ML20213E594
| ML20213E594 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/01/1983 |
| From: | Congel F Office of Nuclear Reactor Regulation |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0647, CON-WNP-647 NUDOCS 8309150169 | |
| Download: ML20213E594 (6) | |
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CEiliRAL FILES SEP 011333 RAB R/F FJCongel/ File f.Li l'af.h)i,n Fi;r:: Cecil 0 Thu,.a s, Cn i e r Standarcization
- s. Special Projects nrruico, UL FWU.:
Frank J. Congel, D11er RaJiulogical Assess..ent liranen, OSI St M CT:
P W,F iu:0 REVIE'.i ":F :J")-t TED,' IC AL SPECIFIC /.Tiv! S Ine Pidiological Assessuent tirartcii nas co:apleted its review of toe proposed Mdiolegical Ettluent Technical Sp"cifications WETS) for t:iP-2.
Based ui.on our revie.., the PET 5 <tre acceptable as tiratted sita t: e inclusion of t..e caan gs noted in tne 3ttaca ent.
no..evar, our final approval of the e.IS is cantirnNnt 'apon tim sua:.;ission an accept <tel a ut tsite Fosr, Calcula-tion ::asn!,tl (O..C..) by the utility f ar Co anission approval as requiraJ cy Tecnnical brecification 0.1a.1.
As of this date the reviaa or toe o!:C;.
is still continuing.
Inese revie,s are being perior,ied oy.t. Wangler,,15/ r.N.
Original s!gned by F. J. Congel Frank J. Cun3el, Cnief
.u.:iological nssess..:ent 3rnacn Ji vi ston of Syste '.s Inte.,rativo ht ?.a c:1' M n t :
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' P K ? & RB9B'l COPY ACitfNISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) where no enclosure exists for purposes of locking, and no enclosure can be reasonab constructed around the individual areas, then that area shall be toere;nd c.ed.
onspicuously posted, and a flashing light shall be activated as a ng cevice.
In lieu of the stay time specification of the RWP, continuous surveillance, direct or remote (such as use of closed circuit TV cameras) marb_e made by personnel qualified th radiation protection procedures to provido prist-tive exposure control over the activities within the. area.
k PROCESJ CONTROL PROGR)lM (PCP) 6.13 6.13.1 The rCo shall be approved by the Cor. mis:; ion prior to implementation.
6.13.2 Licensee-initiated changes to the PCP:
a.
Shall be submitted to the Commission in the Semiannual Radioactive
~
Effluent Release Report for the period in which the change (s) was made.
This submittal shall contain:
1.
Sufficiently detailed information to totally support the rationale for the change without benefit of accitional or supplemental information; 2.
A determin'atio'n that the change did riot reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and 3.
Documentation of the fact that the change has been reviewed and found acceptable by the POC.
b.
Shall become effective upon review and acceptance by the POC.
6.14 0FFSITi'_00SE CALCULATION MANUAL (00CM_1 6.14.1 The ODiM shall be approved by the Comission prior ~to implementation.
6.14.2 Licensee-initiated cnanges to the 00CM:
a.
Shall be submitted to the Coensission in the Semiannual Radioactive Ef fluent Release Report for the period in which the change (s) was made effective.
This submittal shall contain:
1.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supple-mental information.
Information submitted should consist of a package of those pages of the 00CM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
2.
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and WASHINGTON NUCLEAR'- UNIT 2 6-25
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3BLE4.12-1(Continu$d) hk TABLE NOTATIONS It shouTd be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system ang not as an a posteriori (af ter the fact) limit for a particular measurehent.
Analyses sliall te performed in such a manner that the stated LLDs will'ue achieved under routine conditions.
Occasionally background fluctuations, unavoidable small sample sizes, the presence of. interfering nuclides, or other uncontrollable c.ircumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described in th' Annual Radiological Environmental Operating Report pursuant to Speci ficution 6.9.1.10.
lLD for drinking water samples. Mm M[M d
<Y Ub oh ml h/
inn WASHINGT0ft NUCLEAR - UNIT 2 3/4 12-12
RAbI0ACTIVEEFFLUENTS g
li 3/4.11.4 TOTAL DOSE I
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 radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than m equal to 75 mrems.
S gh APPLICABILITY:
A*. all times, ACTION:
With the calculated doses from the relea'se of radioactive materials a.
in liquid or gaseous effluents excepd'ing twice.the limits of Specifica-tion 3.11.1. 2. a, 3.11.1. 2. W. 2. a, 3.11. 2. 2. b, 3.11. 2. 3. a. o r 3.11.2.3.b, calculatiorpMihould"b'h made including direct radiation centributions from the rhactor--tTnits and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.
This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report.
It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the e:,aosure levels or concentrations. If the estimated dose (s) exceeds t'le above limits, and if the release condition resulting in violation if 40 CFR Part 190 has not alreacy been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall 5-determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the 00CM.
4.11.4.2 Cumulative dose contributions from direct radiation from unit coera-tion shall be determined in accordance with the methodology and parameters in the 00CM.
WASHINGTON NUCLEAR - UNIT 2 3/4 11-20
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TABLE 3.12-2
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El REPORTitlG LEVELS FOR RADIDACTIVITY C0fiCEliT9ATIOt'4S Ill Ef4VIR0f4MEliTAL SAMPLES E
E WATER AIRBORiiE PARTICULATE FISil MILK FOOD PRODUCTS p
AtlALYSIS (pCi/L)
LH L*sSES (pCi/m )
(pCi/kg, wet)
(pCi/L)
(pri/kg, wet) 3 C
I il-3 2 x 10 II) 4 3
5 Hn-54 1 x 10 4
-4 3 x 10 2
N Fe-59 4 x 10 4
1 x 10 3
Co-58 1 x 10 4
3 x 10 2
Co-60 !
3 x 10 1 x 104 m
D 2
2 n'-65 3 x 10 4
2 x 10 7
2 Z r-llb-95 4 x 10 1-131 2
0.9 2
3 1 x 10 Cs-134 30 10 1 x 10 60 1 x 10,
3 Cs-137 50 20 2 x 10 70 2 x 10 y
3 3
2 O
Ba-La-140 2 x 10 2
,i c;
3 x 10,
h (1) for drinking water sample The value given is the 40 CFR Part 141 value. 74 a oinalL wo]w[eveLs A,4wQ, a <creAuR----
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TABLE 4.12-1 z
S DETECTI0li CAPABILITIES FOR ENVIRONMEllTAL SAMPLE AllALYSIS*
o2 LOWER LIMIT OF DETECTION (LLD)D E
P WATER AIRBORilE PARTICULATE FISil MILK FOOD PRODUCTS SEDIMENT 7
ANALYSIS (pC1/L)
OR GASES (pCi/m )
(pCl/kg, wet)
(pCi/L)
(pCi/kg, wet)
(pCl/kg, dry) 3 E
Gross beta 4
1 x 10-2 U
9 m
11-3 2000 s
Hn-54 15 130 Fe-59 30
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260 s
[
Co-58,60 15 130 m
g Zn-65 30 260 Zr-95 30 CD o.
lib-95 15
-2 Ro I-131 7 x 10 1
60
- c
-2 Cs-134 15 5 x 10 130 15 60 150
-2 Cs-137 18 6 x 10 150 18 80 180 Da-140 60 60 La-140 15 15
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