ML20141J340

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Forwards marked-up Proof & Review Tech Spec Sections 3/4.11 & 3/4.12 in Conjunction W/Review of Offsite Dose Calculation Manual.Placement of Sections in Offsite Dose Calculation Manual Recommended
ML20141J340
Person / Time
Site: Seabrook  
Issue date: 04/24/1986
From: George Thomas
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To: Noonan V
Office of Nuclear Reactor Regulation
References
SBN-1016, NUDOCS 8604280103
Download: ML20141J340 (33)
v • d • e


Text

{{#Wiki_filter:,_ April 24, 1986 SBN-1016 T.F. B7.1.2 United Statas Nuclear Regulatory Commission Washington, DC 20555 Attention Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5 References (a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNil Letter SBN-846 dated July 26, 1985, " Technical Specifications for Seabrook Station", G. S. Thomas to G. W. Knighton (c) USNRC Letter dated March 13, 1986, "Seabrook Technical Specifications", V. S. Noonan to R. J. Itarrison (d) PSN11 Letter SBN-954 dated March 3, 1986, "Seabrook Station Offsite' Dose Calculaticn Manual", G. S. Thomas to V. S. Noonan

Subject:

Seabrook Station Proof and Review Technical Specifications Stetions 3/4.11 and 3/4.12

Dear Sir:

Enclosed please find our commants on the Proof and Review Technical Specification Sections 3/4.11 and 3/4.12. It is requested that these Sections of the Technical Specifications be reviewed in conjunction with the Seabrook Station Offsite Dose Calculation Manual (ODCM) which was submitted to you by Reference (d). In concert with our current effort on Technical Specification improve-ments, it is proposed that Sections 3/4.11 and 3/4.12 he removed from the Technical Specifications and placed in the ODCM an Section I. With this proposal the existing ODCM would become Section II. Section 6, Administra-tive Controls, of the Technical Specifications would addrens control of changes to Sections I and II of the ODCM. It is requested that you initiate this review to coincide with our current Technical Specification review effort and your prenent review of the ODCM. Should you have any questions on this matter pleano contact Mr. Warren llall at (603) 474-9574 cxtension 4046 8604280103 860424 "/ PDR ADOCK 05000443 4 fyyp l 1r WY ) 'VA A PDR Geor ge'/ s S. Thomas Enclosure Vice President - Nuclear Production cci ASLD Service List ,\\ 1000 B~' ", " O. sod 330, ".JW)h06*ofrf+4G3tW,one (6G3)64;'4000-+-TWX-74GPPG7696

g .h 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.,11.1.1 The concentration of radioactive material released in liquid effluents te bMHMtittefffM4E*S-(see Figure 5.1-3) shall be limited to the concentrations T, specified in 10 CFR Part 20, Appendix 8 Table II, Column 2 for radionuclidos other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 microcurie /mi total activity. APPLICABILITY: At ail times. N dg pj pf -ry,( ACTION: / UA"b kCI d' b0 r (W..iththeconcentrationofradioactivematerialreleasedinliquideffluentsto .""" ^""" exceeding the above limits, restore the concentration to l within the above limits within 15 minutes. l SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according I to the sampling and analysis program specified in Section I of the 00CM. 4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the 00CM to assure that the concentrations f I at the point of release are maintained within the limits of Specification 1 I 3.11.1.1. l l l MAR 131988 Da.,:..iaal 7 k '.t [ 9 SEABROOK - UNIT 1 3/4 11-1 A 1

i RADI0A_CTIVE EFFLUENTS DOSE LIMITING C0h0! TION FOP OPERMION t m i g 3 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited: a. During any calendar quarter to less than or equal to 1.5 arems to the whole body and to less than or equal to 5 arems to any organ, and b. During any calendar year to less than or equal to 3 areas to the whole body and to less than or equal to 10 areas to any organ. APPLICA8ILITY: At all times. ACTION: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above Ifmits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. t b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from Ifquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days. I MAR 131986 l SEABROOK - UNIT 1 3/4 11-2 ji

1 l 5 T RADIOACTIVE EFFLUENTS LIQUID RADVASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION J 1L 123. The Liquid Radwaste Treatment System shall be OPERA 8LE and appropriate dNcy.,g!'.pottions of the system shall be used to reduce releases of radioactivity whenthehejeirddosesdue AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period. APPLICA8ILITY: At all times. ACTION: . a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste

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  • b ~7reatment SysteRnot in operation, prepare and submit to the Commis-e 1^6didtd !'

sion within 30 days, pursuant to Specification 6.8.2, a Special Report cMcN yd,{d 4 that includes the following information: 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inope,rability, 2 '. Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3. Summary description of action (s) taken to prevent a recurrence, b. The provisions of Specifications 3.0.3 and 3.0.4 are not appitcable. SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS dtkmir.ed shall be prcjected at least once per 31 days in accordance with the methodology e and parameters in the OOCH when Liquid Radwaste Treatment Systems are not being fully utilized. 4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2. I MAR 131986 7D / P Q} ,d i<, A (' L SEABROOK - UNIT 1 3/4 11-3 ~~. b

lllI ~ . s' n t o ii) mt1) i c( l 7 6 5 5 7 8 6 7 6 5 Le m t) / 0 0 0 0 0 0 0 0 0 0 reDi 1 1 1 1 1 1 1 1 1 1 eDLc x x x x x 5 x x x x w Lu 5 1 1 1 1 3 1 5 1 1 of( ( Lo ) ) a ss a ss m er m er m d se m d se a nat 0 a nat C) aCt a 9 C) aCt m 3 i h 3 i a l( dd m p r l( ddm r ys as eeE l S as eeE g f ti pr vn A pr vn o ois i e li a ie li a r vy ct 1 oam s 9 5 ct 1 oam P eil nt 3 srm s 8 5 nt 3 srm pt a ii 1 st a 3 o ii 1 st a s ycn rm i nC r r e rm i nC i TAA PE I DE( H C S F PE I DE( sy lan A dna gn h i y c e e l sc t ) t ) t EL p min a 4 i 4 i B m use B ( s ( s a myu P M Mo Qo W M A S il q h p p T nae c m m e i nr a o o t MAF E C C saW d iuq i L M e e y h / h h l l e gc c h c c p p v nn t c t t m m i ie a t a a a a t l u PB Pa PB PB WS MS c pq B a me h h h b b o ar c e c c a a i SF a n a a r r d E O E E C C a _ R g n i ) dt 2 l n ) ( i e s5 s ) uu u( k e Bl oe en s f us t a a ef na e d sT h e nE i e d s i a cl i tl iae uwt t e b p ne uep qds aR rm oR ql Y i ae B uu C TS ( ieT LRT ( LR A B

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l n t o) ii1) mt( l 7 6 5 5 7 8 6 i c m Le) / 0 0 0 0 0 0 0 t Di 1 1 1 1 1 1 1 reLc x x x x x x x eDLu 5 1 1 1 1 5 1 w ( ( of Lo ) a ss m er m dse a nat 0 C) aCt a 9 g 3 i h ~ a l( ddm p r r ys as eeE l S g f ti pr vn A o ois i e li a r vy ct 1 oam s 9 5 P eil nt 3 srm s 8 5 pt a i i 1 st a 3 o s ycn rm inG r r e i TAA PE I DE( H G d F sy lan A dna g ) n de y i E u sc l L p n min B m use i a myu W M M Q A t T S n il q o nae e i nr (c MAF t saW d iuq i L e e e e y l l l l e gc p p p p v nn m m m m i i e a a a a t l u WS MS Ms QS c pq a me b b b b o ar a a a a i SF r r r r d G G G G a e R g ) r I a ( h r c e s t i a D W y o l e t yr e c yl e d s i rl ht i ae v okt r uep r iena ql y e reou i eT S PWMQ LR D PWMQ 9 9 ((l \\

s TABLE Notations (1)The LLD is defined, for purposes of these specifications, as the smallest concentration of radicactive material in a sample that will yield a not count, above system bLckground, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiocht mical separation: 4.66 s LLD = 0 E x V x 2.22 x 10 x Y x exp (-At.t) Where: LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume). sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), i E = the counting efficiency (counts per disintegration), .V = the sample size (units of mass or volume), 2.22 x 10-6 = the number of disintegrations per minute per microcurie, ^ i Y = the fractional radiochemical yield, when applicable, I l h = the radioactive decay constant for the particular radionuclide i (r-1), and at = the elapsed time between the midpoint of sample collection and the time of counting (s). Typical values of E, V, Y, and at should be used in the calculation. 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 an a posteriori (after the fact) limit for a particular measurement. (2)A batch release is the discharge of liquid wastes of a discrete volume. 1 Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling. Seabrook Station - Unit 1

l s TABLE t' Notations (3)The principal samma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, co-60, In-65, Mo-99, Cs-134. Cs-137, co-141, and Co-144 This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report in the format outlined in Regulatory Guide 1.21. Isotopes which have activity less than the LLD may be reported as "not detected." LLD values are not used in dose calculations. (4)A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which *La method of sampling employed results in a specimen that is representative of the liquids released. (5)A continuous release is the discharge of liquid wastes of a nondiscrete

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

(6) Sampling and analysis is only required when Steam Cenerator Blowdown is directed to the discharge transition structure. (I) Principal samma emitters shall be analyzed weekly in Service Water. Sample and analysis requirements for dissolved and entrained gases. tritium, gross alpha, strontium 89 and 90, and Iron 55 shall only be l i required when analysis for principal samma emitters exceeds the LLD, The follo' sing are additional sampling and analysis requirements: a. PCCW sampled and analyzed weekly for principal gasma emitters. b. Sample Service Water System (SWS) daily for principal samma emitters l whenever primary component cooling water (PCCW) activity exceeds lx10-3 uC/cc. c. With the PCCW System radiation monitor inoperable, sample PCCW and SWS daily for principal gamma emitters, d. With a confirmed PCCW/SWS leak and PCCW activity in excess of lx10-4 uC/ce, sample SWS every 12 hours for principal gamma emitters. The setpoint on the PCCW head tank liquid rate-of-change alarm will be e. set to ensure that its sensitivity to detect a PCCW/SWS leak is equal to or greater than that of an SWS radiation monitor, located in the unit's combined SW3 discharge, with an LLD of 1x10-8 uC/cc. If this sensitivity cannot be achieved, the SWS will be sampled once every 12 hours. Seabrook Station - Unit 1

RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS

  • LIMITING CONDITION FOR OPERATION l'fhE114 : The quantity of' radioactive material contained in each temporary unprotected outdoor tank shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases:

APPLICA8ILITY: At all times. ACTION: a. With the quantity of radioactive material in any temporary unprotected outdoor tank exceeding the above limit, immediately suspend all addi-tions of radioactive material to the tant, within 43 hours reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Re-port, pursuant to Specification 6.8.1.4. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each temporary unprotected outdoor tank shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank. i

  • Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

M ))f4Ac l h l D] b1 SEABROOK - UNIT 1 3/4 11-4 iJ 1LL L i

RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS ' DOSE RATE LIMITING CONDITION FOR OPERATION 3:11 2.1 The dose rate due to radioactive materials released in gaseous sff1'ents from the site to areas at and beyond the SITE BOUNDARY (see Figure u 5.1-1) shall be limited to the following: a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and b. For Iodine-131, for Iodine-133, for tritium, and for all radio-nuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 arems/yr to Ony organ. APPLICABILITY: At all times. ACTION: With the dose rate (s) exceeding the above limits, decrease the release rate within 15 minutes to within the above limit (s). SURVEILLANCE REQUIREMENTS 4.11:2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the CDCM. 4.11.2.1.2 The dose rate due to Iodine-131, Iodine-133, tritium, and all radionuclides in pa^ticulate form with half-lives greater than 8 days in gaseouseffluentssl$silbedeterminedtobewithintheabovelimitsin accordance with the saethodology and parameters in the ODCM by obtaining representative sampibs and performing analyses in accordance witn the sampling and analysis program'specified in Section II of the ODCH. La a n i s a mma Ruin I d 1999 4 SEABROOK - UNIT 1 3/4 11-5 j,,A k1

i l = RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES ~ LIMITING CONDITION FOR OPERATION p(12 The air dose due to noble gases released in gaseous effluents, from di unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following: a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation. APPLICA8ILITY: At all times. ACTION a. With the calculated a'ir dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the~ corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to l assure that subsequent releases will be in compliance with the above limits. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and curre' t calendar year for noble gases shall be determined in accordance with j the methodology and parameters in the ODCM at least once per 31 days. \\ l I, MAR 131986 no

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-{ SEAER00K - UNIT 1 3/4 11-6 j ( .T m / _. 1 t

s RADI0ACTfVE EFFLUENTS DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION k {'m,3 gThe dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, t 'm, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following: a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and, b. During any calendar year: Less than or equal to 15 mrems to any organ. APPLICABILITY: At all times. ACTION: a. With the calculated dose from the release of Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit the the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REOUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131, Iodine-133, tritium and radienuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. hlRR 13 Ignq D*3 A P 'S h ih 1 SEABROOK - UNIT 1 3/4 11-7 g

a RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3 ell.E 4" The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLOUP SYSTEM shall be OPER.4BLE and appropriate portions of these systems shall be,cumwlde i I used to reduce releases of radioactivity when the pr:j::ted W s'es in,431 days due to gaseous effluent releases, from each unit, to areas at and beyond the ' Pf bleM. l SITE BOUNDARY (see Figure 5.1-1) would exceed: l l a. 0.2 mrad to air from gamma radiation, or b. 0.4 mrad to air from beta radiation, or c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC. APPLICABILITY: At all times. ACTION: With radioactive gaseous wa:,te being discharged without treatment a. and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that includes the following information: i 1. Identification of any inoperable equipment or subsystems, and l the reason for the inoperability, l 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and ~ 3. Summary description of action (s) taken to prevent a recurrence. i b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. 1 SURVEILLANCE REOUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and Jectedrt least once per 31 days iPddd6%d beyond the SITE BOUNDARY shall be pr: a accordance with the methodology and parameters in the 00CM when Gaseous Radwaste Treatment Systems are not being fully utilized. 4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or 3.11.1.3. MAR 13198G D& DR SEABROOK - UNIT 1 3/4 11-8 I ' -i / M i j L .- a .1 I M j

l ) l ( ) t nc ioc mi/ 2-l l l S I I I 4 6 iti 4 6 s Lcc eu 0 0 0 0 0 0 0 0 rt( 1 1 1 1 1 1 1 1x ee x x x x x x x. 1 wD) 1 1 1 1 1 1 o D LfLoL( ) ) 2 2 ( (s s s r r re e e t t t t t t i i i m m m E E E ys a a am fti m n m ois m n g vy a a 0 a n eil G C a 9 G h i pt a l ycn l l p r l p TAA a a l S a m p p A p i a i i S m c 1 c s 9 c a n 3 n s 8 n i o i 3 1_ e r i 3 r r r r t g r s o P H r P G S P H a r W P s s EL u i e e e o s B t t t A e y s l y a ea ea a a sc l l tl tl T G n min a u iu iu A use ) oe ) ce sce sce e myu 6 cl 6 il Moil Qoil ( rp ( t p pt p pt p ) v d il q M i n nae gam wrm mrm mrm 7 t a i nr ha aa oaa oaa ( c MAF CS PS CPS CPS M ao i da R ) ) ) ) 5 5 5 5 e ( ( ( ( e l s s s s l y p u u u u p gc m o o o o m nn ) a u u u u a ie 4 S n n n n S l u ( i i i i pq ) b t t t t ) b me 3 a n n n n 7 a ar f. r o o o o ( r SF MG C C C C MG ts ru ia Ah x t rE n e e sl V na se ev use t d o oap n nm eey a oe sl T l CR ae P GR 2 1

e TABLE Radioactive Caseous Waste Sampling and Analysis Program (continued) Minimum Type of Lower Limit Caseous Release Sampling Analysis Activity of Detection (l) Type Frequency Frequency Analysis (LLD) (uci/ce) 3. Cland Steam Continuous W Principal Camam Emitters (2) 1x10-Il Packing Exhauster Particulate Sample 1x10-12 Continuous W I-131 Charcoal Sample Continuous H Gross Alpha 1x10-Il Composite Particulate Sample 1x10-Il Continuous Q Sr-89, Sr-90 Composite Particulate Sample 4. Containment P(3) P Principal Camma Emitters (2) 1xio-4 Purgs Each Purge Crab Each Purge Sample H-3 (oxide) 1x10-6

TABLE Notations (1)The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material ia a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent 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 LLD = 6 E x V x 2.22 x 10 x Y x exp (4\\t,t) Where: LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume), sb = the standard deviation if the background counting rate or of the counting rate of a blan ; sample as appropriate (counts per minute), E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 2.22 x 10-6 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, h = the radioactive decay constant for the particular radionuclide (s-1), and at = the elapsed time between the midpoint of sample collection and the time of counting (s). Typical values of E. V, Y, and St should be used in the calculation. It should be reccgnized that the LLD is defined as an a priori (before the fact) Itmit representing the capability of a measurement system and not as an a posteriori (after the fact) Limit for a particular measurement. Seabrook Station - Unit 1

TABLE Notations (2)The principal gasraa emitters for which the LLD specifications applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59,'Co-58, Co-60 Zn-65, Mo-99, 1-131, Cs-134. Cs-137 Ce-141 and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report in the format outlined in Regulatory Guide 1.21. Isotopes which have activity less than the LLD may be reported as "not detected." LLD values are not used in dose calculaticas. (3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one hour period unless; 1) analysis shows that the DOSE EQUIVALENT I-131 concentrations in the primary coolant has not increased more than a factor of 3; 2) the noble gas activity monitor for the plant vent has not increased by more than a factor of 3. For containment purge, requirements apply only when purge is in operation. (4) Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. (5)The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with the Off-Site Dose' Calculation Manual. (6) Samples shall be changed at least once per seven (7) daya and analyses .shall be completed within 48 hours after changing, or after reraoval from sempler. Sampling shall also be performed at least once per 24 hours for at least saven (7) days following each shutdown, startup, or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one-hour period and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLLs may be increased by a factor of 10. This requirement does not apply if 1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. (7) Samples shall be taken prior to start-up of condenser air removal system when there have been indications of a primary to secondary leak. Seabrook Station - Unit 1

~ RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAc, MIXTURE l LIMITING CONDITION FOR OPERATION 3.11.2.S The concentration of oxygen in the WASTE GAS HOLOUP SYSTEM shall be limited to less than or equal to 2% by volume. APPLICABILITY: At all times. ACTION: a. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 2% by volume, reduce the oxygen concentration to the above limit yithin.48 hours. *'nIds= A> hydttcpn cc maec D c -7 K Ve r: D-cf t. De in; $1c n g g (9 yc /e,ny, b. The provisions of Specifications 3.0 3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.S The concentration of hydrogen or oxygen in the WASTE GAS HOLOUP SYSTEM shall be determined to be within the above lie.it by continuously monitoring f.he waste gases in the WASTE GAS H'JLDUP SYSTEM with the hydrogen or oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10. 1 1 MAR 13 Isge 3 l\\ Q ' T SEABROOK - UNIT 1 3/4 11-9 { g [,'t 1 i

E RADI0 ACTIVE EFFLUENTS 3/4.11:4 TOTAL 00SE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from trranium Tuwi 9 kde.r. eye 4e sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 areas. APPLICABILITY: At all times. ACTION: a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifi-cation 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a., or 3.11.2.3b., calculations shall be made including direct radiation contributions from the units and from outside storage tanks to deter-mine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF c3 N(THE PUBLIC fromkure is f=! cyc!e sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition result-ing in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accor-dance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENT 3 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be datermined in accordance with Sr.ecifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the 00CM. 4.11.4.2 Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the mettlodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in ACTION a. of Specification 3.11.4. Mja1o.--- agg } m 1r } SEABROOK - UNIT 1 3/4 11-11 I \\ .h_ i 1 h, A-i L

kb 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING l 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in the CDCM. APPLICABILITY: At all times. 2 ACTION: 1 a. With the Radiological Environmental Monitoring Program not being conducted as specified, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by i Specification 6.8.1.3, a description of the reasons for not conducting i the program as required and the plans for preventing a recurrence. I b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of the REMP when averaged over any calendar i quarter, prepare and submit to the Commission within 30 days from i receipt of the laboratory analyses, pursuant to Specification 6.8.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

  • to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications l

3.11.1.2, 3.11.2.2, or 3.11.2.3. When more than one of the radio-nuclides in the REMP are detected in that sampling medium, this report shall be submitted if: concentration (1) concentration (2)

      • ) 1.0 reporting level (1) + reporting level (2) i When radionuclides other than those listed in the REMP are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose
  • to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of

{ Specification 3.11.1.2, 3.11.2.2, or 3.11.2.3. This report is not i required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Specification 6.8.1.3. 1 3

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

l MAR 13198g I l' N b5 j-t. I C d j l SEABROOK - UNIT 1 3/4 12-1 4L e' J..\\.L AL 21. J. i m =,en =e

=w

, - - = - em ,. ~ - -.. n, ,, -. - -,w ,,,,,, _, -. -. - -.,,. _,,,.,, -. -,, _ _,, + _ ,r_-, ,_,,-n, r ~c.-

RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION ACTION (Continued) c. With milk or fresh leafy vegetable samples unava41 41e from one or ,[ CpRit!O (, yof the sample locations required by the REMP, identify f 4 specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were l Pursuant I'D {U[ NQ[tmeveitaMe may then be deleted from the monitoring program. to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the 00CM including a revised figure (s) and table for the ODCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples, d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to the REMP from the' specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of and the detection capabilities required by the REMP. / MAIL 13 !!!! mm ? m rm i i U ! i i!. ' [ [~ \\ t ' g, SEABROOK - UNIT 1 3/4 12-2

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION l 3.12.2 A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest 2 2 garden

  • cf greater than 50 m (500 ft ) producing broad leaf vegetation.

APPLICABILITY: At all times. ACTION: 'amWith a Land Use Census identifying a location (s)-that' Ieib a calchted-date or dose commiteentTreater than the values currently being calculatehrr$pecif.ication 4.11.2.3, pursuant to Specifica-tion,6.8:1'4, identify the new Tocation(s)-in the_next_ Semiannual ~~ Radiorctive Effluent Release Report. 9 E. With a La*d Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 4 20% greater than at a location from which samples are currently pflg@[h3 being obtained in accordance with Specification 3.12.1, add the new 1ocation_(sLwithin 30 days _to_the Radiological Environmental Moni-itoring Program given in the ODCM/ The sampling location (s), exclud-cgN {or dose commitment (s), via the same exposure pathway, may be deleted AN ing the control station location, having the lowest calculated dose hCMM M ,from this menitoring program after October 31 of the year in which N (GU O f this Land Use Census was conducted. Pursuant to Specification 6.13, g6 sO* ) b submit in the rext Semiannual Radioactive Effluent Release Report Cod I# ' documentation for a change in the 00CM including a revised figure (s) 5 QG /atdtable(s)turtheODCMreflectingthenewlocation(s)withinforma- [ tion supporting the change in sampling locations. j MM c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l l { l l \\ Q O ccCL 11r<d. Lai1 l1 h 5)Y 'I cdcrj t in 06 NET / /rK/M//1cf dW OnMp?I d C M trof CQI

  • Broad leaf vegetation sampling of-at-least-three-iffe %

rent-kinds of-vegetation may be performed at the SITE BOUNDARY in each of two different direction sec-tors with the highest predicted D/Qs in lieu of the garden census. Speci-fJcations-for-broad-leaf-vegetation-sampling -in in-the REMP,- shall'- be fol - lowed rincluding-analysis-of-control samples. kN NM n n* o nm I> SEABROOK - UNIT 1 3/4 12-3 Q_ [g g

RADIOLOGICAL ENVIRONMENTAL MONITORING SURVEILLANCE REQUIREMENTS t w4u M1 10n(d l QFtl Qloiw j eing=the t & ag-seasora6

j 4

4.12.2 The Land Use Census shall be conduc e least once per 12 months using that-information-that-wil1-provide.the best 9 )?Plttr> results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.8.1.3. MARAlsas SEABROOK - UNIT 1 3/4 12-4

RADIOLOGICAL ENVIRONMENTAL MONITORING . 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION r(>W' r1 M A> k 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by the REMP. APPLICABILITY: At all times. ACTION: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.8.1.3. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS T}s tositit{csful ob itw ht* OPfCyct/ bW.OvGro Wy Ltr#f#ter l'9/7/77h,)/ 4.12.3 M hw I n t e rl abo ra tory-f ampa ri s on-P rog ram-s ha l be-des c ri b edi rrthe - 00CM. g g,f A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental lq de Operating Report pursuant to Specification 6.8.1.3. gg i M 0 MAR 131986 p' q A T' N I I SEABROOK - UNIT 1 3/4 12-5 i U L ._ L / .1 l; u

t TABLE Radiological Environmental Monitoring Program Number of Representative Exposure Pathway Samples and Sampling and Type and Frequency a and/or sample Sample Locations Collection Frequency of Analysis 1. DIRECT RADIATION 40 routine monitoring stations: Quarterly. Gamma dose quarterly. l An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY An outer ring of stations, one in each meteorological sector, generally in the 6 to 8-km range from the site; The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and control locations. 2. AIRBORNE C Radioiodine and Samples from five locations: Continuous sampler Radiciodine Cannister: Particulates operation with sample Three samples from close to the collection weekly, or I-131 analysis weekly. three SITE BOUNDARY locations, more frequently if in different sectors, of high required by dust Particulate Sempler: calculated annual average loading. ground-level D/Q. Gross beta radioactivity analysis following filter One sample from the vicinity of change: b a community having the highest Gamma isotopic analysisd calculated annual average ground-of composite (by location) level D/Q. quarterly.

TABLE (Continued) Number of Representative Exposure Pathway Samples and Sampling and Type and freqvsney a and/or Sample Sample Locations Collection Frequency of Analysis One sample from a control location, as for example 15-30 km distant j and in the least prevalent w4nd direction. 3. WATERBORNE a. Surface One sample in the discharge area. Monthly grab sample. Gamma isotopic analysisd One sample from a control location. monthly. composite for tritium analysis quarterly. b. Sediment from One sample from area with existing Semiannually. Gamma isotopic analysisd from or potential recreational value. semiannually. ~ shoreline 4. INGESTION a. Milk Samples from milking animals in Semimonthly when Gamma isotopied and I-131 three locations within 5 km milking animals are on analysis on each sample. distance having the highest dose pasture, monthly at potential. If their are none, other times. then, one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be t greater than 1 mrec per yr." One sample from milking animals i at a control location, as for i example, 15-30 km distant and in the least prevalent wind direction. n.

[ e. TABLE (Continued) Number of Representative Exposure Pathway Samples and Sampling and Type and Frequency a and/or Sample Sample Locations Collection Frequency of Analysis d b. Fish and One sample of three commercially Sample in season, or Gamma isotopic analysis Ihvertebrates and recreationally important semiannually if they on edible portions. species in vicinity of plant are not seasonal. discharge area. I I One sample of similar species in areas not influenced by plant d i schar'ge. c. Food Samples of one to three differont Monthly, when Gamma isotopicd and I-131 Products kinds of broad leaf vegetation # available. analysis. grown nearest each of two different off-site locations of highest predicted annual average ground-level D/Q if milk sampling is not performed. the similar Month.'y,when Gamma isotopicd and I-131 One sample of each of, grown at a I broad leaf vegetation availat'e. analysis. l control location, as for example 15-30 km distant in the least prevalent wir.d direction, if milk sampling is not performed. l ? l l- -

r

  • ~ e ' ',

e. TABLE (Continued) Table Notation a) Specific parameters of distance and direction sector from the conterline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table. in a table and figure (s) in the 00CM. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling l l equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual l Radiological Environmental Operating Report. It is recognized that, at times,_it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Identify the cause of the unavailability of samples for that pathway and identify the new location (s), if available, for obtaining replacement samples in the next Semlannual Radioactive Effluent Release Reporc and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s). l l b) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more af ter sampling to allow for radon and thron daughter decay. If gross beta activity in air particulate - samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. l c) Optimal air sampling locations are based not only on D/Q but on factors such as population in the area, l year-round access to the site, and availability of power. d) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. e) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM. f) If broad leaf vegetation is unavailable, other vegetation approximating broad Icaf vegetation, as i described in the Radiological Environmental Monitoring Program procedures, will be sampled.

llI o e ) yr td n e me 0 0 ik 5 8 d/ 1 1 ei SC p ( s) ttce uw ( do b re Pk 0 0 0 / 6 6 8 s di i oC s op y F( lan A ) e g l k k l / p c m ) i i 1 5 8 5 a D MC 1 1 1 S L p ( L l ( a t n n o s) e i m t et n c t e o e d aw E r t nr L i e ab 0 0 0 0 0 0 B v D eg 3 6 3 6 3 5 A n htk 1 2 1 2 1 1 T E f sr/ o iei r F vC o t np f i I( m s i e L i t r e i e t w a l l ) i o b L y a cm p i/ a ti C rC ~ ap 1 7 5 6 n P( 0 0 0 0 o i es 0 0 0 0 t na c rG e o t b r e ro D i A ) g '5 rk 4 0 5 0 5 0 5 5 8 e/ 0 1 3 1 3 1 1 1 1 t i 0, aC Wp 3 ( a s t 0 0 i e 6 5 4 s D 9 1 y 4 7 l s 4 9 8 5 b 1 3 3 a a s 5 5 5 6 N 3 1 1 L n o 3 1 A r n e o n r s s a G H M F C Z Z I C C B

o- . ~.. o TABLk Table Notation a) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report. b) The LLO is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: 4.66 s b

  • E V* 2.22 Y

omp(~ t) Where: LLO is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume; 4.66 is a constant derived from the Kalpha and Kbota values for f the 95% confidence lovel; j l sb is the standard deviation of the background counting rate or of I the counting rate of a blank sample as' appropriate, as counts per minute; E is the counting efficiency, as counts per disintegration: V is the sample size in units of mass or volume; 2.22 is the number of disintegrations per minute per picocurie; \\ Y is the fractional radiochemical yield, when applicable; i is the radioactive decay ' constant for the particular radionuclide; aM t for environmental saeples is the elapsed time between sample l collection and time of counting. Typical values of E, V, Y, and t should'be used in the calculation. In calculating the LLO for a radionuclido determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., Potassium-40 in milk samples).

f 9 TABLE (Continued) 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 an a posteriori (af ter the fact) limit for a particular measurement. This does not preclude the calculation of an a posteriori LLD for a particular measurement based upon the actual parameters for the sample in question and appropriate decay correction parameters such as decay while sampling and during analysis. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be l identified and described in the Annual Radiological Environmental Operating Report, c) Parent only. d) The Ba-140 LLD and concentration can be determined by the analysis of its short-lived daughter product La-140 subsequent to an eight-day period l following collection. The calculation shall be predicated on the normal ingrowth equations for a parent-daughter situation and the assumption that any unsupported La-140 in the sample would have decayed to an insignificant amount (at least 3.6% of its original value). The ingrowth equations will assume that the supoorted La-140 activity at the time of I collection is zero. e) Broad leaf vegetation only. f) If the measured concentration minus the three standard deviation uncertainty is found to exceed the specified LLD, the sample does not have to be analyzed to meet the specified LLD. (

a

s., - 1 ( 's q ~ ... ~ ~. TADLE x. ~ Repokt'ingLevelsforFgiha'c32VityConcentratione,finJnvironment.41._Samply 3. N. t c: Fish and Invertebrates ' Milk 'Foed Proddcts Airborne Partieg) late Water _,-- Analysis (pCi/kg) ogfsNs (pCi/m (pCi/kg, wet) spCj/kg) (_oCi /kg, wet) 11 - 3 30,000 'n; Mn-54 1,000 30,000 Fo-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 s Zn-65 300 20,000 / Zr-Nb-95 4004 i ..j I-131 0.9 3 100NM Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200* 200*

  • Parent only.

M* Broad leaf vegetation only. _ - - _}}

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