offsite doses. Guidelines are provided t for operating radioactive waste treatment systems in order that offsite ~.,

1. :

doses are kept as-low-as-reasonably-achievable (ALARA). The Radiological Environmental Monitoring Program outlined within this manual provides confirmation that the measurable concentrifions.'gf radioactive material released as a result of operations at Ibe Millstone Site-are not higher than expected. In addition, this manual outlines the information required to be submitted to the NRC in both the Annual Radiological Environmental Operating Report and the Semiannual Radioactive Effluent R.el, ease Report. ~. 0 'uJ y e.* 0 ( a' e i 1 e , g \\ / s <4 A-1 e

.., : 3 ., g., ~.,u, g _.=.. ~ l I i 1/1/86 Rev.0 B. RESPONSIBILITIES } ... s! l All changes.to this manual shall be reviewed and approved by the Station l Operations Review Committee and the Nuclear Regulatory Commission ~ prior to implementation. .~ All changes and their rationale shall be documented in the S'emlannual Radioactive Effluent Release Report. It shall be the responsibility of the Station Superintendent to ensure that this manual is used in performance of the surveillance requirements and",, administrative controls of the Technical Specifications. 1-6 0 3 e e O S 0 O g, G.

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,,. +; c - - r m. c l 1/1/86 Rev.0 h C. LIOUID EFFLUENT SAMPLING AND ANALYSIS PROGRAM i diO ) C.1 Radioactlye liquid wastes shall be sampled and analyzed in accordance with g the program specified in Table C-1 for Millstone Unit No.1, Table C-2 for Millstone Unit No. 2, and Table C-3 for Millstone Unit No. 3. The results i of the radioactive analysis shall be input to the methodology,of the ODCM I to assure that the concentrations at the point of release are maintained within the limits of the Technical Specification 3.3.C.1 for Millstone Unit ~ No. I and within the limits of Technical Specifications 3.11.1 for-Millstone Unit Nos. 2 and 3.

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.r..+ w :7 v -- ~ ~- 4x; 1/1/86 Rev.0 Table C-1 ) MILLSTONE 1 ~ ' ' l l RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM I LOWER LIMIT MINIMUM OF DETECTION (a) SAMPLING ANALYSIS TYPE OF ACTIVITY (LL D) ' LIQUID RELEASE TYPE FREQUENCY FREQUENCY ANAL YSIS TiiCi/m'l) ' A. BATCH RELEASEf

1. Waste Sample Prior to Prior to Principal Gamma

'5 x 10-7 Tanks Each Batch Each Batch Emittersb

2. Floor Drain 1-131, Mo 1 x 10-6 Sample Tank Ce-141, Ce-144 5 x 10-6 4

One Batch Monthly Other Dissolved 1 x 10-5 per month . and Entrained Gases

3. Decon Solution Prior to Monthly H-3

1. x 10-5 Tank Each Batch Composite Gross alpha 1 x 10-7 Prior to Quarterly Sr-89, Sr-90 5 x 10-8 Each Batch Composite F635' 1,xJ0-6 B.

CONTINUOUS RELEASE Daily Weekly Principal Gamma. Grab Composite (c) Emitters (b) 3 x 10-7 Sample (d) 1-131, Mo-99

1. x 10-6 Reactor Building Ce-141, Ce-144 5 x 10-6 Service Water Monthly Monthly Dissolved and 1 x 10-5 Grab Sample Entrained Gases Weekly Monthly H-3(e) 1 x 10-5 Grab Sample Compositec Gross alpha (e) 1 x 10-7 i

Weekly Quarterly (c) Sr-89((e)I -90(e) 5 x 10-8 Sr Grab Sample Composite Fe-55 e 1 x 10-6

1. s 6.

C-2

n, -n i: 1/1/86 Rev.0 A TABLE C-1 (Continued) } ' 33.2 5 4' TABLE NOTATIONS

• 't a.

The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 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 LL D. E

• V
• 2.22 x 106
• Y
• exp (-XAt) where,

LLD is the lower limit of detection as defined above (as uCl per unit mass or volume) ~ i sb s the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) ,-( E is the counting efficiency (as counts per transformation) ( V', V is the sample size (in units of mass or volume) 2.22 x 106 is the number of ~ transformations per minutes per microcurie Y is the fractional radiochemical yield (when applicable) X is the radioactive decay constant for the particular radio-nuclide at is the elapsed time between midpoint of sample collection and midpoint of counting tim'e It should be recognized that the LLD is defined as an a orlori (bef' ore the fact)!!mit representing the capability of a measurement system and not as ~ a posteriori(after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be d achieve under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable, b. The LLD will b'e 3 x 10-7 uCl/ml. The principal gamma emitters for which this LLD apolies are exclusively the fo!!owing radionuclides: Mn-54, Fe-59, Co-58, Co-60, In-45, Cs-134, and Cs-137. g] k 3._.;f1 C-3

y . - v:,y*, . w. m. .:,.: v w- ~ ,n I 1/1/s6 1 Rev. 0 A j 1 This list does not mean that only these nuclides are to be detected and j reported. Other peaks which are measurable and identifiable, together f with the above nuclides, shall also be identified and repo.-ted. Nuclides

t which cre'below the LLD for the analyses should not be raported as lxing 1

present at the LLD level. When unusual circumstances result in,1 priarl. LLD's higher than reauired, the rdasons shall be documented in the i Semiar.nual Radioactive Effluent Release Report. i A composite sample is cne in which 'the quantity of liquid sampic.d,is. c. 3 proportional to the quantity of liquid vaste discharged and in which the method of sampling employeri rsults in a specimen which is,representativs~ "" N of the liquids released. ~ Prior to analysis, all samples.~.taken for the composite shall be thoroughly mixed in ordet for the composite sample Tc' be representative of the effluents release. d. Daily grab sample for service water taken at least five days per week. e. These analysqs are required only if weekly gamma analysis indicates a gamma activity greater than 5 x 10-7 uCi/ml. f. A batch relelse is the discharge of liquid wastes of a discrete volume. Prioir to samphng, each batch shall be isolated and at least two tank / sump. volumes shall be recirculated or equivalent mixing provided. t e e f a O ,9 i i I L,- .C i; ~ l l

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MILLSTONE.2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i LOWER LIMIT (a).. MINIMUM TYPE OF. OF.DETE CTIO'N. 1 SAMPLING ANALYS5 ACTIVITY - ;..(LL D) LIOUID RELEASE TYPE - FREQUENCY FREQUENCY ANALYSIS (uCl/ml) - A. BATCH RELEASE (b) Prior to. Prior to Principal Gamma 5 x 10-7 Each Batch Each Batch Emitters (c)

1. Coolant Waste I-131, Mo-99, 1 x 10-6 Monitor Tank CFist, Ce-144 5 x 10-6.

2. Aerated Waste Monitor Tank One Batch Monthly Dissolved and(d) 1 x 10-5 '

per month Entrained Gases

3. Condensate Polishing Facility - Waste Prior to Monthly H-3(d) -

1 x 10-5 Neut. Sump (e) Each Batch Composite (f,8) Gross alpha (d) 1 x 10-7 Q> Prior:to Quarterly Sr-89(d), Sr-90(d) 5 x 10-8 Each Batch, _ Composite (f,g).Ee-55(d) l I x 10-6 B. CONTINUOUS RELEASE

1. Steam Generator Blowdown (h)

Daily Weekly Principal Gamma 5 x 10-7 . Grab Sample (i) Composite (8) Emitters (c) I-131, Mo-99 1 x.10-6

2. Reactor Building

- Ce-141, Ce-144 5 x 10-6 Closed Cooling Service Water Outlet Monthly Monthly; . Dissolved and (j) 1 'x 10-5 Grab' Sample Entrained Gases Weekly Monthly H-3(j) 1 x 10-5 Grab Sample - Composite (8) Gross alpha (j) ' 1 x 10-7 ' 3'.

3. ' Turbine Buildin' -

g -Sumps (h). g. Weekly . Quarterly (8). Sr-89(j)ILSr-90(j) 5.x 10-8i ( v5 Grab Sample-Composite Fe-55(j 1 x 10-6 C-5 o 1 4 I p t .~.- _...-..._., _ _.~.

~. m w :y u p. y. w n ;s;,.: y ? w W + - n a ;;p_.< m m m.s, w -a:. % w== ~ 1/1/86 L Rev.0 I TABLE C-2 j (Continued) ,,.1 I, Table Notations i a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability, with 5% probability of falsely i concluding that a blank observation represents a "real" signal. ~ For a particular measurement system (which may include radiochei6ical

• separation):

~~ LL D = 4.66ss E

• V 2.22 x 100
• Y exp (-Mt)

. where LLD is the lower limit of detection as defined above (as uCi per unit mass or volume) i sb s the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per transformation) s V is the sample size (in units of mass or volume) 6 s the number of transformation per minute per microcurie 2.22 x 10 i .Y is the fractional radioch'emical yield N/h'e'n" applicable) ~ his the radioactive decay constant for the particular radionuclide At is the elapsed time between midpoint of sample collection and midpoint of counting time. It should be recognized that the LLD is defined as an a priori (before the-fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occassionally background fluctuations, unavoidably small sample sizes, the presence of interferring nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and recorded on the analysis sheet for the particular sample. b. A batch release is the discharge of liquid wastes of a discrete volume. i Prior to sampling, each. batch shall be isolated and at least two tank / sump volumes shall be recirculated or equivalent mixing provided.. i C-6 1 ? l i 1 O

- m%ww;ge--nm ' a;p.= v-w + mmw., mwn ' wm~ m mim~ w, I? ' 1/1/86 -)i Rev.0 2 ) ' M lh TABLE C-2 kd (Continued) .O "i Table' Notations 1;. c ~ The LLD will be 5 x 10-7 uCi/ml. The principal gamma emit'ters for which c. this.LLD applies are exclusively the following radionuclides: Mn-54,. Fe-59, i Co-58, Co-60, Zn-65, Cs-134, and Cs-137. '~ This list does not mean that only. these nuclides are to be detected and-reported. Other peaks which are measurable and,identi'flable, together i with the above nuclides, shall also be identified and reported.. Nuclides - which are below the LLD for the analyses should not be reported as being present at the LLD level.. When unusual circumstances result in a priori LLD's higher than required, the reasons _ shall.b.e documented in.the Semiannual Radioactive Effluent Release Report. - - d. For the Condensate Polishing Facility (CPF) - Waste Neutralization Sump, these analyses are only required if the gamma analysis of the CPF - Waste Neutralization Sump indicates a gamma activity greater than 5 x 10-7 a uCi/ml. For the Condensate Polishing Facility - Waste Neutralization Sump, these. e. analyses are only required when t.he steam generator. gross activity O f2 1.g. (sampled and analyzed 3 times per week as per Table 4.7-2) exceeds 1 x 10-5 i uCi/mL i b I f. A composite sample is one in which the quantity _ of liquid-sampled is proportional to the quantity"of liipid waste discharged and'in'which the method of sampling employed results in a specimen which is representative of the liquids released. g. Prior to analysis, all samples.taken for.the composite shall be-thoroughly ~ ~ mixed in order for the composite sample to' be representative of the 4 effluents release. For'the Steam Generator Blowdown and the Turbine Building Sump, these h. analyses are only required when the steam generator. gross activity-

1.,

(sgled and analyzed 3 times per week as per Table 4.7-2) exceeds 5 x 10-7 i. Daily grab sample for the service water shall be taken at least 5 days per week. 1-J. - For the Service Water, these analyses are only required if a weekly gamma analyses indicates a gamma activity greater than 5 x 10-7 uCi/ml.

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.-x y e _.,.g,.. q, ;, --e. m ,.n <m..,. 1 1/1/86 Rev.0 1 TABLE C-3 1 0 MILLSTONE 3 ,.g RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM j LOWER LIMIT - ( OF DETECTION (a) ,s 1 ' SAMPLING ANALYS5 TYPE OF ACTIVITY ~ (LLD) LIQUID RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (uCi/ml) ~~ A. BATCH RELEASE (b)

1. Condensate Prior to Prior to Each Principle Gamina' 5 x 10-7 Polishing Each Batch Batch Emitters (c)

Facility - Waste I-131, Mo-99 1 x 10-6 Neutrali Ce-141yCF144 5 x 10-6, Sump (e)zation

2. Waste Test One Batch per Dissolved and (d) 1 x 10-5 Tanks month Monthly entrained gases

3. Condensate Prior to each Monthly (f, g)

H-3td> 1 x 10-5 Polishing Batch Composite Gross Alpha (d) 1 x 10-7 racility - Regenerate Distillate Task Prior to each Quarterly (f,8) Sr-89(d), 5 x 10-8 4

4. L ow L evel Batch Composite S r-90(d),

1 x 10-6 Waste Drain Fe 35(d). _ Tank B. CONTINUOUS RELEASE l Daily Weekly Principle Gamma 5 x 10-7 l grab sample (1) Composite (8) Emitters (c)

1. Steam Generator 1-131, Mo 1 ic 10-6 Blowdown (h)

Ce-141, Ce-144 5 x 10-6

2. Service Water Monthly Monthly Dissolved and (j) 1 x 10-5 Effluent grab sample entrained gasses l

3. Turbine Building Weekly Monthly H-3 (j) 1 x 10-5 Sumps (h) grali sainple CompositeI )

Gross Alpha (I) 1 x 10-7 8 Weekly arterl Sr-89( Sr-90(j) 5 x 10-8 grab sample pemposi{e(8) Fe-55 1 x 10-6 4

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- w.es - ; -e, v m m. 1/1/86 - b . Rev. 0 tlig TABLE C-3 l +'J (Continued). a ' 8 Table Notations - t. ~*- a. The LLD is the smallest concentration of radioactive material in a sample l. ~ that will be detected with 95% probability, with 5% probability of falsely. concluding' that a blank observation represents a "real" signal. For a particular measurement system (which may include. radiochemical-separation): ~ ~* LLD = 66sb E

• V
• 2.22_ x 106
• Y
• exp (-XAt) where

~' LLD.is the lower limit of detection as defined above (as uCi per unit mass of volume) '1 i sb s the standard deviation of.the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) q E is'the counting efficiency (as counts per transformation) p. jf V is the sample size (in units of mass or volume) 6 s the number of transformation per minute per microcurie 2.22 x 10 i Y is the fractional radiochemical yield (when applicable) J his the radioactive decay constant for the particular radionuclide'- At is the elapsed time between midpoint of ' sample collected and midpoint of counting time It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement. system and not as a posteriori(after the fact) ilmit for a particular measurement. i \\ , Analyses shall be performed in such a manner that the stated LLDs - ,' l will be achieved under routine conditions. Occasionally background l fluctuations, unavoidable small sample sizes, the presence of. interferring nuclides, or other uncontrollable circumstances may, r render these LLDs unachievable. -In such cases, the contributing factors will be identified and recorded on the analysis sheet for.the ' . particular sample. Q _llg ~ ~ t C-9 j

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1/1/86 Rev.0 TABLE C-3 Continued) Table Notations b. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling, each batch shall be isolated and at least two tank / sump volumes shall be recirculated or equivalent mixing provided. The LLD will be 5 x 10-7 uCl/ml. The principal gamma emitters for which,._ c. this LLD applies are exclusively the following radionuclides;, Ma-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, and Cs-137. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and.. reported. Nuclides which are below the LLD for the analyses should'6ot be reported as being present at the LLD level. When unusual circumstances result in a priori LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report. d. For the Condensate Polishing Facility (CPF) - Waste Neutralization Sump, these analyses are only required if the gamma analyses of the CPF - Waste Neutralization Sump indicates a gamma activity greater than 5 x 10-7 uCi/ml. G For the Condensate Polishing Facility - Waste Neutralization Sump, these e. analyses are only required when the steam generator gross activity (sampled and analyzed 3 time.s per week as per. Table 4.7-2) exceeds 1 x 10-5 ) uCi/mL f. 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 which is representative of the liquids released. g. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluents releases. h. For the Steam Generator Blowdown and Turbine Building Sump, analyses are only required when the steam generator gross activity (sampled and analyzed 3 times per week as per Table 4.7-2) exceeds 5 x 10-7 uC1/ml. l. Daily grab sample for the service water shall be taken at least 5 days per ^ week. j. For the Service Water, these analyses are only required if a weekly gamma analyses indicates a gamma activity greater than 5 x 10-7 uCl/mL 9: C-10

.,..w m .. mm. -w : v.= ~ em - v xmme - - .v-3 ' i. 1n 1/1/86-fl Rev. O D. C.2 LIQUID RAL.OACTIVE WASTE TREATMENT-Q 49 ' i '. All applic,able liquid radioactive waste treatment' systems will be operated p when -the projected dose _due to liquid effluents averaged over 31 ' days exceeds 0.06 mrem to the total body or 0.2 mrem to any organ.: s The term all applicable liquid radioactive waste treatment is defined as that equipment applicable to a waste stream responsible for greater than ten percent ( 10%) of -the total projected dose. The liquid rad.ioactlye. waste treatment systems equipment is specified below for each unit. Millstone Unit No.1 Waste concentrator A ce B and Waste Demineralizer A or B. Millstone Unit No. 2 Degasifier, clean liquid primary demineralyzer, boric acid evaporator, clean liquid secondary demineralizer and the aerated waste demineralizer. Millstone Unit No. 3 Degasifier, ion exchanger, boron evaporator, boron demineralizer, waste evaporator or high waste demineralizer. 's t qf With radioactive waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission a report that includes the following inform.ation: 1. Explanation of why ligt'id 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., If the above treatment systems are not routinely operating, doses due to - liquid effluents to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM. u, C-ll ne+-

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. c -.. m. c :.7s -, ::< = 1/1/86 j Rev.0 .) f O. GASEOUS EFFLUENTS SAMPLING AND ANA1.YSIS PROGRAM ,,.4 5 D.1 Radioactive. gaseous wastes shall be sampled and analyzed in accordance with the program specified in Table D-1 for Millstone Unit No.1, Table D-2 for Mi'Istone Unit No. 2, and Table D-3 for Millstone Unit No. 3. The results of the radioactive analyses shall be input to the methodology of the ODCM to assure that the offsite dose rates are maintained within the limits of Technical Specifications 3.3.D.1 for Unit No. I and within the Specifications of 3.11.2.1 for Unit Nos. 2 and 3. hg 4 e P O ~ . 9 5 y i 9 D-1

r. C1 m_ y _... I' O t ks - ll/1/86 av Rev.0-3 4 TABLE D-1 ... S MILLSTONE I 1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM ~1 ower Limit of i Detection (LLD) - Gaseous Release. Type - Sampling Frequency Analysis Frequency Type of Activity Analysis (uCi/cc)a_, 1 Principal Gaseous Gammab 1 x 10-C 1 A. Steam Jet Air Monthlyc - Gaseous Monthlyc Ejec' tor Discharge Grab Sample Emitters 5 .1 4 B. Main Stack Monthly - Gaseous Monthly Principal Gaseous GammaD 1 x 10-9 Grab Sample Emitters '1 H-3 1 x 10-6 1 f Continuousd Weekly Charcoal I-131 1 x 10-12 -j Sample j 3 l-Ig3e 1 x 10-10 I Continuousd - Weekly Particulate Principal Particulateb-1 x 10,-11 ,7 Sample Gamma Emitters Half Lives . l' . Greater Than K Days L Continuousd . Monthly Composite Gross Alpha l,' 1 x 10-11 ,' Particulate Sample.- ~.. Quarterly Composite.- Sr 89, Sr 90'

i 1 x 10-11 Particulate Sample a

Continuousd Nehle Gas Monitor-Noble Gases-Gross Activity. ~ 1 x 10-6 h g a .-_.e .-m= -2.. m O -_mm- ? =0 -- a

~,m.m +w.m. - ~ n - ~ - h' 1; 1/1/86 jj Rev.O _s p~gy TABLE D-1 g TABLE D-1 (Continued) n 4-TABLE NOTATION. D a. The lower limit of detection (LLD) is defined in Table Notation a. of Tables i ] C-1, C-2, or C-3. n b. For gaseous samples, th'e LLD will be 1 x 10-4, uC1/cc and for particulate. - samples, the LLD will be 1 x 10-11 uCi/cc. The principal gamma emitters, for which these LLDs apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe:138 for gase6us emissions and Mn-54, Fe:.59, Co-58, Co-60, Zn-65, Mo-99, Cs-134,.Cs-137, Ce-141, - and Ce-144 for particulate emissions. The. list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified.and-reported. Nuclides which are bul6w the LLD for the analyses should not be reported as being present at the LLD level for that-- nuclide. When unusual circumstances result in g priori LLD's higher than + required, the reasons shall be documented in the Semiannual Radioactive ~ Effluent Release Report. ~ Analyses shall also be performed within 24 hours following an increase, as c. indicated by the steam jet air ejector off-gas monitor, of. greater than 50%, after factoring out increases due to changes in THERMAL POWER-A level. e9 d. The ratio of the sampls flow rate to the sampled stream flow rate shall be known.- . Analyses for I-133 will not be performed on each charcoal sample. I$ stead, e. at least once per month, the ratio of I-133 to I-131 will be determined from ~ a charcoal sample changed after 24 hours of sampling.- This ratio, along with the routine 1-131 activity detertmination will be used to determine the release rate of 1-133. J -1 f. Samples shall be changed -at least once per 7 days and analyses shall be. If completed within 48 hours after changing. Special sampling and analysis of; iodine and particulate filters shall also be performed whenever subsequent i reactor coolant I-131 samples show an increase of greater than a factor of '1 5. These filters shall be changed following such a -five-fold increase' in coolant activity and every 24_ hours thereafter until the reactor coolant I-131 levels are less than a factor of 5 greater than the original coolant - levels or until seven days have passed, _ whichever'is shorter. $ ample - analyses shall be completed within 48 hours of changing. The LLD's may be increased by a factor of 10 for these samples, i e D-3

- + - - 1/1/86 Rev.0 h ~l TABLE D-2 i MILLSTONE 2 f RADIOACTIVE' GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT s MINIMUM TYPE OF DETECTION (A) '. SAMPLING ANALYSIS OF ACTIVITY (LL D) . GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ANAL YSIS-LUCI/CC) - '~ A 9 ATCH RELEASE '~

1. Waste Gas Prior to Each Tank Principal Gamnia 1 x 104 Storage Tank (h)

Each Tank Discharge' Emitters (b) Discharge

2. Containment H-3 1 x 10-6 Purge B.

CONTINUOUS RELEASE Monthly Monthly (c) Principal Gamma 1 x 104 Grab Sample (c) Emittersb Gases H-3(8) 1 x 10-6 Continuous (d) Weekly (f) I-131 1 x 10-12 l _ Charcoal ....I-lM(e) 1 x 10-10 ) Sample Vent Conunuous(d) Weekly (f) Principal Gamma 1 x 10-11 Particulate Emittersb Sample (I-131, others with Half lives 8 days) y Continuous (d) Monthly Gross Alpha 1 x 10'-11 , ~ Composite Particulate Samples t Continuous (d) Quarterly Sr-89, Sr-90 1 x 10-11 ~ Composite Particulate Samples Continuous (d) Noble Gas Noble Gas ~ 1 x 104 Monitor -Gross Activity D4 D -m

n ....-.:.n.. -... ~ -. ~ 1/1/86 Rev.0f t; TABLE D-2 [ (Continued) l~ .J' TABLE NOTATION .~ 3 L I a. The lower limit of detection (LLD) is defined in Table Notation of Tables. ~ C-1,~ C-2, or C-3. ~[ 5 ~ 7 b. For gaseous samples, the LLD will be 1 x 10-4 uCi/cc and.for particulate samples,' the LLD will be 1.x 10-11 uC1/cc. The principal gammagmitters ~ for which these LLD's apply are exclusively the following radionuclidw Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions-and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99;.Cs-134, 'Cs-137, Ce-141, and Ce-144 for particulate emissions. The list does no't mean' that only these nuclides are to be' detected and reported.. Other peaks which are measurable and identifiable, together with the above naclides, shall also'be - identified and reported. Nuclides which 'are below the LLD: for the. analyses should not be reported as being present'aFthe LLD level for that nuclide. When unusual circumstances result in a oriori LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive

I Effluent Release Report.-

Analyses shall also-be performed within 24 hours following an unexplained

l c.

increase, as indicated by the Unit 2 stack noble gasLmonitor, of greater than 50%, after factoring out increases due to changes in THERMAL .{ POWER levels, containment purges, or other explainable increases. I d. The ratio of the sample flow rate to the sampled stream flow rate shall b'e known. Y Analyses for I-133 will not be performed on 2aIh charcoal sarnple. Instead,n ^ e. at least once per month, the ratio of I-133 to I-131 will be determined from a charcoal sample changed after 24 hours of sampling. This ratio, along with the routine I-131 activity detertmination will be used' to determine.; the release rate of I-133. f. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing. Special sampling and analysis of - iodine and particulate filters shall also be performed whenever reactor-coolant I-131 samples, which are taken 2-6 hours following'a THERMAL. POWER change exceeding 15 percent of RATED THERMAL POWER in one" hour show an increase of greater than a factor of 5. 'These filters shall be changed following such a five-fold increase in coolant activity and every 24-- hours thereafter until the reactor coolant-I-131 levels are :less than a . factor of 5 greater than the original coolant levels or until seven days have n s passed, whichever is shorter. Sample analyses shall be completed within 48 hours of changing. The LLD's may be increased by a factor of 10 for these y samples. - / . g. Grab samples for' Tritum_ shall be taken weekly whenever the ' refueling. cavity is flooded and.Oere is fuel in the cavity. The-grab sample shall be L taken from the stack (UA : and 2) where the containment ventilation is - g D-5 O w, 1-Es'~

1

'M

,= :...m :,+ s.c .o , x.w.. I 1/1/86 Rev.0 being discharged at the time of sampling. h. Waste Ga,s Storage Tanks are normally released on a batch basis. However, for the purp6se of tank maintenance, inspection, or reduction of oxygen. concentration, a waste gas tank may be continuously purged with nitrogen provided the following conditions are met: l -(1) The previous batch of ruficactive waste gas has been discharged to a final tank pressure of less than 5 PSIG. (2) No radioactive waste gases have been added to the tank since ths' - previous discharge. (3) Valve lineups are verified to ensure that no radioactive waste gases will be added to the tank. (4). After pressurizing the tank with nitrogen, a sample of the gas in the tank will be taken and analyzed for any residual gamma emitters and tritium prior to initiation of the nitrogen purge. The measured activity will be.used to calculate the amount of activity released during the purge. O } e O 9 9 i I .i 4 e l ~

3 ~

1' 1/1/861 Rev. 0 -

l. TABLE D-3 i[ 4Y MILLSTONE 3 RADIOACTIVE GASEOUS WASTE SA'MPLING AND ANALYSIS PROGRAM ~- P LOWER' LIMIT.. OF DETECTION (A)- MINIMUM SAMPLING ANALYS5 TYPE OF ACTIVITY (LLD). GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (UCI/ML) ~~ A. BATCH RELEASES ~ - Containment Prior to Each Purge Principal Gamma 1 x 104 Purge Each Purge Emitters (b) H-3 1 x 10-6 B. CONTINUOUS RELEASES 1. Unit 3 Monthly (c) Monthly (c) - Principal Gamma 1 x 104 Ventillation Grab samples Emitters (b) Vent Gases H-3(8) 1 x 10-6 4 O, )1, . Engineered Continuous (d) Weekly I-131 1 x 10-12 2. Safeguards Charcoal I-133(e) 1 x 10-10 Building Sample (f) Continuous (d)~ Weekly "bincipalGamnia(b) - I x 10 -11 ' Particulate 1mitters (I-131, Sample (f) others with half lives : 8 days) Continuous (d) Monthly, Gross Alpha 11 x 10-11 Composite. Particulate Samples Continuous (d) Quarterly Sr 89, Sr 90 - 1 x 10-11 Composite Particulate Samples i'ontinuous(d) Noble Gas Noble Gas 1 x 10-6 ~- Monitor Gross radioactivity ) ~ y a

gagg;,4;pqTce.+.u <n 4

r- : -.'

w r-- mM - ~ 1/1/86 Rev.0 TABLE D-3 l (Continued) TABLE NOTATICN a. The lower limit of detection (LLD) is defined in Table Notation of Tables .s C-1, C-2, or C-3. b. For gaseous samples, the LLD will be 1 x 10-4, uCi/cc and for pa_r.ticu.la.te, samples, the LLD will be 1 x 10-11 uCi/cc. The principal gamma emitters for which these LLD's apply are exclusively the following radionuclidesii ~ Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138.for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134; C'-137, Ce-141, s and Ce-144 for particulate emissions. The list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in a priori LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive Effluents Release Report. Analyses shall also be done within 24 hours following an unexplained c. increase, as indicated by the Unit 3 vent noble gas monitor, of greater than 50%, after factoring out increases due to changes in THERMAL POWER levels, containment purges, or other explainable increases.. d. .The' ratio of the sample flow rate to the sampled stream flow rate shall be

known.

Analyses for I-133 will not be performed on each charcoal sample. Instead, e. at least once per month, the ratio of I-133 to I-131 will be determined from a charcoal sample changed after 24 hours of sampling. This ratio, along with the routine I-131 activity detertmination will be used to determine the release rate of I-133. f. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing. Special sampling and analysis.of iodine and particulate filters shall also be performed whenever reactor coolant I-131 samples, which are taken 2-6 hours following a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour,.show an increase of greater than a factor of 5.' These filters shall be changed following such a five-fold increase in coolant activity and every 24 hours thereafter until the reactor coolant 1-131 levels are less than, a factor of 5 greater than the original coolant levels or until seven dys have passed, whichever is shorter. Sample analyses shall be completed s h tin 48 ~ hours cf changing. The LLD's may be increased by a factor of 10.fm these

samples, g.

Grab samples for tritum shall be taken weekly whenever the refueling cavity is flooded and +here is fuel in the cavity. 9 D-8 l

,. n. - . = ~.c-g -e-c ,.....n-c .a

..= n= v

-t .-J i _ j.. -1/1/86-V Rev. 0 : I D.2 ~ GASEOUS RADIOACTIVE WASTE TREATMENT l< :4.48 .All applicable gaseous. radioactive 3 waste treatment systems shall be - '0 z. j~ ? operated 'when the projected dose due to. gaseous effluents averaged over/ 1 31 days exceeds 0.2 mrad for gamma radiation,' O.4 mrad for beta radiation. or 0.3 mrem to any organ due to gaseous particulate effluents. 9 The term all applicable gaseous radioactive treatment is defined as that J equipment applicable to a waste stream responsible for'greatec.than. ten j percent (- 10%) of the total project dose. The gaseous radioactive wast _e - treatment systems equipment is specified below for each Up,it. ~ Millstone Unit No. t I Offgas System - Recombiner Train' A or B. Charcoal Bed Train A or B and the HEPA filter. e Radwaste Ventilation Exhaust Treatment System Radwaste ventilation HEPA filters.. l Milhtone Unit No. 2 Gaseous Radwaste Treatment System - at least'two (2) gas decay tanks, 4 t the waste gas filter and one waste gas compressor; ~ a } ,h Vent $ation Exhaust Treatment System Atixiliary building = ventilation - j HEPA filter (L26), containment purge HEPA filter (L25). l Millstone Unit No. 3 i.

~

Gaseous Radwaste Treatment System - charcoal bed adsorbers, one HEPA-- filter, and one process gas compressor. Building Ventilation - Auxiliary building ventilation filter,Ifuel building ventilation filter, SLCRS filter. 'With_ radioactive gaseous waste being discharged without treatment, and in 2 ] excess of the above limits, prepare and submit to the Commission a report - that includes the following information: 1. Explanation of why gaseous radwaste was being' discharged without i treatment, identification of any inoperable equipment or subsystems,

• 3

'and the reason for the inoperability,. .e 2. Action (s) taken to restore the inoperable equipment to 6PERABLE. status, and, g l 3. - Summary description of action (s) taken to' prevent a recurrence. = -) If the above treatment systems are not routinely operating / doses due to : i 6 ,0 c n-, t l i

( - a-

. p.-.

.c ~ 1/1/86 Rev.0 f gaseous effluents to UNRESTRICTED AREAS shall be projected at least once 'j per 31 days in accordance with the methodology and parameters in the ODCM. .,.i g

s

.i ,e 1 =.

1. g 0

g e G e = 4 q N O 4 + O O 4 e . i. 'a s s E D-10 1

= ~, .z .,; ~. .r.,,.c ~ .-m+ y 1/1/86 j[ Rev. 0 E. RADIOLOGICAL ENVIRONMENTAL M' NITORING O 1; -jf7 E.1 SAMPLING AND ANALYSIS ' q; [ '[ The radio' logical sampling and analyses provide measurements of radiation - and of radioactive materials-in those exposure pathways and for.those radionuclides which lead to the highest potential radiation exposures of t individuals resulting from Plant operation. This monitoring program thereby supplements the ~ radiological effluent. monitoring. program by verifying that the measurable concentrations.of radioactive mater.lais and levels of radiation ~ are not higher than expected on the basis of the effluent ' ~ measurements and modeling of _ the environmental. exposure -' pathways'.- 4 Program changes may be made based on operational exper,ience The sampling and analyses shall be conducted as specified in Table E-1 for ~ the locations shown in Appendix G of the ODCM. (Deviations are permitted from the required sampling schedule if specimens. are unobtainable due to hazardous conditions, ' Maisonal unavailability, malfunction of automatic sampling equipment or other legitimate reasons). 1 If specimens-are unobtainable due to ~ sampling equipment malfunction, { every effort shall be made to complete corrective action prior to the end I of the next sampling periode j All deviations from the sampling schedule. shall be; documented in the . Annual Radiological Enviror. mental Operating Report pursuant to Section F.1. It is recognized that, at times, it.may not be possible or practicable-ll 0 g>f j to continue to obtain samples of the media of choice at the:most-desired location or time. In these instances suitable alternative imedia _ and J j locations may be chosen for the, particular pathway in. question. and -l 4 substitutions made within. 30 days in the..radiologicalJ environmental. monitoring program. In these Instances identify: - the' _ cause 'of. the' unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s). 3 l and table' for the ODCM reflecting the new location (s). l If the level of radioactivity in an environmental sampling medium at one or- ~ i more of the locations specified in Table E-1_ exceeds the report levels of Table E-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30; days from the end.of the affected calendar ~. F quarter, a Special Report which inicudes an evaluation of any: release-j conditions, environmental factors or other aspects which caused the limits 4-of Table E-2 to be exceeded.. When'more than one of the radionuclides in j Table E-2 are detected in the sampling medium, this report shall be .)" submitted if: concentration (1) g concentration (2)+... - > 1.0 ; reporting level (1) reporting level (2)l ~ =a If milk samples are unavailable from any one or more of the milk sample-locations required by. Table E-1, a grass sample shall be substihated until a - suitable milk location is evaluated as a replacement or' until milk-is. . available from the original location.- - Such an occurrence t will ' be documented in the Annual Radiological Environmental Operating Report.- e "s ^ E-1 p b -. ~.., - ,+ m.., err p4 --3r. ,.e.-.h -y,. .-w -...h-- p e- ,,,, = .-,.g ,mm,.. -, y- .-me,..e., -.g. .-.p-

.-wa., -~ ~>- < - . u,.:. m:.v, .x, -n .,n I 1/1/86 j Rev.0 'l 1 s When radionuclides other than those in Table E-2 are detected and are the j result of plant effluents, this Special Report.shall be submitted if the potential, annual dosa to an individual is equal or - greater than the appropriate calendar year limit of the Technical Specifications 3.8.C.2.1, 3 3.8.D.2.1 or 3.8.D.3.1 for Millstone Unit No. ! or 3.11.1.2, 3.11.2.2 or 3.11.2.3 for Millstone Unit Nos. 2 and 3. This report is not required if the l 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. The detection capabilities required by Table E-3 are state,-of.-the-art fof' routine environmental measurements in industrial laborator.ies. It should be recognized that the LLD is defined as an a " priori"'(before the fact) limit representing the capability of a measurement system and n'ot as "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background. fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in ~ the Annual Radiological Environmental Operating Report. 4 9 e 6 h 't l 5 E-2 a

...~s. . n n., ,c .,n -,, ~ _.,,x, .,-,. a _ j q ~ 1/1/86-4 Rev. 0 ) _ q... . q}3.} E.2 - LAND USE CENSUS. The land use census ensures that changes in the.use of unrestricted areas are identified and that modifications to the monitoring program.are made if required by the results of..this census. This : census satisfies the. 4 requirements of Section IV.B.3 of Appendix I to 10 CFR Part.50. The land use census shall be maintained and shall identify the location of the milk 4 animals in each of the 16 meteorological sectors within a distance of five miles.* The validity of the land use census shall be verifled at least 'once per 12-inonths by either a door-to-door survey, aerial. survey, c'onsulting local agriculture authorities, or any combination of these methods.* With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the doses currently being calculated In the ODCM, make the appropriate changes in the sample locations of l Table E-2. With a land use census identifying a location (s) which has a higher D/Q than a current indicator location the following shall apply: (!)- If the D/Q is at levt 20% greater than the previously highest D/Q, replace one of the present sample locations with the new one within' /) 30 days if milk is available. m ,D O' (2) If the D/Q is not 20% greater ti.an the previously highest D/Q,- consider both ' direction, distance, availability of milk,' and D/Q in 1 deciding whether to replace one of the existing sampie locations. If. applicable, replacement should be withl'"30 days. If no replacement-n is made, sufficient justification should be given in the annual report.' Sample location changes shall be noted in the Annual. Radiological Environmental Operating Report.

• Broad leaf vegetation (a composite of at least 3 different types of vegetation) is sampled at the site boundary in each of 2 different direction sectors with relatively high D/Q's in lieu of a garden census.

0 .s 4 E-3 3 v. Y y-w> c-

- g. m.7,,,. w. e g g p ;r. w. m. ~7, .e.% ,v.- a ~ 1/1/86 ] Rev.0 J i E.3 INTERLABORATORY COMPARISON PROGRAM a f The Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of q radioactive material in environmental sample matrices are performed as -] part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reaserably valid. hnalyses shall be performed on radioactive materials supplied as pyt_o.f an i Interlaboratory Comparison Program which has been approved by the Commission. A summary of the results obtained as part of the above~ required Interlaboratory Comparison Program shall be incidded in the Annual Radiological Environmental Operating Report. 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. O 1 + + 9 9 8 5 i 'i e O e4 e

..y~., ,.,r.. -.~ - 1/1/86 i Rev. 0 1, 5 ?q TABLE E-1 2 ^ 1- .6 l -j' MILLSTONE _ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..= r Sampling and ..., N l Exposure Pathway Number of Collection 4- [ and/or Sample Locations Frecuency. Tvoe and Frecuency of Analysis. 1.. l a. Gamma Dose - 17 Monthly. Gamma Dose - Monthly. 1; Environmetal TLD - N'/A[a) * - Ib. Gamma Dose - 22 Quarterly (a). Accident TLD 2. Airborne 8 Continuous Gr'oss Beta - Weekly, y ) Particulate sampler - . Gamma Spectrum - Monthly on weekly filter composita (by. location), and change on individual sample if gross ) i beta is greater than 10 times .i the mean of the weekly cqntrol station's gross beta results.' i 1 i i 3. Airborne 8 Continuous I-131 - Weekly ) i j Iodine sampler - l weekly canister 4,3 j change 4. Vegetation 5 . One sampff - Gamma isotopic on each - near middle rample and one near. end of growing season 4 4 5. Milk 6 Monthly for Gamma isotopic,1-131, Sr-89 all animals and Sr-90 on each sample except semi-monthly for goats when on pasture 6. Sea Water 2 Quarterly - Quarterly - Fractional Beta, j ' Composite of. Gamma Isotopic and Tritium -- 6 Weekly Grab . on each composite 4 ,. samples 1 j 7. Bottom 7 Semlannual Gamma' Isotopic on Each 3 - Sediment Sample y 1 ,w t A e s E-3 i

,g . #.e. m. - s i' 1/1/86 Rev.O TABLE E-1 (Continued) ] .l MILLSTONE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .l Sampling and Exposure Pathway Number of Collection and/or Sample Locations Frecuency Type and Frecuency of Analysis 8. Fin Fish-Flounder 2 Quarterly Gam'rila I'sotopic on Each and one other type Sa61ple of edible fin fish 9. Mussies 2 Quarterly Gamma Isotopic on Each - ; Sample 10. Oysters 4 Quarterly Gamma Isotopic on Each Sample 11. Clams 2 Quarterly Gamma Isotopic on Each Sample 12. Lobster 3 Quarterly Gamma Isotopic on Each Sample h (11) Accident monitoring TLDs to be dedosed at least quarterly. .~ ~ I I O' E-6

t j; 1/1/86 Rev.0 'l ; '). TABLE E-2

j. 49

] -

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES

• s 5

REPORTING LEVELS m J Airborne Particulate or Fish Milk Veg'etables Anaivsis Water (pCi/1) Gases (pCi/m31 (pCl/Kg, wet) (pC1/l) (pCi/Kg, w6t) H-3 2 x 10 (a) 4 Mn-54 1 x 103 3 x 104 Fe-59 4 x 102 1 x 100-- Co-58 1 x 103 3 x 104 Co-60 3 x 102 1 x 104 Zn-65 3 x 102 2 x 104 [ I.131 (b) 0.9 3 1 x 102 ) 's/ ,,j! Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2 x.103 70 2 x 103 Ba-140 2 x 102 3 x 102 La-140 2 x 102 3 x 102 Zr-95 4 x 102 Nb-95 4 x 102 i (a) For drinking water samples. This is 40 CFR Part 141 value. (b) Level for I-131 not included since no radioactivity discharged to any drinking water pathways; other reporting levels are included for trending of long lived isotopes only. 6 e# 3 g' l [v) +.. E-7

,. - :.: +. :x...;=.. 1/1/86 Rev.0 Table E-3 MAXIMUM VALUES FOR LOWER LIMITS OF DETECTION (LLD)a AIRBORNE PARTICULATE WATER Olt GAS FISil, SilELLFISil MILK FOOD PRODUCTS SEDIMENT ANALYSIS '(pCi/l) (pCi/ndL (pCi/Kg, WET) (pCi/l) (pCi/Kg, WET) (pCi/Kg, DRY) Gross beta ! x 10-2 Factional beta 4 s 11-3 2000 4 Mn-54 30c I30* Fe-59 60C 260 Ig Co-58, 60 30c g30 Zn-65 60c 260 0 L Zr-95 60c Nb-95 30c l 2 1-131 d' 7 x 10-2 g 6db Cs-134 30c 5 x go-2 ,130 15 i) 60 150 i Cs-137 40C 6 x 10-2 150 18-80 180 .1 Be-140. 120C,e 70 Lt-140 30C, e 25 E-8 ~

wm-~xw ~.w w m y = m,- r.t.<: m -ww.m.wm mae=; m g. e.,.x, m.y r

1/1/86 C:j

) Rev.O i b TABLE NOTATION h [. t c a. The LLD is the smallest concentration of radioactive materialin a sample. that will be detected with 95% probability with a 5% probability of falsely; concluding that a blank observation represents a "real" sign'a!.. / For a particular measurement system (which may include ' radiochemical separation). ~ 4.66 sb ,LLD= ~a E

• V
• 2.22
• Y *' exp (-hat) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)'

VJ./. i sb s the standard deviation of the background counting rate or of the counting rate of a blank sample e.s appropriate (as counts per minute) E is the counting efficiency (as counts per transformation) ~ V is the sample size (in units of mass or volume) ~ 2.22 is the number of transformation per minute per picocurie n# Y is the fractional radiochemical yield (when applicable) X is the radioactive decay constant for~tfie particular radionuclide - At is the elapsed time ~ between sample. collectionL(or end of the sample collection period) and time of counting 1 -i j lt should be recognized that the LLD l's defined as a oriori (before the fact) limit representing the capability.of a measurement system and not as a. oosteriori (after the fact) limit for a particulate measurement'. - I Analyses shall be performed in such a manner that the stated LLDs will be ' achieved under routine conditions.. Occasionally background fluctuations, 4 5 j unavoidably small sample' sizes, the presence of interfering-nuclides, or i other uncontrollable circumstances may - render: these.'a. oriori LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report. + 1 .j j b. LLD for leafy vegetables. 2 i To be reduced'by a factor of two if the fractional beta for' the sample L i c. 3 exceeds 15 pCi/1. 6 .c y ~ .i j ' E -9 ' 'l -i, a r -~ + ~ m v-

,g:,u ... _vn.., -..... - -,:.. m,,.- n u ,,;,,,a 1/1/86 Rev.0 d. Level for I-131 not included since no radioactivity discharged to any drinking water pathway. i e. From end'of sample period. 1 ~- t

1. g e

D. O 6 1 i 9 ) e G e e O 9 4 E-10 + 4

m a m.,.,.e,.-.. .m. - mm. ,,,.,m w e - n.nm..pe.- c. ~ >p 3 ?1/l/86- . h.. Rev.' O . fy x ' ' :2 i ' F. ~ REPORT CONTENT' g 1, i. F.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL' OPERATING REPORT Y 1 t :. ,i

The Annual Radiofogical Environmental.. Operating Reports shall include.

. summaries,' interpretations, and statistical evaluation of the,results of the'- N

,9

' radiological environmental surveillance.' activities for the report period,'. D including a comparison with previous environmental surveillance reports ' c L . and an assessment of the observed. impacts of the plant operation.on the. o environment. The reports shall also include the results of:the land:use: L, census required by' Section-E.2 of this = manual.1 If harmful effects <are' f . detected - by -- the. monitoring, the. report 'shall pr. ovide.an ' analysis of the problem and a planned course of action to alleviate the pr'oblem. w ...~ The report shall include a summary table of all radiological environmental samples which shall include the following inforriation for each pathway 4 { sampled and each type of analysis: - ~ (1) Total number of analyses performed at indicator locations. (2) Total number of analyses performed at control locations. (3) Lower limit of detection (LLD). = '(4)~ Mean and range of'all indicator locations together.. o ,j,j (5) Mean and range of all control locations together. - (6) Narae, distance and direction from. discharge, mean and range for the-location with the highest annual mean (ldicator or contfol). n (7) Number of nonroutine reported. measurements -as defined in~ these specifications. l In the event that some results are not available for Lindlusion' 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.- ' ~ ;

• A The report shall also include a map di sampling locations keyed to;a table t

giving distances and directions from the discharge; the report shall also - include a 'summarytof ~ the Interlaboratory Comparison' Data required byL Section E.3 of this Manual. ' ~ -~ .s. r 1) N y> O' v-4 "g8 ~ + -F-lE ] A 1 4 m ~i

, apW ss m: v:3 : w w y,s A. = - - - - - - - - - - - - - - - - - .~ ~ s 1/1/86 Rev.O i: F.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT j The Semiannual Radioactive Effluent Release. Report shall include a ~ j summary 'of' the quantities of radioactive liquid and gaseous effluents released fro'm the unit as outlined in Regulatory Guide 1.21, Revision 1, g June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. In addition, a supplemental report to be submitted 90 days after January,1 of each year shallinclude an annual summary of hourly meteorologIEardata ' collected over the previous year. This annual summary may be either in the form of an hour-by-hour li' sting on magnetic tape pr in th'e form,of joint frequency distributions of wind speed, wind direction,*.and atmospheric stability.** This same report shall include an assessment of the radiatiori doses due to the radioactive liquid and gaseous effluents released from the site during the previous calendar year..The meteorological conditions concurrent with the time of release of radioactive. material in gaseous effluents shall be used for determining the gaseous pathway doses. Dose calculations shall be performed in accordance with the Offsite Dose Calculation Manual In addition, the report to be submitted 90 days after January 1 of each year shall include an assessment of radiation doses to the likely most exposed REAL MEMBER OF THE PUBLIC from the site for the previous 12 consecutive months to show conformance with 40 CFR 190. Doses shall be calculated in acco'rdance with the Offsite Dose Calculation Manual. The semiannual effluedt report-shall also include a summary of each type of solid radioactive waste shipped offsite for burial or final disposal during j the report period. This surnmary shall incidds the following, inforgiation for each type of waste: Type of waste (e.g., spent resin, compacted dry waste, irradiated a. components, etc.). b. Solidification agent (e.g., cement). c. Total curies. d. Total volume and typical container volumes. Principal radionuclides (those greater than 10% of total activity). e. f. Types of containers used (e.g., LSA, Type.A, etc.). The semiannual effluent report shall include the following information for all unplanned releases from the site to. unrestricted areas of radioactive materials in gaseous'and liquid effluents: A description of the event and equipment involved. a. F-2 l t I. =-

. /,:.ej.7 ?. u.. ...;qe :e;;: ~ + - -.-,- y u.:;,, o. x w o i 1/1/86 ji~ Rev.O 1lQ n 4 b. Cause(s) for the unplanned release. -j. n& li c. Actions taken to prevent recurrence.. c. 3' ,e d. Consequences of the unplanned release. + ~ Any changes to the RADIOLOGICAL EFFLUENT and OFFSITE DOSE CALCULATION MANUAL and Process Control Program shall be submitted 'i in the Semiannual Radioactive Effluent Release Report. In lieu of submission w'ith the Radioactive Effluent- {1,elease RepoEt, ~ ~ the licensee has the option of retaining this sumniary' of required meteorological data onsite in a file that shall be provided, to the NRC upon request. 4 e e 9 e** e h i E o .:a 1 \\ i 4 0 I,. s ^ ta, Vo i F-3 +,. 1 i n-,, ,-~,? ,,.,-n $l-w e a

i <..ga., ct.;;e-my:n...:,:co. n. :- .,c.:2,,>.~s.v 4.,e.s;:,. ;; c u :. e :.- :... -g w.;;ww ; - y w r.m a.. .o n. SECTION II- 'OFFSITE DOSE bALCULATION MANUAL' FOR.THE MILLSTONE NUCLEAR POWER STATION. UNITS 1,2 and 3 DOCKETS: No. 50-245 No. 50-336 No. 50-423 f O r 1 s March.1986 - Revision 1 l

-a yasc;2 dW M5,i w m W x 5- ~ ",;u

a. w ::- w Y-a w m - :^ x w w ' v -9:c w w n:-- e c w w ;F x? :c? w s

r~ 1/1/86 1: Rev. 0 - &ji 8 ' OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS ).! ~ .j. Section - Page No. Rev.No. Date 7. 1/1/86 { A. Introduction A 0 B. Responsibilities B-1 0 - -,, , 1/1/86 C. Liquid Dose Calculations '~ 1, C1. Quarterly - Total Body Dose a. Method 1 - Any Unit C 0 1/1/86 0 1/1/86' b. Method 2 - Any Unit C-2 C2. Quarterly - Maximum Organ Dose a. Method 1 - Any Unit C-3 0 1/1/86-b. Method 2 - Any Unit' C-4 0 1/1/86 C3. Annual - Total Body Dose C-5 0 1/1/86 g C4. Annual _ Maxi, mum Organ Dose ' C-6 0 I/1/86 1 't j/! C5. Monthly Dose Projections, a. Unit 1 C. 0- '1/1/S6 b. Unit 2 and Unit 3~~ CT 0 1/1/86' C6. Quarterly Dose Calculations for Semi-Annual Radioactive Effluent - Report C-9 0 1/1/86 O. Gaseous Dose Calculations DI. 10CFR20 Limits (" Instantaneous") a. Noble Gases - All Units D 0 1/1/86-b. Iodines, Particulates and ~0-- 1/1/86 - Other - All Units D-2 D2. Appendix !. Noble Gas Limits 'd 1/1/86 a. Quarterly Air Dose. Method 1 D-3 0. 'i-All Units 7 b.- Quarterly Air Dose. Method 2 D-4 O. =1/1/86 l All Units-J

c. - Annual Air Dose - All Units -

D-5 'O 1/1/86 .e T of CI: n- -g .s e

. mv ..e-y m - w ~-

w. =,

7,. a. _ . w.spig;- ? 1/1/86 Rev.O OFFSITE DOSE CALCULATION MANUAL ] TABLE OF CONTENTS (Cont'd) ,) Section Page No. Rev.No. Date D3. Appendix I - Iodine and Particulate Doses ~ ~ - " ' a. Quarterly Doses - Unit i D-6 0 1*/1/86 ' b. Quarterly Doses - Unit 2 and Unit 3 D-7 " 0' 1/1/86 ~ D-8

c. - Annual Doses - All Units D-9 0

'l/1/86 D4. Gaseous Effluent M'onthly Dose Projections a. Unit 1 D-10 0 '1/1/86 D-11 0 1/1/86 b. Unit 2 D-12 0 1/1/86 c. Unit 3 D-13 0 1/1/86 D5. Quarterly Dose Calculations for Ser,ni-Annual Report D-14 0 1/1/86 D6. Compliance with 40CFR190 D-15 0 1/1/86 E. Liquid Monitor Setpoint Calculations 4 E 1. Unit 1 Liquid Radwaste Effluent ~ Line E-1 0 1/1/86 E2. Unit 1 Service Water Effluent E-2 0 1/1/86 Line E3, Unit 2 Clean Liquid Radwaste Effluent Line E-3 0 1/1/86 E4. Unit 2 Aerated Liquid Radwaste Effluent Line and CPF - Waste Neut. Sump Effluent Line E-4 0 1/1/86 E5. Unit 2 Steam Generator Blowdown E-3 .0 1/1/86 E6. Unit 2 Condenser Air Ejector E-6 0 1/1/86-E7. Unit 2 Re'act'or Building Closed Cooling Water E-7 0. 1/1/86 9~ T of C2

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- v mn - a=:c;"=" i ~ s ~ ,1 3/18/86 Rev.1 OFFSITE DOSE CALCULATION MANUAL : Ci TABLE OF CONTENTS (Cont'd) Section Page No. Rev.No. Date. E8. Unit 3 Liquid Waste Effluent Line E-8 1 3/18/861 E9. Unit 3 Regenerant Evaporator Effluent Line E-9 0 1/1/86 E10. Unit 3 Waste. Neutralization Sump' E-10 O 1/1/86 Effluent Line ' Ell.. Unit 3 Steam Generator Blowdown E-11 0 1/1/86-E12. Unit 3 Turbine Building Floor Drains Effluent Line E-12 0- '1/1/86 ,t F. Gaseous - Monitor Setpoint Calculations F 0 1/1/86 F1. Unit 1 Hydrogen Monitor F-1 0 1/1/86 F2. Unit 1 Steam Jet Air Ejector Off Gas Monitor F-2_ .0 '1/1/86: ) F3. Unit 1 Main Stack Noble Gas Monitor F-3 0 '1/1/86. F4. Unit 1 Main Stack Sampler Flow Rate Monitor F-4 0 1/1/86 F5. Unit 2 Vent Noble Gas Monitor . F-5 0 1/1/86 F6. Unit 2 Waste Gas Decay Tank Monitor F-6 0 1/1/86-1 F7. Unit 3 Vent Noble Gas Monitor F-7 10 -1/1/86. F8. Unit 3 Engineering Safeguards Building Monitor .F-8 0 -1/1/86: . G.. Effluent Flow Diagrams G-1

0 1/1/86c l

O> T of C3 :

l

- c. <, ~. - - n 4 1/1/86 Rev.O LIST OF FIGURES Figure Name Figure Number' Rev.No. Date G-1 MP1 Liquid Radwaste Flow Diagram 0 Ul/86 G-2 MP2 Liquid Radwaste Flow Diagram 0 1/1/86 G-3 MP3 Liquid Radwaste Flow Diagram 0 1/1/86 ~~ ^ G4 MP1 Gaseous Radwaste FlowDiagram" O 1/1/86 G-5 MP2 Gaseous Radwaste Flow Diagram 0 '!/1/86 G-6 MP3 Gaseous Radwaste Flow Diagram 0 1/1/86-O O o G b e 9 e 4 9 T 'of C4

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e. n..

,,.:..w;,..m .~,-, -=.g. 1/1/86 1 ll Rev.O j APPENDICES

• • j p

j h vl$9 t i Rev. No. Date Appx, A - Derivation of Factori for Section 0 1/1/86 C.1 - Liquid Doses Appx. B - Derivation of Factors for Section C.2 -Liquid Doses 0 .,l/1/86 0 1/1/36' Appx. C - Liquid Dose Calculations - LADTAP Appx. D - Derivation of Factors for Section D - Gaseous Doses 0 1/1/36 0 1/1/36 Appx. E - Gaseous Dose Calculations - GASPAR Appx. F - Gaseouos Dose Calculations - AIREM 0 1/1/86 Appx. G - Environmental Monitoring Program Sampling 0 1/1/86 - Locations Appx. H - Methods for Calculating Releases from Unit 3 0 1/1/86 "Unmonitored" Releases m I )\\ (. ,g c O L:, (V T of C5

. w. w & g ; & E ; % M ;p, p m e g t.w w w w.s. =cy m u y y.t zw: mawaur. > >: m ' = m n.. - - _ 1/1/86-- ~ ' i? Rev.'O 3>U; A. INTRODUCTION ![ Vdr e u The purpose ol this manual is to provide the parameters'and methodology to be. ~ used in calculating offsite doses and effluent monitor setpoints at the' Millstone. Nuclear Power Station. - Included are :methodsJ for determining maximum ' individual whole body and organ l doses due -to liquid and gaseous. effluents to : assure compliance with the dose limitations in the Technical: Specifications. Also included are methods-for performing dose projections to assure cp.cnpliance: with the liquid and gaseous treatment system -operability sections ~of-the ~ Radiological Effluent Monitoring Manual. The manual also includes the methods- ~ used for determining quarterly individual-and population doses for. inclusion in.- the Semiannual Radioactive Effluents Release Report. Another:section of this discusses the methodology 'to be used in determining = effluent monitor alarm / trip setpoints to be used to ensure compliance with.the instantaneous release rate limits in the Technical Specifications. Th' basis for some of the factors in this. manual are included as appendices to e this manual. This manual does not include the surveillance procedures and forms required to - document com Specifications. pliance with the surveillance _ requirements iin the Technical. All that is included here is the methodology:to be used :in performance of the surveillance requirements. 4 Most of the calculations in this manual have two or three methods given for the. M', calculation of the. same parameter. These methods.are arranged in order of ~ simplicity and conservatism, Method l being the easi.est and most conservative. - As long as releases remain low, one should be able tu 'se Method 1 as a, simple u estimate of the dose. If release calculations approach the ' limit however,'more - detailed yet less conservative calculations may be used. At any time a more detailed calculation may be used in lieu of a simple calculation. This manual is written common to all three units since some release pathways are shared and there are also site release limits invovled.. These facts make it impossible to completely separate the three units. b 6 ,j i O q_ r A-1 ~ Y

--1

.a v g; m ;. m. w 1.c::a ? w a mo ;

5 1/1/86 Rev.O c d B. RESPONSIBILITIES All changes to' this manual shall be reviewed by the Site Operations Review t Committee prior to implementation. All changes and their rationale shall be documented in the Semiannual Radioactive Effluent Release Report. It shall be the responsibility of the Station Superintendent to ensure Isa~t"this

• manual is used in performance of the surveillance requirements specified in th6 Technical Specifications.

e 0

• • %=

6 O j e 0 I S 9 4 e 8 O B-1 I

-m9n-a ej.; mms.m.w.wn:?.= + -.g,.= :gn n r: a:. ,. -. w- - m - n 1/1/86- - Rev.' O. b 3 C. LIQUID DOSE CALCULATIONS . C.1 - Quarterly - Total Body Dose C.I.a Method 1 - Any Unit 5,tep ), - Determine CF = total gross curies of fission and activation.pr,oducts excluding. tritium and dissolved noble gases, : released ' durmg the, ^ calendar quarter. Steo 2 - Determine CT = total curies of tritium released du' ring the calendar quarter. l Steo 3 - Determine DQT = quarterly dose to the total body in mrem. - l DQT = 1.9 x 10-2

• CFf 5.6 x 10-7
• CT (See Note 1)

Steo 4 - If DQT is greater than 0.5 mrem, go to Method.2. (Note 1)-See Appendix A for derivation of these factors. h w,, -){i' ..+. 4 l l I I e

• O e

e e-I e e

• e

, 9, .i . C-1 i i 1 i j

a s.. , +..: v 1/1/86 Rev.O C.I.b Method 2 - Any Unit If the calculated dose using Method 1 is gr. eater than 0.5 mrem, use the NRC computer code LADTAP to calculate the liquid doses. The e use of this code and the input parameters are given in Radiological Assessment Branch Procedure RAB 4-3, Liquid Dose Calculations - LA DTAP. g ese eem e, e t. O ) e G e t 0 l g i l C-2 l

• 4e

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.r.,- ., ~. - - - . w..y. m j 1/1/86 Rev.O d 2'/ C.2 Cuarteriv - Maximum Organ Dose s i .a3 C.2.a Method 1 - Any Unit 5 ? Step 1 - Determine CF = total gross curies of fission and activation products, excluding tritium and dissolved noble gases, released during the + 2 calendar quarter - same as Step C.I.a. 5-Step 2 - Determine D o = quarterly dose to the maximum organ in mrg!p. Q ~~ D o = 0.2 CF (See Appendix B for derivation of factor.}, '~ Q Step 3 - If D o is greater than 2 mrem, go to Method 2. Q 9e. O e 0 .,. rl

• e O

e 1 6 e 9 6 k_ 4 C-3

.;a.g -, -ww.- y: ;r . - c +-..~:. w, - 1/1/86 l Rev.O I C.2.b Method 2 - Any Unit } If the calculated dose using Method 1 is greater than 2 mrem, use the . 2

l NRC'coinputer code LADTAP to calculate the liquid doses. The use of this code, and the input parameters are given in Radiological Assessment Branch Procedure RAB 4-3, Liquid Dose Calculations -

LADTAP. 0-g eB & -g a g D 4 9

• • G e

m O 4 0 ) e D e 4 /. O O

• I C-4 t

l l t

s.-k;ss.=4u:ess.= &:.v ~a-.yqv.+wsc ax.pyn:,5mnam:.ymw wun. ::, m.;;. ~ :~; s:. 1/1/86 l Rev.0- ~ 1'. . r. t 'D P C.3 Annual - Total Body Dose - Any Unit l J', I Determine DyT = dose to the total body for the calendar year as follows: DYT = .. dot. where the sum is over the first quarter through the present-quarter total body doses. ~ The following should be used as DQT* (1) If the detailed quarterly dose calculations required per Section C.6 for the semlannual effluent report are complete for any calendar quarter,' use that~ result. (2) If the detailed calculations are not complete for a particular' quarter, use the results as determined in Section C.1,. (3) If DYT is greater than 3 mrem and any D T dethrn'ilned as in Section C.1 Q was not calculated using Method 2 of that section, recalculate DQT using Method 2 If this could reduce DYT to less than 3 mrem. O b 1 ~i # m e 4 e G e e D 6 0 .c l C-5

.e n. .~ l 1/1/86 Rev.O i C.4 Annual-Maximum Organ Dose - Any Unit I Determine Dyg = dose to the maximum organ for the calendar year as follows: m Dyo = [DQO where the sum is over the first quarter through the present quarter maximum organ doses. The following guidelines should be used: (1) If the detailed quarterly dose calculations required per Section C.ifEr~ the,' "~ semiannual effluent report are complete for any calendar gyarter, use that result. (2). If the detailed calculations are not complete for a particular quarter, use the results as determined in Section C.2. (3) If different organs are the maximum for differerif du~arters, they may be summed together and Dyo can be recorded as a less than value as long as the value is less than 10 mrem. (4) If Dyo is greater than 10 mrem and any value used in its determination was calculated as in Section C.2 but not with Method 2, recalculate that value using Method 2 if this could reduce Dyo to less than 10 mrem. G ) 6 4 4 C-6 u

v u.,, ~.pr w m m,ww-v w< w m; ./

8. - m

.t [ 1/1/86 j: Rev.0 V C.5 Monthly Dese Projections j '<NN q C.5.a Total Body & Maximum Organ - Unit 1 4 Steo 1 - Determine O'MT = total body dose from the last typical

• previously,

completed month as calculated per the methods in Section C.I. Steo 2 - Determine D'Mo = maximum organ dose from the last typical

• previously completed month as calculated per the methodsin 5, ection C.I.

Steo 3 - Estimate R1 = ratio of the total estimated.volump df liquid batches to be released in the present month to the volumb. released in the past month. E' stimate R ' = ratio of estimated primary coolant activity for the Steo 4 - 2 present month to that for the past month Steo 5 - Determine F = factor to be applied to estimate ratio of final curie released if there are expected differences in-treatment of liquid waste for the present month as opposed to the past month,(e.g., bypass of filters or demineralizers). NUREG-0016 or past expertence should be used to determine the effect of each form of treatment which will vary. F = 1 if there are no expected differences. Steo 6 - Determine D$1T = estimated monthly total body dose as follows: ~Y F D MT = D'MT

• R1*R2*F Determine D$10 = estidiated month'ly mImum organ dose as follows:

Steo 7 - D$to = D'MO + R1*R2*F The last typical month should be one without significant operational differences from the projected month. For example, if the plant was down for refueling the entire month of February and startup is scheduled for March 3, use the last month of operation as the base month to estimate March's dose. Or, if there were no releases during September, do not use September as the base month for October if it is estimated that there will be releases in October. 3 s s f I C-7 e S h

3 ~ 1/1/86 Rev. 0 i C.5.6 Total Body & Maximum Organ - Unit 2 and Unit 3 Steo 1 - Determine D'MT = total body dose from the last typical

• previously

" ~ conipleted month as calculated per the method in Section C.I. a Step 2 - Determine D'Mo = maximum organ dose from the last typical + previously completed month as calculated per the methods in Section C.2. ~ ~ ~ ~ '

• - See footnote in Section C.5.a.

Steo 3 - Estimate Rt = ratio of the total estimated. volume of fliquid batchis~ to be released in the present month to the volunie r%1 eased in the past month. Steo 4 - Estimate R2= ratio of the total estimated volume of steam generator blowdown to be released in present' month to the volume released in the past month. Steo 5 - Estimate F1 = fraction of cuties released last month coming from steam generator blowdown. i.e. F a curies from blo' down 1 w curies from blowdown + curies from batch tanks Steo 6 - Estimate R3 = ratio of estimated secondary coolant activity for the present month to that for the past month. Steo 7 - Estimate R4 = ratio of estimated primary coolant activity for the } present month to that for the past month. Steo 8 - Determine F2 = factor to be applied to estimate ratio of final curie released if tr.ere are expected differences in treatment of liquid waste for the present month as opposed to the past month (e.g., bypass of filters or demineralizers). NUREG-0017 or past experience should be used to determine the effect of each form of treatment which will vary. F2 = 1 if there are no expected differences. Steo 9 - Determine D$ti estimated rnonthly total body dose as followsi D$1T = D'MT (1 - F ) Rt R4 F+F1 R2 R3 t 2 Steo 10 - Determine D$to = estimated monthly maximum organ dose as follows: d -F ) Rg R4 D$to = D'MO F+FR2 R3 t 2 1 C-8 1

y ::: n., - =- . + ;.n.

.;- - c u.s 5;.y:; gu:n ~.,;;;.;;e.y.~.:+ c;..v.a;;.;.;s ~ : -:- :

~ 1/1/86 i Rev. 0

• I s

et b C.6. Quarter!v Dose Calculations for Semlannual Radioactive Effluent Report ' a .;ey). t

j Detailed quarterly dose. calculations required for 'the Semiannual Radioactive

[ Effluent Report shall be done using _the NRC computer code LADTAP. The use I i of this code,'and the input parameters are given -In Radiological Assessment. Branch Procedure RAB 4-3, Liquid Dose Calculations - LADTAP. i 3 4 0 l 4 I ? 'l i i j. I 7, se,'oI ( 9 =. L 4 e i E-i' t I 1 3 .i 1 s e i e l f f ? 1 ) i f 8 } a I 4 =I -j C-9 4 + ~,--3-,- -,m..4 y.-,#,. +,y__, ,,-,._,---~3,-y 3 -,,,,, -, ,-ry,, ,ym., -ep,g,yr.--,,.,,,.,,,,,.-y.. ..,y,.c,,- .---,.,-,-,-vm

c. .e,.- m, c - 4e A 1/1/86 j Rev.O A D. CASEOUS DOSE CALCUL ATIONS I D.1 10CFR20 Limits (" Instantaneous") D.I.a Instantaneous Noble Gas Release Rate Limits - All Units The instantaneous noble gas release rate limit from the site shall ber 91_ 01__ 4 1 G + + 790;000 217;000 217;000 ~ where Q1 = Noble gas release rate from MP1 stack (uC1/sec) Q2 = Noble gas release rate from MP2 vent (uCl/sec) Q3 - Noble gas release rate from MP3 ve'nt (uCl/sec) See Appendix D for deviation of this limit. As long as the above is less than or equal to 1, the doses will be less than or equal to 500 mrem to the total body and less than 3000 mrem to the skin. t 9 ) e G I .O O e 6 e e a 9 9 D-1

m r,i;+9myw.m 22.mawenm new.ggs w nntagwwtmmmmg w ppm "~- ,~ ,r ....a-f 1/1/86 J -Rev.0 . p. ( ~ ^}*~ D.1.b Release Rate Limit -I-131. Particulates With Half Lives p 3 Greater than 8 Days, and Radionuclides Other Than Noble

• I Gases With Half Lives Greater Than 8 Days - All Units l

(1) The release rate limit of I-131 and tritium from the site shall be: y .'.. ^ i i-Q11 QI2 Q13 QT1 QT2 QT3 i + + + + + - d I where, 6.26 0.49 0.49 9.1x105 4.0x104 4.0x104 j .i i l Qgt = Release of I-131 from MP1 Stack -(uC1/ sed -

• l

? ? j 'QI2 = Release rate of I-131 from MP2 Vent -(uCl/sec)* 1 i j Qg3 = Release rate of I-131 from MP3 Vent -(uC1/sec) i i-j QT1 = Release rate of tritium from MP1 Stack -.(uCl/ sac) I i l QT2 = Release rate of tritium from MP2 Vent -(uC1/sec)*- 1 i_ QT3 = Release rate of tritium from MP3 Vent -(uCl/sec) j j (2) The release rate limit for particulates with half lives greater than 3 days, and tritium from the s'lte shall bet i S Q1 Q2 Q3 QT! QT2 QT3 + + '+ + + i n 1 where, j 35 4.2 2.1 9.1x105 4.0x104 4.0x104 i Qt = Release rate of total particulates with half lives greater than'8 days j from the MP1 Stack (uC1/sec). q i i { Q2 = Release rate of total particulates with half lives greater than 8 days. } } from the MP2 Vent (uC1/sec). 1 Q3 = Release rate of total particulates with half Ilves greater than.3 days from the MP3 Vent (uC1/sec). i QT!

• Release rate of tritium from MP1 Stack -(uC1/sec) i i

QT2 = Release rate of tritium from MP2 Vent -(uC1/sec)* QT = Release rate of tritium from MP3 Vent -(uC1/sec) 3 1 J l With releases within the above limits, the does rate to the maximum organ t will be less thari 1300 mrem / year. ) 'i i n [ E, ' Includes releases via the steam generator blowdown tank vent.- h 0-2 y i h i'

) 1/1/36 Rev.0 D.2 Appendix 1 Noble Gas Limits j D.2.a Quarterly Air

• Dose - Method 1 - All Units q

j Steo 1 - Determine CN1 = Total curies of noble gas released from Unit 1 i during the calendar quarter. 1 Steo 2 - Determine CN2 = Total curies of noble gas released from Unit 2 during the calendar quarter. Include all sources - ventilation,. containment purges, and waste gas tanks. as releaied irom Unit 3 Steo 3 - Determine C = Total curies of noble kt sourc'es - ventilation, during the c endar quarter. Include a containment vacuum system, gaseous radwaste system, main condenser evacuation system, and turbine gland sealing system.(for the latter two systems, see Appendix H for methods to determine the number of curies). Steo 4 - Determine Dqct = quarterly gamma air dose from Unit 1 (mrad). Dqct = 7.6 x 10-3 CN1* Steo 5 - Determine Dqs1 = quarterly beta air dose from Unit 1 (mrad). DQB1 = 7.6 x 10-7 CN1

• O Steo 6 -

Determine DQG2 = quarterly gamma air dose from Unit 2 (mrad). ? DGB2 = 6.3 x 10-4CN2* Steo 7 - Determine DQB2 = quarterly beta air dose from Unit 2 (mrad). DQB2 = 1.3 x 10-3 CN2* Steo 8 Determine Dqc3 = quarterly gamma air dose from Unit 3 (mrad). Dqc3 = 6.3 x 10-4 CN3

• Sten 9 Determine DQB3 = quarterly beta air dose from Unit 3 (mrad).

~ DQB3 = 1.3 x 10-3.CN3* Steo 10 if Dqct, Dqc2, or Dgc3 are greater than 1.6 mrad; or Dqat, Og'B2, or DQB3 are greater than 3.3 mrad, go to Method 2.

• See Appendix D for derivation of factors.

O D-3 m

..g v mu

- _me, + I 1/1/86 l Rev. O O h D.2.b Quarterly Air Dose - Method 2 - All Units 4/ i Unit 2,3 - For MP2 and MP3 dose calculations use the GASPAR computer code to determine the critical site boundary air doses. For the Special Location, enter the following worst gase quarterly average meteorology: X/Q = 0.13 x 104 sec/m3 D/Q = 0.13 x 10-6 m-2 If the calculated air dose exceeds the Technical S'pecification limit use real time meterology. Unit 1 - For MP1 dose calculations use the AIREM computer code to determine the critical location air doses. The 3rd quarter 1979 joint frequency data should be used as input for the AIREM code. The reason for this is given in Appendix D. If the calculated air dose exceeds the Technical Specification limit, use real time meteorology. O) (v T.. O e i /^N (o) D4

.w .. ~.m. s., --==r =.-e- = - - -. 7.s. I I . 1/1/86 Rev.0 D.2.c Annual Air Dose Limit Due to Noble Cases - All Units 3 Determine DYGI,Dyc2,DYG3,DYB DYB2 and Dy = gamma air dose and. beta air dose for the calender year for b, nit 1,2 or 3 as ollows: DYG1 = 1DQGl; DYB1 = EDQB1; DYG2 = 1 DQG2; DYB2 = EDQB2; DYG3 = E Dqc3; DYB3* f Dqtj. ~ where the sum is over the first quarter through the,potsent quarter doses. The following should be used as the quarterly doses: (1) If the detailed quarterly dose calculations required p.e.r,the section for the semlannual effluent report are complete for any calendar quarter, use those results. (2) If the detailed calculations are not complete for a particular quarter, use the results as determined above in Section D.2.a or D.2.b. (3) If DYGI 2 or 3, are greater than 10 mrad or DYB1 than 20,mr,ad and any corresponding quarterly dose, 2, or 3, are greater was not calculated using Section D.2.b -real time meteorology, recalculate the quarterly dose using real time meteorology. p i 9 0 8 9 t e l 4 l l D.3 i i i

w v.g :;;;. s >, .a v ~. :=. - as us... 'r-.:am. W p n=a m mR 1

1/1/s6

.,{. Rev.0 i' D.3 Anoendix ! - todine and Particulate Doses .i; '% D.3.a Quarterly Doses - Unit I ~ S (1) Method 1 - Unit I . ~ itgL1-Determine C = total curies of I-131 released in gaseous effluents t I from Unit i during the quarter. M-Determine Cp = total curies of particulates.with h11f livhs. greater than 8 days released in gaseous effluents from Unit I-during the calendar quarter. + M - Determine DQT = quarterly thyroid dose as follows: QT = 13.7 C (See Appendix D) D 1 Ltgt!- Determine Dqo = quarterly dose to the maximum organ other t than the thyroid . D o = 2.4 Cp (See Appendix D) Q S.tgt.),,- The maximum organ dose is the greater of Dqi or D o. If it is Q. . greater than 5 mrem, go to Method 2. (2) Method 2 - Unit 1 D Use the GASPAR code to determine the maximum organ dose. For ' the Special I.ocation, enter the following worst case quarterly average meterology as taken from Appendix.D: X/Q = 7.1 x 10-8 Sec/M3 D/Q = 7.9 x 10-9 M-2 Use the goat milk, vegetation and inhalation pathway in totaling the dose. - If the maximum organ dose is greater than 7.5 mrem, go to Method 3. ~ (3) Method 3 - Unit I Use the GASPAR code with actual. locations, real-time meteorology and the pathways which actually exist at the time at those locations.: ke 8 i 4 D-6 s

~e - n n 1/1/86 Rev.O D.3.6 Quarterly Doses - Unit 2 or Unit 3 (1) Method 1 )> Steo 1 - Determine Cg = total curies of I-131 in gaseous effluents from 3 Unit 2 or 3 during the quarter. Steo 2 - Determine Cp = total curies of particulates with half lives greater than 8 days released in gaseous effluents from Unit 2 or 3 s during the calendar quarter. Step 3 - Determine CT = total curies of triti.um, relessed' in. gaseous effluents from Unit 2 or 3 during the calendar qttartbr. Steo 4 - Determine DQT = quarterly thyroid dose as follows: QT = 285 C + 1.5 x 10-3 CT (See Appendix D) D 1 Steo 5 - Determine Dqo = quarterly dose to the inaximum organ other than the thyroid: ~ ~ D o = 44 Cp + 1.5 x 10-3 CT (See Appendix D) Q Steo 6 - The maximum organ dose is the greater of DQT or Dqo. If i greater than 5 mrem, go to Method 2. (2) Method 2 Use the GASPAR code to determine the maximum organ dose. For the Special 1.ocation, enter the following wdrst~i:ase quarterly avergge meteorology as taken from Appendix D: X/Q = 0.13 x 10-4 sec/M3 D/Q = 0.15 x 10-6 M-2 As shown in Appendix D, the same meteorology can be used for both continuous and batch releases. Therefore, the program need only be run once using the total curies from all releases from Unit 2 or 3. Use the goat milk, vegetation and inhalation pathways in totaling the dose. If the maximum organ dose is greater than 7.5 mrem, to to Method 3. (3) Method 3 - Unit 2 I Use the GASPAR code with the actual locations, real-time meteorology ) and the pathways which actually exist at the time at these locations. The code should be run separately for steam generator blowdown tank vents and ventilation releases, containment purges and waste gas tank releases. 4 9 O 4 D-r

~ - z - g~

; 7. -

p. yy. _,: =- m. - ~ 7s...

x

,y>. ;, c w;.. n.3 1/1/86 s 1 Rev. 0 ~ (4) Method 3 - U' it 3 ,x n il c).50 Use the GASPAR code with actual locations, real-time meteorology and 4 } the path' ways which actually exist at these locations. This code should be i run separately for ventilation, process gas, containment vacuum system, aerated ventilation and turbine gland sealing exhaust; and containment ~ q purges and main condenser evacuation system. ~. ~ ~.. Og e .o l O w ..g g 8 l s .1 I 9 N 'O ); 1 D-8 ,5.

.,. x. aw~ ..-,.,-..,:.m._ a - n.,:.,.., .m _/ l 1 1 l 1/1/86 R'ev. 0 D.3.c Maximum Organ Annual Doses - All Units .i s j Determine Dyci, DYO2, and Dyo3 = maximum organ dose for the calendar year j for Units 1,2, and 3 respectively, as follows: i DY01,2 or 3 = 2 Dgo = sum of quarterly maximum organ doses where the sum is over the first quarter through the present quarter. 7 The following guidelines should be used for use of Dgo: (1) If the detailed quarterly dose calculations required per the section for th6~ - semiannual effluent report are complete for a ty calendar ' quarter, use those results. (2) If the detailed calculations are not complete for a particular quarter, use the results as determined above in Section D.3.2 or D.3.b. (3) If Dyo is greater than 15 mrem and quarterly dose was not calculated using Method 3 of Section D.3.a or D.3.b, recalculate the quarterly dose using Method 3. (4) If different organs are the maximum organ for different quarters, they can be summed together and Dyo recorded as a less than value as long as the i value is less than 15 mrem. If it is not, the sum for each organ involved should be determined. I

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D.4-Gaseous Effluent.Nionthly Dose Projections

f. W~S!

a D4.a Unit I-I- [ (1). Due to Gaseous Radwaste Treatment System (Offgas). ~ i; Steo 1 - If it is expected that the augmented offgas treatment system will be out of service during the month, go to Step 7. Otherwise, - , ~ continue with Steps 2 through 6 Steo 2 - Determine C'N = number of curies of noble gag released during-the most recent month of operation from thq aQgmented offgas system. Steo 3 - Estimate R1 = ratio of expected fulf power offgas rate at the air ejector for.the upcoming month compared to the reference month of Step 2. '2'- Steo 4 - Estimate R2 = ratio of expected unit production capacity for the upcoming month compared to the reference month of Step 2.. E Steo 5 - Determine DMG = estimated monthly gamma air dose. DMG (mrad) = 7.6 x 10-5 c'N R, R (Factor is from Appendix D) 1 2 Steo 6 - Determine DhB = estimated mont'hly beta air dose. \\p*y E DMB = 7.6 x 10-7 C'N Rt R2 (Factor is from Appendix D). Steo 7 - If the augmented 6ffgas systent is 'spected to be ' ut of. service o during the month,- determine the following: Q= Estimated curies /sec at the air ejector at the expected maximum power for the month. R= estimated curie reduction factor from air ejector to stack via the 30 minute (actual time is approximately 55 minutes) holdup line (in decimal fraction). d= estimated number of days the 30 minute holdup pipe will' be used. DbG = estimated monthly gamms air dose. s - ^ = 7.6 x 10-5 mrad /Ci x Q Ci/secx R x d (day) x 8.6 x 104sec/ day.. u DhG,= 6.5 x Q x R x d E DMB '= estimated monthly. beta air dose. . DbB = 0.0~65 x Q x R x d f 4

• N./

(2) Due to Ventilation System Releases - '1 Steg_j,- For (the last quarter of operation, determine DQT or Dqo**..as determined per Section D.3.a.++ ~

D-10 4

-c n?.,, c:3.y;.. v :.. . : + m..,.: m. I 1/1/86 .) Rev.0 .i Steo 2 - Estimate R1 = expected ratio of primary coolant lodine level for the coming month as compared with the average level during the ...a q'uarter'used in Step 1. J Steo 3 - Estimate R2 = expected ratio of primary leakage rate for the coming month as compared with the average leakage rate during .s the quarter used in Step 1. E Steo 4 Determine DMO = estimated monthly dose to the maximum.._,. D$to = 1/3 R D o (or DQT)* 1 R2 ~ ~ Q ~ Whichever was greater +-

• • - Section D.3.b for Unit 2 t

O i 4 =C t 1 G D-11

y3 .mx. ' ..;; ' :i.;=.:!.'; 7. m ;.;, 5psRmpy s-w i:. :; n ~ I i, 1/1/86 Rev.0 r' % a %g .D.4.b Unit 2 i (1) Due to Gaseous Radwaste Treatment System Steo 1 - Estimate CVy = the-number of curies of noble gas to be released; from the waste gas storage tanks during the next month. Steo 2 - Determine D%iG = estimated monthly gamma air dose. ~ ~ ~ Dh,1G (mrad) = 7'.6 x 10-5 Ch ~ ~ (Factor is from Appendix D for the Unit 1 stack Ueleases since the ~ Unit 2 waste gas tanks are discharged via the Unit 1 ' tack. This s factor should be conservative as the isotopic mix would only be the longer lived noble gases which would have lower dose conversion factors than the typical mix from Unit 1.) F Steo 3 - Determine D MB = estimated monthly beta air dose. Dkts.(mrad) = 7.6 x 10-7 Dh.. (2) Due to Steam Generator Blowdown Tank Vents and Ventilation Releases ~ Use the same method as given in Section D.4.a (2) for Unit 1. e N Q..y 3 . e ee9e 9 8 5 .sm 9 r D-12 H-W ++ n< + +, +,---u- = w m c3w.ew w s,m -e er-b (

=- .z.. z ...,mc. = :-:ac: = m - 1 c. - c. 1/1/86 Rev. 0 e -l D.4.c Unit 3 1 i 4 f4 (1) Due to Radioactive Gaseous Waste' System, Steam Generator Blowdown Tank Vent. ~ ' Use the same method as given in Section D.4.b.(1). (2) Due to Ventilation Releases ~~ ~~ ~ Use the same method as given in Section D.4.a.(2). s i 1 e 6 9 9 9 l D-13

,-:..: p : R h 2 M T = !-5. s 4 % %.

4*'=B ; l

.':2. 2?M&,;%ni.es:b-%,:,..t.?:vn:. ~:m:xp.E.xs..qwg .,1 3;. . 1/1/86 4 ~ 'j - Rev.0 4- .1 Y. D.5 Ouarterly Dose Calculations for Semiannual Report ].>l 5 Detailed qua(terly dose calculations required for the Semlannual Radioactive. i Effluent Report shall be done using the computer codes GASPAR and AIREM.- ~ t- );- 't a ' )

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. ~,~ ymg.s t ww-m w. - v A. i 1/1/86 1' Rev.0 ) I D.6 Compliance with 40 CFRi90 i ..um The following sources should-be considered in determining the total dose to a i real individual frorn uranium fuel cycle sources: a) Gaseous Releases from units 1,2, and 3. l b) Liquid Releases from units 1,2, and 3. i ~~ ~~ ~ c) Direct Radiation from the Site ~ d) Since all other uranium fuel cycle sources.arg greaitr~than 5 miles away, they need not be considered. .ee ... e 9 e 6 e ~ e 3 e

== e e m D-1J 4 e t v -

~WGigisweMis?W4G D e-r > %L;yw,V!Me 'NW A. '" W4f ? e - WNWec22.w] I 1/1/86 ? .Rev.0- ,y s y '}N. g ~ -E. LIQUID MONITOR SETPOINTS h Wh A E.1 Unit i L.iould Radwaste Effluent Line N k The trip / alarm setting on the _ Unit 1-liquid radwaste discharge line depends.on, dilution water flow,' radwaste discharge flow, the. isotopic comp'osition of the. {: liquid, the-background count rate of the monitor and the efficiency of the monitor.. Due to the variability these parameters, an alarm / trip'setpoint will be 2 determined prior to the release of each batch. The following methcdology will be used: Steo 1 - From ' the tank' isotopic analysis and. the-MPQ lalue.s for each 1 identified nuclide (including noble gases) deterniine the required reduction factor, i.e.: ~ R = Reduction Factor = 1/ k uCi/ml of nuclide i MPC of nuclide-i Steo 2 - Determine the existing dilution flow = D = circulating water pumps x: 100,000 gpm + # service water pumps x 10,000 gpm. Steo 3 - Determine the allowable discharge flow = F F = 0.1 x R x D Note th'at discharging at this flow rate would yield a' discharge .e.g" concentration 10% of the Technical Specification Limit-due to the. ~ safety factor of 0.1. Steo 4 - Determine the total uC1/mi in the tank. ' ~ ~. Steo 5. - Using the latest monitor calibrationH curve, determine the J" cps" corresponding to two times the total uCi/mi determined in' Step 4 This will be the trip setpoint. Note: If discharging at the allowable discharge. rate as' determined in. Step 3,' this would yield ia discharge'- concentration corresponding to 20% of the Technical Specification lim,it. 1 Steo 6 - The allowable discharge flow rate ' calculated iin Step.~3. may' be ' increased by up to a factor of 5 withf appropriateLadministrative controls. 's S - y t \\J9p ,[ d h,. E-I ' t , #'s i s. ~ ~

mwy. -;c... na c;4;q q;... ~ 5 p. y :c q c w.. m +v-m- i 1/1/86 1 Rev.0 i i E.2 Unit 1 Service Water Effluent Line } The MP1 Reactor Building Service Water Monitor. Hi alarm setting is approximately 1.3 times the ambient background and the Hi-Hi Alarm is - t approximately 2 times the ambient background reading on the monitor in counts per second. 1 4 - ee

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-:?-n " : -- - - - "- ~ -- -~~ ~ I: 1/1/86 Rev.0 6,t A E.3 Unit 2 Clean Licuid Radwaste Effluent Line ]4.;;r:i* ,r j, Same as Section E.1 of the MP1 Liquid Radwaste Monitor except for Step 2 where: Dilution Flow = D = # circulating water pumps x 135,000 gpm + # service .~ water pumps x 4,000 gpm. f 3

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. _..s e. f 1/1/86 Rev.0 4 4 E.4 Unit 2 Aerated Licuid Radwaste Effluent Line and Condensate Polishing Facility Waste Neut. Sump Effluent Line

g Same as E.3 for Clean Liquid Monitor, except that for the Condensate Polishing Facility Waste Neut. Sump, the monitor has a digital readout of uCi/mi and the 3

alarm setpoint is set directly on uCi/ml and not the corresponding count rate. 1 8 Og e g 6 4 e e eee y ) 1 4 e d 6 S 1 1 E-4 L

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~., 1 1/1/86 E l [ Rev.0 y, i y E.5 - Unit 2 Steam Generator Blowdown - L -{-. Qf) [ Assumptions used in determining the Alarm'setpoint for this monitor are: -j Maximum possible total S.G. blowdown flow rate = 500 gpm. a. c i b.- Minimum possible. circulating water dilution flow during periods of. .blowdowa = 270,000_ gpm (2 pumps). c. Unidentified MPC for unrestricted areas = 1 x 10-7 uCi/ml*. ,ek Therefore, the alarm setpoint should correspond to a concentratihn of: Alarm (uCi/ml) = 270.000 x i x 10-7 = 54 x 10-5 uCi/ml 500 The latest monitor calibration curve should be used t$ ' determine the alarm setpoint in cpm corresponding to 1.1 x 10-4 uC1/ml.- This setpoint may-be. increased through. proper administrative controls if the ~ steam generator blowdown rate is maintained less than 500 gpm and/or ~more than ' 2 circulating ; water pumps are available. The percent increase would correspond to the ratio of flows to those assumed above or: ' r i Alarm (uCi/ml) = 5.4 x 10-5 uC1/mi x # Cire water ounios - 30 0 i x 8: 2 S/G Blowdown (gpm) ~.y '- t.4 x 10-2 uCi/ml x # Cire water pumps total S/G Blowdown (gpm) C' - e Note:The Steam Generator Blowdown alarm criteria.is in practice l based on setpoints required to detect allowable levels of primary to secondary leakage. This. alarm criteria is - typically more restrictive.than that~ required to meet discharge limits. This fact should be verified 'however. whenever the alarm setpoint is recalculated. }

• In-lieu of using the unidentified MPC.value, the identified 1MPC valves' for unrestricted areas may be used.

4 e 4 1 P b = 4-i . l .S O,h L E-5 ~ t ,) e ,,,-..,,-ew-- +, "=m- + -4*- ww ' t-=4- 'e 'N-- " ~ " * - ' ' ' ' '

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~- < c i 1/1/86 .i Rev.O i E.6 Unit 2 Condenser Air Eiector .~% i. This monitor is included as a liquid monitor since the reason it's in the Technical Specifications is for control of the Steam Generator Blowdown liquid activity. It } can be used in conjunction with or in place of the blowdown monitor to ensure that the blowdown concentration is within 10CFR20 limits. Gaseous release limits are not controlled by this monitor but rather by the monitor at the final discharge point. A detailed study was performed to determine the equilibrium steam generator blowdown activity as a function of blowdown rate and primaf910 secondary leakage rate. It turns out that in order to reach 10CFR20 lirdits'as determined in Section E.5 the minimum primary to secondary leakage rate required is 0.ti gpm. The air ejector monitor is set to alarm at a level corresponding to approximately 0.2 gpm. leakage. Thus it ensures adequate control of blowdown. The above values are for primary coolant activity level used at the time of the study. _ However, if the coolant activity increased such that the leakage rate required to reach 10CFR20 limits was less, there would be an equal increase in the sensitivity of the air ejector monitor. J e)

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'-).,'* 4j _. : y ' ' ~' .-1 n n 'r - s, _,w arq / e ) i -1/1/86 ' J[ Rev. O T .i ~ P E.7 Unit' 2 Reactor Building Closed Cooling Water - The alarm setting is approximately 2 : times the ambient background readinE of: ~ the mor.itor. 4 ) i - 1, 1 l i 4 .g l O Y 1 Y' i 4 ...o i 4 I j t 1 1 i d -[ i 4 i -I t i 4 k i. . y { i I i i, i s y .8 ? ? ~. . s i-i. b .t g 2 t 4. . h 8 4 t ^ 4 6 1-l. E-7 t ~ }. e. i . i -[ + r I' 1_.-.--.-..-.:.=-.-..,- ---~~

a,. .g ~ ~ 3/18/86 Rev.1 E.1 Unit 3 Licuid Taste Monitor Similar to the Unit I liquid discharge line, the setpoints on the Unit 3 liquid waste monitor oepend on dilution water flow, radwaste discharge flow, the isotopic composition of tne liquid, the background count rate of the monitor and the efficiency of the monitor. Due to the variability these parameters, the alert and alarm setpoints will be determined prior to the release of each batch. The following methodology will be used: Steo 1 - From the tank isotopic and the MPC values for each identified nuclide (including noble gases) determine the required reduction f actor, i.e.: R - Reduction Factor - 1/1i uCi/ml of nuclide i MPC of nucitee i Steo 2 - Determine the existing dilution flow = D = # circulating water pumps x 150,000 gpm + # service water pumps x 15,000 gpm. Stec 3 - Determine the allowable discharge flow = F F = 0.1 x R x D Note that discharging at this flow rate would yield a discharge concentration 10% of the Technical Specification Limit due to the safety factor of 0.1. Steo k - Determine the total uCi/ml in the tank. ' Steo 5 - The Alert setpoint will be 1.5 times the total JCi/ml determined in Step 4, plus background. Steo 6 - The Alarm setpoint will be two times the total JCi/ml determined in Step 4 (Note 1) or 8 x 10-5 uCi/ml (Note 2), whichever is greater, plus background. Note 1: If discharging at the allowable discharge rate as determined in Step 3, this would yield a discharge concentration corresponding to 20% of the Technical Specification limit. Note 2: This value is based upon worst case conditions, assuming maximum discharge flow, minimum dilution water flow, and 20% of an assumed mix of nuclides as specified for an unidentified liquid release in 10 CFR 20. This will assure that low level releases are not terminated due to small fluctuations in activity causing valve closure upon high radiation alarm. Steo 7 - The allowable discharge flow rate calculated in Step 3 may be increased by up to a factor of 5 with appr'opriate acministrative controls. E-8

v~ yi.:2%r:VW.tssoway.%:g&wr'r%Mi A;::c. n,- . 8=:m: n : - 1/1/86-4 J: Rev.0 4 h E.9 - Unit 3 Regenerant Evaporator Effluent Line The MP3 Regenerant Evaporator Monitor alert setting is approximately 1.5 times the normal reading and.the alarm setting is 2 times the ' normal reading. a g ' '. N l 9 r i aehe. p. e49 .6

e. g 4

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..,7. .g_s;,.m.c : _-gra. a;.. .x- ..~,_.,., 1/i/86 j Rev.0 l E.10 Unit 3 Waste Neutralization Sumo Effluent Line Same as S.ection E.8. t e - ee e e e6 &g + $s e e . ~ y 4 e E D p 1 6 I OJ E-io \\

y-

: y 9 y.,.n; y ;.w x,- m um mm.y 7:pr:m mmawwm.gr,-y

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a..

E.ll Unit 3 Steam Generator Blowdown j-The Alarm setpoint for this monitor assumes:

i-steam generator blowdown rate of 76 gpm for each steam generator.

m a. for a total of 304 gpm. b. the release rate limit is conservatively set at 10% of the 10CFR Part ' 20 limit (0.1 times the -unidentified MPC* for unrestricted. areas which equals 0.1 x 1 x 10-7 uC1/mi - 1 x 10-8 uC1/ml). ~ ~ minimum possible circulating and service water dilution. flow during - c. periods of blowdown = '456,000 gpm'(3 circulating water pumps).+ 30,000 gpm (2 service water pumps) = 486,000 gpm. - Therefore, the Alarm setpoint should correspond to a concentration of: Alarm (uCi/ml) = 486.000 x 1 x 10-8 = 1.6 x 10-5 uCi/mi 304 A 4 This setpoint may be increased through proper administrative controls if _ the steam generator blowdown rate is maintained less than 304 gpm and/or more than 3 circulating and 2 service water pumps are available.. The amount of the increase would correspond to the ratio of flows to those assumed above or: Alarm (uCi/ml) = 1.6 x 10-5 uCi/mi x circulating & service water flow (rom) 486,000 gpm x 304 nom-5/G Blowdown (gpm). = 1 x 10-8 uCi/ml x circulating & service wate flow (rom) total S/G Blowdown (gpm) Note:The Steam Generator Blowdown -alarm criteria-is In practice based on setpoints required to detect allowable levels _of primary to secondary leakage. This : alarm criteria -is typically more restrictive than : that - required to meet discharge limits. ' This fact should be verified ho' wever whenever the alarm setpoint is recalculated.

• In -lieu of using the unidentified MPC value, the identified MPC values for unrestricted areas may be used.

'4 F

I

(; 1 i 3) E-Il m 4 4 9-'

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~ i 1/1/86 j Rev.0 4 4 l', E.12 Unit 3 Turbine Building Floor D' rains Effluent Line 't ?! The Alarrn setpoint for this monitor assumes: ~ ' " i d a. Drinking water is not a real pathway at this site. Therefore the NRC code, LADTAP, is used to calculate the dose to the maximum individual. s b. 3 The dilution flow is 5 gpm (1.11 x 10-2 ft /sec) c. Near field dilution factor = 13,000. Far field dilution factor = 32,000. (

Reference:

Millstone 3 FSAR, Section 2.4.I'3) ' d. Isotopic concentrations were taken from the Millstone 3 FSAil, Table 11'.2-4 (See column under Turbine Building). e. Each concentration above was multiplied by the total annual flow 9 (9.95 x 10 cm3, conservatively assuming 5 gpm continuous). f. The maximum individual organ dose is set equal to 0.1% of 1500 mrem. The limiting individual is the child; maximum organ is the thyroid. .j The setpoint corresponding to 1.5 mrem to the child's thyroid is 7.6 x 10-5 ~ uCi/ml. g c. gg i l l I e, t .g b O E-12 b wee sw-

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>y.i *:C mm 1/1/86

-Rev.0 1. s h-F. GASEOUS MONITOR SETPOINTS ' ,l 'd? F.1 Unit i Hy'drogen Monitor ~ Per Section 3.3.D.6 of the Technical Specifications, the alarm setpoint shall be ' 4 'e e less than or equal to 4% hydrogen by volume. eee9 e On se 6g

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a. +m.w j

1/1/86 Rev.O i .f F.2 Unit 1 Steam Jet Air Elector Offgas Monitor 1 } Per Section 3.8.D.6 of the Technical Specifications, the maximum allowed noble i gas in-process hetivity rate shall not exceed 1.47 x 106 uCi/Sec. This value will be more limiting than the instantaneous stack release rate limit. Using the latest offgas monitor calibration curve, determine the reading in mR/HR corresponding to 1.47 x 106 uCi/sec. The alarm setpoint should be set at less than or equal to this value. e a h e e 9 4 6 e e D S 9 ) e w 4 ek e e e s t 4 4 i G =F-2 y

w. TG.-}"f ':W :' M.w @ n " m W.+' ' -m ~ + - ~ N * ~ i q: 1/1/86 d Rev.0 ~O,+ F.3 Unit i Stack Noble Gas Monitor c, - g.) l-Per Technical Specifications 3.8,0.1 and _ODCM Section D.I.a, the instantaneous release rate limit from the site shall be: p Q1 Q2 Q3 .+ + gi i [ 790,000 217,000 217,000 where Q1 = noble gas release rate from MP1 stack (uC1/sec) ~~~ 1 Q2 = noble gas release rate from MP2 vent (uCi/sec) Q3 = noble gas release rate from MP3 vent (uCi/sec) Assume 33% of the limit is from MP1 stack. Therefore Q1 should be less than 260,000 uCi/sec. The MP1 stack noble gas monitor calibration curve (given as uCi/sec per cps) is determined by assuming a maximum ventilation flow of 170,000. Therefore, the alarm setpoint should be set at or below the " cps" corresponding ] to 260,000 uC1/see from the calibration curve. The alarm setpoint may be increased if the MP2 or MP3 vent setpoints are at j; levels corresponding to less than 33% of the site limit.' a e e

• . I e.

e ~ ~) O l.~ 4 4. .F-3 i. 4-, -..,,.e

,;+,;_ v y;;n.:,,,,- c. =- l 1/1/36 8 Rev.0 F.4 Unit 1 Main Stack Samoler Flow Rate Monitor J 2 The MP1 main stack sampler flow control alarms on low pressure indicating loss ~ ~ ' of flow, or on high' pressure indicating restricted flow. The alarm will occur with either: a) Pressure Switch #1 less than 2" Hg l or b) Pressure Switch #1 greater than IS" Hg and Pressure Switc!rTZ'le'ss j l than 20" Hg O e e O S 9 l l l 9 O e d F-4

7.g ,w. e :. r -~ v:.;c. m. 7.n.

v. s.g,,.:c;,:r.u.~. 3.;,2 v

m;. ~ 1/1/86 Rev. 0 4 V 'T - F.5 _ Unit 2 Vent - Noble Gas Monitor a.lh.L Per Section D.I.a of this manual, the instantaneous release rate limit from the site shall be: 91 Q2 'Q3 ( g + +- ~ 790,000 217,000 217,000 Assuming 33% of the limit is from the MP2 vent, the r'elease rate limT6for nit ' 2 is 71,000 uCi/sec. ~. _ The MP2 vent noble gas monitor calibration curve (given as GCI/sec per cpm)-is determined by assuming the maximum possible ventilation flow for various fan combinations. Curves for 3 different fan combinations are normally given. ~ The " cpm" corresponding to 71,000 uCi/sec should -be determined from the appropriate curve. The alarm setpoint should be set at'lis's than or equal to this value. The alarm setpoint may be increased if the MP1 stack or MP3 vent setpoints are at levels corresponding to less than 33% of the site limit. ,-g, b 2 '4 } a I W j i l O 4 9 J 1 l 5

)

W[p F-5 4 - i e t t w w ~ " * ~ - '--r

x. .. ;, n: 1.s.., ;;,. s ex ~ ~ 1/1/86 Rev.0 i F.6 Unit 2 Waste Gas Decav Tank Monitor .6 Per Section D.I.a,of this manual, the instantaneous release rate limit from the site shall be: Q1 Q2 Q3 + + g1 ~ f. 790,000 217,000 217,000 Administratively all waste gas decay tank releases are via the MIM stack. - Assuming 33% of the limit is from the MP1 stack, the release rate limit for MPI- - is 260,000 uCi/sec. Releases from waste gas decay tanks are much lower than this limit,and' are based upon ventilation dilution, conservative meteorology (X/Q = 10-3) and release flow rates to maintain off site concentration below MPC, values. The MP2 waste gas decay tank monitor (given as uCi Ec'pe'r cpm) calibration curve is used to assure that the concentration of gaseous activity being released from a waste gas decay tank is not greater than the concentration used in discharge permit calculations. O- ) e a. G I \\ 1 F-6

p ;.,y.;:;;w n y;.,- w.c..a.m ;w, .:y w m a.m v>- .- m ;; & yr mr;;a p<,x w ay-rwe,; w.:n.. E 1/1/86-Rev.0 . f h F.7 ' Unit 3 Vent Noble Gas Monitor .,d9 Per Section D.I.a of this manual, 'the instantaneous release rate limit from the-site shall be: i e 'Q3 4 g .Q1 + ' Q2 + 's j. 790,000' 217,000 217,000 Assuming 33% of the limit is from the MP3 vent, the release rate limiY~for Unit - 3 is 71,000 uCi/sec. Based on the maximum ventilation flow rate-of 230,680_ CFM (1.325 x f08 cc/sec, see Table 3.5-16 of MP3 FSA.R) this coAver.ts to: 8 Alarm setpoint= 71,000 uCi/sec/1.325 x 10 ;,cc/sec 5.3 x 10-4 uCi/cc = 4 I i r t 4 'il.,N.3 J se#3 m egeo e 5 5 j i 4 (* + 2 e e e i

• r 0#

- I t. F-7 ..i 3 --.y... - -....m, ..-,-.,.y, y _,,,. _, _,,.,y... .,,_,,.,.,,m,-.,-,y,.-.,.

w~ +m-- e.. s.,. 1, ; m

_m..3..ang eva x~ 3 r.

.j 1/1/86 1-Rev.0 1 F.S - Unit 3 Engineering Safeguards Building Monitor ..s 4 Per Section D.I.a of this manual, the instantaneous release rate limit from j, the site sitalf be: i Oi + 09 + O, ( l s ~' j 770 000 217,000 217;000 s ~~ - Assuming releases less than 10% of the MP3 F5AR &:.ign re' eases of Kob'le gases (Table 11.3-11, 1.4 x 104 Ci/ year which is equal,t,o 3 f; uCi/ sect ~ assures that less than 1% of the above instantaneous release rhte.is added (450/217,000 = 0.21%). Asdiming a flow rate by this intermittent pathway /sec) for this pathway translatu this limit to: of 6,500 CFM (3.05 x 10-6 cc 0.1 x 450/3.05 x 106 = 1.5 x 10-5 uCi/cc The Alarm setpoint should be set at or telow this value. = 0 h e 9 g F-8 ^ t 9

-r.gu g am.mm:..nn,w gn m;.m,...- n c.;. y-m vn.>n. L I ' 1/1/s6 ' 1 - Rev. 0 5 p G. EFFLUENT FLOW DIAGRAMS ' G: $1 5.1.<W a

3 Figures 1, 2,' 3,' 4, 5, and 6 present simplified flow diagrams for the liquid and -

~ d .i ;; gaseous radwaste systems for Units 1,2 and 3. They also indicate the location of.. the radiation monitors listed in the Technical Specifications. - ~ i. ^ M*_. ~ O% e 0 a 0 e ~~. :. e O = f

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.~a.. .....,x., a .....>.s..-~..r~s d + 1 nainer w - N' M.MC "'f'. w. wm,. ta'. w waras * *j w c....a w us.. se is m,,,,,,,, iesicusa. comm usri >=ic acie s gettoe tasy pggwg ~ A?rtivta far stafeaN8 agggg,. ggy suuss.gse es p.eae -as. r e :,, M 83.** a'L si see swseiner ug....,_, gg gyg g g,g pca gastsp Taan pe eu. Clean j Liquid g E"" Rad Hon w. ecuse = se w a.en.e w - to at Condensate _.. - nemanam same unmen se.; -- Polishing ' Ei,5ao sa,gi, "f,8 '* Fac Waste t Moin t. Rump Rad Hon am n*** th e uneee ~ 88Mt s are e seaseast Laque Activeri ume R w,, w,,,,. i. SG Blowdown wa**" th rusans,, m,,, ro. --- -- Rad Monitor d i. j 4 A .A,,,- a-.A.n Be M11#",,

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r)3. _. kr V.', Figure 3 Simpilf fed Flow Diagram - Liquid - Hillstone linit #3 - r ~l Q

catainment Building Sump

-i y 40 GPD

4h

) xillary Building Sump 4' 200.GPD-s 'lligh Level Waste Test Waste Waste U .leictor Plant Samples Sinks Waste Drain Evaporator Task Pump Demineralizer Demineral.lzer 35 GPD Tank-1.' Filter 15~~000 Gal 35.GPH 21.000 Gal ?horatcry Wastes ,i: 400 GPD .isc. Illgh-Level Waste b 660 GPD t. tactar Coolant Bleed to Chemical and Degas- ' Cesium Boron Baron Test Baron Bonn Recovery Volume Control ifier Removal Recovery Evaporator Tank Demin-Filter 1440 GPD System IX Tank _eralizer 150,000 25 GPH 12,000 ,l

tat Gaseous Drains Gal Gal 355 GPD

+{6 e. Low-Level ' Ef fluent sc. Low-level Waste Waste Drain Pump Fil ter 40 GPD Tank Drain ? 5 50gpa Liquid h

• ' ?

Regenerant Regenerant , Regenerfant.- Waste Monitor sclerAgenerant Chemicals Evaporator Evaporator 4 Pump Demineralizer Deminealizer . Dfaeliarge tuinel E Regenerant 3400 GPD a Feed Tank, Flitei-i g 3,600 gat ~~ 15 GPH t' Regenerant Evaporator Monitor 3 ..E f Coodensate Polishing ~ Sum (Honi.60r Facility Waste' \\iv ^y HentralizaLion-Sump V' n- ~n O Y Flash D - Steam Generator Blowdown Tank-T 5 team Generator Blouilc'n lionitor , '. T hine' Bu'_ilding-Dra ins.

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qr figure 6

- Simplified Flow Diagram - Gaseous - Hillstone Unit #3 d d AuxIll:ry ,y Atmosphere Bulldt g Filters Service Building i V:ntilation Auxillary BullIling Honitors Ventilation g t l, Alterate Path from Fu31 Gasous Waste System 6uilding F11ters Unit #3 f' Ven'ilction , fuel Building Honitor Containment , a-Purge I Vent Containment Purge Monitor i e' 't 4sste i Disposal. Liquid Waste System l'l Boron Recovery System Nilding 4 \\kntilation Gaseous Waste System Degassiffer 'i n, p Ventilation Vent Honitor Condersnte Deminearlizer Liquid Waste System i - Containment Vacuum Pumps Exhaust i Air Ejector Monitor

CcndNsate Air Renioval System I

W' . Reactor Plant Aerated Vent System

Procmss Gas Charcoal Bed Adsorbers Radioactive Gaseous I

Waste System ~^ Reacter Plant Gaseous Vent' System Si_CRS' Monitor Atmogphere ~, 1 i, W' + Atmosphere EST lionitor .l i Unit #1 7 kginnred R ESF Stack 5 p faty features Building Exhaust 5ulldi g 5' R 5t Atmo phere ,Atmo phere Atmo phere (du Ing star. tup) og Iurbine Building Roof ~ Condenser ~ Containment forbin3 Gland Exhaust Vacunn ming Vacuum W am m m.a, t am, m ~ mm _t

mmq3m:me. ~ m, a ; .3 -r~ ~ ~ - =. - ji-1/1/86- - Rev. 0 .n -( h APPENDIX A e.t id DERIVATION OF FACTORS FOR SECTION C.1 -LIQUID DOSES * - 1. Section C.I.a - Steo 3' ~ 7. Unit 1 - Liquid - Whole Body Doses DQT(F)/Cp .-DQT(H)/CH - Year. Otr. Q DOT (F) (mrem /Cl) CH D T(H) Imrem/Ci) O 1976 1 3.60 7.6(-2) 3.8(-3) .5.12. ND 2 0.053 1.3(4) 2.5(-3) 9.19-

• 2.1(-6) 2.3(-7)

~ 3 0.48 6.3(-3) 1.4(-2) '1.33 'ND. 4.3(-7), 4 0.15 1.3(-3) 8.7(-3) 4.42 1.9(-6) 1977 1 0.12 1.1(-3)- 9.2(-3) lil1 7.3(-7) 2.3(-7) 2 0.36 4.6(-3) 1.3(-2) . 0.64 - 1.3(-7)' 2.0(-7)- 3 ' O.012 1.1(4) 9.~2(-3) 0.002

3.0 (-10)

3.5(-7) 4, 0.028 1.5(4) 5.4(-3) 0.66 2.3(-7) 3.5(-7) ~ 1978 1 0.119 1.3(-3)' 1.l(-2) 0.98 3.9(-7) . - 3.9(-7) 2 0.049 5.2(4) 1.l(-2) 1.29 2.9(-7) 2.2(-7) 3 0.002 2.l(-5) 1.1(-2) 0.93 4 0.005 5.3(-5) 1.2(-2) 0.0002 ~ 1979 1 0.045 4.4(4) .l.0(-2) 1.78-2 0.146 1.5(-3) 1.0(-2) 2.33 3 0.009 9.7(-3) 1.1(-2)

.. 0.94 4

0.010 4.6(-5) 4.6(-3) 2.37' 1980 1 0.013 6.2(-5) 4.3(-3) 2.40 3.04(-7) - 1.27(-7) 2 0.014 1.6(4) 1.1(-2) 4.96 1.54(-6) 3.10(-7) 3 0.011 1.2(4) 1.l(-2) 6.45 1.67(-6) 2.59(-7) 4 0.686 1.2(-2). 1.S(-2) 13.50 1981 1 0.314 5.8(-3) 1.9(-2). 1.42 2 0.042 7.6(4) 1.l(-2) 0.38 - ^ 3 0.029 3.5(-4) 1.2(-2). 0.31 4 0.009 1.2(4) 1.3(-2) 0.006 5 1982 1 0.008 1.2(4). 1.5(-2) 0.12 2 0.030 1.3(4) 6.0(-3) 0.12 ~ 3-

• 0.577 7.4(-3) 1.3(-2) 3.88 p

4 0.538 6.1(-3) 1.1(-2) 2.08 1983 1 0.777. 3.9(-3) 5.0(-3) 1.61 2 0.007 ' 7.3(-5) 1.0(-2) 1.87 3.96(-7) 2.12(-7) ' 3 0.007 1.0(-4) 1.4(-2) 3.64 1.16(-6) 3.19(-7) 4 0.016 2.0(-4) 1.3(-2) 1.26 i 1 1 9 1

n.,~. .~ 2 = >. '. " ~

v. p

~ I 1/1/36-Rev. 0 - ~ APPENDIX A ' s i DERIVATION OF FACTORS FOR SECTION C.1-- LIQUID DOSE 5* I 1. Section C.I.a - Steo 3 l Unit 2 - Liquid - Whole Body Doses DQT(F)/Cp .DQT(H)/CH Year Otr. C_E DOT (F) (mrem /Cl) CH DOT (H) (mrem /Cl) 1976 1 0.102 1.3(4) 1.3(-3) 34.7 1.2(-5) 3.4(-7) 2 0.179 2.4(4) 1.3(-3) 37.3 2.7(-5) -3.l(-7) 3 0.037 0.9(4) 2.4(-3) 70.0 -2.0(-5) 2.3(-7) 4 0.025 1.0(4) 4.0(-3) 35.4 3.7(-5) 4.3(-7) - 1977 1 0.217 7.0(4) 3.2(-3) 6d.I ~ 2.l(-5) 3.4(-7) 2 0.302 6.l(-3) 7.6(-3) 73.3 3.0(-3) 4.I(-7) 3 0.037 1.6(4) 1.6(4) 42.1 1.5(-5) 3.5(-7) 4 0.509 1.9(-3) 3.7(-3) 35.0 1.l(-3) 3.3(-7) 1973 1 0.432 5.2(-3) 1.2(-2) 1.3 3.9(-7) 4.9(-7) 2 1.27 6.6(-3) 5.2(-3) 43.6 1.2(-3) 2.7(-7) 3 0.715 4.3(-3) 6.7(-3) 91.3 4 0.372 1.3(-3) 4.3(-3) 72.0 1979 1 1.65 9.6(-3). 5.3(-3) 64.6 2 2.43 2.3(-2) l'. l(-2) 27.3 3 0.331 2.3(-3) 3.5(-3) - - - -63.4. 4 0.411 3.0(-3) 7.3(-3) 93.0 1930 1 0.635 4.0(-3) 6.3(-3) 97.7 2 0.235 1.7(-3) 6.0(-3) 57.0 1.09(-5) 1.91(-7) 3 1.17 7.9(-3) 6.3(-3) 43.3 4 0.723 1.2(-2) 1.7(-2) 64.3 2.23(-3) 3.52(-7) 1981 1 0.435 6.3(-3) 1.6(-2)' 55.3 2 0.343 5.3(-3) 1.7(-2) 149.0 541.(-5) 3.63(-7) 3 0.265 1.6(-3) 6.0(-3) 37.2 1.77(-3) 2.03(-7) 4 3.14 1.0(-2) 3.2(-3) 79.9 1982 1 1.65 1.0(-2) 6.l(-3)

7. 4 2

9.94 3.4(-3) 3.5(4) 33.3 491.(-5). 3 1.14 3.l(-3) 7.l(-3) 113.0- ~ 5.56(-7)' 4 1.14 1.3(-2) 1.l(-2) 32.6 e G~ 2- .w-~

m n F 2 P M VR7.gi?w M R 2;c. W P m m + 7 =s?l ? % MY'%i:M*:;:: ? W ' m, T4 n w :7-t, +:=~ .1/1/86- _;j Rev.O u ye g . APPENDIX A 1 4 a,. 3 DERIVATION OF FACTORS FOR SECTION C.1 -LIQUID DOSES * ~ 1. Section C.I.a - Steo 3 ^ Unit 2_- Liquid - Whole Body Doses .,DQT(H)/CH L-DQT(F)/Cp Year Otr. 95, DOT (F)- . (mrem /Ci) CH-DOT (H) -(mrem /Ci) c 1983 1 1.48' l.1(-2) 7.4(-3) . - 70.7.. .2 0.685 7.2(-3) i1.1(-2) .- 36.7 ' ' ' 3 2.42' -3.6(-2) 1.5(-2). 6.5 4 3.22. 4.5(-2) -1.4(-2) 6.8 Unit 3 -Liquid Whole Body 65ses i Dose Rate Projected Releases

• C1/yr (mrem /yr).

~ Dose /C1 Total Fission and 0.18 -8.8(-4) ~ 4.9(-3) Activation (ex.H-3) 6> H-3 730 1.6(-4) 2.2(-7) A ~ - a. Since the maximum values DQT(F)/Cp and DOT H /CH are.not much different for Units 1 and 2, the same factor can be used Yo(r a)ll three units'(for simplicity).' ~ Also, the maximum values.are less than four times' the average values,' this. Indicates that the dose per total curie does not-fluctuate ' greatly; hence this method is not overconservative.

• from Unit 3 EROLS Table 5.2-4.

where, Cp = Curies of fission and activation products released during calendar. quarter.-

DgT(p) = Calculated total body dose to the maximum individual (mrem) 'due to. fission and activation products.. Dose calculated using computer code. o LADTAP. CH = Curles of tritium released during calendar quarter. l r. L - 4 ( t. L

..:3

m p m.c

,w 1/1/86 Rev.0 DQT(H) = Calculated total body dose to the maximum individual (mrem) due to tritium releases. Dose calculated using computer code - i. LADTAP. c Maximum Value of DQT(F)/CF-Unit 1 = 1.9 x 10-2 mrem /Ci Unit 2 = 1.7 x 10-2 mrem /Ci Unit 3 = unknown Average Value of DQT(F)/Cp - Unit 1 = 1.1 x 10-2 mrem /Cl Unit 2 = 7.4 x 10-3 mrem /Ct ,,, ~ Unit 3 = 4.9 x 10-3 mrem /Ci Maximum Value of DQT(H)/CH-Unit 1 = 4.3 x 10-7 rnrem/Cf Unit 2 = 5.6 x 10-7 mrem /Ci Unit 3 = unknown Average Value of DQT(H)/CH-Unit 1 = 2.3 x 10-7 mrem /Ci Unit 2 = 3.5 x 10-7 mrem /Ci Unit 3 = 2.2 x 10-7 mrem /Ci DQT(F)/Cp = 1.9 x 10-2 mrem /Ci DQT(H)/CH = 5.6 x 10-7 mrem /Ci

• Note: Although operation of Unit 3 increases the dilution flow, the near field dilution factor is reduced from 5 to 3. Therefore, the net effect is to reduce the doses only by a factor of 0.86. For conservatism, this factor

} will be neglected. ""~ ha t +

x., . sy y :w, :.. +,,, y = c h. 1/1/86 Rev.0 APPENDIX B jj %g .pv DERI.VATION OF FACTORS FOR SECTION C2 -LIQUID DOSES a i} 1. Section C.2.a - Sten 2 Unit 1 - Liquid Doses Do Doc /.9F Year Otr. 9_F._ Max. Organ Q ~ 1976 1 8.60 GI(LLI) 0.054 0.0062 ~ 2 0.053 GI(LLI) 0.0003. " 0.0056 3 0.48 GI (LLI) 0.059 -0.123 4 0.15 GI (LLI) - 0.0057 0.038 1977 1 0.12 GI (LLI) 0.0021 0.018 2 0.36 GI (LLI) 0'.dO' 1 0.011 4 3 0.012 Liver 0.00017 0.014 4 0.028 GI (LLI) 0.00086 0.031 1978 1 0.119 GI (LLI) 0.024 0.202 2 0.049 GI (LLi) 0.0031 0.063 3 0.002 GI (LLI) 4.0(-5) 0.02 4 0.005 GI (LLI) 1.3(-4) 0.026 s 1979 1 0.045 GI(LLI) 1.8(-3) 0.04 'r'..M, 2 0.146 GI(LLI) 9.3(-3) 0.064 3 0.009 GI(LLI) 9.0(-4) 0.10 4 0.01 ., GI(LLI) 2.1(-4) 0.021 1980 1 0.013 GI(LLI) 1.7(4) 0.013 2 0.014 GI(LLI) 5.5(-4) 0.039 3 0.011 GI(LLI) 3.0(-4) 0.027 4 0.686 Liver 1.7(-2) 0.025 i 1981 1 0.314 GI(LLI) 9.75(-3) 0.031 2 0.042 GI(LLI) 1.88(-3) 0.045 3 0.029 GI(LLI) 7.94(-4) 0.027 4 0.009 GI(LLI) 2.58(-4) 0.029 1982 1 0.008 GI(LLI) 2.58(-4) 0.032 2 0.030 GI(LLI) 3.09(-4) 0.010 3 0.577 Liver' l.24(-2) 0.021. Thyroid 1.42(-2) 0.025 4 0.538 Gl(LLI) 1.17(-2) 0.022 i'. i 1983 1 0.777 GI(LLI) 1.26(-2) 0.016

.3 2

• 0.007 GI(LLI) 1.73(-4) 0.025 l,; ;

3 0.007 GI(LLI) 2.15(-4) 0.031 4 0.0.16 GI(LLI) 4.12(-4) 0.026 c) i [ l e t t: 9

a., gm;.,,,.- :m v_.~ 3s. ,:y; . m, ;; g. - y .,v. r I 1/1/86 Rev.O i G f APPENDIX B i ~,L I DERIVATION OF FACTORS FOR SECTION C2 -LIQUID DOSES 1. Section C.2.a - Steo 2 Unit 2 - Liquid Doses Year, Qtr. _C_E Max. Orzan Doo Doo[.Gp- ~ 1976 1 0.102 GL (LLI) 0.0017 0.016 "~ 2 0.179 GI (LLI) 0.0051 ". 0.028 3 0.037 GI (LLI) 0.0024 0.065 4 0.025 GI (LLI) 0.00075 0.036 1977 1 0.217 GI (LLI) 0.012, 0.055 2 0.802 GI (LLI) 0.036-0.045 3 0.035 GI (LLI) 0.0014 0.040 4 0.509 GI (LLI) 0.012 0.024 1978 1 0.432 GI (LL1) 0.039 0.090 .2 1.27 GI (LLI) 0.13 0.120 3 0.715 GI (LLI) 4.2(-2) 0.059 4 0.372 GI (LLI) 9.0(-3) 0.024 1979 1 1.65 G1 (LLI) 4.l(-2) 0.025 2 2.48 GI (LL!) 2.3(-1) 0.097' 3 0.331 GI (LLI) 1.8(-2)- 0.054 4 0.411 G1 (LLI) ,,,1.6(-2) 0.039-1980 1 0.635 GI (LLI) 1.l(-2) 0.017 2 0.285 G1 (LLI) 3.9(-3) 0.014 3 1.1-CI (LLI) 1.0(-1) 0.085 4 0.723 GI (LLi' 7.4(-2) 0.102 1981 1 0.435 GI (LL'.. 2.91(-2) 0.067 2 0.343 GI (LLI) 2.91(-2) 0.085 3 0.265 GI (LLI) 7.47(-3) 0.028 4 3.14 Liver 1.67(-2) 0.005 1982 1 1.65 GI (LLI) 9.6(-2) 0.058 2 9.94 G1 (LLI) 5.76(-2) 0.006 Thyroid 3.59(-1) 0.036 3 1.14 GT (LLI) 2.43(-2) 0.210 Thyroid 2.84(-2 0.025 4 1.14. Liver 1.09(-2) 0.010 1983 1 ' l.48 Liver 1.66(-2) 0.011 2 0.685 Liver 1.14(-2) 0.017 3 2.42 GI (LLI) 6.36(-2) 0.026 4 3.22 GI (LLI) 7.74(-2) 0.024 2

'~. f ; y h g S C ? k'. 'Ws #r. M+= ' - ' " ~ s i-1/1/86 d' Rev.0 g Unit 3 - Liquid Doses .,3 ji ) I* Projected Rele$tses Maximum Dose Rate kom ER C1/vr Organ (mrem /vr) Dose /Ci + 'i 0.13 Thyroid 6.3(-3) 0.035 ?,.

• ~.

where,

~* CF = Curies of fission and activation products released during calendar quarter. GI (LLI) Gastro - Intestinal Tract - L ower Large Intestine. = Dgo Calculated critical organ dose to the maximum individual = (mrem) for the calendar quarter. Dose was calculated using the computer code LADTAP. Note: Tritium has never contributed more than 1% to the maximum organ dose and thus is it not iricluded in the calculation. (] Maximum Value of Dqo/CF -Unit 1 - 0.202 mrem /Ci s L' 3 Unit 2 - 0.120 mrem /Ci "W Unit 3 - unknown Average Value of Dgo/CF - Unit-I - 0.038 mrem 7Cle-Unit 2 - 0.044 mrem /Ci Unit 3 - 0.035 mrem /Cl Since the maximum value of Dgo/C i F s within a factor of two for Unit I and 2, the same factor can be used for all units for simplicity. Also, since the maximum value is within a factor of 6 of the average value, this indicates that . the dose per total curie does not fluctuate greatly, hence this method is not over-conservative. Thus, Dgo/CF = 0.2 mrem /Ci 1 e o e o S \\ o) ( /L ..y -3 a

m.:.5 nu::,;4%&z. y 3.

mv:p w - >+.a-n%nns.wwww.m 6:. 4 m :

n, T 1/1/86 jj. Rev. O h. '.D. APPENDIX C % "N = ] , LADTAP -LIQUID DOSE CALCULATIONS 't. n The LADTAP code was written by the NRC to compute doses from liquid releases 1 using the models given in Regulatory Guide 1.109. There is no revisloh date on the copy of the code which was obtained, but it was purchased in March 1976. The only - change made to the code since that time was a change in the ingestion dostfactors - from those given in Rev. O of Reg. Guide 1.109 to those in Rev.1. . ~. For calculating the maximum individual _ dose it. Millston'e', the following options and parameters are used: 1. Real time, measured dilution flow 2. Salt water site 3. Reconcentration - cycle time - 12 hrs. '(MP1 and 2 FES). Recycle fraction = 0.025 (Final Environmental Statements,for MP1 and 2) 4. Shorewidth factor = 0.5 (Table A-9, Regulatory Guide 1.109) 5. Dilution for Max. Individual Pathways - = 3 (page 5.2-5 of MP3 h Environmental Report) ~ . 9' 6. 30 min. Discharge Transit Time - time to transitLquarry; estimated from chloride study. ~ 7. Reg. Guide 1.109 usage factors for Max. Individual for fish, shellfish,- shoreline, swimming and boating pathways. 8. Zero usage for algae, drinking water, and irrigated food pathways.- p 6 b e .g 5'.'l - -

m, g-

.

jyK.y

• .'i

r, s

s 1/1/36 Rev.O APPENDIX D DERIVATION OF FACTORS FOR SECTION D GASEOUS DOSES 1. X/Qs, D/Qs Unit i Stack Elevated X/Qs, D/Qs Quarterly Averages - Maximum Values ~ Year Quarter Maximum X/Q Maximum D/Q 1976 1 2.7(-8) .l3.(-9) 2 2.3(-8) 2.l(-9) 3 4.7(-8) 5.5(-9) 4 2.6(-8) 7.9(-9) 1977 1 2.3(-8) 1.4(-9) ~ 2 4.1(-8) 4.2(-10) 3 4.3(-8) 2.2(-9) 4 5.4(-8) 4.3(-9) 1978 1 4.7(-8) 6.6(-9) 2 5.3(-8) 1.2(-9) 3 4.0(-8) 2.2(-9) 4 7.l(-8) 4.3(-9) 1979 1 4.2(-8) 5.l(-9) 2 5.2(-8) 1.5(-9) 3 3.2(-8) 2.4(-9) 4 5.7(-8) 4.9(-9) 1980 1 5.3(-8) 2.3(-9) 2 4.0(-8) 1.7(-9) 3 4.6(-8) 1.3(-9) 4 6.3(-8) 4.0(-9) 1981 1 4.5(-8) 4.3(-9) 2 1.6(-8) 9.l(-10) 3 6.3(-8) 1.6(-9) 4 4.9(-8) 6.2(-9) 1982 1 5.9(-8) 2.4(-9) 2, 2.6(-8) 2.4(-9) 3' 4.3(-8) 2.2(-9) 4 5.l(-8) 1.2(-9) i O..

y : :..:,,' c, .. u,.- ~: e-a :.. ,.., 3m, cg.7-.i,. : p g ;,:p , :.,,.w-

w 9c 1/1/86 s

Rev. O r i Year Quarter Maximum X/O Maximum D/O 4 - N.. + ! { m,tk )i 1983 1 -3.7(-8) 3.3(-10) 2 6.0(-8) 3.9(-10)- }f i 3 4.4(-8) 5.5(-10) 4 6.0(-8)' l.S(-9) i

1. 3

,t I l: Maximum Quarterly Average X/Q = 7.1 x 10-8 sec/M - 3 Maximum Quarterly Average D/Q = 7.9 x 10-9 M-2 j g ) E 'e g e 9 8 b t, r 4 I t j t t 1 !A - 8 e j i' t b i i od!/ - 6 a I e

• *t

?

• 's..

s e ) 9 j r i .l 4 - l l 1 l 4 1 i O A O 4 e t ? -f i, 1. e

• b

.e e 1

g.,<.

h [,' e I I -. .t. j i J 3 t e 4 e , + m v g,p -e--+ o-n-e -r. ,mm--4,.pv ,--g--.-,,, 4- -+g.,ny,v..,4..,p.e,,n,-,,.--m w-n w +.,,, ,,g.,-w.-. p -,,, s r gem v m .-o p y wm e m geww w m. m p-wwey em

-s,. z m 1 1/1/86 Rev.0 Unit 2 and Unit 3 - Vents

• t Quarterly Average X/Qs - D/Qs

{ Maximum Values 'j Maximum X/Q Maximum D/O Year Qtr Continuous Batch Continuous.. Batch 1976 1 5.0(-6) ND 4.3(-8). ND 2 1.3(-3) ND 6.7(-8) ND 3 4.4(-6) 3.!(-6) 4.5(-8) 3.0(-8) 4 2.2(-6) 5.9(-6). ,2.5,(-8), ' ', ' ' 6.5(-8) 1977 1 2.3(-6) 4.l(-6) 3.2(-8) 5.4(-8) 2 1.9(-6) 1.4(-6) 1.3(-8) 1.3(-8) 3 3.2(-6) 7.5(-6) 1.5(-7) 1.5(-7) 4 3.5(-6) 2.6(-6) 6.9(-8). 5.2(-8) 1978 1 2.5(-6) ND 4.3(-8) ND 2 5.3(-6) 1.6(-6) 3.7(-8) 2.9(-8) 3 9.l(-6) 3.2(-6) 1.4(-7) 1.l(-7) 4 3.3(-6) 4.2(-6) 3.7(-8) 8.0(-8) 1979 1 2.2(-6) ND 3.8(-8) ND 2 5.l(-6) 5.0(-6) 3.0(-8) 6.2(-3) 7.5(-6) 5.l(-6) 1.3(-7) 9.4(-3) 3.3(-6) 4.6(-6) 9.3(-8) 1.0(-7) 2 1980 1 2.3(-6) 9.5(-7) 3.l(-8)' 6.5(-8) 2 6.9(-6) 6.3(-6) 'l~.1(-7) 1.3(-7) 3 7.3(-6) ND 1.2(-7) ND

• 4 3.2(-6)

ND 7.6(-8) ND 1981 1 3.9(-6) 1.3(-7) 6.5(-8)

1. !(-3) 2 7.9(-6) 3.3(-9) 1.0(-7) 7.0(-10) 3 4.9(-6) 7.3(-8) 9.6(-8) 4.9(-9) 4 1.7(-6) 3.5(-8) 4.!(-8) 5.l(-9) 1982 1

2.9(-6) 5.4(-8) 4.5(-8) 2.l(-9) 2 6.5(-6) ND 9.2(-3) ND 3 6.7(-6) 4.5(-8) 1.2(-7) 2.1(-9) 4 4.2(-6) 2.9(-8) 1.0(-7) 1.4(-9) 1983 1 1.3(-6) 9.l(-8) 2.6(-3) 6.7(-10) 2 5.4(-6) 1.7(-7) 1.l(-7) 2.0(-9) 3 3.!(-6) 2.4(-7) 1.5(-7) 4.4(-9) 4 2.3(-6) 1.2(-7) 6.2(-8) 6.4(-9) Maximum Quarterly Average X/Q = 1.3 x 10-5 Sec/M3 Maximum Quarterly Average D/Q = 1.5x 10-7 M-2,

.~.: e,,.;..g s.,,,y:sa m y.,.,,.- .sww mz,i:.n.. .e

wn7,yc.m m -m.

.lll 1/1/86 Rev.0 j ,e / a From the above data we can also see that the batch releases are of a random 8 -l;- enough nature such that the batch release meteorology approximates the !i. continuous met,eorology as shown by the average of the.above values: 'l

1. [

Average Max. Qtr. X/Q - Continuous Release - 5.0 x 10-6 .~ * * - Average Max. Qtr. X/Q - Batch Releases - 2.7 x 10-6 *. 4 [ Average Max. Qtr. D/Q - Continuous Releases - 7.3 x 10-8 ..n,, ~ Average Max. Qtr. D/Q - Batch Releases - 4.5 x 10-8 Therefore, the same.X/Qs and D/Qs can be used for both batb' and continuous. releases. Release heights for these two vents are approximately the same. Tables D-2a and D-2b of the NRC Draft Environmental $iatement for Millstone 3 show that the average X/Q for Unit 3 to be less than Unit 2 (because of location), however the D/Qs are equal. I ..,-jf 5 e e e S 4 3 6 e Q. i

- n ;%. < W - x F m en =:j.:m. o;.a m..-n 1/1/36 Rev.0 g 2. Section D.I.a - Noble Gas Release Rate Limits 3 . Unit 1 Stack Gaseous Releases - Curies vs. Dose Max. Individual mrem per Avg. Noble Gas Dose (Mrem) uCi/Sec Year Quarter Release Rate (uCl/Sec) W. B. Skin W.11. and Skin .{ 1976 1' 17,400 1.9 1.9 1.L14) 2 25,600 4.2 4.3 1.6 (4) 3 20,100 3.4 3.4 .,,1.7(4) 4 2,600 0.3 0.3 1.0 (-4) 1-4 16,400 9.3 9.9 6.0 (4) 1977 1 11,600 1.1 1.1 8.6 (-3) 2 13,000 1.9 1.9 1.5 (-4) 3 24,000 4.6 ' 4.'6 ' ' l.9 (-4) 4 29,700 2.2 2.2 .7.4 (-3) 14 19,600 9.3 9.3 5.0 (-4) 1973 1 50,300 4.4 4.4 3.7 (-5) 2 20,300 3.1 3.1 1.5 (4) 3 350 0.04 0.04 1.3 (-4) 4 530 0.03 0.03 6.4 (-5) 1-4 13,100 7.6 7.6 4.2 (-4). 1979 1 t,180 0.032 0.032 2.7 (-5) 2 380 0.024 0.024 6.3 (-5) 3 640 0.06L. 0.061. 9.5 (-5) 4 420 0.024 0.024 5.7 (-5) - 14 655 0.14 0.14 2.1 (-4) 1980 1 360 0.018 0.020 5.0 (-5) 2 230 0.019 0.019 3.2 (-3) 3 880 0.20 0.20 2.3 (-4) 4 40 6.4(-4) 6.4(-4) 1.6 (-5) 1-4 380 0.24 0.24 6.3 (4) 1981 1 1.2 6.0 (-6) 6.0 (-6) 5.0 (-6) 2 25 0.004 0.004 1.6 (-4) 3 1580 0.19 0.19 1.2 (-4) 4 220 0.015 0.016 6.3 (-5) 14 460 0.21 0.21 4.6(-4) 1982 1 160 0.004 0.004 2.5 (-5) 2 140 0.042 0.042 3.0 (-4) 3 490 0.051 0.052 1.0 (-4) 4 240 0.002 0.002 8.3 (-6) 1-4 260 0.10 0.10 3.3 (-4) 9 -3 e.

y+2xypma n -.:..c7a..samAmy. ~, o w ~ m,w w wmuc,w-m nt w w. ? , ~. ~ -- L: -:l 1 = 1/1/86' l.j

• • v 0

'4 Max. Individual-mrem per - d ff Avg. Noble Gas -Dose (Mrem) . uC1/Sec-

Ij Year Quarter Release Rate (uCl/Sec)

W. B.7 Skin W.B. and Skin ' Aii 1983 1 %0 ' O.002 f 0.002 3.'6 (-6) 2 120 - O.014 0.014 - 1.2 (4)- -12 3 74 0.012 0.012 1.6 (-4) '

3 4'

0.003 0.003-5.4 (-3) I 1-4

200

.0.031-10.031' 1.6,(-4) '. ~ Unit 2 Stack-Gaseous Releases - Curies vs. Dose l.. -~. Max.'Individuall * 'nfrem ph Avg. Noble Gas . Dose (mrem) Luci/Sec.. ' Ratio ' Skin. - W. B. - Skin /W.B. Year Quarter Release Rate (uC1/Sec) W. B. 1976 1 0.63 0.00016 0.00047 - 2.5 (-4) 2.9 : 2 83 0.058' . 0.16.. 7.0 (-4) ~ 2.3-3 54 .0.015-0.055 2.3 (4)

3.7(

4 63' O.022

0.035' 3.5 (-4) -

1.6 : 14 50 ' O.095 0.25. 1.9 (-3) 2.6 .q 1977 1 134 0.023 0.058 1.7 (-4) 2.5 2 70 0.007 0.018 ' 1.0 (-4) 2.8 'i 3 39 0.019 -0.056 4.9 (-4) _ 2.9. 4 69 0.010 0.030 ' 1.4 (4) i 3.0 s ,g) 1-4 78 0.059 0.162~ - 7.6 (4) ' 2.7 i 1978 1 10 0.0068

0.012 6.1 (4),

.1.8 ~ 0.019 ' * ' O.U58 : 2.1 (4) . 3.1 ~ 2 91 3 313 0.13 ' O.37 4.2 (-4). 2.8 4 21 0.0054 0.011 - 2.6 (-4). - 2.0 1-4 109 0.16 0.45 1.5 (-3) ' 2.8. 1979 1 7.1* 0.0081 0.019 ;, 1.1 (-3). 2.3 2 2.6 0.0066 0.0021

2.5 (-4) 3.2 a 3

38 O.013 0.037. ' 3.4 (-4) 2.8 4 23 0.0052 0.015-

2.3 (4) '

-2.9 14 18 '0.027 0.073

1.5 (-3)

• ~ 2.7 54 0.0086'

'O.'022 1.7 (4) ~ ~ 2.6 1980 1 2 47 0.020-0.056 ' 4.3 (4) 2.8 _-- 3 67 0.066' O.131 9.9 (4) 2.0 '4 1.7 - 0.0028 0.0043 1.8 (-3) 1.5 4 1-4 42 0.098 ' 'O.212 - 2.3 (-3)

2.2 1981 1

.16 0.0061 10.014 ~ 3.8 (-4) 2.3 2 .124 0.075 0.20 6.0 (-4). 2.7 3 64 0.030 0.078 4.7 (-4)' . 2.6 - 4 74 0.013 - 0.033- ' 1.6 (-4) ' 2.5 14 70 -'O.124. 0.325 1.8(-3) ' 2.6 ' .q.._. - 6 a e

m.. ..m - -r. m l 1/1/86 j Rev.O i Max. Individual mrem per j Avg. Noble Gas Dose (Mrem) uCi/Sec Ratio L Year Quarter Release Rate (uCi/Sec) W. B. Skin W. B. Skin /W.B. I ~ A 1982 1 5.3** 0.013 0.022 2.5 (-3) 1.7 I 2 322 0.13 0.49 5.6 (4) 2.7 3 205 0.13 0.34 6.3 (4) - 2.6 4 191 0.074 0.18 3.9 (4) 2.4 Li 14 ISO 0.397 1.032 2.2 (-3)..,, 2,6 1983 1 464 0.041 0.11 8.3.(-5) 2.7' - 2 659 0.22 0.62. 3.Y(4) 2.3 3 0 0.0045 0.0053 1.2 4 0 0.0020 0.0023 1.2 1-4 280 0.268 0.737 9.6 (4) ' 2.3 Only continuous ventilation (purge data leads to an unconservative value). Beginning in 1982, purges are released through Uni.t I stack. Unit 3 Vent - Gaseous Releases - Curies vs. Dose Max. Individual mrem per Noble Gas Dose (mrem) uCi/Sec Ratio Release Projection Release Rate (uC1/Sec) W.B. Skin W. B. Skin /W. B. Unit 3 FSAR and ER 14.2 0.16 0.29 1.1 (-2) 1.3 e Design releases from Unit 3 FSAR Table 11.3-11 and Unit 3 ER Table 3.5-14: 14,141 Ci/yr = 443 uCi/sec. Expected releases from Table 11.3-11: 448 C1/yr which equals 14.2 uCi/sec. Maximum value of mrem / year per uC1/sec is from 1980 for Units 1 and 2. Since the average X/Qs are less for Unit 3 than for' Unit 2, a conservative estimate for Unit 3 would be to assume its value would be the same as for Unit 2. These values for whole body doses are Unit 1: 6.0 x 10'-4 ' mrem /yr. per uCi/sec Unit 2: 2.3 x 10-3 mrem /yr. per uC1/Sec Unit 3: 2.3 x 10-3 mrem /yr per uCi/Sec. . i.

..,7 p m,,,. .., ~ ~ 29mmy 3

• I 1/1/s6 -

Rev.0 .1 , j. The 10CFR20 limit is 500 mrem to the whole body and 3000 mrem to the skin.- i j v.g*j/ ' Since the skin dose has never been as much a six tl:/.es the whole body dose for .j ~ 'j] Unit' 1 or Unit '2 - releases, we can use-the 500 meem as the -limiting dose. !j Therefore, the release rate limits would be: - ~ Unit 1: -500/6.3 x 104 = 790,000 uC1/sec. )j Unit 2: ' 300/2.3 x 10-3 = 217,000 uCi/sec. Unit 3: 500/2.3 x 10-3 = 217,000 uCl/sec. t ~~ However,10CFR20 is a site limit, therefore the limit is: 01 O2' + 03- ,<. ' l 790,000 217,000 217,000

where, l

Q1 = noble gas release rate from MP1 stack (uCi/sec) ' ; - Q2 = noble gas release rate from MP2 vent (uCi/sec) 4 Q3 = noble gas release rate from MP3 vent (uCl/sec) .l Y Justification for Above Method

i The above method of determining instantaneous release rates will ensure j

compliance with 10CFR20 for the following reasons: 1. The doses presented for Unit I were calculated using the EPA AIREM code, [ W) which uses a finite cloud model similar to that in Reg. Guide 1.109. This. code has compared very favorable with data actually-measured at the critical site boundary with a pressurized..lon chamber.. Plant related quarterly doses measured 6y the lon chambd' were calculated uping a j model developed by ERDA's Health' and Safety Lab. These doses have ~' always been within 30% of those' calculated by AIREM. The average difference has been 14%, with the AIREM code calculating the ' higher i dose. Thus, we are ensured that the AIREM code yields reasonable, if not i s!!ghtly conservative, estimates of the maximum individual whole body dose. 6 ( 2. The doses presented for Unit 2 were calculated using the NRC GA, SPAR code which uses the methodology of' Reg. Guide 1.109. 3. The doss per curie release can be seen: from the tables not to vary significantly from one quarter to the next.. -I Unit 1: Minimum Value - 3.6 x 10-6 mrem /qtr. per uC1/sec Average Value - 1.0 x 104 mrem /qtr. per uC1/sec l ~

i. '

Maximum Value -~ 3.0 x 104 mrem /qtr per uC1/sec j I j. Unit 2: Minim'u'm Value - 3.8 x 10-5 mrem /qtr. per uC1/sec 4 mrem Average Value - 5.2 x 10 Maximum Value - 2.5 x 10-3 mrem /qtr. per uC1 /qtr. pcr uCl/sec

1. I

.g-7,, w. .- ~; 1/1/86 Rev.O It can be seen that the maximum value observed is only a factor of 3 j greater than the average value even though there have been sig/or nificant .7 changes.in the isotopic compositions of the releases and the meteorological frequencies. ~ The isotopic changes include significant operational changes such as: y a. Operation with and.without the recombiner-charcoal delay system on the Unit 1 off-gas. ~~ b. Period when a unit was down the entire quarter for re, fueling. Quarters with many MP2 containment purges and'qtiarters with no ~ c. purges. d. Quarters with relatively high and relatively low fuel leakage from MPl. Thus, the dose per curie released is not that sensitive to operational changes such that a gross curie release ratio can be used. We have been conse*vative in taking the worst annual ratio abserved. 4 It should also be recognized that there is a great deal of conservatism between this method and the actual requirements of 10CFR20 for the following reascns: 10CFR20 states that " release rates may be averaged over a year, a. however we are using this as an instantaneous release rate limit. b. 10CFR20 ilmits are i;ound level ' con'cEkation limits,' which for elevated releases from the Units I stack would be less restrictive than the use of the elevated finite cloud model as used here. 5. It must also be recognized that the type of empircal method given above is the only practical operational method. The use of a method similar to that given in NUREG-0133 would be an operational nightmare, would be next to impossible to implement and could yield allowable release rates many times that given above. For example, releases from the Unit I stack could include any of the following releases: MP1 ventilation from radiological areas MP1 off-gass release from the off-gas treatment system MP1 off-gas releases via the 30 minute holdup pipe MP1 mechanical vacuum pump MP1 gland, seal condenser MP2 waste ga' tank discharge s MP2 containment purges MP2 ventilation from radiological areas MP2 condenser air ejector MP2 mechanical vacuum pump > i e - e on+.

-cr V :.m a=;? ' x m< ~. rmW- ' ' ~ 1/1/36 i Rev.0 o ,h MP3 ventilation from radiological areas y, ^l W.V MP3 condenser air ejector 1-MP3 reactor plant gaseous vents ~ lj. MP3 radioactive gaseous waste system f MP3 containment vacuum pump MP3 reactor plant aerated vents j. MP3 steam generator blowdown tank vent 2: These sources may exist in any possible combination and each has its own particular, but changing, nuclide mixtures. Thus, the ratio of ~riuclid.'es - being released is a constantly changing parameter. ~ It is impractical to recalculate a stack release rate based on isotope specific dose conversion factors each time a source stream is initiated or terminated or a new isotopic analysis is performed on any of the source streams. This could require 4 or 5 recalculations and monitor set point changes each day..The plant could not operate in'ihis manner. It would als be unnecessarily restrictive to assume the worst possible mixture and use that as the limit for all situations. The only practical solution is to use a conservatively determined empirical method as given above. ~) g:e \\ 4 C' 0 j, A M [ i .*h l L j' J., 0

-.:~.-. : y..ac. - ~., =,,....,.,.:,. v, mn -,.m., -, I 1/1/86 Rev.0

i j

3. Section D.I.b -Iodine. Particulate and Other Limits 1 i a. Iodine, Iodine Release vs. Dose - Unit 1 Thyroid Curies Dose Year Quarter I-131 mrem mrem /Cl '~ 1976 1 0.58 0.6 1.0,,,, 2 0.75 3.8 5.,1 3 0.58 4.9 8.4 ' 4 0.29 0.6 2.1 14 2.20 9.9 4.5 1977 1 0.39 0.3 '" '" 0.8 2 0.59 1.2 2.0 3 1.57 5.4 3.4 4 2.1 4.6 2.2 14 4.65 11.5 2.5 1978 1 1.70 8.7 5.1 2 1.15 3.1 2.7 3 0.18 0.6 3.3 4 0.16 0.3 1.9 14 3.19 12.7 4.0 1979 1 0.21. 0.01.... 0.05 2 0.10 0.60 6.3 3 0.04 0.44 10.2 4 0.06 0.004 0.07 14 0.41 1.05 2.6 1980 1 0.021 0.004 0.19 2 0.048 0.32 6.7 3 0.111 0.59 5.3 4 0.034 0.002 0.06 14 0.214 0.916 4.3 1981 1 2.4 (-5) 1.9 (-5) 0.79 2 0.001 0.004 4.0 3 0.042 0.50 ' 11.9 4 0.032 0.002 0.06 14 0.075 0.51 6.8 1982 1 0.032 0.'002 0.06 2 0.027 0.23 S.5 3 0.038 0.52 13.7 3 4 .0.002 1.2 (-4) 0.05 14 0.099 ~ 0.752 7.6 e. A

. pfg y ar w e.S $ p w w w w c ee., .s, +.mwm --. =.-, m :n ~+ F -1/1/86 Rev. 0 todine Release vs. Dose - Unit 1 - g li Thyroid ~ - j[' Curies Dose 3 Year Quarter I-131 mrem mrem /Ci

s

? 1983 1 0.006 - 2.3 (4) ^ 0.04 ' - i' 2 0.007 0.054 7.7 3 0.010 0.10 10.0 '~ 4 0.007 - 5.7. (-4) 0.08 i 14 0.030 0.155 54, Iodine Release vs. Dose - Unit 2 Curles Dose 'd inrem/Cl Year Quarter I-131 mrem 1976 1 3.3 (-3) 0.015 4.5 2 4.0 (-3) 0.076 19.0, 3 1.3 (-3) 0.077 43.7 4 4.2 (-4) 0.023' 54.3 14 9.5 (-3) 0.191 20.1 1977 1 2.6 (-4) 0.010 38.5 2 1.3 (-3) 0.047 26.1 -<3 . Ji 3 6.9 (4) 0.037 53.6 4 2.5 (-3) 0.064 25.6 y 14 5.2 (-3) 0.151.. 30.4 1973 1 6.9 (-4) 0.024 34.8 2 1.0 (-3) 0.051 51.0 3 5.7 (-3) 0.52 91.2 4 6.7 (-5) 0.017 253.3 1-4 7.5 (-3) 0.612 81.6 1979 1 1.2 (-2) 'O.004 0.3 2 7.4 (4) 0.054 73.0 3 9.1 (-4) 0.16 175.3 4 1.2 (-3) ' O.006 6.0 14 1.5 (-2) 0.22 14.9 1980 1 6.4 (-4) 0.003 '4.7 2 2.1 (-3) 0.21 80.8 ~. 3 3.2 (-3) 0.30 93.8 i 4 3.3 (4) 0.094 284.8 -h. 1-4, 6.3(-3)- 0.61 96.8 / 1981 I 4.6 (4) 0.007 15.2 2 7.8 (4) 0.13 166.7' 3 3.4 (-4) 0.041 120.6 7> 4 1.0 (-1) 0.093 0.9 .J' 1-4 1.0 (-1) 0.27 - 2.7 l.4

y g g c. c.. 7. e, m w vm .m l 3 1/1/86 il Rev. O i [ Iodine Release vs. Dose - Unit 2 .4 Curies Dose i Year Quarter I-131 mrem mrem /Cl 1982 1 4.3 (-3) 0.009 1.9 2 1.1 (-2) 0.677 61.5 3 3.2 (-2) 2.31 37.3 4 3.7 (-3) 0.022 2.5 1-4 5.7 '(-2) 3.52 61.3 1983 1 1.1 (-2) 0.009 0,3". 2 1.1 (-2) 0.33 75.5 3. 1.3 (-3) 0.17 130.8 4 9.5 (-3) 0.003 31.6 1-4 2.3 (-2) 1.01 ,,,, 4 3.9 lodine Release vs. Dose - Unit 3 Curles Release Projection

• I-131/vear mrem /yr mrem / Curie Unit 3 FSAR 0.065 3.6 55.4
• Expected releases from Unit 3 FSAR Table 11.3-1 and from Unit 3 ER Table 3.5-14.

) Maximum Annual Value for MP1 is for 1982 = 7.6 mrem /Cl I-131 Maximum Annual Value for MP2 is for 1980 = 96.3 mrem /Cl I-131 Since D/Qs for Unit 2 and Unit 3 are equal (See NRC Draft Environmental Statement for Unit 3) this value should be approximately equal to Unit 2's value. Therefore, the Maximum Value for MP3 = 96.3 mrem /Cl1-131. 1.imit is 1500 mrem /yr. to the thyroid MP1 allowable release rate = 1500 mrem /yr/7.6 mrem /Cl x 106 uCl/Cl x 3.17 x 10-8 yr/sec = 6.26 uCi/sec MP2 and MP3 allowable release rate = 1500 mrem /96.3 mrem x 106 x 3,17 x 10-8 0,49 uCl/sec 9 G ~l3 -

. c. wm;m .v w qw.* r.~ ., mr n - ~ + -b 1/1/86 . I Rev. 0 y 'I-Since this is a site limit, the allowable release rate for I-131 is:. M) J 4 QIl +.Q12 QI3 + $1 o 1 f-6.26 0.49 0.49 1

t N

'p-where t Qtt = Release rate of I-131 from MP1 Stack (uC1/sec)- QI2 = Release rate of I-131 from MP2 Vent (uC1/sec) Q13 = Release rate of I-131 from'MP3 Vent (uC1/sec) b. Particulates with Half 1.lves Greater Than 8 Days Particulate Releases vs. Dose - Unit 1 "f #

• Total Curles Max. Organ Max. Organ

.Y_9.E Quarter Particulates Ex. Thyroid Dose (mrem) mrem /Cl 1976 1 0.040 Bone 7.9 (-3) - 0.20 2 0.043 Bone 2.1 (-2) 0.49 3 0.051 Bone 1.7 (-2). 0.33-4 0.014 - Bone 1.1 (-2) 0.79. 1-4 0.148 ~ 5.7 (-2) 0.39 ~ s. 1977 1 0.009 Bone 3.2 (-3) 0.36 2 0.014 Liver.. ;... ,4.3 (-3) 0.31 3 0.075 Bone 1.5(-2) 0.24 4 0.103 Bone 5.0 (-2) L 0.49 l-4 0.201 7.6 (-2). 0.38 1978 1 0.156 Bone ~ 1.6 (-1)- 1.02 2 0.963

Bone 9.5 (-2) 0.10 3

0.131 Bone. . 2.7 (-2) 0.21 4 0.105. Bone-2.5 (-2) ' O.27 1-4 1.355 3.1 (-1) 0.23 e 1979 1 0.083 Bone 3.4 '(-2) - 0.41 2 0.038 Bone 3.5 (-3) 0.09 3 0.031 Bone-1.2 (-2) 0.39 4 0.037 Bone .1.1 (-2) 0.30 1-4 0.189 6.1 (-2). 0.32 l 1980 1 0.028' ' _ Bone ' - 1.6 (-2) 0.57 1 r 2 0.020 Bone' 3.1 (-3). 0.26 I' 3-0.063 Bone

3.0 (-2) 0.48 t

de 4 - 0.008 - . Bone-1.2 (-2) 1.50 1-4 . 0.119 6.3 (-2). 0.53 '6 l* 6 t ,1 qe i 'h 1 F.

f.w .e m- ~ 1/1/86 Rev.0 3 Total Curies Max. Organ Max. Organ Year Quarter Brticulates Ex. Thyroid Dose (mrem) mrem /Cl ' ? I 1981 1 0.002 Bone 1.2(-3) 0.60 2 0.008 Bone-1.7(-3) 0.21 3 0.24 Bonc 6.3(-3) 0.26 4 0.039 Bone 9.5(-2) 2.44 1.0(-1) 1.37.. 14 0.073 ~ ' ~ 1982 1 0.038 Bone 1.l(-2),,,, 0,29 2 0.033 Bone 1.0(-2), 0.30 3 0.031 Bone 7.7(-3) 0.25 4 0.009 Bone 1.3(-3) 0.14 14 0.111 3.0(-2) 0.27 1983 1 0.007 Bone ' 4.4(4) 0.06 2 0.006 Bone 8.2(4) 0.14 3 0.010 Bone 1.4(-3) 0.14 4 0.010 Bone 4.0(-3) 0.40 14 0.033 6.7(-3) 0.20 Particulate Releases vs. Dose - Unit 2 Total Curies Max. Organ Max. Organ Year Quarter Particulates Ex. Thyroid Dose (mrem) mrem /Ci r 1976 1 3.2(-5)~ Lung 3.'(-4) '10.2. 3 2 3.6(-5) GI-Tract 5.4(-5) 1.5 3 1.2(-5) Bone 3.l(4) 25.8 ( 4 1.8(4) Bone 6.3(-4) 3.5 14 2.6(-4) 1.3(-3) 5.1 / 1977 1 1.6(4) Liver 1.0(-3) 6.5 2 4.1(-7) Bone 1.9(4) 463.4* 3 1.3(-5) GI-Tract 2.9(-5) 2.2 4 2.2(4) GI-Tract 7.l(4) 3.2 14 3.9(-4) '1.9(-3) 4.9 ~ 1978 1 2.5(4) G1 Tract 8.9(4) 3.6 2 4.1(-5) Bone 1.8(-3) 44.0 3 1.0(4) Bone - 2.0(-3) 20.I' 4 6.4(-5) Bone 5.5(-4) 8.6 14 4.6(4) 3.2(-3) 11.4

• Outiler O 1 e

v.,. -

. a:, v ;.;,, .; y - n i. w.. ......n-. 1/1/86 4 .j i Rev.0 t 'b Total Curies Max. Organ Mix. Organ !; xfM Year Quarter Particulates Ex. Thyroid Dase (mrem) mrem /Cl e l! 1979 '1 9.3(-5) Bone 1.5(4) 1.5 ~

• j 2

1.3(4) Bone 4.6(4) 3.5 3 9.4(-5) Bor e 8.5(4) 9.1 j' 4 5.5(-5) Lung 1.S(-5) 0.3 1.5(-3) 3.9 .1-4 3.S(4) i: 1980 1 5.4(-5) Lung 1.3(-5) 0.24 ~~ 2 6.9(-5) Bone 5.6(4), 8.2 3 7.9(-3) Bone 7.6(c5), 1.0 4 4.0(-5) Lung 8.9(-3) 2.2 7.4(-4) 3.1 14 2.4(-4) 1981 1 4.4(-5) Lung ... 2.2(-5) 0.5 2 5.3(-5) GI-Tract ' " I'.7(-4) 3.2 ^ 3 3.2(-5) Bone 3.3(-5) 2.3 4 3.6(-5) GI-Tract 1.9(-5) 0.5 3.0(-4) 1.8 14 1.7(-4) 1982 1 3.5(-4) Lung 1.2(4) 0.3 2 5.4(-5) Bone 1.0(-4) 1.9 3 1.7(-4) Bone 1.4(-3) 3.1 eq 4 3.6(4) Lung 3.0(-5) 0.08 l-4 9.3(4) 1.7(-3) 1.8 1983 1 3.4(4) Bone 7.4(-6) 0.02 3-2 1.5(4) _ Bone.;.. 3.l(-3) 20.7 3 5.3(-5) Bone 1.'l(-3) 19.0. 4 5.4(-5) Lung 1.4(-5) 0.3 1-4 6.0(4) 4.2(-3) 7.0 Particulate Releases vs, Dose - Unit 3 Maximum Total Organ Particulate Maximum Organ Dose Release Projection

• Curies Excluding Thyroid (mrem) mrem /Ci Unit 3 FSAR 0.16 Liver *
• 3.6 22.5 Expected releases - from Unit 3 FSAR Table 11.3-1 and.from Unit 3 ER Table 3.5-14.

From Unit 3 ER Table 5.2-10 (Note: some of the liver dose may be from H-E 3, however the. bone dose is 3.2 mrem, all of which should be due to particulates), i. 5. Maximum Value for MP1 is.for 1981 = 1.37 mrem /Ci v.& .3

.... ~.,. >: r,.. ;ae, e- ,.. w..m ~ m 1/1/36 .j Rev. O A Maximum Value for MP2 is for 1973 = 11.4 mrem /Ci 4 { Limit is 1500 mrem /yr to the maximum organ h MP1 allowable release rate = 1500 mrem /yr/1.37 mrem /Cl x 106 uC1/Cl x 3.17 x 10-8 yr/sec =r 35 uCl/sec MP2 allowable release rate = 1500/11.4 x 106 x 3,17 x 10-8 = 4.2 uCi/sec ~ ~ ~ ~ MP3 a11owable release rate = 1500/22.5 x 106 x 3,17 x 10-8 = 2.1 uC1/sec Since this is a site limit, the allowable release rate for p'uticulates is: Q1 Q2 Q3 1 + + 35 4.2 2.1 where Release rate of total particulates with half lives greater than 8 days Q1 = .from the MP1 Stack (uCi/sec) Release rate of total particulates with half lives greater th'an 3 days Q2 = from the MP2 Stack (uCi/sec) Q3 Release rate of total prticulates with half lives greater than 3 days = from the MP3 Stack (uC1/sec) O 4 y' .I f o O.

2-- ' *:. %*'" I " ~.4 ' K '-rff.. l* i * , ;

• 4 ' b,

L, -3.; 'u~, '6 ' o s IC'Q,;~y ll M *K: P:, ..2."* ~.7.. .i i I 1/1/86 1 Rev.0 'h c. Tritium ]l Unit 1 Tritium Releases - Curies vs. Dose .) ; Dose (mrem) Due Year Quarter Curies to Tritium mrem /Ci ~ 1976 1 3.71 2.5(-3) 6.7(-6) 2 1.47 8.l(-6) 5.5(-6) 3 11.4 8.2(-5) 7.2(-6) ~ 4 12.1 6.2(-5) 5.1(-6), 14 28.7 1.8(4) 6.3(c6), 1977 1 7.17 3.2(-5) 4.5(-6) 2 9.24 7.5(-5). 8.l(-6) 3 19.3 1.8(-4) ...' " 6.3(-6) 9.4(-6) 4 29.5 1.9(4) 14 65.2 4.8(4) 7.4(-6) 1978 1 16.8 L7(4) 1.0(-5) 2 7.68 8.6(-5) 1.1(-5) ~ 3 13.1 1.l(4) 8.5(-6) 4 11.1 1.7(4) 1.5(-5) 14 48.7 5.4(4) 1.l(-5) (~ 1978 1 Iti 1 4.4(-6) 3.1(-7) 2 11.8 7.8(4) 6.6(-5) 3 24.2 2.3(-3) 9.5(-5) 4 9.22 2.8(-6) 3.0(-7) 14 59.3 3.l(-3) 5.2(-5) 1980 1 15.2 7.9(-6) 5.2(-7) 2 11.3 6.7(4) 5.9(-5) 3 27.2 8.l(-4) 3.0(-5) 4 41.8 7.l(-4) 1.7(-5) 14 95.5 2.2(-3) 2.3(-5) 1981 1 9.96* 2 26.9 1.0(4) 3.7(-6) ~ 3 U.9

• 4 30.9*

14 26.9 1.0(4) 3.7(-6) 1982' 1 18.6 6.0(-6) 3.2(-7) 2 11.6 1.2(-3) 1.0(4) 3 12.5 8.2(4) 6.6(-5) 4 11.1 1.8(-6) 1.6(-7) 14-53.8 2.0(-3) 3.8(-5) ,.:,q) 1

~ n.;x-e :.m mxp.; v.:.c.mmm.2. -- .:,m w-m -n 1/1/86 s Rev.0 j 'l Dose (mrem) Due j Year Quarter Curies to Tritium mrem /Cl ..o 1983 'l' 15.6 1.3(-6) 1.2(-7) l 2 17.0 5.l(4) 3.0(-5) 's 20.7 1.2(-3) 5.8(-5) i 4-22.6 6.9(-6) 3.1(-7) 14 75.9 1.7(-3) 2.3(-5) ?

• Note:

These were, inadvertently left out of the GASPAR runs for thes6~ '- quarters (dose consequence is insignificant), therefore' total is for 2nd quarter only. Unit 2 Tritium Releases - Curies vs. Dose Dose (mrem) Due Year Quarter _ Curies to Tritium mrem /Ci 1976 1 0.16 2.6(-5) 1.6(4) 2 2.15 1.S(-3)' 8.4(4) 3 4.34 1.7(-3) 3.9(4) 4 1.79 6.2(4) 3.5(4) 14 8.4 4.1(-3) 4.9(4) 1977 1 2 3 2.30 3.4(-3) 12(-3) 4 1.39 1.3(-3) 1.4 4.69 '4.7(-3) ~' ' 7.l(4) l.0(-3) 1978 1 2 3 16.9 2.6(-2) 1.5(-3) 4 22.7 1.2(-2) 5.5(4) 14 39.6 3.S(-2) 9.6(4) 1979 1 20.5 7.3(-3). l.6(4) 2 12.4 1.l(-2) 8.9(4) 3 57.4 7.l(-2) 1.2(-3) 4 13.5 2.l(-3) 1.5(-4) 14 103.3 9.l(-2) 8.S(-4) 1980 1 9.3 9.0(4) 9.2(-5) 2 10.8 1.3(-2) 1.2(-3) 3 103.0-3.5(-2)- 3.4(4) 4 725.0 3.8(-1) 5.2(4) 14. 348.6 4.3(-1) 5.1(4) 1 i O ~-

a sp:yyty ;y j a.c w.~~. mr m. - n.~7:;*w p? m.m..n:m e c.m = - m 1 - - a. .= ..._ e w n.m -= P 1/1/86 . Rev. 0 - L /i h Dose (mrem) due ii. d$ Year - Quarter Curies to Tritium mrem /Cl i: ' 1981 1 '39.4 6.2(-3) 1.6(4) 2 ~53.4 '7.0(-2) 1.3(-3)' 3 23.7 -1.9(-2) 8.0(4) ~. 4 22.3 6.2(-3) 2.8(4) ' ' 14 138.3 1.0(-1) 7.3(4). 1982 1 '13.8 1.6(-3)' 1.2(4)' .~ 2 9.1 - 1.0(-2) 1.1(-3L' 3 20.8 3.1(-2) 1.5(,-3) ' 4' 24.1 4.1(-3)- 'l.7(-4) 14 67.8 4.7(-2) 6.9(4) 1983 1 34.4 1.6(-3) 4.7(-5) 2 50.5 4.6(-2) 3 -21.7 2.9(-2) "* 9.1(4) l.3(-3) 4. 30.3 2.8(-3): 9.2(-5) 14 136.9 7.9(-2) 5.8(4). Unit 3 Tritium Releases - Curies vs. Dose The Unit 3 Environmental Report (ER) does not include an isotopic breakdown of the dose consequences. Therefore this cannot be calculated from the FSAR or O .w"! ER. However, since Unit 2 has a similar release. point as Unit 3, the Unit 2 value ' can be used here. Maximum value for MP1 is for 1978 = 5.2 x 10-5 mre.m/. curie - H-3. Maximum Value for MP2 is for 1977 = 1.0 x 10-3 mrem / curie - H-3 Limit is 1500 mrem /yr to the maximum organ-MP1 allowable release rate = (1500 mrem /yr/5.2 x 10-5 mrem /Cl) x 106 uC1/Cl x 3.17 x 10-8 yr/sec = 9.1 l 5 x 10 uC1/sec ) 't MP2 and MP3 allowable release rates i = (1500/1.0 x 10-3) x 106 x 3.17 x 10-8 = 4.8 x 10" uCi/sec Since this is a site limit, the allowable release rate for tritium is: ~ a. Qrl QT2 + QT3 1 + g,gx1'o4 4,3xio4 <- 1 9.1x105 ' 20-d 7 ,y__ e-

.:;.m. p - c ;r.z. ::: y w - s i 1/1/36 Rev.O where s .X QT1= Rele,ase rate of tritium from MP1 Stack -(uCi/sec) QT2 = Release rate of tritium from MP2 Stack -(uCi/sec) i QT3 = Release rate of tritium from.M3 Stack -(uCi/sec) ' ~ Since exposure to tritium produces whole body exposure, the release rate fraction for tritium must be added to the release rate for I-131 and particu@tes.. The combined release rate limits then are: I-131 and tritium 9Il + QI2 + QI3 + QT1 + QT2 + QT3 $1 6.26 0.49 0.49 9.1 x 105 4.3x104 4.Sx10..... 4 Particulates and tritium Q1 Q2 + Q3 Q3T1 + QT2 + QT3 1 + + 35 4.2 2.1 9.1x105 4.3x104 4.Sx104 O 4. Section D.2.a - Noble Gas - Quarterly Air Dose Method 1 (1) Unit 1 From the table in Section D.I.a of this Appendix quarterly value of mrem /qtr. per uCi/sec is 3.0 x 104.the maximum This value is mrem to the whole body. To convert to mrad air dose we must multiply by 2 because there is a factor of 0.7 to go from mrad to whole body mrem (The Distribution of Absorbed Dose Rates in Humans From Exposure to Environmental Gamma Rays, Health Physics, January 1976) and also a factor of 0.7 for building shielding and occupancy (Regulatory Guide 1.109, Rey,1, Pg. 43) used to originally calculate the whole body results. Therefore, the conversion factor for the air dose is: 6.0 x 10-4 mrad /qtr. per uCi/sec or 6.0 x 10-4 mead-see x 106 uCi/C1 x.26 x 10-7 qtr./sec qtr. - uCi = 7.6,x 10-5. mrad /Ci This is the gamma, air dose at 'the critical location. Since the critical location is the site boundary and is only 0.5 miles from a 375 foot stack, the beta air dose at the critical location is near zeio as the dose is from ) the overhead finite cloud (see earlier discussion in Section D.I.a). The O

g.

3

y.; y,..-

-.n. i 1/1/86 Rev.0 3 beta air dose at the critical location has always been less than 0.01 ti tes j the gamma dose. Thus, the beta dose can be recorded as: -5 i3 less than 7.6 x 10-7 mrad /Ci t ,j (2) Unit 2 - Likewise, for Unit 2 from Section D.I.a, the maximum quarterly value of mrem /qtr. per uCi/sec is 2.5 x 10 '

n..

'~ Converting to mrad /Ci we have 2.5 x 10-3 x 2 x 106 x 1.26 x 10-7 = 6.3 x 50-4 m'rdd/Ci This is the gamma air dose. The following is the ratio of the beta air dose to the gamma air dose at the critical location as calculated by the GASPAR code: Ratio 1976 1977 1973 1979 1980 Ist qtr. 2.9 3.1 6.9 3.1 2.3 2nd qtr. 2.9 3.0-2.3 3.3 2.7 I-) 3rd qtr. 3.5 2.5 3.0 3.1 1.7 D,/ 4th tr. 3.0 3.0 3.0 3.0 1.3 193 f 1982 l'983 1st qtr. 2.3 1.3 2.6 2nd gtr. 2.4 2.3 2.7 3rd qtr. 2.2 2.2 4th qtr. 2.2 2.4 The average ratio = 2-3 Beta air dose = 1.3 x 10-3 mrad /Cl

• No continuous releases these quarters (3)

Unit 3 L .i Again, as mentioned in Section D.I.a, since the average X/Q's are less for Unit 3 than for Unit 2, a conservative estimate for Unit 3 would be to assume its values would be the same as for Unit 2. ? j ) (V 0 e

.s

g.,..,,,,

.m m. 1/1/86 j Rev.0 q 5. Section D.2.b j Unit i Finite Cloud Code Curies of Dose (mrem) Year Quarter Xe-138 due to Xe-138 Dose / Curie s 1976 1 2.4 (+4) 0.29 1.2 (-5) ~ 2 3.9 (+4) 0.61 1.6 (-5)~ 3 3.3 (+4) 0.52 1.6 {-5) ~ 4 7.5 (+3) 0.08 . T,0 (.-5)- 1977 1 2.1 (+4) 0.19 8.9 (4)' 2 1.9 (+4) 0.22 1.2 (-5) 3 3.4 (+4) 0.52 '

• 6.4 (-6) 1.5 (-5) 4 3.4 (+4) 0.22 1978 1

6.5 (+4) 0.31 4.3 (-6) 2 4.7 (+4) 0.57 1.2 (-5) ~ 3 9.0 (+2) 0.019 2.1 (-5) 4 1.6 (+3) 0.015 9.2 (-6) 1979 1 1.98 (+3) 0.010 5.1 (-6) 2 8.42 (+2) 0.013 1.5 (-5) 3 1.05 (+3) 0.028 2.7 (-5) 4 1.06 (+3) 0.019 1.8(-3) 1980 1 1.09 (+3) 0.011 1.0 (-5) 2 5.42 ( 2) 0.0.13. ' "' ~ 2.4 (-5) 3 2.43 (+3) 0.052 2.1 (-5) 4 3.5's (+1) u.0 (-4) 1.1 (-5) 1981 1 2 1.41 (+2) 2.7 (-3) 1.9 (-5) 3 3.77 (+3) 0.033 8.8 (-6) 4 8.48 (+2) 0.004 4.7 (-6) 1982 1 2.40 (+2) 2.3 (-3) 9.6(-6) 2 3.59 (+1) 6.1 (-4) 1.7 (-5) 3 1.09 (+3) 0.012 1.1 (-5) 4 1983 1 8.89 (+1) 2.8 (-4) 3.1 (-6) 2 4.52 (+2) 7.8(-3) 1.7 (-5) 3 3.55 (+2) 7.7 (-3) 2.2 (-5) 4 2.11 (+2) 2.1 (-3) 1.0.(-5) O

%y9T NW; Siw.? !Mn;.b:.%mD%.wm t^ '.= ' ArctSe5xu 57R %s~ mmua%5+=- m m " ? -1/1/86 Rev.0 The above table normalizes the dose for each quarter to the same location'- { ; ..e from' a particular radionuclide.. Thus, the only variance in dose per curie -.j ~; should he due to the quarterly meteorology.~ Using this method, we can. l' . determind that the worst case meteorology occurred during the 3rd quarter - _4 1979. Thus, the 3rd quarter joint frequencies should be used as input for, the AIREM code. i' 6.~ Section D.3 a. Unit 1 ~~ The only-significant contributor to the thyroid dqse'ih I 131.,If the particulates _were significant a different org'an w'ould be ' limiting.. Tritium releases have never contributed more than 1% of the doses. from Unit 1. Thus, to determine the quarterly thyroidEifose we can use the maximum quarterly value observed of mrem / curie of I-131 as presented in Section 3 of this appendix. This maxirsum value is : 13.7 mrem / curie - I-131 - The critical organ dose due to particulates with half lives greater T than 8 days can also be determined from the maximum quarterly dose 3,) per curie given in Section 3 of this appendix. J This maximum value it: j 2.4 mrem / curie of particulates b. Unit 2 l For Unit 2, we must consider tritium in both # calculation;of the - thyroid and other organ doses. The dose factor' for all organs for - tritium is the same. The maximum quarterly values of mrem per curie-as presented in Section 3 of the appendix are as follows: For I-131, 285 mrem /Ci - I-131 - For_ Particulates, 44 mrem /Cl ~- Particulates '- i: i l For Tritium,1.5 x 10-3 mrem /Cl - H-3 ~ c. Unit 3 As previously, discussed, for conservatism,' assume the conversion factors for. Unit 3 are the same as for Unit 2. y ,i (.4 ~ 0 +

- - : g.. ; t.,:s:.;wg. ~ c. :;.yaz.+- ;vpm - M +.mr:rai mwmrtw w,': r ~ i, 1/1/86

{

Rev.0 .t { - APPENDIX E - x ej~i'$ 1 GASEOUS DOSE CALCULATIONS -GASPAR The GASPAR code was written by the NRC to compute doses from gaseous ~ releases using the models given in Regulatory Guide 1.109. The revision date of the code which was purchased is February 20,1976. The only changes made to the code were to change the dose factors 'and inhalation rates from those given. in Rev. O of Reg. Guide 1.109 to those in Rev.1. For calculating the maximum individual dose at Millstong,'the following options and parameters are used: 1. Real time meteorology using a X/Q, D/Q 'model which incorporates the methodology of Reg. Guide 1.111. Meteorology is determined separately for continuous releases and batchieleases and.%r - elevated releases and vent releases.

2. '

100% of vegetation grown locally,76% of vegetation intake from garden. 3. Animals on pasture April through December - 100% pasture intake. 4. Air, water concentration equals.3 g/m?. O 5. Maximum individual dose calculations are performed at the land location with maximum decayed X/Q, at the nearest vegetable garden (assumed to be nearest residencelwith the maximum D/Q, and at the cow and goat f arms with maximuid'D/Q's. - 6 d ] 4 l s a -w .ee 9

. -,... =. - .,,..r....,..., ..m.., n .,y. k I 1/1/86 Rev.O APPENDIX F GASEOUS DOSE CALCULATIONS - AIREM - ~ } The AIREM code was written by the EPA to compute doses from atmospheric emissions of radionuclides. The code is composed of two basic parts - a diffusion calculation and a dose calculation. 4 For the maximum individual dose at Millstone, cloud gamma doses are calculated 1 using dose tables from a model which considers the finite extent of the cTdudin' .l the vertical direction. Beta doses are calculated assuming semi-infinite cloud j concentrations which are bo'ed upon a standard sector averaged diffusion equation. i d 6

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~. ENVIRONMENTAL MONITORING PROGRAM-5dMPLING LOCA'TIONS ' ): j The following lists the environmental sampling.-locations and the types. of. samples ~ obtained at each location. Sampling locations are also shown on Figures G-Q2, and G-- 3. 4 j .. Location Distance From. Direction & - Number Name Release Point ** Samole Tvoes 5-l-I* Onsite - Old Millstone Rd. 0.6 Mi. - NNW- ' TLD, Air Particulate, lodine,. Ve"getation 2-I Onsite - Weather Shack 0.3' ML - SSE TLD, Air Particulate, Iodine 3-I Onsite - Bird Sanctuary 0.3 ML - NE - TLD,- Air Particulate, Iodine - 4-I -Onsite - Albacore Drive 1.0 ML - N. TLD, Air Particulate, lodine 5-I Floating Barge 0.2 Mi.' - SSE. TLD 6-I . Quarry Discharge 0.3 Mi. - SSE TLD 7-I Fox Island 0.3 Mi. - ESE - TLD l 8-I e r ironmentalLab 0.3 ML - SE. TL D ' i 9-I Bay Point Beach 0.4 M1. - W TL D ' 10-I Pleasure Beach 1.4 Mi. - E ' - TLD, Air Particulate, Iodine _.,hi l-I New London Coontry Club ' l.6 M1. - ENE. TLD, Air Particulate, Iodine 9 i ~12-C Fisher's Island, NY -8.7 Mi. - ESE TLD : l 13-C Mystic, CT i 12.0 Mi. - ENE :.... TL D, 14-C -Ledyard, CT 12.0 Mi.- NE1 "~ TL D - x 15-C Montville, CT 14.0 Mi. - N - TLD, Air Particulate, Iodine 16-C Old Lyme, CT 8.5 Mi. - W TL D ' a j 17-1 Site Boundary 0.5 Mi. - NE Vegetation IS-I New London Country Club 1.6 Mi.~ - ENE. . Vegetation 19-I Cow Location #1 - 6.0 Mi. - N Milk 4 i 20-1 Cow Location #2 9.5 Mi - NW Milk - 21-1 Cow Location #3 11.5 Mi. - NE Milk : .i 22-C Cow Location #4 16.0 Mi. - NNW Milk j i 23-I Goat Location #1 2.0 ML '- ENE - Milk

y 24-C Goat Location #2 14.0 Mi. - NE Milk.

25el Fruits & Vegetables Within 10 Miles nVegetation 26-C Fruits & Vegetables : Byond 10 Miles Vegetation j 27-I Niantic 1.7 Mi. - WNW TLD, Air Particulat.e, Iodine . I 28-! Two Tree Island 0.8 Mi. - SSE Mussels .i e 29-I Jordan Cove .0.4 ML - NNE ' Clams ~ M 30-C Golden Spur 4.7 ML - NNW. ' Bottom Sediment - 31-I Niantic Shoals 1.8 Mi. _- NW Bottom Sediment, Oysters. 1.5 Mi. - NNW. Mussels l j 32-I Vicinity of Discharge ' Bottom Sediment Oysters,1 Lobster, Fish, Seawater, s 33-1 Seaside Point l.8 Mi. - ESE Bottom Sediment' Oi.c335-I (34-I Thames River Yacht Club ' 4.0 ML - ENE ' Bottom Sediment i Niantic Bay O.3 Mi. - W l obster, Fish.- l ,b .36-1 = Black Point 3.0 ML - WSW Bottom Sediment, Oysteg V ,I -l ' 'l y g ~..-M, ...,,,,,-p. p.,-, _,,, _, - - -, ,v. 9 .,[..,4.c., f -. p- ,-s y ,h r-r 4.w. +y-

.,;, <.. :,., a.. 1/1/86 Rev.0 [ Direction & Lccation Distance From l Number Name Release Point ** Sample Types 37-C Giant's Neck 3.5 Mi. - WSW Bottom Sediment, Oysters, ~ Lobster, Seawater ~~ 38-1 Waterford Shellfish Bed #1 1.5 Mi. - NNW Clams

1. 1 = Indicator C - Control

• • For terrestial locations, this is the MP1 stack, for aquatic it is the quarry cut.

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s g; v. e ;:, u- ~ 1/1/36 j Rev.0 ) APPENDIX H jj ds METHODS FOR CALCULATING RELEASI:.S

i FROM UNIT 3 "UNMONITORED" RELEASES - FOR SECTION D2 and D3 H

Ti 1. Main Condenser Air Removal Mechanical Vacuum Pump Exhaust This system only operates during startup operation. r_.. uCi of MGrab Sample from* I (Condenser I ~ ~- Noble' Gas Air Ejection, uCi/cc, l Volume, cc[

• Iodines and =[' Mechanical Vacuum uCi of Grab Sample during } f Flow rate fminutes

. [ units ) l from Mech-of conversion I, Particulates { Pump. Exhaust, uCi/cc) anical Pumps operation (if necessary)/ 2. Turbine Gland Sealing System Exhaust [ Air Ejecto) [ Air Ejectof f Steam to Gland Seal h / minutes uCi of Gas s Ci cc ) /mi ( Steam to 51 n Condenser dp rationj .i. uCi of f Steam yf I (' 2., h Steam to Glandh l 'n Iodines Generator ) [ operation / carry-over '[' Seal Condenser [DF for Gland t .;F

and, Blowdown

= Parti-concen-fraction **; \\cc/ min. (uCi/cc ~ .-- - ( Seal Condenser k ) culates tration s ' ' " ~

• Crab sample from air ejector adjusted by monitor reading prior to shutdown and decay corrected from shutdown
  • carry-over fraction = 100 for lodines and 1000 for particulates.

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s 1. -i 4 MILLSTONE NUCLEAR: POWER STATION t a a- ~ w , e d DOCKET NO. 50-213 ...i - i 1 .:t. - t u l

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j j ~ January 1986 Ll Revisior 01 3 ,i .s. T S a , e lj ?- .ss L',, x. . + J. -e s e, . Y :, e - y e m t l .t.. h-*' 'T'

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-1 1/1/86 ( Revision 0 gJ s W 3.3 PROCESS CONTROL PROGRAM FOR THE MILLSTONE NUCLEAR POWER STATION

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,k T, =. .d OBJECTIVE: The primary objectives of the Process Control Program-1 (PCP) are to: = 8.1 ( 1. Ensure safe and effective solidification of various ']; low level radioactive waste liquids and slurries for ~' ~" offsite disposal. 2. Ensure compliance with NRC shipping. and burial regulations (e.g.10CFR71,' 10CFR61 and' 10CFR20) for low level waste. 3. Ensure compliance with DOT shipping regulations (~49CFR for low level waste s 4,. Ensure compliance with disposal site specifications for low level waste. ~~ PHILOSOPHY: This PCP is a listing of station management's commitments necessary to ensure the above objectives. The details required to meet these commitments will be maintained in. l3 either approved station procedures or approved vendor 7-,[} procedures or PCP's. %s b JNE .e

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. -e.wm n. I/ 2 1/1/86 / Revision 0 i O COMMITMENTS: s 3 The* Millstone Nuclear Power Station is committed to the establishment and maintenance of the management system and procedures necessary to ensure that: .s k 1. All liquid wastes will be solidified in accordance with regulatory guide and disposal site criteria prior to shipment offsite. 2. Containers, shipping casks and methods.of packaging wile m'e'et - - applicable federal regulations e.g. 10CFR71 and 49 CFR. 3. Waste classification will meet the requirements'of'10CFR61 and disposal site requirements. 4. Approved station or vendor procedures will include the following detailed information: a. A general description of laboratory mixing of a sample of the waste to arrive at process parameters prior to commencing the solidification process. b. A general description of the solidification process including types of solidification agent, process control parameters, parameter boundary conditions, proper waste form properties, and assurance the solidification systems are operated within ~% established process parameters. A general description of sampling of at least one represeittative ' c. i sample from every-tenth batch to +nsure solidification and action to be taken if the sample fails to verify solidification. Provisions to verify the absence of free liquid. Provisions to process containers in which free liquids are e. detected. f. Specification of the process control parameters which must be met prior to capping the container if the solidificatiott is exothermic. 3 ) I: s .}}