ML20134J863
| ML20134J863 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/30/1985 |
| From: | Dietz C CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20134J843 | List: |
| References | |
| NUDOCS 8508290504 | |
| Download: ML20134J863 (19) | |
Text
- - _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ - _ _-
Brunswick Steam Electric Plant Senlannual Radioactive Ef fluent Release Report January 1 to June 30, 1985 l
ATTACHMENTl
- 1. Supplanental Information .
- 2. Effluent and Waste Disposal Data
- 3. ODCM and' PCP -Revisions 4 Environmental Monitoring Program 5 .' Inoperable, Effluent Instrumentation
- 6. Major Modifications to Radioactive Waste Treatment Systems 1 7. Meteorological Data
- 8. Potential Dose Assessment I
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.8508290504 850823 l PDR ADOCK 05000324 R, PDR ;_
ATTACHMENT 1 Suppl eental Information January 1 to June 30, 1985 2
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EFFLUENT WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility: Brunswick Steam Electric Plant
~ Licensee: Carolina Power & Light Company 1.~ Regulatory Limits
-A.- Fission and activation gases (Technical Specification 3.11.2.2)
- (l) Calendar- Quarter (a) 10 mrad gamma (b) 20 mrad beta (2) ' Calendar Year (a) 20 mrad gamma (b) 40 mrad beta
. B. Iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days (Technical Specification 3.11.2.3)
- (1) Calendar Quarter (a) 15 mrem to any organ (2) Calendar Year (a) 30 mrem to any organ .
C. Liquid effluents (Technical Specification 3.11.1.2)
- (1) Calendar Quarter (a) 3 mrem to total body
.(b) 10 mrem to any organ (2) Cs.lendar Year (a) 6 mrem to total body (b) 20 mrem to any organ NOTE: Dose calculations are determined in accordance with the Off-site Dose Calculation Manual (CDCM) .
- Used for percent of technical specification limit determinations in Table 1A.
- Used for percent of technical specification limit determination in Table 2A.
(
)
- 2. Maximum permissible concentrations and dose' rates which determine maximum instantaneous release rates.
A. ' Fission and activation gases (Technical Specification 3.11.2.1.a)
(1) 500 mrem / year to total body (2) 3000 mrem / year to the skin B.. Iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days (Technical Specification 3.11.2.1.b)
(1) 1500 mrem / year to any organ C. Liquid effluents (Technical Specification 3.11.1.1)
The concentration of radioactive material released in liquid effluents to unrestricted areas af ter dilution in the discharge canal shall be limite.t to the concentrations specified in 10CFR20, Appendix B, Table II, column 2, for radionuclides other than noble gases.
- (1) Tritium: MPC = 3 x 10-3 uc i/ml; and
- (2) Dissolved and entrained gases: MPC = 2 x 10-4 pC1/ml
- 3. Measurements and Approximations of Total Radioactivity A. Fission and activation gases Analysis for specific radionuclides in representative grab samples by ganna spectroscopy.
B. Iodines ,
Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy.
C. Particulates Analysis _for specific radionuclides collected on filter papers by gamma spectroscopy..
. D .- Liquid Effluents Analysis for specific radionuclides by individual releases by gamma spectroscopy.
C*Used as applicable limits for Table 2A.
b L- . A
Nuclear counting statistics are reported utilizing .1-sigma error. Total error where reported represents a best effort to approximate the total of all individual and sampling analysis errors.
- 4. Batch Releases A. ' Liquid (1) Number of batch releases: 2.61E+02 (2) Total time period for batch releases: 2.63E+04 minutes (3) Maximum time period for a batch release: 1.88E+02 minutes (4) Average time period for a batch release: 1.01E+02 minutes (5) Minimum time period for a batch release: 1.20E+01 minutes
- (6) Average stream flow during periods of release of effluent into a flowing stream: 4.77E+05 gpm B. Gaseous (1) Number of batch releases: None (2) Total time period for a batch . release: 0.00E00 minutes (3) Maximum time period for a batch release: 0.00E00 minutes (4) Average time period for a batch release: 0.00E00 minutes (5) Minimum time period for a batch release: 0.00E00 minutes
- 5. Abnormal Releases A. Liquid (1) Number of releases: 0.00E00 (2) Total activity released: 0.00E-00 Ci B. Gaseous (1) Number of releases: 2.00E00 (2) Total activity released: 2.67E-02 C1 (3) A release of noble gases from the Stack Filter House, lasting approximW'cely 6840 minutes, occurred between January 19, 1985,
'to January 24, 1985. This release was caused'by off-gas leaking around a loop seal located in the Stack Filter House.
A release of noble gases from the Stack Filter House, lasting approximately 1764 minutes, occurred between February 8,1985, to February 9,1985. This release was caused by off-gas leaking around a loop seal located in the Stack Filter House.
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JATTACHMENT 2 Effluent 1and Waste Disposal Data
-Brunswick Steam Electric Plant January _' June, 1985 Table IA: ' Gaseous Effluents - Summation of All Releases Table IB: Gaseous Effluents - Elevated Releases Table IC: : Gaseous Effluents - Ground Level Releases Table 2A: . Liquid Effluents - S'ummation of All Releases Table 2B: Liquid Effluents -
Lower Limits.of Detection Table 3: Solid Waste and Irridated. Fuel Shipments O-
Tcble 1A
-Ef fluedt and' Waste. Di soosal -Semiannual - Rooort ' Year 1985 Gaseous Effluents - Summa tion of All Releases Est..
Total Unit Qtr 1 Otr 2 Error.%
A. Fission 'nd a activation-gases
- 1. . Total release Ci 4.41E 03 4.06E 03 1.50E 01 2._ . Average release rate uCi/sec 5.67E 02 5.16E 02
-for period
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- 3. Percent of technical specification limit % 2.98E-01 1.26E-01 B.- Iodines
- 1. Total lodine-131 Cl 1.29E-02 9.01E-03 1.50E 01
~2. Average release rate uCi/sec 1.66E-03 1.,15E-03 for period C.- Particulates
- 1. Total release .Ci 9.22E-03 4.47E-03
- 2. ' Average release rate uCi/sec 1.18E-03 5.69E-04
.for' period ,
-3. Gross alpha Ci 7.57E-05 3.42E-05 D. . Tritium
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-1. Total re1 ease Cl 1.46E 00 5.84E-01 1.50E-01 2.--' Average release rate
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uCi/sec 1.88E-01 7.43E-02 for period LE. -Iodine-131, Iodine-133, Tritium and Particulates
- 1. ' Total release Cl 1.53E 00 6.29E-01 2~. Average release rate uCi/sec 1.97E-01 8.00E-02 for period 3.- Percent of technical %' 4.44E-01 3.13E-01 specification limit
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s Table 18 Effluent and. Waste Discosal Semiannual Report Year 1985 Gaseous - Ef fl uents - El ev'ated- Rel ease Continuous Release Nuclides Released HUnit Qtr 1 Otr 2
- 1. Fission Gases
.a r g on-41. Ci 2.62E 01 1.22E-01 krypton-85m- Ci 7.52E-01 3.67E 00 krypton-87 Ci 3.74E 01 2.67E 00 krypton-88 Ci 2.63E-01 ( LLD xenon-133 Ci- 1.17E 02 -3.67E 01
-xenon-135m Ci 1.23E 02 5.67E'01
~ xenon-135 Ci 6.56E 01' 2.74E 01 xenon-137 C i- 3.44E 02 1.43E O2 xenon-138 Ci 1.54E 02' 7.95E 01 total for period Ci 9.69E 02 3.50E 02
- 2. Iodines ~
iodine-131 Cl 1.21E-02 8.29E-03 lodine-132 Ci 2.14E-03 1.13E-03 lodine-133 Ci 4.34E-02 2.82E-02
- i od i n e-135 Ci 4.60E-02 3.14E-02 total'for period Ci 1.04E-01 6.90E-02
-3.Particulates
- chromium-51_ Ci 7.66E 2.75E-05 '
manganese-54 Ci 1.00E-05 6.60E-05
_ cobalt-58 Ci 4.28E-06 4.44E-07' cobalt-60 Ci 3.09E-05 1.49E-04 strontium-89 Ci 6.06E-04 4.44E-04 strontium-90 Ci 4.27E-06 1.58E-06 yttrium-91 Ci 4.61E-04 ( LLD cesium-137 Cl 1.31E-05 6.59E-06 barium-lanthanum-140 Ci 2.06E-03 6.51E-04
-total for period Ci 3.27E-03 1.35E-03 4
.. Tritium hydrogen-3 Cl 1.11E-01 1.67E-01
c-Table 1C Effluent and Waste Disposal Semiannual Report Year 1985 Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released Unit Qtr 1 Otr. 2
- 1. Fission Gases krypton-85m Ci 1.26E 00- 3.39E-01 krypton-88 Ci 5.98E 00 1.61E-00 xenon-133m- Ci 1.21E 02 1.57E 02 xenon-133 Ci 2.49E 03 2.80E 03 xenon-135m Ci 5.57E 00 1.50E 00 xenon-135 Ci 8.15E'02 7.55E O2 total for period Ci 3.43E 03 3.72E 03 L2. Iodines iodine-131 Ci 7.99E-04 7.24E-04 iodine-132 CI 4.54E-05 ( LLD iodine-133 Ci 3.41E-03 3.63E-03
,. Llodine-135 Ci 1.26E-03 1.55E ______________________________________________________
total for period Cl 5.52E-03 5.90E-03 3.Particulates chromium-51 Ci 4.94E-03 1.09E-03 manganese-54 Cl 1.91E-04 5.58E-04 cobalt-58 Ci 3.80E-05 6.42E-05 iron-59 Ci ( LLD 4.37E-05 cobalt-60' Ci 6.12E-04 1.22E-03 ~
strontium-89 Cl 3.72E-05 9.93E-05
. strontium-90 Ci 5.00E-07 6.55E-07 ruthenium-103 CI 6.54E-07 ( LLD cesium-137 CI 5.97E-06 1.10E-05 barium-lathanum-140 CI 1.20E-04 3.36E-05 cerium-141 Ci 1.42E-06 ( LLD cerium-144 CI ( LLD 3.?6E-06 total for period Ci 5.94E-03 3.12E-03
- 4. Tritium hydrogen-3 Ci 1.35E 00 4.17E-01
TABLE 2A Effluent and Waste Disposal Semiannual Recort Year 1985 Liquid Effluents - Summation of.All Releases Unit Gtr 1 Qtr 2 Est' Tot.
Error.,1G A.-Fission-and activation products
' 1. Total release-(excluding Ci 3.01E-02 2.21E-02 1.50E 01 tritium, gases, alpha) 2.Av._ diluted concentration uCi/ml 2.12E-09 6.64E-10
- 3. Percent limit X 5.80E-02 5.20E-02 B.~ Tritium
- 1. Total' release Cl 1.84E 00 5.02E 00 1.50E 01' 2.Av.' diluted concentration uCi/mi 1.29E-07 1.51E-07
- 3. Percent limit X 4.30E-03 5.03E-03 C.' Dissolved and entrained gases
- 1. Total release Cl 6.14E-02 3.20E-01 1.50E 01 2.Av. diluted concentration UCi/ml 4.32E-09 9.61E-09 ,
- 3. Percent limit % 2.16E-03 4.81E-03 D.' Gross alpha radioactivlig
- 1. Total release Ci 2.78E-04 2.51E-03 1.50E 01-E. Volume of waste liters 4.17E 06 1.28E 07 1.25E 01 r
. F.-Volume of dilution water used liters 1.42E 10 3.352 10 1.30E 01 m
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TABLE 2B Effluent and Waste Disposal Semiannual Report Year 1985 Liquid Effluents - Batch Mode .
Nuclides. Released Unit Gtr 1 Gtr 2
- 1. Fission and activation products
. fluorine-18 CI 2.45E-06 ( LLD sodium Ci 8.89E-06 < LLD
. chromium-51 Ci 2.46E-03 8.98E-04
! manganese-54 Ci 4.29E-03 5.05E-03 iron-55 CI 2.32E-03 < LLD manganese-56 Ci 8.96E-06 < LLD cobalt-58 Ci 8.65E-04 7.78E-04 Iron-59 Ci < LLD 1.36E-05 cobalt-60 Cl 1.67E-02 1.01E-02 zinc-69m' Ci 2.OOE-06 < LLD arsenic-76 Ci -3.87E-04 2.14E-05 strontium-69 Ci < LLD < LLD strontium-90 Ci 2.97E-05 9.03E-05 yttrium-91m Ci 1.99E-05 9.05E-05 yttrium-92. Ci 4.25E-04 5.81E-04 strontium-92 Cl 1.55E-05 4.15E niobium-97 Ci 2.25E-04 1.40E-04 technetium-99m Ci 3.76E-05 1.27E-05 technetium-104 CI 2.15E-06 < LLD ruthenium-105 Ci ('LLD 5.13E-05 silver-110m Ci 6.51E-05 2.10E-05 silver-111 CI 4.41E-05 9.03E-06 '
te11urium-129 CI < LLD 2.07E-05 te11urium-129m CI < LLD 3.50E-05 iodine-131 Ci 8.(5E-05 2.84E-06 te11urium-132 Ci < LLD 7.65E-06 iodine-133 Ci 9.73E-05 6.41E-06 cesium-134 Ci 3.08E-04 1.97E-04 cesium-137 Cl 1.27E-03 3.83E-03 barium-lanthanum-140 Ci 3.77E-04 9.21E-05 lanthanum-142 Ci 9.37E-06 2.28E-05 neptunium-239 Ci < LLD 5.49E-05 total for period Ci 3.01E-02 2.21E-02 i
- p. 7 1
' 31 '
x E
--= ^ TABLF 2B (cont)'
_ Effluent _and Waste Disposal Semiannu'al Report . Year 19P5 Liquid Effluents - Batch-Mode f
- 2. Dissolved and Entrained Unit Gtr 1- 'Gtr 2 Gases krypton .CI < LLD -2.23E-03 krypton-85m CI ( LLD' -3.79E-06 xenon-133' Cl 1.40E-02 7;37E-02 xenon-133m Ci 1.29E-04 2.46E-03 xenon-135 'Ci 4.73E-02 2.41E-01 xenon-135m CI 7.32E-06 2.60E-04 total for-period- Cl. 6.14E-02 3.20E-01
+-
L~
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9
~
s Lower Limits of Detection UCi/mi
~
- 1. L'iquid Releases 2. Gaseous Releases F-18 1.86E-08 Kr-88 5.24E-08 Na-24 3.55E-08 Fe-55 1.73E-07 3. Iodines and Particulates
-Mn-56 8.08E-08 Fe-59 5.01E-08 Fe-59 3.17E-14
.Zn-69m 1.71E-08 Y-91 1.04E-11
.Kr-85 5.44E-06 Ru-103 3.88E-14 Kr-85m 1.85E-08 I-132 -2.88E-13 Sr-89 1.07E-08 Ce-141 3.34E-14 Tc-104 4.98E-08 Ce-144 1.75E-13 RU-105 4.63E-08 Te -129 3.30E-07 Te-129m 3.57E-07 Te-132 1.01E-08 Np-239 1.02E-07
- NOTES:
(1) The above values represent typical 'a priori' LLDs for.
Isotopes where values of "< LLD' are indicated in Tables 1A,-18,,1C,2A and 28.
(2)'Where activity for any nuclide is reported as "Less than ~
LLD', that nuclide is considered not.present and the LLD activity listed is not considered i n summary data.
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m - .<n.s
r TABLE 3 E: FLUENT AND WQSTE DISPOSAL SEMI ANNUAL REPORT (6-MO. PERICD) .
SOLID WASTE AND 1RRADIATED' FUEL SHIPMENTS
_J_a_n_ _ _ n e u J_un_e_ _ _8_5_
WASTE CLASS:____ A_____ _
Total volume s*:ocee, m3__7 *___________. 73E02 7
' Tot a. C1 cuantitv. ________;25E02_,,,_
Unit 6-montn pertoc est. total
- 2. Tyoe of waste-
- a. Scent resins. fi
___ _ __ _ __ _ _ _l t er s l uc c. e s s _ _ m. 3_ _ i _ _ f _. 7
____________________________________ c_1_ _ _E_, _7_. f a2 02____ _ _ i _ _1_ _. 0_0_E_
- b. Dry active waste..comoactec.__m_ 3__, _ __8_. o f EDI__ __ __ i
_ __ - _ n_ o_ n_ _-c. om_ o m_ e_ t_ e_ c. _: _ _________. - _ _ _ 5__ _f_f_f_0__
_ _ _ _ ____ _ C___ _: i _ _1_ _. 00E_
- c. Irraciated ecmoonents: -_ m_3_ _ i _ _ _ _ _N_7A_ _ __ _ _ _ _ _ i
_ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ N7A_ _ _ - _ - _ _ *_ _ -_/- _A__-__--
C_ _2 _ i _ _ _
- c. Otner'(cescr:be): ~ m3 e~
G - ~~~ 00E01
__ __ .Ahsorhed.n41 / ci n qs _-_-_----_- CI_ i _"f -- ~926E _-__-__ t _ 1. -- _- --
- 3. Estimate of mayor racionucisce commesitzen (ev waste tyoe>
~ -~~~
a.______ Cr__51g g _ . _ _ _ _ - - _ _ ___..________ _ _ _ _____ _ _ _ _ _
g _ , _ _~__~
i -__ _6._65E 00
___55____________________-_i Fe- %
_Co.58__________.._.______._ e . . _ _ _ _ _ _ __ x _ _ _ i _g __3 _. 7 6E 00
. . _ _ _ _ _ _ _N i- 6 3 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -
_==
% 1 5 04E00
...._Cs13_7._-___---______-.___i_______-_____-_-_.__-_-_--_
__t____-__-___--_
.-.---.-_ .__-_._--_-..... ___~_ __-____-_-- __i _-_-______--_
,t__-____ _-_%___1__-____---_-
'....... ---.%.__i__---__-_-_--_
___.--___--___.-_-_-_--_-_-_--_-_-_-____-_-___x_______-__-_-_-__ %
---___--_ _ ... _-___- -__-_-__ __ . -_-_.-_-_-- -__i___ - ____
= __ .._______---_-__-_-_-- ____- _-___ __ __- _
_________Fe.55 --__________________-_i - - - _ __ _ _ _ --__-_ _ _________-____ _ _ _ _5 _. 7 1 E 01_ _ __ _
__________-___-_______t__________. x__ i___1_.95_E0_0____
_ _ _ _ _ . _ _ _C.s_ _1_3_4
%__. i ___3. 9 6E00_ ___ _
.._ __-_Cs__137..__.________________:--_______-
_...._____ __._..__________-_________ _-_________ i %___1_____-________
. . . .... .._. . __...____._________a___________%...i_____--_______
m.
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TABLE 3 (Cont'd)
EFFLUENT AND WASTE DISDOSAL SEM2 ANNUA RdPORT (6-MO. PER200)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS WASTE CLASS: --_-------
A Jan 7nro June 85 7.73E02 Total volume shtooec. m3 --------------
. 7.25E02 Total C1 cuantity. ---------_-_-----_-
- 2. Type of waste Unit 6-month period est. total
_rror--- e L % ----
- a. Soent resinse filter sludcess----- I m3 ----------------
I
_------------------------------- ------=---
C1 I --- ---
I _-_-----
- b. Dey active waste. comoactec. ----- m3 i ----- ---
i non-com
9act ed :
---- Ci i 1
- c. Irradiated component s: m3
_---_I ------ ---- i Ci i - - - - - -
- d. Other (desertbe): m3 I ----------------
I
_Ab.sor_b ed o ill31gj3g----------_ C1 I
--- ---------------- ---- - _==--- i
- 3. Estimate of mayor radionuclice comoosition (by waste typel
- d. ------- E-3 1 %--_I ---_-_0E-OL--- 5.6 ----
r- I % i 1.58E00 Mn- 4--------------------- i_--------_ % --- ___1u i 83 -- E QO -- --- -
Fe-35 l 5
--- --- _. 9_7 E_01 1
~
._--_---Do6D----------------_--.------__---__.%
_-= = _-
I %
-_--- --- -= -
i 2 . 8 2EQL---_ . .
s- 4---------_---------_ i = --- ---
% i u(7E 2 -- QQ----
_----U7_---------------------l---==--=
- _ -_- -- _ . C_s - - ------_-_ ---_--- -----------
% ---i -- 16 4 gqq -
- _-----_-__._--------------------_- ---_------- --- -- 6 ----
1 % I - - -
I % I l % i I -----------% --- -------------- i I ---_------.% --- -------------- I I -----------% --- -------------- i
_t ----------- --- - % I _ -_ -----
I ..% --- ---=
i =- ===---
1
% -- -- ==i - _ =----
I -----------%...i --------------
-.----------------....-------------- ----------- --- ----------~~--
I % i I
- - - . - - - - - - - . . . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -%--- -------------- i I -----------% --- -------------- i I -----------% --- -------------- i 1
% --- -------------- i t -----------% --- -------------- i
TABLE 3 (Cont'd)
A .
. WASTE CLASS __________
l 4 Cross reference table, waste st ream, form, cont a 2 ner t > oe.
S_t__re_ am_
_ F_o_ _rm_ . C_ o_
_ _TY_r n_t a_ _i n_ e_ _ce_ No_. sm__i _ome_
__ _ _ _ _ t _s
- a. Resin 20 D_ e_ w a t er_ e_ d_ _ _ __ _ _ _T_Y _pe_ _Q / _T v _ee_ _ p____________________f__14______
Sciteiftec comcactec/nor-
- c. Dry active conoacted ____LjA/jyy,,_____,,,_,,_____,{_7___,,,,,,,
waste material
- c. Irrad: at ed comoonents
_________________________________N_/_A_______________________N/_A_ ________
- f. Otner DOT 7A Absorbed oil / sludge LSA/STP 8
- 5. Shtoment Discoszt ton A. Solid Waste Number gf E19'_**Dt5 '.M.99f 9f IE!Dsggrtgilgn Qgg11gg11gg 51 -
Sole Use Chan-Nuclear Systems, inc<
Barnwell, SC '
8 Sole Use U.S , Ecology R1chland, WA B. I.aradiat ed Fuel N__ u m_ _be_ r_ o__f S_h__a ___ _orne_n_t s ' M_o_d_e_ o_^f _ _ T_r_an__s_Do_rt__a
_ _ t _t e__r De_ _st__i
_ ___ nat 1e_ _r.
N/A N/A N/A I
k._
. ATTACHMENT'3 OFF-SITE DOSE CALCULATIONS MANUAL'(ODCM)
AND PROCESS CONTROL PROGRAM (PCP) REVISIONS
- January 1 to June 30, 1985
/ ENCLOS'URE ' 1: IR'e visions 4 of . the Off-site Dose Calculation . Manual (ODCM) f S
a t
h r
7 l
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4 'd
i ENCLOSURE 1 Revision 4 of the Off-site Dose Calculation Manual Pages 3-1 to 3-12 have been revised to reflect changes in the meteorological data. 'A note was added for the Turbine Building and Stack vide range gas
. monitors for clarity.
Table 3.1-2 has been revised to reflect changes in the meteorological data.
Pages 3-15 to 3-19 were revised to reflect changes in the meteorological data.
Page 3-24 was revised to correct a typographical error.
Pages 3-26 to' 3-28 have been revised to reflect changes in the meteorological data and to reflect a change in the control locations.
Pages 3-30 to 3-31, 3-37 to 3-40, and 3-46 to 3-48 were revised to reflect changes in the BSEP control locations discovered in the 1984 Land Use Census and the associated meteorological data. Site boundry distances were updated 4 to the site boundry as defined in the FSAR. ,
Pages 4-2, ' 4-3, and 4-5 were revised to provide a more representative listing of plant TLD locations.
. Typographical errors were corrected on page 6-3.
Pages A-2, A-5 to A-7, A-10 to A-13, A-16 to A-19, and A-22 were revised to reflect the changes in the meteorological data associated with the special locations that were updated due to findings of the 1984 Land Use Census. -
Page E-1 was revised to delete the Service Water Effluent from Augmented Off-Gas Pre-Cooler Radioactivity Monitor and Reactor Building Component Cooling (Service Water) Radiation Monitor. This equipment is not installed at this time.
Page E-3 was revised to denote Unit I and Unit 2 instrumentation.
AI-61, Attachment 1, has been included to provide documentation of PNSC review.
- ' s. .
s- 1 7
RECEIVED i KITACHMENT 1 1 JUN 3 1985 I REQUEST FOR OFF SITE DOSE CALCULATION MANUAL CHANGE )
. ' S_N_.P 8 Q00. C.ONTROM ;
{
Or.iginator: Ic.. if da Iro a Date: 2 // [9'/ l Pages and sections revised: f. 6.'- 3./ .<, 1-1i.1 1, ! Ah t 2.
,,. , ,,3 -/t r. f.<f y
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,. :, . p.,.4-s M w A,. d w e. ,. e 1Le ch L adev dr<. ) c. + I tu./,.% . InetJJ
'$eason for change: d 'l', r e v;<a '
- 4. L . a .us; L+ . tl +l . IH'1 f J u n c o ura. ) c ur / r;/*
la. J a
- V .r. h a.,a:,.. .J. I r. .r. n a t...u.a sm.ss
.' Safety Analysis Complete , .
~
(BSEP Form 8): [ A4 I- - Date: 2// </ /f 5
. .'REVIFNS:
mme at Recommended Date: 2- S-25 ALC Supervisor
~
f -[ Y 2-28-P[
q bommended['ot
' RecommendedDate:
'. - &C Project cialis *
//, !A fl///C~ -
b commende Not Recommended Date: I-/ - C
'RC PrincipaV Specialist
- YES ReviewrYuiredbyHEECRadiologicalandChemicalSupportSection:
$11ajs 5'3 NO
) ,
/ du/LOf/N /Not Recommended Date: / 2f5
. Principal, Specialist -
Environmental APPROVALS:
/;
A & Recommend /Not Recommended Date:
Manager - ESRC 70/fT
( D. Q .
PNSC Chairman omme /No,t gecommended D9te: ,
d.h General Man'ager e Approved Date: So /P.T ESEP/Vol. I/AI-ol 3 Rev. 0
/
, _ _ . -