ML20135B573

Semiannual Radioactive Effluent Release Rept for 850215- 0630

ML20135B573
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	06/30/1985
From:	LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20135B563	List: ML20135B573 SNRC-1204, Forwards Semiannual Radioactive Effluent Release Rept for 850215-0630. Facility Achieved Initial Criticality on 850215,however No Power Ascension Occurred During First & Second Quarters 1985.Low Power License Received on 850703
References
NUDOCS 8509110103
Download: ML20135B573 (28)

Text

p _ -..

_t.___._

l l

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT let and 2nd Quarters of 1985 Facility: Shoreham Nuclear Power Station Unit 1 l

Licensee: Long Island Lighting Company, Inc.

The Shoreham Nuclear Power Station achieved initial criticality on February 15, 1985. However, no power ascension occurred during the 1st and 2nd quarters of 1985. LILCO received a low power license to allow testing to 5%

power on July 3, 1985. This report is submitted in accordance with Technical Specification 6.9.1.7 and covers the periods from February 15, 1985, through March 31, 1985, as the first quarter and April 1, 1985, through June 30, 1985, as the second quarter.

A.

SUPPLEMENTAL INFORMATION 1.

Regulatoty Limits Shorehan's affluent regulatory limits are defined in Facility Operating License NPI-36, Shoreham Nuclear Power Station, Appendix A, Technical Specifications.

a)

Limits for gaseous effluents and noble gases are covered by Technical Specifications 3.11.2.1 and 3.11.2.2.

b&c) Iodines and particulates with half-lifes greater than 8 days in gaseous affluents are addressed in Technical Specifications 3.11.2.3.

d)

Liquid effluent limits are described in Technical Specifications 3.11.1.1 and 3.11.1.2 e)

In addition, the following radiunuclides for liquid offluents had typical minimum detectable activities of:

Cr-51 4.0E-7 uCi/mi Zr-95 9.0E-8 uCi/a1 Nb-95 2.5E-8 uCi/mi Tc-99m 3.9E-8 uCi/mi Ba-140 1.6E-7 uCi/mi La-140 5.6E-8 uCi/mi 8509110103 950829 PDR ADOCK 05000322 R

PDR

_ -. - _ _ _ _ ~

.~

L_.____

c_ _

The following radionuclides in gaseous eff16ents had typical minimum detectable activities of:

Kr-85 1.3E-6 uCi/cc Kr-85m 4.0E-9 uci/cc Xe-135m 2.0E-8 uCi/cc I-133 5.0E-13 uCi/cc I-135 1.5E-9 uci/cc Ba-140 1.5E-13 uCi/cc La-140 7.6E-14 uCi/cc 2.

Maximum Permissible Concentrations a-d) Maximum permissible concentrations are those specified in 10 CFR 20, Appendix B Table II, Column 2.

If an isotope is listed with values for SOLUBLE and INSOLUBLE states, the more conservative value is utilized.

For gaseous affluents MPCs were not used. Direct calculation of dose were utilized to satisfy Technical Specifications 3.11.2.1.

3.

Averste Enerdy No isotopes above minimum detectable activities were measured.

Therefore, there is no reportable average energy for this time period.

4.

Measurements and Approximations of Total Radioactivity a-d) Samples were collected in the manner and with the frequency prescribed in Technical Specifications Surveillance Requirements 4.11.1.1.1 and 4.11.2.1.2.

Samples were analyzed in accordance with Technical Specifications Tables 4.11.1.1.1-1 and 4.11.2.1.2-1 regarding both type of analysis and level of sensitivity. Most samples were analyzed by gamma spectroscopy with a Ce(L1) detector. A liquid scintillation counter was used to analyse for H3, Fe-55 and Sr-89,90.

Samples analyzed for iron and strontium underwent a chemical separation prior to counting. Approved sample collection and analysis procedures were followed.

Analytical results are examined to ensure that the minimum sensitivity levels required by Technical Specifications lower limits of detection have been met. Any identifiable peaks above background are quantified.

The methods above were used for batch releases. These methods combined with gross activity measurements on process streams and total flow for these streams were used for continuous discharges.

No estimate of percent total error is provided in Tables IA and 2A because all values were determined to be less than required lower limits of detection (LLDs). Counting Libs reflect a two-sigma level of confidence.

.-.K...

~..

5.

Batch Releases j

a)

Liquid 1st Quarter 2nd Quarter

1. Number of batches 30.

122.

2. Total Time (minutes) 4,563.

18.905.

3. Maximum Time (minutes) 175.

309.

4. Average Tina (minutes) 152.

155.

5. Minimum Time (minutes) 92.

20.

6. Average Flow (gpe) 1.39E+05 1.51E+05 j

b)

Caseous - None

6. -

Abnormal Releases a)

Liquid - None l

b)

Gaseous - None i

4 0

1 4

__-_.-,._,,,..,_.~.-, -,.,-,--,.

... - -..... ~,

..._-m-

_... L..

j SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT B - CASEOUS EFFLUENTS Ist and 2nd Quarters of 1985 All samples of gaseous offluents were analyzed and determined to be at or below minimum detectable activities for all radionuclides listed in Shoreham's Technical Specifications. These MDAs were below the lower limits of detection required in Technical Specifications Table 4.11.2.1.2-1.

In addition, no other radionuclides were identified. Therefore, no entries were made in Tables 1A, 18 or IC.

.J 9

..?.

-~.

TABLE 1 A I

EFFLUENT AND WASTE DISPOSAL SEMlANNUAL REPORT (YEAR)

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES umt Guerme Ouseter Est Toisi l

E rror, s.

A. Fision & activation genes I. Total release Ci E

E E

2. Averase release rate for penod pCs/see E

E g

3. Percent of Technical specification limit

?-

E E

a B.ledines I. Total iodine 131 Ci E

E E

2. Average release rate lor penod pCi/see E

E

3. Percent of techracal specification limit 7

E E

C. Particulates I. Particulates with half lives >B days 06 E

E E

2. Averaet release rate for pened uClisec E

E

3. Percent of technical speetl'acation limit E

E

4. Gross alpha radioactivity Ci E

E D. Tritium

1. Tot 21 release C6 E

E E

2. Average release rate for period pCl/see E

E

3. Percent of technical spectrication limit G

E l E

l e

=

I

~

1.21 14

o

^~

~

=. - - - _ _..........

~.

e TABLEIS EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REFORT (YEAR)

{

GASEOUS EFFLUENTS-ELEVATED RELEASE CoasTINuous smoot BATcM escot

~

NustasmsRe w Urut Quarter thserter Quarter Chsarser j

1. Fission games krypton.85 Ci E

E E

E krypton.85m C

E E

E E

krypt on.67 Ci E

E E

krypton.88

• Ci E

E E

xenon.133 Ci E

E E

menon.135 Ci E

E E

menon.135 m Ci E

E E

li menon.138 Ci E

E E

E Ci E

E E

E Others (specifyl Ci li E

E E

E E

E Ci umdentified Cl E

E E

Total for period C

E E

E E

2.lodines iodine 131 Ci E

E E l E

todine.133 C

E E

E i E

iodine.135 Ci E

E E

E E

E I

Total for period C

E

3. Particulates strontium-89 Ci E

E E

E st rontium70 Cs E

E E-E cesium 134 C

E E

E E

cesium.137 Ci E

E E

E banum-lanthanum.140 Cs E

E E

E E

Others ispecifyl Ci E

E E

t Ci E

E E

E Cs E

E E

E unidentified Ci E

E E

E f

l.21 15

~

V

• ~

TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)

GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES E

CONTINUOUS MODE SATCM MODE Nucs.on neweise ur=

overte omric ovute cuaria I. Fision pises I

krypton-85 Ci E

E E

E krypton-85 m Cs E

E E

E krypton 47 C

E E

E krypton 88 Ci E

E E

menon 133 C

E E

E menon.135 C

E E

E i E

xenon.135m Ca E

E E

E senon.138 Ci E

E L

k Others (specifyl C

E E

E E

C E

E E

E C

E E

E E

unidentined t

C E

E E

E Total for penod l

C6 E

E E

E I

2. lodines lodme 131 Ci E

E E

E sodine.133 Ci E

E E

E iodine 135 C

E E

E E

i Total for period Ca E

E E

E

3. Particulates strontium.89 Ci E

E E

E strontium 90 C

E E

E E

cesium 134 Ci E

E E

E comum 137 Ce E

E E

E benum-lanthanum.140 C

E E

E E

Others (specify)

C E

E E

E e

C E

E E

E C

E E

E E

unadentified C

E E

E E

f I

w 1.21 16

.. -.. 2,:. := -

-==.

-z.: :

=

2.. -. - - - :=:: : ztz--"

i l

1 I

SEMIAIGIUAL RADIOACTIVE EFFLUENT RELEASE REPORT l

]

C - LIQUID EFFLUENT i

let and 2nd quarters of 1985 i,

j All samples of liquid effluents were analysed and determined to be at or below minimum detectable activities for all radionuclides listed in Shorehan's i

j Technical Specifications. These MDAs were below the lower limits of detection a

required in Technical Specifications Table 4.11.1.1.1-1.

In addition, no other radionuclides were identified. Therefore, no entries were made in Table 25.

t The only entry in Table 2A pertains to waste volumes released and dilution 1

I volumes.

t i

i 4

i 4

1 t

4 t

l

+

t 5

i i

j 4

l t

j i

i

a w

+

u -

- - - - - ~ ~ -

TABLE 2A i

EFFLUENT AND WA5TE DISPOSAL SEMIANNUAL REPORT (Y. EAR) i LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Oierter Chaerior Est Totes let 2nd Ea*.5 t

A. Fission and activation prodmets

1. Total toisase (not meludes intium, sness, alpha)

Ci E

E E

2. Average dduled concentreten during period pCL/ml E

E

3. Percent oT sppbcable hmit E

E B. Trision I. Total release C6 E 1:

E I

E l

2. Average dduted conantration during penod pCl/ml E

E J. Percent of apphcable hmat E

E C. Dimolved and entre 8aed mass

1. Totai release C

E E

E l

2. Average dduted concentration during period MCl/mi E

E

3. Percent of appbcable hrrut E

E D. Geoes alples radioactivity l

1. Totsi release l Cs l

E l E l.

E I E. Volunne of weste released (prior to dilution) liters

?.08 E06 8.52E0(

5.00E og F. Volume of dilution water used during period liters 2 61 E09 1,08 ll g,noEog E

l.21 17

• ~ a

~4 ~ - -

9 TASLEIS EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)

Ll0UID EFFLUENTS g'

~

CONTINUOUS MODE BATCHWOO4 Nues.e ne o

unes cuarise on. sew, cuenee cheerwe strontium 49 Ci E

E E

E strontium 90 Cs E

E E

E g

cesium 134 C

E E

E cesium.137 Ci E

ii E

E sodine.131 I

Cs E

E E

E cobalt 58 Ci E

E E

cobalt 60 Ci E

E E

i iron 59 Cs E

E E

zinc.65 Ci E

E 6

• manganese.54 Ci E

E chromium.51 Cs E

E E

E tirconiummiobium 95 Ci E

E E

mohbdenum 94 C

E E

E techrietium 49m C

E E

bariumhnthanum.140 Cs ii E

E cerium.141 C

E E

E i

E Other (specify) l Cl E

E l E

E Cs E

E E

C:

E E

E

)

C E

E E

Co E

E E

unidentined Cs E

E E

E l

Total for penod (abow) l Ci l

E l.

E l.

E l.

E menon.133 Cl E

E E

E menon.135 Ci E

E E

E 9

6 e

f I

1.21 18

-.. ~

t...

SIMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT D - SOLID WASTE let and 2nd Quarters of 1985 1

i No shipments of solid wastes or irradiated fuel were made during the 1st and 2nd quarters of 1985.

t i

(:. _..c ;;

. - - =

{..---

., ~, ;~ ; ' --

^

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)

(

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irressted p.am s.t. Tow W

l. Type of weste

.,,, w serer, s

a. Spent reans. filter sludges. evaporator erf E

Ci E

E bottomt. etc.

m' E

b. Dry compressable waste. contanunated Ci E

E equip etc.

m' E

c. Irraduted componenis. control Cl E

E tods, etc.

m' E

d. Other (desenbe)

Cl E

E

2. Estimate of maior nucEde compeeltion (by type of weste) 9 a.

5 b.

5 E'

c.

{

4 d.

4 E

3.

Solid Weste Disposition Number of Stupments Mode of Transportation Destmation None B. IRRADIATED FUEL SHIPMSNTS (D6eposit6en!

Number of Stupments Mode of Transportstion Destination None

{

1.21 19 1

u

_._t

~

l ii t

t c

l P

n h

SDlIANilUAL RADI0 ACTIVE NFLimrt

.p i

Il RELEASE REPORT o

s y

u G - ODCM RRISICIIS AIED REMP II0ll-COMPLIARICES s

,~

.h.

s

'Y) g i

t

/

,J

,3-h s

k )

,1 f

[.

i t

i 6

t d'

i h

9

{

l I

s

,r 4

t 1J f

e g0 h

I ir

,g

.*r.

T '

g 'i

,1 i

I

,r g

o o

b i

t sq

s. n.\\1 3

l

-, ' /,

u, l

i

)

.I

v-

j g

-f r

I ' ll

~.

o a

6 n

e l

s t

0 t

In accordance with Technical Specifications 6.9.1.7 which'atates that revisions to the ODCM shall be included in the next semi-annual radioactive effluent release report issued, the following revisions to the ODCM have been identified.

Revision 5 was issued to incorporate new setpoint calculation inputs and calibration curves. The revision was needed as a result of moving the sample point for ID11-RE-12A&B (the main condenser air ejector radiation monitor) h downstream of the air ejector glycol cooler condenser and installation of temporary detectors. The effected pages are 2.2-6, 2.2-7, 2.2-8 and figures 2.2-5 and 2.2-6.

Revision 6.was issued for the following reasons:

1.

Incorporation of new setpoint calculation inputs and text description resulting from moving the semple point for ID11-RE-12A&B to downstream of the air ejecchr'desupetheater condenser. Effected pages are 2.2-6, 2.2-7 and 2.2-8; r

h 2.

Pages 3.3-5, 3.3-6, 3.3-8. 3.4-3, 3.4-5 and 3.5-12: The definition of C13, the containment drywell purge exhaust concentration of radionuclide i is changed to include description of purge events bypassing the primary containment purge filter; i

' 3. Pages 3.3-8 and 3.5-12: The definition of C13, the containment drywell filter train exhaust concentration of radionuclide i, gaseous sample was changed to iodine and particulate filters to accurately describe the samples taken to derive organ doses and dose rates; 4.

Table 5-5: Alternate locations for Ia1 and Ia2 were included, and; 5.'

Figure 5-2: Location 11C1 was added to the map.

Item 4 is a result of efforts to satisfy Technical Specifications requirements for milk sampling (Table 3.12.1-1.4.a).

Milk sampling locations within the distances prescribed by this Technical Specification are acutely limited.

Normal animal husbandry practices result in the seasonal loss of milk samples for approximately four months every year from locations 651 and 10F1.

The wording of Technical Specification 3.12.1 requires that an LCO be entered whenever samples cannot be collected from the locations identified in the ODCM.

Therefore, alternate locations for Ia1 (11C1) and Ia2 (802) were identified and i.

sampled during the interim period. The original locations (6B1 and 10F1) are b

sampled preferentially because they are superior to 11C1 and 802 with respect to having the highest dose potential".

Therefore, the ODCM is being revised to describe a preferred and a secondary location for both Ia1 and Ia2.

The objective will be to collect milk samples at 6B1 (for Ial) and 10F1 (for Ia2) at all times that samples are available from those locations.

If samples

, s are unavailable from 6B1 or 10F1, then 11C1 will be substituted as Ia1 and 8G2 will be substituted as Ia2 as necessary.

By this change, unavailable milk samples resulting in LCO's should be limited while ensuring the integrity and intent of the environmental monitoring program.

The revised pages are appended to this section.

e

~

SNPS-1 ODCM 2.2.3.1 InitialSetPointforRE-12A,BMon-bypassModeOheration 1.

Decay the t=0 GE noble gas spectrum for off-gas system release rate prior to treatment (GE document 22A27038 Rev. 3, Table V) for 203 seconds.

Scale it to the Shoreham RETS (3.11.2.7) limit of 244,000 VC1/sec at 30 minutes decay by multiplying by 2.44.

Divide it by the air ejector cooler condenser maximum flow rate (3.6E+04 cc/sec) to obtain the limiting concentrations C (ici/cc) of each radioisotope 1.

g 2.

Using the isotopic concentrations, C (pci/cc), defined above and the 4

effective gamma energy per disintegrition, E (MeV/ dis) calculate the of the following,ctivity, Agg(MeV/cc-sec), foNthe i-th isotope in each specific gamma a gansna ray energy binsi. 0-0.4, 0.4-0.8, 0.8-1.3, 1.3-1.7, 1.7-2.2, 2.2-2.5, and 2.5-3.5 (MeV). Thus:

Ag=K* Egg

• Cg where E of the Nth isotope by gansna rays belonging to the i-th energy defined above. The factor K = 3.7 x 10 (dis /sec/pC1) is introduced for unit conversion.

The total specific gamma activity, A (MeV/cc-sec), for each gasuna energy bin,i, is calculated by sunding the specific gasuna activity, Agg, for bin i, over all isotopes.

Ai"i1 Agg 3.

Using the response curve for RE-12A,B given in Figure 2.2-5, calculate the dose rate.

shown in Figure 2.2-6.The generic linearity response curve for RE-12A,B is 7

DR =

CF

• A g

g (anm/hr) where:

a h

s the efficiency (

-) at the i-th energy group 4.

The high alarm set point (see NOTE in Section 2.1.1, but note the background unit is in arem/hr) for RE-12A,B in the non-bypass mode will be:

S

< 0.8

• DR g

(mrem /hr)

EN1-11600.02-92 2.2-6 Revision 5 - July 1985

)-

,N

.~.

SNPS-1 ODCM 2.2.3.2 Subsequent Adjustments of Set Points for RE-12A,B in Non-bypass Mode operation 1.

During operation, a gaseous sample from the monitor will be taken and analyzed for noble gases isotopic composition and concentration, C,

s (UCi/cc). Theconcentrationsshouldbecorrectedforelapseddecahtime between sampling and measurement. In addition, computed concentrations should be obtained for short lived isotopes. Before startup, C will be calculated as noted in Section 2.2.

g i

2.

At the time of sampling, the net dose rate reading (excluding background) of the monitor will be recorded, DR (area /hr).

3.

The isotopic release activity concentrations, C, are sumaned and multiplied by the air ejector cooler condenser klow rate, V (cc/sec)* to obtain the noble gas release rate in UCi/sec.

4.

The release rate in step 3 is normalized to the RETS Section 3.11.2.7 release limit of 2.44E+05 VCi/sec at t=30 minutes as follows:

2.44E+05 F=

([.C )

• V ii 5.

From above, the high alarm set point (see NOTE in Section 2.1.1, but note the background is in mrem /hr) based on a release rate of 2.44E+05 pCi/see at t=30 minutes can be calculated as follows:

S12 = 0.8

• F

• DR (arem/hr) 2.2.4 Main Condenser Air Ejector Monitor (RE-12A,B) High Alarm Set Point for l

Bypass Mode Operation 2.2.4.1 Initial Set Point for RE-12A,B in Bypass Mode Operation 1.

Same as steps 1, 2, and 3 in Section 2.2.3.1 2.

The offsite total body dose rate D C rresPonding to the above T

concentration is calculated ast D,= 10+6

• X/Q

• V * (E DFB.

• C.)

i 1

1 and the beta and gansna skin dose rate is calculated as :

= 10*0

• X/Q

• V * (E K.

• C.)

Ds t sim 1

• Note:

If flow rate increases, the setpoint must be recalculated. If the flow rate decreases, recalculation of setpoint is optional.

BN1-11600.02-92 2.2-7 Revision 5 - July 1985

(

- - - ~ ~ ' -

~

-~

SNPS-1 00CM where:

D

= Predicted total body dose rate (area /yr)

T D,

= predicted beta and gasuna skin dose rate (area /yr)

X/Q = annual average atgspheric dispersion factor at 366 meters NNE (6.6E-07 sec/m ) due to releases via the station ventilation exhaust point V

= air ejector cooler condenser maximum exhaust flow rate (ce/sec)

(se,e 2.2.3.1 Step 1)

DFB g = Table 2.2-1 total body dose rate conversion factor ("Ci/m** Y#) from 3

p K,g = skin dose rate conversion factor ("#'"

Y) free Table 3.

The normalizing factor F is chosen to be the smaller of the two (to comply with 25 percent of the RETS (3.11.2.1) dose rate limit):

y, 125 mrem /yr T

DT y, 750 mrem /yr S

D3 F = the smaller of F rF3 (unitless)

T 4.

The high alarm set point (see NOTE in Section 2.1.1, but note the background is in arem/hr) RE-12A,B in bypass mode is set att S g 0.8* F

• DR (arem/hr) 2.2.4.2 Subsequent Adjustments of Set Points for RE-12A,B in Bypass Mode Operation 1.

A gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, C (pCi/ce) 2.

At the time of sampling, the net dose rate reading, DR (arem/hr), of the monitor will be recorded.

3.

Follow procedures 2, 3, and 4 of Section 2.2.4.1 to get the high alarm set point for RE-12A,B in bypasa mode.

BN1-11600.02-92 2.2-8 Revision 5 - July 1985 u

PF"F F# *N *Wi"El"U #M'W" 'A

'E 3*'t"M"F'"'CW'*MF'F HE nemc e isi 9

2-o p u o H

i t

i pi

, y n lu i!

op w muu M9 lu.h & M n: F N Ph t a 1 U 1

g i

ii r 3 i i I' I

l:ll i II :III. li 11!il!:! '1: !I i

i

1. '!!!11:

P tif !F il-

'l: 101 7,Dil u ll B I

l i

Ill

+

i

, u i innipipi-y.*

,i 1

. li a

11 I

i

[i !9i-iiill f 'r1

it l I F iniita '!p V

Ilp>'

!. WI I!:i ine yC i

i 11 r m.:U.:.ip' i !,

i l

iinV.il i P i

l 4' i

'i i

i i j 14 ij lil' lfi' '. i

?.

i.I

' flit 'I,

$ liF l.4;te ;if 1,li. llil l WI,!! ll. iHl j

i j

II rilI, il

, d ll

'i !Il f li 11 11 ililliilip ilt 'l!II.i, i

1i h

Il fI i!

Ml} )

! IIIll I'

, illt l liIII Il!

I I

'l Il IIl l illI!. ill.37g l'

i l'

f

!i.; ' in i 4 11 1i Y? Il li hL ll' l< ' il li

I ll l Lu

'i ll R, li

' r! I I

i i

il I !! {llsf! P.1"t u'11 i

g 3) i i,

i i

in it l i i n n i it

.1 i i 'i f

p 4

1 i ">

1 i

t i lli t i,

' F li

)

u lu i

4 i

1 11 i n.cHA c:t 4

n i v o m:

1 m a 9 i o i

i i n i miui n, :i t

9 o

u i

t a l i

o u i

n i

m a i

a i

t i n i n uni

g. -

1.5 l

I I I i

'f i

l

'l

' l

, a c I l Il 1A k jh

'I I

l L l l l l lll l ll I

i

(

y i

Qi se g n j

n

,g i,

ll l

i i

3 q

o g

.J 9

i 1 1 ; l I

! -li ;

His l I ll l b i

I h

! l 4

I I

ll

.i i

n i

o t u i u iu i

(d s

i Il r!!,

t -l i Mr, ;

m t

i ni u m i

an l

1 I

l l i t L

dl! t.y W F

i n e T!'

g l '

i l

. M il l i lil P

n, M 1

I l llP I I

t U l l l

il 1 1 1 'l f

I i t i st n l i I "

1 1 I !

I !

I ll.

2 i

I; l'

l !

. i4 1

M i

i t il l

~ F ",$

i li l W l

I F. l i

.) 3 il l 141 i n li, I

i l R 'ili :H Ml l i;li

!' ul

((!]

!j L !l lil s i

n

' i J

F0t$b O M lf $ 0Y9Mf f1 lb I

I IN li!

l>

I l

t

.d,.

1 F

I in n

i 1

~

i c

i a

1 uii nu onn u i

"N.t1i

(;

l0 4

@a I

l t u

i l

i r o p a

4 W n

n

,1 i

i u i

b ifE II 11111 f

z W T L l

y.!g!

W-W

. 1 1

!I 1

l i ']

if Il i 1

1 i>

il 1 :t :!

.1 ;

i f

h l

it i 1

1 n u e

i M

i o

i n

g";

'j q-

>i :

i +

i t m

i a

i n

i i

i ili

?'

i E

{g.%.y 1

m i r,,

a;

- ys u. i

- -"n

+t h ;

, f.,.m n

)

c, 4,

i h

v t

w d-hq1 t

1 i

a, AL r : n q.

j,i j q, q#

j,n.,

4 r v p q',

1 77

'- --e ir 4p p

q 7

3,

4A d W q q i i.

i y

1,-3 g, (,3 y,y{

q ja

.y

, h 4

h,,,

j c.

[

1 a

7 N

q Je F.. l r

a 7 3 m

,g g,

o.5 manum,1u i l,m mu M llbd [ i l i dill.I ll1.

g iig s

h.3, o

i Iil i.o 2.0 ao 4.o f.rw t.

GAMMA ENERGY (MEV) m,

.s.

l) 7[

FIGURE 2.2-5' k, -'

DETECTORS RE-12A,8 C

souncEs EFFICIENCY VS. GAMMA ENERGY

1. NED CALCULATION C-RPD-153 i

SHCRENAM NUC1. EAR POWER STADON-UNff 1 i

t 0FFSITE DOSE CALCULATION MANUAL i

SAMMA ENERGY BfMS (CF )

e g

REVISION 5 JULY 1985

.- - ~-. _.

e SNPS-1 ODCM i

3.3.2 Method 2:

(Backup Method) 3.3.2.1 Noble Gas Total Body Dose Este

• { hFB *(C

• V

-C

-C

• Vd DT, = 0.7

• x/Qg g

gg g

12 2

g3 3

+ 0.7

• v

• X/Q *{[DFBg 12

• C 2

2

+ 0.7

• v

• X/0 3

3 * { (DMg *Cg3]

(aren/yr)

During periods of no intermittent releases such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the following:

• X/Q d

DT,= 0.7

• Yg g * { [DN *Cgg]

g where:

DT,

= total body dose rate from all radionuclides releases (ares /yr),

= the total body dose rate factor due to gamma emissiog)s for each DFBg identified noble gas radionuclide (area /yr per pCi/m (Table 2,2-1),

i C

= the station ventilation exhaust duct release concentration of il radionuclide, i (pci/cc) (from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor),

C

= the air removal pump ventilation exhaust duct release 12 concentration of radionuclide, i, (pci/cc) (from the isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor),

C

= the catainment d w ell p ge ventnation exhaust cacentration of g3 radionuclide, i. (pCi/cc) obtained from a sample taken during a filtered release or from the containment drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter (The concentration is obtained from the isotopic analyses performed on the gaseous sample taken.),

V

= 1.73E+08 cc/sec (3.66E+05 cfs), station ventilation exhaust duct 7

ventilation exhaust flow rate, V

- 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct 2

ventilation exhaust flow rate, V

= 5.70E+05 cc/sec (1200 cfs), containment dryvell purge ventilation 3

embmust f1pv rate, BN1-11600-02-92 3.3-5 Revision 6 - August 1985

gNPS-1 ODCM x/Q

= annual average X/Q at 366 meters NNE due to releg)se via t g

station ventilation exhaust point (6.6E-07 sec/a X/Q

= short term X/Q at 366 meters NNE due to air removal p 2

via the station ventilation exhaust point (3.6E-06 sec/m X/Q

= short term X/Q at 366 meters NNE due to containment d 3

via the station ventilation exhaust point (3.6E-06 sec/a 0.70

= shielding factor that accounts for dose reduction due to shielding from residential structures.

3.3.2.2 Noble Cas skin Dose Rate DS, = X/Q *{[K,g*(C

• V

-C

-C

• Vd g

gg 3

12

• Y2 g3 3

s.

+V

• X/0

• k (X

+

• X/03*[(K,g*Cg3) (area /yd 2

2 si 12 3

t During periods of no intermittent releases auch as no main condenser air removal pump operation and no containment dryvell purge the above formula reduces to the following:

D3, = Vg g

• X/Q *{(K,g*Cgg}

(ana/yr) where:

DS,

= skin dose rate from all radionuclides released (area /yr).

K

= the skin dose factor due to beta and gasma emissions for each si identified noble gas radionuclide (area /yr per pCi/m ) from Table 2.2-1, i

C

= the station ventilation exhaust duct release concentration of I

radionuclide, i (pC1/cc) (from isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor),.

i C

= the air removal pump ventilation exhaust duct release 12 concentration of radionuclide

1. (pci/cc) (from the isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor),

C

= the containment drywell purge ventilation exhaust concentration of g

radionuclide, i, (pci/cc) obtained from a sample taken during a filtered release or from the containment dryvell atmosphere monitor with the purge lines bypassing the primary containment purge filter (The concentration is obtained from the isotopic analyses performed on the gaseous sample taken.),

l V

= 1.73E+08 cc/sec (3.66E+05 cfa), station ventilation exhaust duct g

ventilation exhaust flow rate,

\\

i BWi-11600.02-92 3.3-6 Revision 6 - August 1985 J L

_._u...

SNPS-1 ODCM C

" t * *ir r** V81 P mP ventilation exhaust duct release 12 concentration of radionuclide, i, (pci/cc) (from the isotopic analyses performed on the iodine and particulate filters taken from l

~

the air removal pump discharge monitor),

Cg

= the containment drywell purge ventilation exhaust concentration of radionuclide, i, (UC1/ce) obtained from the lodione and particulate filters during a filtered release or from the containment drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter.(The concentration is obtained from the isotopic analyses performed on the iodine and particulate filters.),

Vg

= 1.70E+08 cc/sec (3.60E+05 cfa), station ventilation exhaust duct ventilation exhaust flow rate, V7

= 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct ventilation exhaust flow rate, V3

= 5.70E+05 cc/sec (1200 cfa), containment drywell purge ventilation exhaust flow rate.

X/Q

= annual average X/Q at 2478 meters ESE due to releg)ses via the g

station ventilation exhaust point (1.54E-07 sec/m X/Q

= short term X/Q at 2478 meters ESE due to condenser air removal 2

pump g)elease via the station ventilation exhaust point (4.22E-07 sec/m X/Q

= short term X/Q at 2478 meters ESE due to containment drywg 3

via the station ventilation exhaust point (4.22E-07 sec/m EN1-11600.02-92 3.3-8 Revision 6 - August 1985

~

3NPS-1 ODCM 3.4.2 Method 2:

(Backup Method) 3.4.2.1 Noble Gas Camma Air Dose l'

[

The general equation is:

D

= 3.17E-08 *X/Q *{[Hg @ gg C

g V t

-C s.

g g 12 2 2 13 '3*

~

+ 3.17E-08 *V2 **2 *X /0 *k ("i 12

• C 2

~

+ 3.17E-08 *V

• t

• x/0 * { @g* cg3]

(araO 3

3 3

During periods of no intermittent releases, such as no main cetsenser air removal pump operation and no containment drywell purge, the above formula reduces to the following:

D

= 3.17E-08 *V

• t

• x/Q M (M 4g3]

(arad) g g

g g g g

where:

D

= the total gausna air dose from the releases (arad).

g 3.17Eh8 = the inverse of number of seconds in a year.

M

= the air dose factor due to gamma emissions for each g

identified noble gas radionuclide (arad/yr per DCi/m )

3 from Table 3.4-1

'e, t

= 7.88E+06 see for quarterly dose calcu1'acion.

g

= 3.15E+07,see for yearly dose calculatios t

~

" rel**88 period (sec) lor con' denser air removal pump 2

t

= release period (sec) for containment dryvell purge 3

exhaust C

= the station ventilation exhaust duct release I

AI concentration of radionuclide

1. (UCi/ce) (from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor).

C

= the air removal pump ventilation exhaust duct release 12 concentration of radionuclide, i. (UCi/ce) from the isotopic analyses performed on the gaseous s(ample taken from the air removal pump discharge monitor).

C

= the containment dryvell purge ventilation exhaust g3 concentration of radionuclide, i. (tci/cc) obtained from a sample taken during a filtered release or from the containment drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter (The concentration is obtained from the isotopic analyses performed on the gaseous i

sample taken.).

BN1-11600.02-92 3.4-3 Revision 6 - August 14E5

7 _

I i

gNPS-1 ODCN t g

= 7.88E+06 see for quarterly dose calculation.

= 3.15E+07 see for yearly dose calculation, ty

= release period (sec) for condenser air rencval pump, C3

= release peri d (see) for containment drywell purge

exhaust, C

= the station ventilation exhaust duct release gg concentration of radionuclide, i.,(pci/cc) (from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor),

i C12

= the air removal pump ventilation exhaust duct release j

concentration of radionuclide, i. (pCi/cc) (from the isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor),

Cg3

= the containment drywell purge ventilation exhaust concentration of radionuclide, 1. (pCi/ce) obtained from a l

sample taken during a filtered release or from the containment drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter,(The concentration la obtained from the isotopic analyses performed on the gasecus sample taken.).

V i

3

= 1.73E+08 cc/sec (3.66E+05 cfa). station ventilation exhaust duct ventilation exhaust flow rate, i

V2

= 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct ventilation exhaust flow rate, I

l V

= 5.70E+05 cc/sec (1200 cfa), containment drywell purge 3

ventilation exhaust flow rate, 1

X/Q

=annualaveragex/Qat457metersESEduetoreleasevja y

the station ventilation exhaust point (8.44E-07 sec/m ),

1 i

X/Q

= short tern X/Q at 457 meters ESE due to condenser air 2

i removal pump release via the station ventilation exhaust 3

i point (1.83-06 sec/m ), and X/Q

= short term X/Q st 457 meters ESE due to containment 3

i i

drywell purge release *I*

• * ****I * **"*II**I * ** ""**

3 point (1.83E-06 sec/m ).

j BN1-11600.02-92 3.4-5

-Revision 6 - August 1985 L.

A

-A-

l

\\

SNPS-1 ODCM i

The dose factors P P

are based on the'* critical individual organforthechi1Mg,rouNsincethisgroupismostrestrictive.

t

= 7.88E+06 see for quarterly dose calculation g

= 3.15E+07 sec for yearly dose calculation, t

= release period (sec) for condenser air removal pump, y

t

= release period (sec) for containment drywell purge exhaust, 3

~

C

= the station ventilation exhaust duct release concentration of radionuclide, i (pCi/cc) (from the isotopic analy' es performed on s

the iodine and filter cartridge taken from the station ventilation exhaust monitor),

C

= the air removai pump ventilation exhaust duct release g

concentration of radionuclide, 1. (pCi/cc) (from the isotopic analyses performed on the iodine and particulate filters taken from the air removal pump discharge monitor),

C

= the containment drywell purge ventilation exhaust concentration of g3 radionuclide, i. (pCi/cc) obtained from the iodine and particulate filters during a filtered release or from the containment drywell atmosphere monitor with the purge lines bypassing the primary containment purge filter.(The concentration is obtained from the isotopic analyses performed on the iodine and particulate filters.),

v

= 1.73E+08 cc/sec (3.66E+05 cfa), station ventilation exhaust duct g

ventilation exhaust flow rate, 4

V

= 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct 2

ventilation exhaust flow rate, V

= 5.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation 3

exhaust flow rate, X/Q

= annual average x/Q at 2478 meters ESE due to relegses via the g

station ventilation exhaust point (1.54E-07 sec/m ),

X/Q

= short tern X/Q at 2478 meters ESE due to condenser air removal 2

pump 3elease via the station ventilation exhaust point (4.22E-07 sec/m ),

X /Q

= short tern X/Q st 2478 meters ESE due to containment drywgli purge 3

via the station ventilation exhaust point (4.22E-07 sec/m ),

D/Q

= annual average D/Q deposition factor at 2478 meters ESE due t g

releases via the station ventilation exhaust point (3.08E-09 m 2),

D/Q

= sh rt tern D/Q deposition factor at 2478 meters ESE due to 2

condenser air removal pung2)eleases via the station ventilation r

exhaust point (8.47E-09 m BN1-11600.02-112 3.5-12 Revision 6 - August 1985 4

d

,--.,n.

' ~ ~ -

SEPS-1 CDCM

~

TABLE 5-5 RADIOLOGICAL ENVIRONMENTAL MDEITORING FROGRAM (REMP)

INCESTICE MONITORING STATIONS Location Codes NUREG-0473 Shoreham REMP Location Description Is1*

631 Goat Farm,1.54 mi. ESE 8

11C1 School (Coats), 2.4 mi. SW Ia2*

10F1 Goat Farm, 9.2 mi. SSW 8G2 Dairy (Cow) 10.8 mi. SSE Ib1 3C1 Fish and Invertebrates, outfall area 2.9 mi. NE Ib2 14C1 Fish and Invertebrates, outfall area 2.1 mi. Whv Ib3 13G2 Fish and Invertebrates, background, 13.3 mi. W Ici 831 Local Farm, 1.2 mi. SSE Ic2 SC2 Local Farm, 2.8 mi. E Ic3 1281 Background Farm 26 mi. WSW

• Sar:ples will be obtained from one of the locations listed as available.

will be given to the first of the two locations listed.

Priority If samples are unavailabla from that location, substitution will be made from the second location listed.

l l

I I

l l

BN1-11600.02-112 1 of 1 Revision 6 - August 1985

V IPN' ' N F U Mi" Ih ddifl"f **!V M DU"Y W "Rif ?' 'Ud'E'?F;' Nila'"

dHU FP 6' M'Ti' 20 si n t

. i I

so i ', u i

1. l!]

,.pi p w e tcu n i

i i

q.c mu 9ti, ps,i,nn,i

, oi c i o p hy c,.;q' li i

ir i ll il l. hll!!!',' f.' 1

:l i

I. 4 li hp igi l- 'l: tI!i.g l.i n I lli j

1 )

q i ',

u,g i

11 i

i i

i 4

l 19 Jjn ',ll ? 6' ;il l I, ill!ii j!ti iVL it!i.'

9'01 MIit lib h11:

1 i

! : 14: U:1;. ' Ui

)

g i!

i i

4 i

'i i

i l

l t

J 11"l l IIIl# !.

d I. ' l'I h 'l

'hlI l'l' I.ll 'lt iF %. " i[I -

"l f1b li i

r o

a ii i c i !4 m na m m

a i ? n ai n l 4 0

Fit i ! i o i

>; it io i

t i

I l ii ipp:,

31 6 i

j l

il

(

l R

ll. ' t,L.

I 'lll l ti lfD IL h

1l' ll i I

,ff

i u

'l i l

'i lt lit.

I!

h.I II 1

n ii i nuu n i u i

i i a

l j llil' I%, ;

F l

i nw, ri on 9

4 L

I '"

i l Ihll bl i

. n m o;

' i '

I :

1 l i ?' l li l

ill i f I!

! 5 i

,i

,1 i

y mp u n i

i i

- m n i

I ii ll

f. 5 ]~

I ai i 4c i

r.

l it, I

'L I

i l;

i 1,

I I

i 1

g se i u u

ut

! I.

I o

1 1

i i

II i

i i

i J

'! 'l i t

9 u

u' i ul

o c

"g l

u t i

, o m

i i'

i

, i i

i

. o i

i 1

I i

L i

$4

.".i' 1 I i

{

o a

I ll l i u

e i*

w, m i,~ ou t i

i l ib

.l !

u p 1 1 i l I !

I !

l il i I

m.

t.tj g

1/ 't i i l 1 1 l i

' n% !

I l il a

U l l i

i u n n i o

l

- ".m u l w o o o

e al n ii l l 1

ti 1 1 t 't i

} 3 i

9.1 t

I G.li t

[

{ N I[

.1 1 i

l i I

h 4li F3,d'Mi' M i

I i

di l

t 1M ;

l l l#i F' 1l 1

I

1. i I

1 iT I

i l i l l

. ll l 1

' Mil l i i

t

, w a

i o

i " u m ra 1 1 l

. j i

t m

o I.eOf.U 1

1 Is i l'i j il l n

I [Ifl [ $ H U i

h t;

l0 i

Z

. y L

II I

I li

'I Y

I I i um o ln n n i

ii i n o o n g

g

.y.,j.

j

{

i l'.

k g l,g.I,j i-1 J.i i

ll u

4.il g

i p il u

n o

i.

i s W d, L' %

, 7' I

t" te!, '. '..J

.r 4

l

' it i

i g

q q 7

,r i

i

',[.

3 c

7 4"

"' "t 4 1

%o i $t w

L.L

}

6.

}.-

g<..

l a f.

qq

..h t{

[ 4{.[4 g j q f 1

u I"

h(

e j

j s

l-l j

,,j g

.c p',

g g-g-t a

F 7

O y

7 g

y

,p.Q p, y

i4 p g o

l q ;. 4 q

g 1

, 4 e

.u j

j u

i n

p 7

m 7

q j y

, p ; y,.. o.

mm m

g q gj t

l

,q 3,q a -

0.5 "

i""

o i.o 2.0 3.0 4.0

!.(gn; SAMMA EfERGY (MEV)

I sd I

3 9't p

M)3 -

DETECTORS RE-12A.8 4

FIGURE 2.2-5' Y

souncts:

EFFICIENCY VS. GAMMA ENERGY I

1. NED CALCULATION C-RPD-153 SHOREHAM NUC1. EAR POWER STAT 10N48NT 1 h

t 0FFSITE DOSE CALCULATION MANUAL

. saansa EwEney sens (cr )

g REVISION 5 JULY 198S i

1 i

~

l.

l

,2 1

c sa.m t e 2

., T. -

a v

--_Lp !

I I. t:-

F e

-q, s..

,1 - :

- {.,

..rl:n

r- -: - - : -.

.- -N sw,- -

Y '

W J

1

• J y

a j

j

,r -;

-i

/..I i

.a

-I-

~

~

s:.

~

i J

.t.I r.

sv -

.W a

e n

l

1. 1P l

a e

f

.P

,/

d i m

1; 5

.L q 10,

/ l.

1

' I 3

lic

. 4..

, s w

i j

in.7 _

. 3..

e

4.,

..j....j j.

.y.q. 4 "T."

gn L..;.

.4

.#I 4

.).4.{

w 1

.p.

..A...j/.,

~~'

"'" M

....t-w,f ly i

I i

3 j.'

l--t.-

_2.

n is m.

i

'i i

i e:,,

\\

. 4

.s.

-p

.a.

..e ge i

( j.i

.a e

g.

t.

4

_..L.

p_.*. 2

.g._;.

.i..

. l'._

1/.

I i

to -

i y

= = = --

ra***

1 i

A t

.. L f

- _. i... -

4..

.g.

4 4

.q a..

_4.

=

4

.... y y.. 4 y..

._.p. _ 4.. L L'

s t

l g '/l.:. !;I...

.l '

.l..1

. i J

8_.

l.. L l

10 00' 10 10" d.

i SOURCte l

RAD SERvtCES INC.

CALSRATION Ol' ESE'RLINE EXTERNAL PRoet RO-17A CALisRATION DATE 01/11/ 85 l

m loEAL cumvt ACTUAL DATA FIGURE 2.2-8 GENERIC LINEARITY CURVE FOR DETECTORS RE-12 A,8 SHOREHAM NUCLEAR POWER STATION-UNIT I OFFSITE DOSE CALCULATION MANUAL REvistom S JULY. IMS

'e-l

~ n Jf'

--L-~~~~--

____________D___-____________-_____

W.

t

{'

k s

g i

N

\\s i

/

N'/

'y lLON6! ISLAND /

OUNO s#

\\

N, s

4,4,, g,\\sk f

to ts so unn

,.c 4

insi 4,

s

_____ h teen

\\

,, A A J, i no - - - - - ~

~______

1 f,

Sc(

I" 5N w-

,, , y ) 3 g, ~kqs~

UkD M.

I 1

, a i,se r,,,,

g.

's s

=

t s

- er e s

suas,,s "

/

j Y\\

s, recowc I

\\

,8 l

!n

\\

\\

_N

• • Y k

IN, \\,

{

s s

,,s s

\\

,4

_f f

A

/

i W

i

)

a

)

i s

/

i 1

M

~

!l 1

b g

f- #

encar,,'

sours ear i

j gw>\\

s/

r N/

\\

FleURE s-t I

\\

I

/

OFFSITE SAMPUNG LOCATIONS i

- 8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM o

s to SHOREHAM NUCLEAR POWER STATl0N4SNTI 0FFSITE DOSE CALCULATION MANUAL 5

SCALE - MILES I

REVtssON 6 - Augugg 1995

_-----