ML20212G292
| ML20212G292 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1986 |
| From: | Barnes W, Hickman O, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 87-088, 87-88, NUDOCS 8703050312 | |
| Download: ML20212G292 (107) | |
Text
SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION JULY 01,1986 TO DECEMBER 31, 1986 PREPAREDBY:[ Ud we William C. Barnes, III Assistant Supervisor Health Physics (Count Room & Environmental)
REVIEWEDBY:(( ?.
O. E. Hickman, Jr. '(/
Supverisor Health Physics (Technical Services)
REVIEWED BY: M de A.1.Stafforjr/
Superintendent Heal Physics APPROVED BY:
E. Wayne Harre 7 Station Manag /
hokO DOC 5 PDR 38 R
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4 FORWARD This . report is submitted as required by- Appendix A to Operating License Nos.
NPF-4 and NPF-7,. Technical Specifications for North Anna Power Station,~ Units .1 and 2, Virginia Electric and Power Cdmpany, Docket Nos. 50-338, 50-339, Section
. 6.9.1.9.
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. SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT FOR THE-NORTH ANNA POWER STATION JULY 01, 1986 TO DECEMBER 31~ , 1986 INDEX
-SECTION N0. SUBJECT ~ PAGE 1 PURPOSE AND SCOPE . . . . . . . . . . . . . . . 1 2 DISCUSSION .................. 1
-3 SUPPLEMENTAL INFORMATION ........... '3 Attachment 1 Effluent Release Data .................. 4 Attachment 2 Annual and Quarterly Doses . . . . . . . . . . . . . . . 5 Attachment 3 Revisions to Offsite Dose Calculation Manual (0DCM) .. 6 Attachment 4 Revisions to Process Control Program (PCP) . . . . . . . 7 Attachment 5 Major changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems ............. 8 Attachment 6 Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Inoperable . . . . . . . . . . . . . . . 9 Attachment 7 Unplanned Releases . . . . . . . . . . . . . . . . . . . 10 I
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Page 1 1.0 PURPOSE AND SCOPE' ;
i The Semi- nnual Radioactive Effluent Release Report includes a summary -
i of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and p Reporting Radioactivity in Solid Wastes and Releases of Radioactive j
. Materials in Liquid and Gaseous Effluents of Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly i
basis following the. format of Appendix B thereof. The report also includes a list of unplanned releases during the reporting period.
As required by. Technical Specification 6.15, changes to the ODCM for the time period covered by this report are included. Information is provided to support the changes along with a package of those pages of the ODCM changed.
This report includes changes to the PCP with information and documentation necessary to support the rationale for the changes as required by Technical Specification 6.14.
Major changes to radioactive liquid, gaseous and solid waste treatment i
systems are reported as required by Technical Specification 6.16.
Information to support the reason (s) for the change (s) and a summary of the 10 CFR Part 50.59 evaluation are included. In lieu of reporting major ,
4 changes in this report, major changes to the radioactive solid waste treatment system may be submitted as part of the annual FSAR update.
As required by Technical Specification 3.3.3.10.b and 3.3.3.11.b a list and explanation for the inoperability of radioactive liquid and/or gaseous
, l effluent monitors is provided in this report.
2.0 DISCUSSION The basis for the calculation of the percent of technical specification for the critical organ in Table 1A is Technical Specification 3.11.2.1.b.
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a Technical Specification 3.11.2.1.b require's that the dosesrate for-iodine-131, for tritium, and for all' radionclides in . particulate form with
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Lhalf tlives greater than: 8 ' days shall _be less than or equal. to 1500 mrem /yr to the critical organ at and beyond the site boundary. The critical organ is. the child's thyroid;-inhalation-pathway.
~
The basis for' the_ calculation:of percent of technical specificatio'n for..
the total body and skin in Table 1A is' Technical Specification 3.11.'2.1.a.'
- Technical ~ Specification 3.11.2.1.a requires _that the dose rate'for noble gases.to areas at and beyond site boundary shall be less than or equal'to 500 mrem /yr'to the total body and less than or equal to.3000 mrem /yr.to the.
skin.
The basis for the calculation of the percent of. technical specification-g in' Table.2A is Technical Specification 3.11.1.1. Technical Specification
~
3.11.1.'1 states that the concentration of radioactive material released in p liquid effluents to unrestricted areas shall be-limited to the
. concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2-
~for radionuclides other than dissolved or entrained noble gases. For
~
dissolved or entrained noble gases, the concentration shall be limited to 2:
~
x 10 microcuries/ml.
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. Percent 'of technical . specification calculations are based on the total L gaseous or liquid effluents released for that respective quarter.
Unplanned releases presented in Attachment 7 are defined according to
- the criteria presented in 10 CFR Part 50.73. Gaseous unplanned releases are those radioactive releases that exceed 2 times the applicable concentrations o
L of the limits specified in Appendix B Table II, of 10 CFR Part 20 in unrestricted areas, when averaged over a time period of one hour. Liquid unplanned releases are those effluent releases that exceed 2 times the L
. -Page 3 ,
limiting combined Maximum Permissible Concentration (MPC) specified in Appendix B, Table II, of 10 CFR Part 20 in unrestricted areas for all radionuclides except tritium and dissolved ' noble-gases, when averaged over a time period _of one hour.
.3.0 -SUPPLEMENTAL INFORMATION 7There!are no-inclusions for the time period covered by this report.
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EFFLUENT RELEASE DATA a - ,'
7/86 - 12/86 -"
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' This attachment includes e summary; of the quantitids' - ,
r, of radioactive liquid and gaseous effluents atrd solid waste,~ [,.i ?,c /'
'as outlined in Regulatory Guide.1.21. " i' "
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g'% % 4 EFFLUENT AN2 isASTE DISPOSAL.SDfI-AidNUAL PJPORT.(1986) > ~ .T-E'gp
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EST. TOTAL _ 6p UNITS- 3rd QUARTER- 4th QUARTER- -% ERROR '.,w.:.d31
% .- 4 y A.- Fission and Activation Gases:
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- 1. Total Releese Ci 1.09E+3- 6.23E+11 1.7E+1- .
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- 2. Average Release hte for Period pCi/see 1.37E+2 -7.84E+C a' - , e E. Iodines: ,
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- 1. Tots! Iodine-131 Release .Ci 1.77E 9.37E-4 -l'7E+1
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- 2. Average Release Rate for Period: uci/see ' 2.23E-3 1.24E-4 C. PARTICULATES (T > 8 days): "J_ . . . . ,
- 1. Total Particulate (Th > 8 days) ".elease Ci 1.70E-4 S.50E-5~ 1.7E+1' -
2 .- Average Release Rate for-Period pCi/sec 2.14E-5 1.07E-5 ~%1
- 3. Gross Alpha Radioactivity Release Ci 1.22E-4 9.27E-5 1.7E+11 -
D. Tritium: M ._
- 1. Total Release Ci 1.18E+1' -4.03E+1- 1.7E+1-2.. Average Release Rate for Period pCi/see 1.49E+0 5.07E+0 E. Percentage of Technical Specification Limits: .
- 1. Total Body Dose Rate % 5.llE-2 7.63E-3'
- 2. Skin Dose Rate % 2.02E-2 2.17E-3
- 3. Critical Organ Dose Rate % 2.34E-2 4.75E 0 Less than Lower Limits of Detection
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'~L EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL' REPORT.(1986)"~ '
' [ '
LIQUID. EFFLUENTS-SUMMATION;OF ALL RELEASES.. 4 gg NORTH ANNA; POWER.. STATION -
t
- . EST. TOTAL--
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' UNIT ^
j;_ 3rd QUARTER 4th QUARTER- ERROR %i ,
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. A. ' Fission & Activation Products - ,
a
- 1. Total release (not including tritium, .
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- gases, alpha) Ci
- 7.67E-2 4.19E-1< l~7E+1.
%. .,e a g i 2. Average diluted concentration during '
- - - L '
j period pCi/ml 1.01E 5.72E y
! 3. Percent of applicable limit (T.S.) % 2.95E-3 1.64E-2 >r I
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B. Tritium ~
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- 1. Total release activity. C1 4.50E+2 4.26EA2' l.7E+1L' N!
- 2. Average diluted concentration:during V I~
, period. pCi/ml- 5.92E-7 -5.81E-7 N: '
- 3. Percent of applicable limit.(T.S.) % l.97E 1. 94E--2 7 "
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- 1. Total release activity. Ci 8.86E-1 -l.28E40' ' lC7E+1 '
- 2. Average diluted. concentration during J.
j period. pCi/ml' l.17E-9 1.75E-9 l 3. Percent of applicable limit -(T.S.) % 5.83E-4 8.73E-4 D. Cross Alpha Radioactivity .
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- l. Total release. activity. Ci- .* ~* .?l.7E+1 f
l E. Volume of waste released.(prior.to .
dilution) . Liters 4 ~.93E+7 - 8.97E+7' :2.0E+0 F. Volume of dilution water.used during l period -Liters ~7.60E+11i ,7.33E+11-- 2.0E+0' 4
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l a e t L N i t t e e o o o r i h a i i o e a a e t o i n o o e r h n e o F S S C C I C C 1 Z C M N Z M T B L C O S S A I I T I P A T T *
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" TABLE 3'l(7/86 - 12/86)' 4 EFFLUENT AND WASTE. DISPOSAL: SEMI-ANNUAL REPORT SOLID WASTE-AND IRRADIATED ~ FUEL SHIPMENTS lAi ' SOLID WASTE SHIPPED OFFSITE FOR BURIAL.0R DISPOSAL (NOT IRRADIATED FUEL)
MONTH- EST. TOTAL
- 1. l Type'of; Waste UNIT PERIOD l ERROR,%2
- a. 3 pent resins, filter sludges, m3 - 1.24E+2 2.5 E+1-2.5 E+1,
~
, evaporator bottoms, etc. Ci 4.07E+2
- b. ~ Dry . compressible waste, .
m5 8.44E+1- 2.5 E+1 -
-contaminated equipment, etc.. Ci 1.16E+1- 2.5 E+1
.c. . Irradiated components, control m3 -
. rods, etc .. Ci
- d. Other-(describe) .m3 g _ Absorbed Oil Ci Estimate of major nuclide composition'(by type of waste)
~
, 2.
- a. Managanese - 54' % 1.80E+0 2.5 E+1
' Cobalt - 58 % 1.31E+1 2.5 E+1 Cobalt - 60 % 2.48E+1 2.5 E+1 '
Nickel - 63 % 3.50E+0 2.5 E+1-Cesium - 134 % 1.35E+1 2.5 E+1 Cesium -137 % -3.43E+1 -2.5 E+1
.b. Managanese --54 % 1.30E+0 2.5-E+1 Iron- 55 % 6.81E+1 2.5 E+1 Cobalt - 58 % 3.80E+0 2.5 E+1 Cobalt - 60 % 1.40E+0 2.5 E+1 Nickel - 63 % 1.07E+1 2.5 E+1 Tritium -% 1.10E+0 2.5 E+1-
, Cesium - 134 % 1.50E+0 2.5 E+1 Cesium - 137 % 4.20E+0 2.5 E+1 Cerium - 144 % 1.30E+0 2.5 E+1 Barium / Lanthanum 140- % 3.30E+0 2.5 E+1
" 2.5 E+1 Strontium - 89 % 1.40E+0 Plutonium - 241 % 1.90E+0 2.5 E+1 .
j c. None
(; d. None
- 3. Solid Waste Disposition DESTINATION NUMBER OF SHIPMENTS MODE OF TRANSPORTATION t
18 Truck Barnwell, SC i B. IRRADIATED FUEL SHIPMENTS (Disposition)
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION l
I None l
1
% e Pagel5 ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES
'(1/86'- 12/86)
This attachment includes an assessment of radiation doses to
-the maximum exposed member of the public due to radioactive j liquid and gaseous effluents released from the site.
N^
s 4
w r-w w---ww ~-7--777- **m- N e yg V- ey- e t'7Fi+v -t--v- -mw ww - ils :7c4T---w -*- -7 - MT' w -
m--ty'+r'--W -t--'T-e"M'
t ^ 5 ., ,
r
.. - no Ky Y
Liqu'id Eff1'uents:-
.s . -
T + x
+Y .,
1st- 2nd 3rd 4th Annual.
Quarter - Quarter Quarter - Quarter:- ' Total Total DoseBody' (mrem ) 0.04 0.03 0.02 0.80' O.90
, Critical Organ
. Dose;(mrem) 0.13 0.04 0.032 1.01' l'.21 JI.
Gaseous Effluents:
._lst 2nd 3rd 4th Annual
-Ouarter Quarter Quarter Ouarter Total Noble Gas Gamma Dose (mrad) 0.;46 0.11 0.08 0.01 0.65 Noble Gas-Beta Dose -(mrad) 1.19 0.21 0.22 0.01 1.63 Critical Organ Dose for I-131,-
H-3, Particulates 0.08 0.04 0.64 0.06 0.80 with Ti ? 8' days (mrem)-
- =-- , .
t 4
T
- Page 6 ATTACHMENT 3 (7/86-12/86)
REVISIONS TO 0FFSITE DOSE CALCULATION MANUAL (0DCM)
As required by Technical Specification 6.15, revisions
- to the ODCM for the time period covered by this report are synopsized below. Supporting documentation and affected pages of the ODCM are attached.
10-23-86: Revisions were made to HP-0DCM-14 to reflect the change to the US EPA Interlaboratory Comparison program of eliminating Ba-140 as a cross-check nuclide for analysis of Environmental Milk and food products.
10-23-86: Revisions were made to HP-0DCM-4 to reflect changes to the liquid effluent pathway dose calculations due to affects of recirculation in the cooling water reservior.
12-11-86: Revisions were made to HP-00CM-13 for clarification of the Environmental Monitoring location maps, f
a., - , .. .w . , , , -- , , , - . , . - , - .-,.-----n -- - -~ - .n-.. , - -.-- ---a
REQUEST TO CHANGE PROCEDURE ADM-5.4 NORTH ANNA POWER STATION Attach:2nt 3 VIRGINIA POWER Page 1 of 1 09-04-86
[V IUPERVISOR RESPONSIBLE FOR FOLLOWING PROCEDURE:
ABNORMAL CURVE BOOK OPERATING PERIODIC TEST WELDING ADMINISTRATIVE EMERGENCY ANNUNCIATOR IN-SERVICE INSPECTION $JHEALTHPHYSICS CALIBRATION MAINTENANCE SPECIAL TEST CHDilSTRY NON-DESTRUCTIVE TEST START-UP TEST PROCEDURE NO: 2 UNIT NO: 3 REVISION DATE: 4
///-p bc 2 . JY / / 2. - )/ s 's - pg=
T1TLE s Awk W" n'" s Y" ra.s omiw ka s po <** s a ma sns,9e er s. 5
.Sc. Y:=
- d inw 3*xe re.e ,# re,.yn a , s . a nmem CHANGES REQUESTED: (GIVE STEP NUMBER, EXACT SUGGESTED WORDING AND LIST REFERENCES, STAPLE 6 COPY OF PROCEDURE WITH SUGGESTED CHANGES MARKED TO THIS FORM.)
5h ,#rnaa/ /r7.co.a s/ sw /.T, v. 4.< n .A, sys r 7~ mr4 4
< s <g
REFERENCES:
REASON FOR CHANGES: 7
//' 5 M /,4 A br 4 Ln4,.+ t'n., n ,wn anua- An .s in/
_ 4 d.,9- No & ten - r/ued .inM.
[:, , J m.b nd , ,L4 dr s ms h " -J
/ ' /
Anel m e L b
- / /A / nwa c Ja- n ., ,4 6 . use .<4J 4 d',d L ,.a l a ces 4, A. /f Va. ,V- K-ev ' / * /
CHANGE REQUESTED BY: 8 DATE: 9 k YmW / r - c '/ - s c ACTION TAT.EN: 10 DOES THIS CHANGE THE OPERATING METHODS AS DESCRIBED IN THE UFSAR7 YES DOES THIS CHANGE INVOLVE A CHANGE TO THE TECH. SPECS? YES DOES THIS CHANGE INVOLVE A POSSIBLE UNREVIEVED SAFETY QUESTION? YES IF ALL "NO", NO " SAFETY ANALYSIS" IS REQUIRED. IF ANY "YES", A " SAFETY ANALYSIS" IS UIRED.
(10CFR50.59) APPROVED COPY TO BE PROVIDED TO LICENSING COORD. FOR INCLUSION IN ANNUAL REPORT.
l RECOMMENDED ACTION' -
11 l DISAPPROVED DOES THIS PROCEDURE CREATE A PROVE)D QA DOCUMENT 7 YES h 12 DATE:
BYs (COGNI p T UP VISOR) j 13 d G. )1* Ad-45 af 6 REVIEWED BY QUALITY ASSURANCE':
CHANGES MADE: YES 40) 14 BY: 15 DATE IT ku/
VIEWED BY STATION NUCLEAR SAFF,TY AND OPERATING COMMITTEE:
- r. ) i n
/
I' .
17 5l0 DISAPPROVED APPROVED AS MODIFIED BY COMMIT CHAIRMAN SIGNATURE: 18 DATE: ,
19 NEW PROCEDURE REVISION DATE: 20 ACTION COMPLETED BY: 21 DATE: 22
H.P.-0DCM-14 Page 1 of 2 12-19-85 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAI. NOh A CONTROLLED
, nnruMrNT J AN 211987 SECTION 14- NO ; ivCESSAmLY THE LATEST REVIOlON Interlaboratory Comparison Proaram Part Sub' ject Pm 1 Technical Specification Requirement 2 2 Program 2 , h, 3 Results - 2 l
l l
,-_- - - - , . - -..c,_- . . _ . _ . _ . - - - -. - , . - . . . . _ . , . , ., _ . _ - _ . - . . , , . . - . - . _ _ . _ _ _ _ _ , _ . . . _ _ . - -
c
'N.P.-0DCM-14 Page 2 of 2 i
'12-19 -
-- -a
, 1. TECHNICAL SPECIFICATION REQUIREMENT l
l Technical Specification 3.12.3 requires that: " Analyses shall be-l performed on radioactive materials (which contain nuclides produced.at nuclear power stations) supplied as part of an Interlaboratory Comparison Program, described in the ODCM, that has been approved by the Commission".
I l
- 2. PROGRAM I 3;
In order to comply with the above Technical Specification, analyses are .j performed as part of the cross check programs sponsored by the Quality Assurance . Branch NERC-LV of the U.S. Environmental Protection Agency.
I Participatio lude)( the following analyses:
I Program Cross-Check Of:
Iodine in Water -
I-131 i Tritium in Water H-3 ..
I bf l Gamma in Water Cr-51, Co-60, Zn-65 l
Ru-106, Cs-134, Cs-137 Radionuclides in Milk Sr-89, Sr-90, I-131,
l
- 3. METHODOLOGY AND RESULTS The methodology and results of the cross-check program shall be maintained in the contractor supplied Nuclear Reactor Environmental Radiation Monitorina Quality Control Manual, IWL-0032 .361. This Manual shall be available for inspection at the station.
l l
] 9-REQUEST TO CHANGE PROCEDURE ADM-5.4 NORTH ANNA POWER STATION Attachssnt 3 VIRGINIA POWER Page 1 of 1 09-04-86 SUPERVISOR RESPONSIBLE FOR FOLLOWING PROCEDURE:
ABNORMAL CURVE BOOK OPERATING WELDING ADMINISTRATIVE EMERGENCY PERIODIC TEST ANNUNCIATOR IN-SERVICE INSPECTION 6EALTH PHYSR!D CALIBRATION MAINTENANCE SPECIAL TEST CHEMISTRY NON-DESTRUCTIVE TEST START-UP TEST PROCEDURE NO: 2 UNIT NO: 3 REVISION DATE: 4 O O c n1 - 4 I + .2 - -
n-n -rs-
Dod.m-4 . K2 M Aco Md' a 1 -1 CHANGES REQUESTED: (GIVE[TEPNUMBER,EXACTSUGGESTEDWORDING,ANDLISTREFERENCES, STAPLE 6 COPY OF PROCEDURE WITH SUGGESTED CHANGES MARKED TO THIS FORM.) '
5* X/ YJ7r .I f
REFERENCES:
o db Y J h*2 lbY 2;&An__b ] , .
l l
CHANGE REQUESTED BY: 8 DATE: 9 ACTION TAKEN: ([ 10 i
l DOES THIS CHANGE THE OPERATING METHODS AS DESCRIBED IN THE UFSAR? YES DOES THIS CHANGE INVOLVE A CHANGE TO THE TECH. SPECS? YES DOES THIS CHANGE INVOLVE A POSSIBLE UNREVIEWED SAFETY QUESTION 7 YES IF ALL "NO", NO " SAFETY ANALYSIS" IS REQUIRED. IF ANY "YES", A " SAFETY ANALYSIS" IS REQUIRED.
(10CFR50.59) APPROVED COPY TO BE PROVIDED TO LICENSING COORD. FOR INCLUSION IN ANNUAL REPORT.
l RECOMMENDED ACTION: - 11 e [APPROV M DISAPPROVED DOES THIS PROCEDURE CREATE A QA DOCUMENT? YES M
, BY (COGNI S E ISOR) 12 DATE: 13 A . /$$~$$
REVIEWEDBYQUALITYASSURANCy 15 DATE g,,
BY: 16 s,/
N:f &J-c/ /
- f n ?? ~? /.;> ~
REVIEWED BY STATION NUCLEAR SAFETY AND OPERATING COMMITTEE: 17 h,PP DISAPPROVED APPROVED AS HODIFIED BY COMMIT CHAIRMAN SIGNATURE: r 18 DATE: If V b "E]~ So 20 NEW PROCEDURE REVISION DATE:
l l
ACTION COMPLETED BY: 21 DATE: 22
~
-b V
MEMORANDUM h
TO: A. H. Stafford/0. E. Hickman North Anna Power Station FROM: E. Dreyer October 16, 1986 Proposed Changes to ODCM 4 Attached is the subject change to ODCM 4 and supporting calculational basis.
1
. !d -
E. Dreyer .
Sr. Staff Health Physicst EWD/sla
, cc: W. C. Barnes, III 1
4 I
s l
O
4 .
PROPOSED CHANGES TO ODCM 4
'is/ 1.0 PURPOSE 1.1 Proposed changes to include effects of recirculating cooling water in the liquid effluents pathway dose calculations of ODCM 4 are discussed. A marked-up copy of ODCM 4 is included (Attachment 1).
2.0 REFERENCES
2.1 Liquid Effluent Dose Limits, North Anna Power Station ODCM Sect' ion 4, 12-19-85.
2.2 A4 Factors ODCM 4, Memo E. Dreyer to E. Hickman. 7-15-86.
2.3 Regulatory Guide 1.109, Rev. 1, 10-77.
2.4 NUREG CR-1276, 5-80.
~
2.5 WASH 1258, Volume 2, 7-73.
2.7 NUREG - 0133, 10-78.
(~)
3.0 DISCUSSION 3.1 As a result of recirculating cooling water in the Lake Anna Reservoir - Lagoon system, dilution of released radionuclides is dependent on radioactive halflive and, therefore, is different to each individual nuclide. Using common dilution factors for all nuclides is not conservative for nuclides with halflives longer than the average recirculation time of the Reservoir - Lagoon system (i.e., 1.326 cft/4140 cfs = 3.2 E+6 sec z 37 days).
To account for recirculation, the factors depending on dilution in the expression for calculation of dose contribution from liquid effluents (Section 2.1 of Ref. 2.1, see Attachment 1) should be modified:
i D = t F IC 4 A $
i
In this expression F (near field average dilution factor) and A g
.r% -
(site related ingestion dose comitment factor) both are dependent l]
on recirculation effects.
4.0 MODIFICATIONS 4.1
- A_9 Factors The Ag Factors are a function of.the dilution factor D,and D, (see Att. 1. Sec. 2.1). A revised metho'd to calculate Aj , D,, and D, for Cs-134/Cs-137 is given in Ref. 2.2. Following this method, A j factors for adults are calculated for the 42 nuclides listed in ODCM4(Attachment 4). Data and parameters used for these calculations are:
, Attachment Reference
- Adult dose ingestion factors 3 2.3, 2.4
- Bioaccumulation factors 2 2.3, 2.4,
,O 2.5 GI
- Lake specific parameters 2 2.6 The Whole Body jA factor for Cs-134 and Cs-137 are in agreement with the hand calculated values of Ref. 2.2.
3.2 F Factors The nearfield average dilution f ctor, F, is multiplied by an individual dilution factor, f , for each considered nuclide to 9
account for the buildup caused by recirculation. For the j derivation of f j , it is assumed that concentrations in the Discharge Channel have reached the equilibrium level or, for longlived nuclides, that a further increase from current levels is t
! not desired. For this case the concentration for the i th nuclide iA iV in the discharge channel is described by expressions 11.2-7 of Ref. 5:
~.-r- .------,,--,,e, - - , - - . - - --,.- , ,- ,-w ~ - - - - - - - , - - - , - - - - - - - - - , , - - - - -
~
~
P g
C Ci
= + C Ri (3.2.1) jp R RL-where: C Ci
= Concentration for i th nuclide in the Discharge Channel.
P 4
= Release Rate of the i th nuclide.
R RL
= Flowrate from Reservoir to Lagoon.
C Ri
= Concentration for i th nuclide in the reservior.
C Ri describes the part of the activity recirculated from the Reservoir.
Without CRi expression (3.2.1) would be applicable for a situation with once through cooling. By introducing the (individual dilution) multiplication factor f ,g (3.2.1) changes to:
P CCi " *f i (3.2.2)
R -
RL Where the dimensionlessg f factor describes the increase in concentration in the discharge channel dyp to recirculation. fg is
's - equal to the part in parenthesis in expression (11.2-8) UFSAR and can be written as:
R R -I RL LR fi= 1- (3.2.3)
Where the nomenclature is the same as in the UFSAR, except that indices "i" have been added to the Removal Constants A t andA R because of their dependence on the individual nuclide's halflife. Calculated values for f gare listed in the last column on Attachment 2.
A check for the calculation is that nuclides with halflives shorter than the average recirculation time of the Reservoir - Lagoon system (3.2 E+06 seed 37 days) should have f4 values of I and that longlived nuclides should have gf values roughly equal to the ratio of recirculation flow rate to flow rate over the dam (i.e., R /ROR RL = 4140 cfs / 220 cfs = 18.8), which is the case.
r.
After including f ,g the expression to calculate the liquid pathways i dose reads:
- b); 1 D = t x F I C, x fg xA g NOTES:
- 1. Instead of using the multiplication factor f >g 1 an Effective Dilution Flow can be defined which is less than or equal the actual flowrate from the Reservoir to the Lake (Second last columnofAttachment2). Using this Effective Dilution Flow to calculate nearfield dilution factors would be analoguous to the Method in Reference 2.7. It can be seen that only shortlived nuclides are diluted with the total recirculation flow of 4140 cfs. For very longlived nuclides the effective dilution flow is roughly equal to the overflow rate over the Dam (ROR = 220 cfs).
- 2. Recirculation flow rates from the Reservoir to the Lagoon and vice versa as listed in Table 11.2-26 UFSAR are divided by 2 to account for a two unit plant. This applies to 8 running l circulating water pumps. Since a higher recirculation rate gives more conservative results than a lower recirculation rate, operation with less than 8 circulating water pumps is conservatively covered by this consideration. ,
I l
V ATTACH 11ENT L H.P.-0DCM-4
'Page 1 of 5 12-19-85
.=
, \_ w . -
b c '. .?
.q,A eio s C NORTH ANNA POWER STATION 1:.\N .?
,,46 ,'l. '? '
t,8 d 0FFSITE DOSE CALCULATION MANUAL SECTION 4 LIQUID EFFLUENT DOSE LIMITS
?
Part Subject m P ,
1 1 Technical Specification Requirement 2 g 2 Calculation 2 3 Example 3 4 Quarterly Composite Analyses 4 l
\
l
H.P.-0DCM-4 Page 2 of 5 12-19-85
.-T.'
- 1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.1.2 requires that: "The dose or dose commitment to the maximum exposed MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-1) shall be limited:
4
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 arem to the critical organ, and
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 arem to the critical organ".
- 2. CALCULATION be calculated for all radionuclides
- -2.1 Dose contribution shall identified in liquid effluents released to UNRESTRICTED AREAS baspd g on the following expressions
- h D=tFIC A i i li $
ik Where:
D= the cumulative dose commitment to the total body or critical organ, from the liquid effluents for the time period t, in mrem; t= the length of the time period over which C and g F are averaged for all liquid releases, hours; F= the near field average dilution factor for C during any liquid effluent release. Defined as the ratib of the average undiluted liquid waste flow during release to the average flow i-ji. f rom ,nhrdent 4 discha ,.ge the site.khenfire tostructure secouart to UNRESTRICTED v in en.sn ras.cout en AREAS; fnWon
[ ~
livent uuthdes str5 in To w e 't.
.Cg=te lenIerage a de to concentration ret 'reut o/ ra ionufromd de, i, in undiluted liquid effluent during time period, t, from any liquid releases, in pCi/al; l A the site related ingestion dose commitment factor to the total i g = body or critical organ of an adult for each identified principal samma and beta emmitter listed in Table 4.0, in arem-al per br-pCi; Ag
=1.14E+05(730/D,+21BF/Dg)DF g g i
l where:
1 1.14E+05 = 1E+06 pCi/pci x 1E+03 al/kg + 8760 hr/yr, units conversion factor; i
l
l C t- H.P.-0DCM-4 Page 3 of 5 l 12-19-85 l
-- . ~ 4"a. fCg 1 730 = adult water consumption, kg/yr from NUREG-0133; D = dilution factor from the near field area withIn one quarter
" re'. ease point to the potable water / intake for the ,
mile of the adult water consumption. Dw includes the dilu on contributions i from the North Anna D to Doswell (0.73) the Waste Heat
'3 am The potable Treatment Facility ;), and Lake Anna ( .
wa,ter sixing ratio wils calculate as -1/0.00 X G.o., X G.75 - 3.29.-
s = a CR(Cs .73 wktte- c e,cg andca a re. t h e.
- Af(Ce/c )(C /ts)*.13 N BF g = the bioaccumulation factor or nuclide, i, in fish, pCi/kg ,
per pCi/1, from Table A-1 Regulatory Guide 1.109; c4/cc & 6 w
= dilution factor for the fish pathway, calculated as 1/0.55 - 1.51.
, . . . . . . . .--- - .. ~ , . . . . . en.e.;.s. _ , _ e fra ec>< siefered s< uelide.
M(gg"..
s et 4s z n KL. Cs are f ai'pren*u s t As the.etwernfestio-Weste fe d S*k* s forbrT54de'l'*' t%en cetesotatoest is Pn DFg = the critical organ dose conversion f actor for nuclide, i, for adults, in eres/pci, from Table E-11 of Regulatory Guide 1.109, Rev. 1.
ftsyetfie e Cosseeufenfious for fhe con sideved *ta c/s'de. h
/
- 3. EXAMPLE ftse bite 4nege ClosunriCettulal!**A4p*sfc.
- Per Expressie.,s ll.g.ffeaf Trenfme.st 3
C, tt.L. & p en d 02-1Facils'f 4 54R. Cl 4 L<e Restevene .
l 3.1 Compilation of data from release records for a 31 day period provides the following information:
Total Volume of . Undiluted Liquid Effluent Released = 2.00E+10 ml Total Volume of Dilution Water Used During Period = 1.59E+14 al Average Concentration of Radionuclides in Undiluted Liquid Effluent Cs-134 = 6.23E-08 pCi/ml l Cs-137 = 2.13E-07 pCi/ml I-131 = 5.17E-07 pCi/ml Co-58 = 1.53E-07 pCi/ml Co-60 = 7.27E-07 pCi/ml H-3 = 4.62E-03 pCi/ml 3.2 31 Day Total Body Calculation:
D = t F IkgAg i
Obtain total body Ag values from Tame 4.0 l t = 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br /> mrem-al mrem Nuclide C i (pci/al)x f'. d A i pci-br = hr Cs-134 6.23E-08 x Il 8f A 5 . @ #^5 5".82E+f = 3.555-e2 it.gp E-f/
Cs-137 2.13E-07 x H.0 x 2.' b 5 S'*fff f = 7.37E-02 (4 0 D 00 I-131 5.17E-07 x !.f. x 3. ;;-;2u0E4L = . 70E-06 g,.ft E -05' Co-58 1.53E-07 r $.3 x .;;;;;;t.ste<t1 = 4.61E-05 f. 50 f. cat Co-60 7.27E-07 x lio x g.,rrHHNt MZ E dL = 6.19E-04 MI I 03 H-3 4.62E-03 x 88 4 X (sj9Evee 6455#' = 3.04E-02 6 10 f*dr I C gfg Ag = l 425 01 i gf g E +0C
H.P.-0DCM-4 Page 4 of 5 12-19-85
-Tl 2.00E+10 (el)
.F= 1.59E+14 (al) 23tgen
- h ';2E ?
Therefore, D = 744(br) x 59E 1.23f
- 0t D = b-33E-M area to Total Body.
3.3 31 Day Critical Organ Calculation:
D=tFI Ag i
Obtain Critical Organ Ag values from Table 4.0.
t = 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />.
?
' aree-al arem
- Nuclide C
i ( Ci/el)# It *Ai pCi-br =
hr (
Cs-134 6.23E-08 # 18 # # M 7.itt W = 4.:4r?E W f.'f4 N 1f Cs-137 2.13E-07 r Nd r 5-996+05 5.n f W = 1.135 01 I-131 5.17E-07 r &f. m.;,7t:1^2 :4: seet. = 2 a7 --e4 1 1i f'.80 g,gqgpt Co-58 1.53E-07 4 $3 Jr i . 2':E*021.4* f*es. = N S 5 76 E*85 Co-60 7.27E-07 r l6d a 3 865+et M7f*#8 = 2 ";;-04 1.4!. f #3 H-3 4.62E-03 Y l#4 1r 6e999+06 6 tf M = 3. O i:- 02 f. 20 f
- 0I 1 18t*00 1 Cg A
- .... un i
F= 2.00E+10 (al) ,
1.59E+14 (al) .
0 10 1.lf f *W Therefore, D = 744(hr) x
- 49e~'T 4 1 f.48f-01 l
D = N ares to critical organ.
- 4. QUARTERLY COMPOSITE ANALYSES t
For radionuclides not determined in each batch or weekly composite, the dose contribution to the current monthly or calendar _ quarter cumulative summation may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses. However, for reporting purposes , the calculated dose i contribution shall be based on the ' actual composite analyses.
l
M.P.-0DCM-4 Pa8e 5 of 5 12-19-85 4
TABLE 4.0 SITf AS AJbLIQUID kG DOSE FACTORS wo now,oIa mann- ruram -
~
g/AM UNIT E 1 AND 2 Total Body A Critical Organ
- A.
Radionuclide .LdMddel.fi I
Dil. Fec W eres/hr mees /hr WCi/e1 pCi/mi H-3 /4.0 2.80E+00 6.fr 6400 2.80E+00 6.lT Ecc Na-24 l. 0 3.11E+02 4,43Sc0/ 3.11E+02 9.4 5 E +ct Cr-51 1,4 9.05E-01 f. IF 6400 - -
Mn-54 l.3 5.71E+02 f. 61 Ee c 2. 2.99E+03 4.54 E* c 3 Fe-55 #3 6 8.10E+01 f.10 E+#1 3.47E+02 6.59 E 4 0 Z
> ! Fe-59 1.5" 7.15E+02 4.74 2 +02, 1.86E+03 2.Kr E dos Co-58 2.3 1.74E+02 f.57 f +p1 7.75E+01 .t.W E*ot Co-60 16 . 0 4.91E+02 f.51 f442 2.23E+02 3 77 BiOL l Zn-65 ie O 2.21E+04 I.07 E dpv 4.89E+04 217 B oy Rb-86 l. 6 3.12Et04 37# E40t 6.70E+04 7.E Reo*
Sr-819 2,9 6.41E+02 4.tv 3.pE - --
Sr-90 14,0 1.35E+05 240 Fe05 - -
Y-91 2A 2.44E-01 1.57 EN - -
Zr-95 3.I 2.01E-01 1.18 f *#I 2.97E-01 f.fi f-Ot Zr-97 10 4.73E-03 f.fr f.09 1.03E-02 tag 6-fy Nb-95 lel 8.79E+01 5.st f*W 1.64E+02 t.cz EfdL Mo-99 10 3.37E+01 f.f1 f*06 1.77E+02 466E44 Ru-103 2,3 3.27E+00 sese0 5400 - -
Ru-106 40 1.43E+01 f.10 840f - -
An-110m 1.3 2.54E+00 Gdi f.#0 4.28E+00 f.56 E+00 l Sb-124 2,4 2.98E+01 4 10 f*0I 1.42E+00 2 24 E H.0~
l Sb-125 t,3 1.14E+01 S.47 f+## 5.37E-01 2.8 8 E -vi l Te-125m 24 2.35E+02 S.10 f+02. 6.36E+02 (.ft a 402.
Te-127a 4. ti 5.41E+02 7.ft Egt 1.59E+03 211 #405 Te-129e 2.1 1.19E+03 f.f 7 f+#$ 2.81E+03 3.pt f4c3 l
Te-131s leo 4.62E+02 f.11 ###2 5.54E+02 f.59 Eact Te-132 1,1 1.00E+03 4.71 fear. 1.07E+03 6 01 54 M.
I-131 1,2 1.67E+02 f.fo f ee. 2.91E+02 l.it e*oE l I-132 1.0 9.29E+00 f.16 E-df 2.66E+01 131 f.4 I I-133 1,0 3.68E+01 4.16 f +se 1.21E+02 136 f*#l I-134 1,0 5.04E+00 148 EdL 1.41E+01 7 30 f.st.
1-135 1,0 2.09E+01 1.f7 E 8f 5.67E+01 211, f*do Cs-134 l2.4 3.84E+05 f.82 fees' 4.70E+05 '7. f r F4 cr Cs-136 1,4 5.87E+04 6 11 f*ft 8.16E+04 g.pt gsov Cs-137 14.C 2.27E+05 S45 ieff' 3.46E+05 f.27 F+dr l Cs-138 1,C 1.71E+02 f.11 f +ed 3.E46+02 22f f*40 Ba-140 1.4 4.20E+01 1.3784# 8.06E-01 f.ft E #/
, La-140 l,0 2.15E-02 f.36 8 -#3 8.15E-02 f.99 f*d2 l Ce-141 2,l 1.93E-02 f.38 d.#2 1.70E-01 2JO E-Ot l Ce-143 f,0 3.63E-03 f.76 f dV 3.28E+01 (.54 f d#0 Ce-144 ) . 4 7.04E+01 (45 f e88 5.48E+00 1 1% f
- 08 Np-239 1,6 2.65E-03 & f a d'- t 4.80E-03 f.fi E-os l
- Critical Organ is defined in HP-0DCM-A2, Page 2 of 2.
.W,( / 6 / ~.5 i- E _
N2RTH ANNA LAKE SPECIFIC DATA See UFSAR CH 11.25 and ODCM 4 for Nomenclature Volumes -Ed Reservoir VR = 1.06E+10 cft Lagoon VL = 2.66E+09 cft Flow Rates : Reservoir to Lagoon RRL = 4140 cfs/sec Lagoon to Reservoir RLR = 4144.5 cfs/sec Lake over Dam ROR = 220 cfs/sec l Evap. Rates : Reservoir RER = 59 cfs/sec Lagoon REL = 21 cfs/sec
- NUCLIDE HALFLIFE BIOACCUM. EFF.DIL. FLOW fi INDIVIDUAL (sec) FACTOR (cfs) DIL. FACTOR 1 H-3 3.89E+08 0.9 230 18.0 2 Na-24 5.40E+04 100.0 4127 1.0 3 Cr-51 2.39E+06 200.0 2194 1.9
! 4 Mn-54 2.70E+07 400.0 500 8.3 i 5 Fe-55 8.52E+07 100.0 305 13.6 i 6 Fe-59 3.86E+06 100.0 1687 2.5
- 7 Co-58 6.12E+06 50.0 1267 3.3 8 Co-60 1.66E+08 50.0 259 16.0
, 9 Zn-65 2.11E+05 2000.0 3999 1.0 . .
10 Rb-86 1.61E+06 2000.0 2634 1.6 "L 11 Sr-89 4.37E+06 30.0 1566 2.6 )I 12 Sr-90 9.02E+08 30.0 218 19.0 13 Y-91 5.06E+06 25.0 1430 2.9 14 Zr-95 5.53E+06 3.3 1351 3.1 4
15 Zr-97 6.08E+04 3.3 4124 1.0 16 Nb-95 3.12E+05 30000.0 3887 1.1 17 Mo-99 2.38E+05 10.0 3971 1.0
! 18 Ru-103 3.40E+06 10.0 1816 2.3 19 Ru-106 3.18E+07 10.0 458 9.0 20 Ag-110m 2.16E+07 2.3 567 7.3 21 Sb-124 5.20E+06 1.0 1405 2.9 22 Sb-125 8.34E+05 1.0 3291 1.3 23 Te-125m 5.01E+06 400.0 1438 2.9 '
24 Te-127m 9.42E+06 400.0 956 4.3 25 Te-129m 2.90E+06 400.0 1983 2.1 26 Te-131m 1.08E+05 400.0 4094 1.0 27 Te-132 2.82E+05 400.0 3922 1.1 28 I-131 6.95E+05 15.0 3440 1.2 29 I-132 8.28E+03 15.0 4140 1.0 30 I-133 7.49E+04 15.0 4116 1.0 31 I-134 3.16E+03 15.0 4140 1.0 4 32 I-135 2.38E+04 15.0 4137 1.0
- 33 Cs-134 6.50E+07 2000.0 334 12.4 l 34 Cs-136 1.14E+06 2000.0 3002 1.4
, 35 Cs-137 9.51E+08 2000.0 218 19.0 I
36 Cs-138 1.93E+03 2000.0 4140 1.0 37 Ba-140 1.11E+06 4.0 3030 1.4
" ' 38 La-140 1.45E+05 25.0 4064 1.0 i
L, 39 Co-141 2.81E+06 1.0 2019 2.1 l 40 Ce-143 1.19E+05 1.0 4085 1.0 1 41 Co-144 2.46E+07 1.0 527 7.9 i 42 Np-239 2.04E+05 10.0 4007 1.0 l
i
, - _ _ _ . - _ _ - _ _ - , . _______m - - , _ _ _ _ _ _ _ . . , . . , _ _ _ _ , _ _ _
- /
f p ( (IM E f/ T 3 ,
Y' INGESTION DOSE FACTORS.FOR ADULf3 (area /pci ingested) -
.;' l 4 -Nuclide. BONE LIVER W. BODY THYRCID KIDNEY LUNG GI-LLI ;
'; 1 H-3 ----
1.05E-07 1.05E-07 1.05E-07 1.055-07 1.052-07 1.06E-67.
Na-24 2
1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-QO
- 3 Cr-51 ---- ----
2.66E-09 1.59E-09 5.86E-10 3'.53E-09 6.69E-07 4 Mn-54 ----
4.57E-06 8.72E-07 - - -
1.36E - -
1.40E-05 5 Fe-55 2.75E-06 1.90E-06 4.43E - - - ----
'1.06E-06 1.09E-06 ,
6 Fe-59 4.34E-06 1.02E-05 3.91E - - - ---- 3.95E-06 3.40E-05 7 Co-58 ----
7.4SE-07 1.67E - - - ---- ----
1.51E-05 '
l 8 Co-60 ----
2.14E-06 4.72E - - - ---- ----
4.'02E 05 9 Zn-65 4.84E-06 1.54E-05 6.96Ea06 - - - '1.03E - - - 9.70E-06
^
10 Rb-86 ----
2.11E-05 9.83E-05 - - - - ~~---
4.16E-06 ,!
11 Sr-89 3.08E-04 - - - - E.84E-06 - - - - ---- ---- 4.94I-OS, 12 Sr-90 7.58E-09 - - - - 1.36E-03 - - - - ---- - - -
.2.19E-04 13 Y-91 1.41E-07 - - - - 3.77E-09 - - - - ---- ----
7.76E-05 .
14 Zr-95 3.04E-08 3.75E-09 6.60E-09 - - - - 1.53E - - - 3.09E-05
, 15 Zr-97 1.68E-09 3.39E-10 1.55E-10 - - -
5.12E - - - 1.05E-04 ;
16 Nb-95 6.22E-09 3.46E-09 1.86E-09 - - - - 3.42E - - - 2.10E-05 17 Mo-99 ----
4.31E-06.8.20E-07 - - - - 9.76E - - - 9199 06 l 18 Ru-103 1.85E - - - 7.97E-08 - - - - 7.06E - - - 2.16 5 1
19 Ru-106 2.75E - - - 3.48E-07 - - - - 5.31E - - - 1.78 4 20 Ag-110m 1.60E-07 1.48E-07 8.79E-06 - - - - 2.91C - - - 6.04E-05
- 21 Sb-124 2.80E-06 5.29E-08 1.11E-06 G.79E - - - 2.18E-06 7.95E-05 22 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E - - - 1.38E-06 1.97E-05 23 Te-125m 2.68E-06 9.71E-07 3.59E-07 8,06E-07 1.09E - - - 1.07E-05 24 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E - - - 2.27E-05 25 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E - - - 5.79E-05 26 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E - - - 8.40E-05 27 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E - - - 7.71E-05 28 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E - - - 1.57E-0G 29 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 S.65E - - - 1.02E-07 30 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E - - - 2.22C-06 '
31 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.34E - - - 2.51E-10 :
32 I-135 4.43E-07 1.16E-06 4.20E-07 7.65E-05 1.86E - - - 1.31E-06 33 Cs-134 6.22E-05 1.48E-04 1.21E - - - 4.79E-05 1.59E-05 2.59E-06 34 Cs-136 6.51E-06 2.57E-05 1.85E - - - 1.43E-05 1.96E-06 2.92E-06 i 35 Cs-137 7.97E-05 1.09E-04 7.14E - - - 3.70E-05 1.23E-05 2.11E-06 36 Cs-138 5.52E-08 1.09E-07 5.40E - - - 8.01E-08 7.91E-09 4.65E-13 37 Ba-140 2.03E-05 2.55E-08 1.33E - - - 8.67E-09 1.46F/08 4.18E-05 38 La-140 2.50E-09 1.2CE-09 3.33E - - - ---- ----
9.25E-05 39 Co-141 9.36E-09 6.33E-09 7.18E-10 - - - - 2.94E-09 - - - - 2.42E-05 !
40 co-143 1.65E-09 1.22E-06 1.35E-10 - - - - 5.37E-10 - - - - 4.56E-05 41 Co-144 4.88E-07 2.04E-07 2.62E-08 - - - - 1.21E-07 - - - - 1.65E-04 42 Np-239 1.19E-09 1.17E-10 6.45E-11 - - - - 3.65E-10 - - - - 2.40E-05 i._._ . _ _ ..-.._. _ ._._ _ _ _ __... _ .. _ _ _ _ .. _ _ __ _ _.._.. _ __ _ .
N T TlVfIMEtr
's , , i 6 e ,
it Wjf #
(~ .
I' f . .
-SITE RELATED INGESTION DOSE COMMITMENT FACTORS FOR ADULTS a .
(area-al/uci-hr)-
I ,tm,i i.
7" i ff Nuclide RONE LIVER W. BODY THYROID KIDNEY LUNG GI-LLI
, l. , .-
C l' H-3 . ,
6.25E+00 6.25E+00 6.25E+00 6.25E+00 6.25E+00 6.25E+00 e,'2 Na-24,- 4 . 4 3 E+01 4. 43E+01 4. 43E+01 4. 4 3E+01 4. 4 3E+01 4. 4 3 E+01 4. 4 3 E+ 01
3 Cr-51' ---- - --- 1.15E+00 6.87E-01 2.53E-01 1.52E+00 2.89E+02 l< ' ,4 Mn-54 ----
4.54E+03 8.67E+02 - - - - 1.35E+03 - - - - 1.39E+04 3.12E+02 3.21E+02 5 Fe-55 8.09E+02 5.59E+02 1.30E+02 - - - - ----
i 16 Fe-59 1.09E+03 2.55E+03 9.79E+02 - - - - ---- 7.14E+02 8.51E+03
- 7 Co-58 ----
1.14E+02 2.57E+02 - - - - ---- ----
2.32E+03 l 8 Co-60 ---- 3.77E+02 8.32E+02 - - - - ---- ----
7.08E+03 1 9 Zn-65 7.46E+03 2.37E+04 1.07E+04 - - - - 1.59E+04 - - - - 1.50E+04 10 Rb-86 ---- 7.96E+04 3.71E+04 - - - - ---- ----
1.57E+04 l 11 .tir-SS 3.17E+04 - - - - 9.10E+02 - - - - ---- ----
5.08E+03 l 12 Wr-90 9.80E+M1 - - - - 2.40E+05 - - - - ---- ----
2.83E+04
! 13 Y-91 1.34E+01 - - - - 3.57E - - - ---- ----
7.35E+03 14 Or-95 1.47E+00 1.81E-01 3.18E - - - 7.38E - - - 1.49E+03
, 15 Zr-97 2.00E-03 4.04E-04 1.85E - - - 6.10E - - - 1.25E+02
! 16 Nb-95 1.84E+02 1.02E+02 5.50E+01 - - - - 1.01E+02 - - - - 6,21E 5 l
17 .Mo-99 ---- 4.66E+01 8.87E+00 - - - - 1.06E+02 - - - - 1.08E 18 Ru-103 1.02E+01 - - - - 4.40E+00 - - - - 3.90E+01 - - - - 1.19
, ,19 Ru-106 2.13E+02 - - - - 2.70E+01 - - - - 4.12E+02 - - - - 1.38E+04 l 20 Ag-110m 9.25E+00 8.56E+00 5.08E+00 - - - - 1.64E+01 - - - - 3.49E+03
- *
- 1 8b-124 1.19E+02 2.24E+00 4.70E+01 2.87E - - - 9.23E+01 3.37E+03 l
22 Sb-125 2.51E+01 2.80E-01 5.97E+00 2.55E - - - 1.93E+01 2.76E+02 i
4 23 Te-125m 2.46EA03 8.92E+02 3.30E+02 7.40E+02 1.00E+04 - - - - 9.82E+03 e 24 Te-127m 6.50E+03 2.32E+03 7.92E+02 1.66E+03 2.64E+04 - - - - 2.18E+04 25 Te-1293 9.90E+03 3.69E+03 1.57E+03 3.40E+03 4.13E+04 - - - - 4.99E+04 l 26 Te-1313 3.24E+02 1.59E+02 1.32E+02 2.51E+02 1.61E+03 - - - - 1.58E+04
, 27 Te-132 9.42E+02 6.09E+02 5.72E+02 6.73E+02 5.87E+03 - - - - 2.88E+04 28 I-131 1.34E432 1.91E+02 1.10E+02 6.27E+04 3.28E+02 - - - - 5.04E+01 29 I-132 1.34E-01'3.59E-01 1.26E-01 1.26E+01 5.71E - - - 6.74E-02 10 I-133 7.84E+00 1.36E+01 4.16E+00 2.00E+03 2.38E+01 - - - - 1.23E+01
~ 31' I-134 2.69E-02 7.30E-02 2.61E-02 1.26E+00 1.16E - - - 6.36E-05 32 I-135 8.25E-01 2.16E+00 7.97E-01 1.42E+02 3.46E+00 - - - - 2.44E+00 33 Cs-134 2.99E+05 7.11E+05 5.82E+05 - - - - 2.30E+05 7.64E+04 1.24E+04 34 Cs-136 2.25E+04 8.88E+04 6.39E+04 - - - - 4.94E+04 6.77E+03 1.01E+04 35 Cs-137 3.86E+05 5.27E+05 3.45E+05 - - - - 1.79E+05 5.95E+04 1.02E+04 f
36 Cs-138 1.14E+00 2.25E+00 1.12E+00 - - - - 1.66E+00 1.64E-01 9.62E-06 37 Be-140 4.69E+02 5.89E-01 3.07E+01 - - - - 2.00E-01 3.37E-01 9.66E+02 38 ,La-140 3.95E-02 1.99E-02 5.26E - - - ---- ---- 1.46E+03 39 'Co-141 3.11E-01 2.10E-01 2.38E - - - 9.76E - - - 8.03E+02 10 Co-143 2.15E-03 1.59E+00 1.76E - - - 7.01E - - - 5.95E+01 41 'C n-14 4 2.70E+01 1.13E+01 1.45E+00 - - - - 6.70E+00 - - - - 9.14E+03
'42 'Np-239 1.13E-02 1.11E-03 6.10E - - - 3.45E - - - 2.27E+0?
(h ,
RIQUEST TO CRANGE PRDCEDURE ADM-S.4 NokTM ANNA POWER STATION Attoch ent 3 t
VIRGINIA POWER Pcge 1 of 1 09-06 -B t>
UPERVISOR RESPONSIBLE FOR POLLOWING PROCEDURE: WELDING CURVE BOOK OPERATING ABNORMAL EMERGENCY PERIOD 1C TEST ADMINISTRATIVE ANNUNCIATOR IN-SERVICE INSPECTION QiREALTHPNYSICS MAINTENANCE SPECIAL TEST CALIBRATION NON-DESTRUCTIVE TEST START-UP TEST CEMISTRY 3 REVISION DATE: 4 PROCEDURE NO: 2 UNIT NO:
}4.! < O p c en - / 3 141. -
l2 f 9.cy b
TITLES o F F S
- et DoaC gu a g e ro.,.a towe. .. o. s .._.
L e 4,i s ok 4 .tu s.uasi t% An m he<%a .
(GIVE STEP NUMBER, EXACT SUGGESTED WORDING AND LIST REFERENCES, STAPLE 6 CRANGES REQUESTED:
COPY OF PROCEDURE WITH SUGGESTED CHANGES MARKED TO THIS FORM.)
M4 n ce p <-. J.~ n,w um nt6. . s / .~.,~.:..,< pm n
REFERENCES:
7 REASON FOR CBANGES:
A . >- 'l
- & rroue ! - x 4.' m m .:.< ,,~~ d A L*.A' /
'dA. 0 .1/ do , rh f/-07 cv.
8 DATE: 9
, CRANGE REQUESTED BY:
/g & g _ /WS /.' s'S -Cc.
10 ACTION TAKEh:
YES DOES THIS CIRNGE THE OPERATING METHODS AS DESCRIBED IN THE UFSAR?
TES DOES THIS CHANGE INVOLVE A CEANGE TO THE TECH. SPECS?
YES DOES THIS CHANGE INVOLVE A POSSIBLE UNREVIEVED SAFETY QUESTION?
IT ALL "NO", NO "SATETY ANALYSIS" IS REQUIRED. IF ANY "YES", A " SAFETY ANALTSIS" IS REQUIRED.
(10CTR50.59) APPR07ED COPY TO BE PROVIDED TO LICENSING COORD. FOR INCLUSION IN ANN 1]
RECOMMENDED ACIION-DOES THIS PROCEDURE CREATE A hROVED) DISAPPROVED QA DOCUMENT? YES @
VISOR) 12 DATE: 13 BY:
l (COGN)
(J.
.' 'T,,UP u 30 /)-/}-8 6 REVIEWEDBYQUALITYASSURAhg' YES (C 14 CHANGES MADE:
5' g ( h[ l'
_ JIEkT.D BY STATION NUCLEAR SATETY AND OPERATING COMMITTEE:
PROVED AS MODIFIED BY COMMIT
@RO@ DISAPPROVED 18 DATE: _ g l' CHAIRMA.N SIGNATURE:
NE Ph00EDL'El REVISION DATE-
HP-0DCM Page 1 of 23
- A eM1 TROLLED NORTH ANNA POWER STATION '
-RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATION'S SECTION 13 .I A1211987
- i. ve.sa.t.f THE w60T REV:CION Sample Location Sample Location I.D. Number (s) M I.D. Number (s) Page Envir. Sta. 01 2a Sector TLDs NE-5/37 2a Envir. Sta. 01A 2a Sector TLDs NE-6/38 6 Envir. Sta. 02 3 Sector TLDs ENE-7/39 2a Envir. Sta. 03 4 Sector TLDs ENE-8/40 6 Envir. Sta. 04 5 Sector TLDs E-9/41 2a/b
-Envir. Sta. 05~ 5 Sector TLDs E-10/42 12 Envir. Sta OSA 6 Sector TLDs ESE-11/43 2a/b Envir. Sta. 06 7 Sector TLDs ESE-12/44 7 l Envir. Sta. 07 8 Sector TLDs SE-13/45 2a Envir. Sta. 08 9 Sector TLDs SE-14/46 7 Envir. Sta. 09 10 ' Sector TLDs SSE-15/47 14 Envir. Sta. 11 7 Sector TLDs SSE-16/48 9- 6*
Envir. Sta. 12 11 Sector TLDs S-17/49 2a/b Envir. Sta. 13 3 Sector TLDs S-18/50 14 Envir. Sta. 14 6 Sector TLDs SSW-19/51 2a/b
-Envir. Sta. 15 12 Sector TLDs SSW-20/52 3 l Envir. Sta. 16 11 Sector TLDs SW-21/53 2a/b I
Envir. Sta. 21 13 Sector TLDs SW-22/54 9 Envir. Sta. 22 13 Sector TLDs WSW-23/55 2a/b Envir. Sta. 23 14 Sector TLDs WSW-24/56 13 Envir. Sta. 24 8 Sector TLDs W-25/57 2a/b Sector TLDs N-1/33 2a Sector TLDs W-26/58 13 Sector TLDs N-2/34 6 Sector TLDs WNW-27/59 13 l- Sector TLDs NNE-3/35 2a Sector TLDs WNW-28/60 13 l Sector TLDs NNE-4/36 5 Sector TLDs NW-29/61 2a/b l
Sample Location I.D. Number (s) Page Sector TLDs NW-30/62 10 I Sector TLDs NNW-31/63 2a/b Sector TLDs NNW-32/64' 10 Qtr. Control TLDs C-1/2 8 Qtr. Control TLDs C-3/4 8 Qtr. Control TLDs C-5/6 4 Qtr. Control TLDs C-7/8 4 Page Legend for the North Anna Power Station l Environmental Monitoring Stations overview Maps 15 Figure 1 overview Map 16 Figure 2 Overview Map 17 Figure 3 Overview Map 18 Table 1 Radiological Sampling Stations Distance and Direction from Unit No. 1. 19 - 23
HP-0DC3-13 Page 2a of 23 W,
i l ZAKE ANNA INNE-3/351 3 9 l
i j ,31/6
,1 p
,29 ENE-5/37]
l CON "B" _ ENE-7/39l g,9G - 1 L.
pCY
" NAPS" O
g_
BIDG.
! QSE-11/43l l W-25/57l ggggyyoyg \ W
~ IS-17/49]
l ENVIR. LAB j l lo1Al (SW-21/S3l SE-13/45 lWSW-23/S5l lSSW-19/51L \'h i
~
COOLING LAGOON N1
.,vir. Sta. 01 has an air sampler mounted to the " NAPS" Waste Treatment Facility roof at the end of " NAPS" parking lot "B" along with Qtr. and Annual TLDs and Sector TLDs NE-5/37.
- nvir. Sta. 01A has a rain gauge / collector mounted to the Va. Pwr. Biology Lab roof and is the wall water sample location for " NAPS", along with the Sector TLDs SE-13/45 on the Va. Pwr.
Biology Lab entrance gate.
'ector TLDs N-1/33 are located on the stairwell structure of the Bearing Cooling Tower approximately 150 feet from " NAPS" security building.
ector TLDs NNE-3/35 are located at the end of " NAPS" parking lot "C" at the old rain gauge
' location next to Lake Anna.
ector TLDs ENE-7/39 are located on the island on the weather tower fence near " NAPS" training facility.
NP- 0DCM-13 PJ:gs 2b of 23 13ect:r TLDs E-9/41^are located on the island on the third power pole across from " NAPS" training facility towards the " NAPS" Recreation Field.
- Secter TLDs ESE-11/43 are located on the island after crossing the dike from " NAPS" parking lot *A* on the first power pole across the " NAPS" Training Facility.
Sector TLDs S-17/49 are located on entrance gate to the " NAPS" Warehouse compound about 0.35 miles from " NAPS" security building.
' Sectsr TLDs SSN-19/51 are located on fence on " NAPS" site access road about 0.70 miles from " NAPS" security building.
" NAPS" security building.
- S:ctor TLDs WSW-23/55 are located on the first 500 kv power line tower on the right hand ,
Ride upon entering the " NAPS" site access road off Route 700.
i S:ctor TLDs W-25/57 are located at the " NAPS
- radio tower about 0.15 miles from the " NAPS" vicitor's center entrance on Route 700.
- Sector TLDs NW-29/61 are located past Units 1 and 2 intake structure at the end of the road on th) transformer fence.
S:ctor TLDs NNW-31/63 are located on the fence near Units 1 and 2 intake structure.
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4
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1
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. _.m .,, . , , - . . . , _ . _ ... . _ - _ . - . . ___.
HP-0DC.M-13 Page 3 of 23
^
J.
.[Rt. 61S } _
(Rt. 614]
\
. Fil Msw 20/S2/
Spicer
- Lake
,3 (Rt. 722)
. l
%:rreli T L Rt- 68 0 $ ,
Dairy ~~
Rt*
So, Fredericks Hall s
(Rt. 6S6]
[Rt. 618) lMvir. Sta. 02 has an air sampler nounted on the power pole about 200 yards from the intersection of Route 618 and 614 on Route 618 about 100 feet from the road (North Side) along with Otr. and Annus2 TLDs, and Sector TLDi SSW-20/S2 Soil sample is obtained from the area near this location.
Mvir. Sta.13 is located on the E. Terrell Dairy, which is about 0.25 miles West on Route 618 from Fredericks Hall, road crosses railroad tracks to Dairy. Milk sample is obtained from this location.
HP-ODCM-13 Page 4 of 23 C-7/8 Louisa e4nG O'* oI (Rt. 33) ,
,Stop) 'Rt. 22/33)
M Gle Light '
l l
l JRt. '2D . k Lto Mineral, VA )
,Ott. Control TLDs C-7/8 are located on power pole behind the Glen Marye Shopping Center off Rt. 22/33 in Louisa r VA.
l C.
l (Rt . 22 (Rt. _522)
\
L
- Lpg, gf 7 }
f
, - kRt. 618 )
l,tle s
' Mineral N3 l
C-5/6l l
P
_ 1 (Rt. 22/522)
Envir. Sta. 03 has an air sampler mounted cn the power pole about 200 feet off Rt. 618 on Albemarle Street behind the house on the corner in Mineral, VA. Otr. control TLDs C-5/6 i are attached to this station. A soil sample is obtained from the area near this station.
I
- ~I (Rt. S_22) Pags 5 of 23
( Rt. _613)
(Rt. 208)
Ware's Crossroads I
(Rt. .'623]
]
(Rt. 522 )
Envir. Sta. 04 has an air sampler mounted on the power pole about 100 feet from the intersection
.of Rt. 613 and 522 along with Qtr. and Annual TLDs. A soil sample is obtained from the area ne:r this station.
i (Rt. 601)
(Rt._752)
(Rt: 208]
NNE-4/36l
( Rt. 20B) _
( Rt. 601 )
1 Envir. Sta. 05 has an air sampler mounted on the power pole about 250 East on Rt. 752 from the intersection of Rt. 208 and 752 along with Qtr. and Annual TLDs. A soil sample is obtained from the area near this station.
j S5ctor TLDs NNE-4/36 are located on the power pole at Good Hope Church at the intersection of Rt. 208 and 601.
HP-OVA-13 Page 6 of 23 CRt. 208 )
(Rt . 601]
Q ' ~ ~
l lN-2/34 l Stuz1pon Creek (Rt.2083 4 Rt. 71 3 )
(Res 689) 4 sturgeon r
Creek gabiE-6/38 h. 713} ENb8/405 14 l
a
? !
i f g (Rt. _614'
, h (Rt.'757]
1 A
(Rt, 601A
- \
E Ay N,
(Rt: 614)
I f
i Envir. Sta. 05A has an air sampler mounted on the power pole about 200 feet from the entrance of \
Sturgeon's Creek Marina off Rt. 208 along with Otr. and Annual TLDs, and Sector TLDs N-2/34, A soil sample is obtained from the area near this station.
\
Envir. Sta.14 is located about 1.7 miles Nest from the intersection of Rt. 601 and 713 near the Laks Anna Marina where a wgetation sample is obtained.
Sector TLDs NE-6/38 are located off Rt. 601 at the end of Rt. 713 on the power pole at Lake Anna Marina entrance.
l Ssctor TLDs ENE-8/40 are located on the power pole off Rt. 601 at the entrance of Rt. 689.
l
'HP-ODCM-13 Page 7 of 33 (Rt. 601) (Rt. 622]
SE-12/44p f
~~~ 4 Dt . 62 4
l IN/ i I
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G i
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LAKE ANNA q$
/ s
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- North j s*lSE-14/46 Anna V River
/ ,
I
( Rt'. 601]
l (Rt . 701) 1:nvir. Sta 06 has an air sampler mounted to the vower pole about 0.1 miles from the intersection Otr. and Annual TLDs, and Sector
? of Rt. 601 and 622 on Rt. 622 about 25 feet from the road.
TLDs ESE-12/44 are attached to the station. A soil samole is obtained from the area near this
> location.
Tnvir. Sta il is located in the North Anna River just below the North Anna Dam. Surface water
[
.and squatic sediment are obtained from this location.
,iector TLDs SE-14/46 are located at the intersection of Rt. 601 and 701 at the entrance to the i
access road to the North Anna Dam.
l
.n.
HP-0DCM-13 Page 8 of 23 (Rt. DS, ' 00 l
%. i (Rt. 601) i (Rt.r618) C- ff e L' 1
umPass
\Rt. 701) i (Rt. ~618) l Envir. Sta. 07 has an air sampler mounted on the power pole about 175 feet behind the Bumpass Post Office at the intersection of Rt. 601 and 618 along with Qtr. and Annual TLDs, and Otr.
l Control TLDs C-1/2. A soil sample is obtained from the area near this station.
?-
l' 1
t (Main Street] -
O'^"9'
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\ E Rt. 20)
. 1 ,'
\<
Q . .
IC-3/4 b. ,
( Rt. 15 ]h l Envir. Sta. 24 has an air sampler mounted to the roof of the Orange Virginia Regional Virginia l Power Office Building about 1.0 miles South from the intersection of Rt. 20 and 15 along with Otr. and Annual TLDs and Otr. control TLDs C-3/4. A soil sample is obtained from the area near this station.
s
(Rt?690]
(Rt. 652] %) HP-0DCM-13 Page 9 of 23 f f
- g S ,$
_,7 , -
9 b MSE-16/4Bl l
Y1k Creek Store (Rt. '614] Q o
b .
O Creek
.,0-1 l
(Rt. 552Y (Rt- 728)
I (Rt . 690) ,$
' c Envir. Sta. 08 is located in' the Second Cooling Lagoon (Elk Creek) near Dyke M2 where fish, surface water and aquatic sediment samples are obtained.
Sector TLDs SSE-16/48 are located on the power pole beside Elk Creek Store at the intersection of Rt. 614 and 652.
l (Rt. ,652) 1
! Rt. 685) gg 22
/54
/;
(Rt. 700} .
(Rt. 712) Rt. 700to" NAPS")
(Rt. 652)
Sector TLDs SW-22/S4 are located on the power pole about 2.5 miles from the intersection of Rt. 652 and 700 leaving " NAPS" near an abandoned House and dumpster.
I t
HP-0DCM-13 Page 10 of 23
- -- ? l
[Rt. 65S}
l Pigeon l
Run lp 4 , 620
+ 'Ja ,,
Rt. 238}
9 Lake Anna l 8t. 200 Campgrounds Brid
- Ol (Rt. 208 4 Cree k t ,,
itche _
g l hl Contrary fCreek l \
l
'nvir. Sta. 09 is located in Lake Anna near Rt. 208 Bridge where the fish, surface water, and aquatic sediment samoles are obtained. A shoreline soil sample is obtained from the shore naar Rt. 208 bridge.
Tector TLDs NW-30/62 are located on the punt pole midway between the entrance off Rt. 208 l and the Office for Lake Anna Campgrounds.
Tector TLDs NNW-32/64 are located on the power pole at the intersection of Rt. 6SS and 209 on Rt. 208.
l
HP-ODCM-13 Page il of 23 (Rt. 522]
Pamunkey Creek (Rt.,654) f *e ,
I *b O
e ,e I
I 12 i e
\
( Rt. 612)
(Rt. 522) l (Rt. 612 )
[ '
PL:
' ?nvir. Sta.12 is located about 0.5 miles East on St. 612 from the intersection of Rt. S22 and 612 ct the R.C. Goodwin Dairy Farm where a milk sample is obtained.
i (Rt. 629) (Rt. 522 to Unionville)
(\
i
)
(Rt, 651]
R 522 QRt. 649)
,g, g l Envir. Sta.16 is located near the intersection of Rt. 522 and 629 about 10.2 miles North from j the intersection of Rt. 522 and 208 where a vegetation sample is obtained.
HP- W ~13 page 12'of 23
-(Rt,60gge,6M
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r-10/421 orning Glogy Dr.)
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L A X E A N N (gg, 501) 2nvir. Sta.1S is located about 1.5 miles West from the intersection of Rt. 601 and 614, at the l end of the Rt. 614 where a vegetation sample is obtained.
l 3ector TLDs E-10/42 are located on the SCO kv power line tower at the intersection of Rt. 601 and Morning Glory Drive.
- g. , , .,, _ - . , -
--g. .,---,g--- - - ,
HP-CDCM-13 Page 13 of 23
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M np ElW-28/6
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~lNNW-27/59] s l
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ef CB l
- 5) %
g lW-26/SBl
(
' To NAPS t' l
59 1
(Rt. 700)
( Rt. 652)
- nvir. Sta. 21 has an air sampler mounted to the power pole at the end of Route 68S to the left of 1 tha bztricade about 1.50 miles from the junction of Route 6S2 and 685 along with Otr. and Annual i TLDs, and Sector TLDs WNW-27/S9. Soil and vegetation samples are obtained from the area near this location.
invir. Sta. 22 has an air sampler mounted to the power pole about 0.80 miles from " NAPS" Vistor Center, west on Route 700, at the exclusion area boundary on the right hand side. Otr. and Annual TLDs, and Sector TLDs WSW-24/S6 are attached to this station. Soil sample is obtained from the area near this location.
\ ?ector TLDs W-26/S8 are located on the power pole on Route 685 about 1.00 miles from the intersection of Route 652 and 685 on right hand side (near an abandoned trailer),
i
[iector TLDs WW-28/60 are located on the power pole at the end of private road (oresently
! H. Purcell's property) off the left side of Route 685.
1 f__ _ - _ - - - _ - - _ -
HP-ODCM-13 Page 14 of 23
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. .. 4-g 4
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COOLING LAGOON N 1 l l
\
l' SSE-1W47 i l " ASPEN l
HILLS"
.n , IRt. 690) b u
lS-18/50l Rt. 614 (Rt. 652)
Envir. Sta. 23 has an air sampler mounted on the power pole about 25 feet from the shoreline on Lot # 34 on Carr Circle in the " Aspen Hills" subdivision along with Otr. and Annual TLDs, and Sector TLDs SSE-1S/47. Soil vegetation samples are obtained from the area near this location.
Ssctor TLDs S-18/50 are located on the power pole about 0.25 miles from intersection of Route 614 and 652 on Rt. 614.
HP-ODCM-13 Pagn 15 of 23 c- LEGEND FOR THE NORTH ANNA POWER STATION
.4 -
-ENVIRONMENTAL MONITORING STATIONS OVERVIEW MAPS-(FIGURES 1, 2, 3)
MAP ENVIRONMENTAL STATION MAP ENVIRONMENTAL STATION DESIGNATION IDENTIFICATION DESIGNATION' IDENTIFICATION 1 N-1/33 23' WSW-23/55 2 N-2/34,05A
- 24 WSW-24/56,22
- 3. NNE-3/35 25 W-25/57 4 NNE-4/36 26 W-26/58 5 NE-5/37,01 27 WNW-27/59,21 6 NE-6/38,14 28 WNW-28/60 7 ENE-7/39 29 NW-29/61_ -
8 ENE-8/40 30 NW-30/62,09 9 E-9/41 31 NNW-31/63
. 10 E-10/42 32 NNW-32/64 11 ESE-11/43 33 03, C-586 12 ~- ESE-12/44,06- 34 04 ,
13 SE-13/45,01A 35 05 14 SE-14/46 36 07, C-l&2 15 SSE-15/47,23 37 08
[
16 SSE-16/48 38 11 i
17 -
S-17/49 39 12 18 S-18/50 40 13 19 SSW-19/51 41 15 20 SSW-20/52,02 42 16 21 SW-21/53 43 24, C-384 22 SW-22/54 44 C-7&8 r
C Map Designation # L 1 Road Numbers
HP-0CCM-13 Paga 16 of 23
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HP-0DCM-13 Page 18 of 23 FIGURE 3 Ai ' NORTH ' ANNA POWER ' STATION ENVIRONMENTAL ' MONITORING STATICNS OVERVIEW MAP l
14 44 )
I (*c- 0*)
z ,,, ,,3 Glen Marge Shopping Center 1 (Rt. 22/33) ,
[
Rtf22 3 to Mineral, VA) Louisa, VA n.
t':
eb h Orangeo VA (Re.20)
B q>
(Rt.'1S]
TABLE 1 RADT01AGICAL SANPLING STATIONS DISTANCE APO DIRECTION FROM UNIT NO.1 Sample Station Diatance Collectton Media Location No. (elles) Direction Degrees Frequency Remarks
.I I NAPS Sewage 01 0.20 NE 42 Quarterly On-Site ,'
Fnvfronmental j Thermolumincscent Treatment Plant & Annually Domimetry (T1.D) Fredericks llall 07 5.30 SSW 275 Quarterly
& Annually Mineral, VA 01 7.10 WSW 743 Quarterly.
& Annually
- Wares Crossroads 04 5.10 WNW 787 Quarterly
& Annually Route 752 05 4.20 NNE 20 Quarterly
& Annually Sturgeon's Creek OSA 3.20 NME 11 Quarterly I
a Marina & Annually Levy, VA 06 4.70 ESE 115 Quarterly
& Annually Bumpass, VA 07 7.30 SSE 167 Quarterly
& Annually Enit of Route 685 ?! 1.00 WNW 301 Quarterly Exclusion
& Annually
' Boundary Route 700 27 1.00 WSW 242 Quarterly Exclusion-
& Annually Boundary
" Aspen Ill11s" 23 0.93 SSE 158 Quarterly Fxclusion
& Annually Boundary Orange, VA 74 22.00 NW 325 Quarterly Control
& Annually Bearing Cooling Town N-1/33 0.06 N 10 Quarterly on-Site I k' Sturgeon's Creek N-2/34 3.20 N 11 Quarterly l Marina $$
Parking Lot "C" NNE-1/35 0.25 NNE 37 Quarterly On-Site N -
Good Ilope Church NNE-4/36 4.96 NME 25 Quarterly a Parking tot "B" NE-5/37 0.20 NE 42 Quarterly On-Site kU 1.49 34 Quarterly N Lake Anna Marina NE-6/38 NE Weather Town Fence ENE-7/39 0.36 ENE 74 Quarterly On-Site Route 6H9 ENE-R/40 2.43 ENE 65 @arterly Quart erly Near Training. IM/41 0.10 E 91 (m-9f te FarfIIty 5%...
l
TABLE 1 (cont.)
RADIOLOGICAL SAlfLING STATIONS DISTANCE AND DIRECTION FROM UNIT NO. 1 Sample Station Distance Collection 1.ocat ton No. (miles) Direction Degrees Frequency Remarks Media Fnvironmental "Mnrning Clory E-10/42 2.85 E 93 Quarterly.
Therw ltant nencent 11111" Ibst met ry (TI.!O Taland Dike ESE-11/43 0.12 ESE 103 Quarterly on-Sitef,
^'
Route 627 ESE-12/44 4.75 ESE 115 Quarterly VEPO) Stology SE-13/45 0.75 SE 13R Quarterly on-Site 12 6 Route 701 SE-14/46 5.88 SE 137 Quarterly (Das Entrance)
" Aspen II111s" SSE-15/47 0.93 SSE 158 Quarterly Exclusion Boundary Elk Creek SSE-16/48 2.33 SSE 165 Quarterly Warehouse Compound S-17/49 0.22 S 173 Quarterly on-Site Cate Elk Creek Church S-18/50 1.55 S 178 Quarterly NAPS Access Road SSW-19/51 0.36 SSW 197 Quarterly on-Site Route 618 SSW-70/52 5.30 SSW 205 Quarterly NAPS Accenn Road SW-21/53 0.30 SW 218 Quarterly on-Site Route 700 SW-22/54 4.36 SW 232 Quarterly 500 KV Tower WSW-23/55 0.40 WSW 237 Quarterly On-Site Rmste 700 WSW-24/56 1.00 WSW 242 Quarterly Exclusion Boundary NAPS Radio Tower W-25/57 0.31 W 279 Quarterly on-Site Route 685 W-26/58 1.55 W 274 Quarterly End c f Route 685 WNW-27/59 1.00 WNW 301 Quarterly Exclusion ,
Roundary H. Purcell's WNW-28/60 1.52 WNW 303 Quarterly Private Road End of 81/87 NW-29/61 0.15 MW 321 Quarterly on-Site intake I.ake Anna NW-30/62 2.54 NW 319 Quarterly .
Campground gy NNW 34 9 Quarterly on-Site QO s1/87 Intake NNW-31/63 0.07 Route 708 NNW-32/64 3.43 NNW 344 Quarterly Nh Ittmapagn Post C-1/2 7.30 SSE 1 #.7 Quarterly crint rol Office %W 22.00 375 Quarterly Control 4 Orange, VA C-3/4 NW .
Minern!, VA C-5 /f. 7.10 WSW 743 Quarterly Onntrn!
c<.nt rol 1.outsa VA C-1/R 11.54 %- 757 9 arterly
TABLE 1 (cont.)
RADIOIACICAL SAMPLING STATIONS -
DISTANCE AND DIRECTION F1t0M UNIT NO.1 Sample Station Distance Collection Media location No. (elles) Direction Degrees Frequency Remarks Airborne Particialat e NAPS Sewage 01 0.20 NE 42 Weekly On-Sitt i and Radiolodine Treatment Plant Fredericks Hall 07 5.30 SSW 725- Weekly Mineral, VA 03 7.10 WSW 743 Weekly Wares Crossroads 04 5.10 WNW 787 Weekly Route 752 05 4.20 NNE 20 Weekly Sturgeon's Creek 05A 3.20 NNE 11 Weekly Marina Levy, VA 06 4.70 ESE 115 Weekly Bumpass, VA 07 7.30 SSE 167 Weekly rnd of Route 6A% 71 1.00 WNW 301 Weekly Faclusion Roundary Route 700 22 1.00 WSW 242 Weekly Exclusion Boundarv.
" Aspen Hills" 23 0.93 SSE 158 Weekly Exclusion Boundary Orange, VA 24 22.00 NW 325 Weekly Control Surface Water Waste Heat 08 1.10 SSE 148 Monthly.
Treatment F.acility (Discharge Lagoon)
Lake Anna (tipatream) 09 2.70- NW 320 . Monthly Control River Water North Anna River 11 5.80 SSE 128 Quarterly (downntream)
Cround Water VEPO) Biology Lab 01A 0.75 SE 138 Quarterly (well water) ne 9 e k
oO Aquittic Sediment Waste liest 08 1.10 SSE 148 Semi-Annually uh Treatment Fac!11ty I (Discharge Lagoon) kU, Lake Anna (tipstream) 09 2.70 NW 320 Semi-Annually Control 'N.
North Anna River 11 5.80 SSE 128 Semi-Annually (d.wnsaream) ily
TABt.E 1 (cont.)
RADIOLOGICAL EAMPLINC STATIONS DISTANCE AND DIRECTION FROM UNIT NO.1 Sample Station Distance Collection Media Location No. (miles) Direction Degrees Fequency Remarks Shoreltne Soll I.ake Anna (tipstream) 09 2.70 MW 370 Semi-Annually .
Soft NAPS. Sewage 01 0.20 NE 42 Once per 3 yrs On-Site Treatment Plant Fredericka Hall 02 5.30 SSW 225 Once per 3 yrs Mineral, VA 03 7.10 WSW 243 Once per 3 yrs Wares Crossroads 04 5.10 WNW 287 Once per 3 yrs Route 757 05 4.20 NME 20 Once per 3 yrti-SturReon's Creek 05A 3.20 NME 11 Once per 3 yrs Marina Levy, VA 06 4.70 ESE 115 Once per 3 yrs ilumpa s s , VA 07 7.30 SSE- 167 Once per 3 yrs End of Route 685 21 1.00 WNW 301 Once per 3 yrs Exclusion floundary Route 700 72 1.00 WSW 742 Once per .3 yrs Excluston Rounderv
" Aspen liills" 23 0.93 SSE 158 Once per 3 yrs Exclusion-Roundary Grange, VA 74 22.00 MW 325 Once per 3 yrs Control Milk. Ilolladay Dairy 17 R.30 MW 310 Monthly (R.C. Goodwin)
Terre 11's Dairy 11 5.60 SSW 205 Monthly.
(Frederteks Hall)
Fi rls Waste IIcat OR 1.10 SSE 148 Quarterly.
Treatment Factllly (Di sclin rge I.agoon) 1.ake Anna (upstream) 09 7.20 MW 176 Quarterly Centrol' yg N '
Fomt I s educ t s Route 711 14 varies NME 43 Mnnthly if available (Itr. rut l eaf or at harvest 4 v..pe r a t l en i Route f.14 1 *, varies ESE 133 'Nonthly If available o or at harvent g 4
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' TABLE 1 (cont.)'
l'ADIOISCICAI. SAMPl.1NG STATIONS DISTANCE AND DIRECTION OF (fMIT No. 1 -
Station Distance Collection sampic Remarks No. (miles) Direction Degrees Frequency-Media Incatinn NW 314 Monthly if available coerAe&'
Fond Products Route 629/57f 16 varies or at harvest f (Broa.1 traf . -' . '
Route 685 71 varies WNW 301 Monthly if avaltable veget at l on) or at harvest SSE 15R Monthly if available
" Aspen Hills" Area 73 varies or at harvest 4
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._I Page 7 ATTACHMENT 4 .
(7/86 :12/86) .
-REVISIONS-TO PROCESS CONTROL PROGRAM (PCP) S e
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As require'd by Technical Specification 6.14, revisions to totihePCPforthetimeperiodcoveredbythisreportare;synopsized-below. Supporting documentation and affected pages of the.PCP are 1
attached.
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12-31-86: The PCP was revised in its entirety to ensure accuracy and concurrency with present radwaste processing methodologies.
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REQUEST TO CHANGE PRDCEDURE ADM-5.4 1 i
NORTH ANNA POUER STATION Attechuant 3 VIRGINIA POWER Page 1 of 1 09-04-86
_ SUPERVISOR RESPONSIBLE FOR FOLLOWING PROCEDURE:
ABNORMAL CURVE BOOK OPERATING WELDING ADMINISTRATIVE EMERGENCY PE1 iodic TEST ANNUNCIATOR IN-SERVICE INSPECTION cffF5d.TE'PHYSICE>
CALIBRATION MAINTENANCE EPECIALiTEST -
CHEMISTRY NON-DESTRUCTIVE TEST STAEF UP TEST PROCEDURE NO: 2 UNIT NO: 3 RENSIONDAT1,: 4 PCP NA ~ -
n > r- w TITLE: 5 CHANGES REQUESTED: (GIVE STEP NUM!!ER, EINCT SUGGESTED WORDING AND LIST REFERENCES, STAPLE 6 OPY OF PROCEDURE WITH SUGGESTED CHANGES MARKED TO THIS FORM.) '
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REFERENCES:
ps udfo.#-u-w REASON F0 CHAN S: 7
/} A _? dd'0W4ALA Y A11ALLnos b
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. 8 DATE: 9 CHANGEREQUESTEDBY*$. h 0 l$~lb~$$
ACTION TAKEN: [ 10 A
DOES THIS CHANGE IHE OfERATIEG METHODS AS DESCRIBED IU THE UFSAR? YES /
DOES THIS CHANGE INVOLVE A CEANGE TO THE TECH. SPECS? TES 0 DOES THIS CHANGE INVOLVE A POSSIBLE UNREVIEWED SAFETY QUESTION? YES .
[
IF ALL "NO", NO " SAFETY ANALYSIS" IS REQUIRED. IF ANY "YES", A " SAFETY ANALYSIS" IS sg IRED.
(10CFR50.59) APPROVED COPY TO BE PROVIDED TO LICENSING COORD. FOR INCLUSION IN ANNUAL REPORT.
RECOMMENDED ACTIO 11 APPRO DISAPPROVED DOES THIS PROCED ,EATE A QA DOCUMENT? YE " UO BY: (COGNIZANT SUPERVI 12 DATE: ,
13 REVIEWED BY QUALITY A$SURANCE: (( CRANGES MADE: YES 14 BY: , 15 DATE 16 17 VIEWED BY STAT 10 % EAR SAFETY AND 0.PEAATING' COMMITTEE:
h ROVFN d l/ rl DISAPP20VED APPROVED AS MODIFIED BY COMMIT
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CHAIRMAN SIGNATURE: 18 DAT ,
19 NEW PROCEDURE REVISION DAffE: '
20 ACTION COMPLETED BY: 21 DAT3: 22
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Process Control Program Page 2 of 27 p,'
D 11-27 85
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NORTH ANNA STATION PROCESS CONTROL PROGRAM TABLE OF CONTENTS PAGE 1.0 -SCOPE /.
2.0 SYSTEM DESCRIPTION 3.0 CHARACTERISTICS OF WASTE FEED i
4.0 SYSTEM OPERATION ,
5.0 COLLECTION AND ANALYSIS OF SAMPLES l' 6.0 STATION RECORDS 7.0 INTERFACE BETWEEN STATION AND CONTRACTOR SERVICES l
APPENDIX A - SAMPLE FORMS l
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Process Control Program Page 3 of 27
._ . 11-27-85 1.0 SCOPE 1.1 Purpose The purpose of the North Anna 4lmenese-Power Station Process Control Program is to ensure that:
- a. Sofifiedliquidwastes,devatoredresins,andaqueousfiltermedia are packaged in the proper containery b ased on their activity level;
- b. Dewatered resins and aqueous filter media are packaged with no detectable free standing liquid prior to transportation;
- c. Liquid wastes are solidified or, in the case of contaminated oil, any be aborbed in an approved absorbent and contain no detectable -
~
I
- i. free standing liquid; and l
- d. Resultant so ified/ absorbed wastes are in compliance with the l provisions of 10 CFR Part 61.
1.2 Applicability This Process Control Program (PCP) shall be implemented by all personnel who operate dewatering equipment, operate solidification l
equipment,processwasteoil, package)(spentfiltercartridges, collect and process samples used to verify conditions required by the Program, and prepare documentation for shipping of radioactive waste.
2.0 SYSTEM DESCRIPTION 2.1 Dewaterina Systes
! T&
l Poue sources of spent resins for dewatering and disposal exist at the feuaA North Anna Station. The first is the Spent Resin Holdup Tank which collects for decay and disposal spent resins for the primary coolant purification system. These resins are dewatered in disposable high integrity containers. The second is the M Level Liquid tJaste l
_ .- . _ _ _ _ ~ , _ _ _ _ _ _ _ _ , _ . . - _ . _ - _ _ = _ _ _ _ _ . - . __- -
Process Control Program Page 4 of 27 11-27 ,
-2.0 SYSTEM DESCRIPTION (cont.)
Treatment System. Shur syssau Utilizes resins vnten are ..s i..J -
en-afen in ore-loaded di r- 'l: ce;;;i;;;;. "ic; :h; :::'- :h:::
svo .. .. _:: '--da ; - h---* A a-
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T :; r- $1 6. . These resins are loaded into pressure vessels i already on-site. When chemically exhausted, the resins are sluiced to an applicable container for devatoring. The L source of spent resin is from the condensate polishing domineralizer system. This is a I ~
l powdersd resin system and the contaminated resins are transfered to a A.
sopprate holdup tank for later transfer to a dewatering container.The following sections provide a description for each dewatering system.
2.1.1 Dewatering System For Resins In The Spent Resin Holdup Tank The dewatering system for spent resins in the Spent Resin Holdup i Tank consists of the Spent Resin Holdup Tank, the Radwaste Metering Pump (1-LW-P-18), the Spent Resin Recirculation Pump (1-LW-P-21), the dewatering container, the shipping cask, the devatoring pump, the-9% ese64ar, interconnecting hose and piping, valves, instrumentation and controls, and sample caps.
2.1.1.a Spent Resin Holdup Tank The Spent Resin Holdup Tank is a 1600 gallon atmospheric tank. It col,lects spent resins from the h
primary coolant purifica*een system to provide for radioactive decay and temporary storage.
~
Page 5 of 27
__: 11-27-85 2.1.1.b -Spent Resin Transfer Pump (1-LW-P-18)
The Radweste Metering Pump is a 12 spa,' progressive cavity pump. It takes suction from the discharge of 1-LW-P-21 (Bead Resin), 1-LW-P-25.(Powered Resin) or liquid waste evaporator bottoms, (NOT USED). 1-LW-P-18 discharges-through a flexible hose to the dewatering container.
2.1.1.c Spent Resin Recirculation Pump (1-LW-P-21)
The Spent Resin Recirculation Pump is a 70 spa, centrifugal pump. It takes suction from the bottom of [
the Spent Resin Holdup Tank and discharges to the top l
of the Spent Resin Holdup Tank.
2.1.1.d Dewaterins Container The devatoring container can be any certified high intearity container designed for use in dewatering and approved for transportation and disposal of devatared l-spent resins.
2.1.1.e Shippina Cask The shipping cask can be any licensed shipping cask, designed for use with the high integrity container utilized, which provides adequate radia eershielding A
and package integrity for transportation of devatered spent resins.
l 2.1.1.f Dewatering Pump The dewatering pump is an air driven,1-1/2",
" Sandpiper" pump or equivalent.
l
. I i
l Process Control Program Page 6 of 27 l 11-27-85 2.:.;.. T r;_i;es, Th nitor is a re te display el 1sion uti z ,
(~ i w en requLred, to nito the con iner 111ag l cperation. This nitor rovide informat on to the a perator cn cont iner resin water level resin W1urry con se cy.
2.1.1.% b- Interconnectina Hose and Piping l l
The resin transfer line used to sluice resin from the primary coolant purification domineralizers to the l
l Spent Resin Holdup Tank, as well as connections from i
the tank to the Spent Resin Transfer Pump, Spent Resin Recirculation Pump, and plant ventilation systes_are permanently installed stainless steel piping. The connection from the Spent Resin Transfer Pump to the dewatering container, the connection from the dewatering container to the dewatering pump.-and the connection from the dewatering pump back to the Spent Resin Holdup Tank are all flexible rubber hose.
2.1.1 t Valves i
Valves are installed in the system, as required, to select flow paths and isolate portions of the
, dewatering system as may be necessajy.
L 2.1.1 4. Instrumentation and Controls ControlsareprovidedtoremotelystartandstoppumpsX&we[
remotely open and close valvese u s ;ely avul 6 the er- ri- r fill = head 1..1 ;;l lofluenc fiv., .od remotely-indicata7herecurriner fill and ui.derge
. 44.au.
t Process Control Program Page 7 of 27 11-27-85
~
- r
-k 2.1.1.)r Sample Taps
'As an example, a sample tap is provided on the I
~
e discharge side of the Spent Resin' Recirculation Pump.
Q 2.1.1.4*-Spent Powdered Resin Recirculation Pump 1-LW-P-25 The spent powdered resin recirculation pump is a l
progressive cavity pump, which takes suction.from the bottom of the spent powdered resin tank and discharges to the top of the tank and provides positive pressure to the suction of 1-LW-P-18.
i 2.1.2 Dewatering System for Resins Received In Disposable Containers
~
The High Level Liquid Waste (HLLW) System contains from two to seven disposable filter /demineralizer vessels. The devatering i
system for' the HLLW disposable filter /demineralizar vessels consists of the disposable vessel and the dewatering pump.
2.1.2.s Disposable Vessel The disposable filter /demineraliser vessel can be any container, designed for use as a disposable IV filter /deg raliser vessel, with provisions for dewatering.
2.1.2.b Dewatering Pump The dewatering pump is an air driven, 1-1/2",
" Sandpiper" pump or equivalent.
2.1.3 Devatoring Sys a for Resins Loaded Into Pressure Vessels On-Site i
si The High Level Liquid Waste (RLLW) System may contain sluteable filter /demineralizar vessels. The dewatering system for HLLW ti 5
. sluteable filter /demineralizer vessels consges of sluciable pressure vessels, a dewatering pump, applicable container and heat enhanced dewatering system.
Proc 2ss. Control Program Page 8 of 27 11-27-85
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2.1.3.a Slukable Pressure Vessel The sluciable filter /demineralizer vessel can be any container designed for use as a sluciable filter /demineralizer vessel.
2.1.3.b The dewatering pump is an air driven, 1-1/2",
" Sandpiper" pump or equivalent.
.2.1.3.c The applicable container can be any container designed for use in dowatering and approved for. transportation l
and disposal of dewater resins.
2.1.3.d The heat enhanced devatoring system can be any. system j designed for use in dewatering resin materials using heated air circulated through the media to prepare liners for transportation and disposal. '
2.1.4 Dewatering System For Filter Cartridges The High Level Liquid Waste Filter utilizes disposable cartridge l
filters. The cartridges are air dried prior to disposal; I
therefore, no dewatering system or equipment is needed nor exists for dewatering spent filter cartridges.
2.2 Solidification System There is no permanently installed, operating so ification system on-site. Intheeventcontractorservicesareutilizedforsopification, the contractor will be required to provide to Virginia Power a complete description of the solidification system to be used. The system description provided will be subject to Virginia Power review and acceptance and once accepted, will be incorporated by reference into
! this Process Control Program. Thesopificationsystemwillnotbe operable until the system description is accepted by Virginia Power.
l
Process Control Program Page 9 of 27
._. 11-27-85
~_ z 2.3 . Absorption System t
l The oil absorption equipment consists of a batch tank de;;:::'--::17 2IS
- 11. ;), a recirculation pump, a mixing pan, and a mixing hoe.
2.3.1 The batch tank is a 50 cubic foot, carbon steel, cask liner l= ,
modified to contain a lower drain / recirculation line, and is i:
nounted on four two-foot legs.
t
- 2.3.2 The recirculation pump is an air driven,'l-1/2", " Sandpiper" pump h .or equivalent.
2.3.3 The mixing pan is a 4 foot by 3 foot by 1-1/2 foot stainless l
steel container.
(2.3.4 The mixing hoe is a standard garden hoe.
3.0 CHARACTERISTICS OF WASTE FEEDS 3.1 Dewatered'Resine ,
as Resins to be dewatered are either slu6eed to the disposable dewatering s
high integrity container or are contained in a disposable container.
Low activity resin may be shipped in a carbon steel liner.-
3.2 Filter Elements Spent filter, e enents are removed from the filter vessel housing and are
. processed as individual units A a4 J.kQao .
C 3.3 Liquids For Solidictation "
l A 4l l PresentlyliquidwastesarenotfedtoasolidgLationsystem. In the event contractor services are utilized for sol lication, the waste stream characterization will be provided by either:
- a. Virginia Power personnel collecting and analyzing samples in accordance with station approved procedures; or
- b. The contractor collecting and analyzing samples in accordance with station approved procedures.
Process Control Program Page 10 of 27 11-27-85
-The procedures will consider the solidification process utilized and fwill analyse for parameters or constituents which may affect the solidification' process. Sample collection and analysis procedures will.
be subject to Virginia Power review and acceptance and once accepted.
wil1 be incorporated by reference into the Process Control Program. The so dification system will not be operable until the sample collection and analysis procedures are accepted by Virginia Power.
3.4 Contaminated Waste 011: Solid'tication/ Absorption n
Radioactively contaminated waste oil is collected and stored until such time as a volume, sufficient to warrant a shipment to a disposal .
5 facility, is to be processed. Approved Health Physics procedure (s) will be used for the absorption process; Virginia Power approved vendor procedures will be used for solidification, as delineated in step 3.3.
4.0 SYSTEM OPERATION 4.1 Dewatering 4.1.1 Dewaterina Resins From the Spent Resin Holdup Tank Spent resins from the primary loop cleanup system are sluiced to the Spent Resin Holdup Tank for decay and storage. The spent resin storage time in the tank is maximized to the extent possible to allow for maximum radioactivity decay. -Ouri g th:
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- 11-a ana resia packio.c Prior to resin transfer to the dewatering container, the tank contents will be mixed. A sample for isotopic analysis may be taken from the sample cap on the
! recirculation line. Sample requirements are defined in Section 5.0. If a sample is taken from the recirculation line, a portion L - - - . _ . - -- .___ _ ,_ __. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . -
s Process Control Program Page 11 of 27
- _ s 11-27-85
-of.the recirculating slurry is drawn into a sample container, the sample container contents decanted, and an isotopic analysis performed in accordance with approved procedures in the station
(- Health Physics Procedures Manual Section 3.
t Following mixing and sampling (if performed), the radwaste metering pump is used to transfer resin slurry to the disposable i
dewatering container. The Spent Resin Recirculation Pump will be operating during resin transfer. The operator fills the container with slurry until the container has been filled. 4h4e -
- 1. ...;fi.J L, ti: r - *= Tv - fter. When the container is i filled, the transfer of slurry to the container is stopped. 4he.
=~ r:: .;;;;; i: tirr ;;_.;;J by ;;he J...i.uos y.-y. Thi. ..u c i; :;e ef.ssed te;t t; ti: "--* Rada T.;10.y I.ui. After the excess water is removed, slurry is again transferred to the container until the container is filled with the resis and water mixture. The container is again drained using the dewatering
! pump. This process continues until the container is filled with l
resin (i.e., sljcing water removed). The resin-filled container l
is dewatered in accordance with one of the following station l
l approved devatoring procedures:
i f
i i
t
- Process Control Program F Page 12 of 27 j ,
11-27-85 t
I- Virginia Power Procedure 1-OP-20.2 for devatoring
! disposable containers.
l Virginia Power Procedure 1-OP-20.6 " Dewatering Procedure for CNSI 14-195 or Sas11er Liners Containing l
Bead Resins".
Each procedure specifies a series of minimum periods for dewatering pump operation and shutdown and provides a minimum time period for sample collection. These procedurcs are not included as they are considered proprietary. The procedures have been tested for compliance in dewatering to less than the specified percentage as required by Chem-Nuclear Systems, Inc., ;
- State of South Carolina Radweste Material License No. 97.
The approved procedures must be strictly followed and the documentation required by the above procedures must be complaced.
4.1.2 Dewaterina Resins In Disposable Filter /Demineralizer Vessels Spent resins from the High Level Liquid Waste System are contained in disposable filter /demineraliser vessels. The
} vessels any be removed from service when either calculations indicate the resin contain close to I uCi/gm radioactivity or the resins have insufficient ion exchange capacity remaining for adequate liquid processing. Once removed from service, the
, vessels are drained and dewatered in accordance with one of the following procedures. The procedure selected will be determined by the container to be dewatered.
Process Contro1' Program Page 13 of 27
-. 11-27-85 Virginia Power Procedure 1-OP-20.2 for devatoring disposable containers.
Virginia Power Procedure 1-OP-20.3, " Dewatering Procedure for the 24-inch Dismeter Pressure Domineraliser Vessel Containing Activated Carbon, 0.5% Free-Standing Water."
Virginia Power Procedure 1-OP-20.4, " atering Procedure for the 24-inch Diameter Pressure Domineraliser Vessel Containing Ion Exchange Resins,
- O.5% FSW."
i Each procedure specifies a series of minimum periods for devatoring pump operation and shutdown and provides a minimum l time period for sample collection. These procedures have been l
! tested for compliance in dewatering to less than the specified l
percentage as required by Chem-Nuclear Systems, Inc., State of South Carolina Radweste Material License No. 97 The above procedure (s) must be strictly followed and the documentation required by the above procedures must be completed.
1 1
l l
L -. .- ~ , , _ _ - - _ _ . . . _ _ . _ _ , - , _ _ _ . _ _ _ . _ . _ _ __ , , _ _ , _ _ _ , _ _ . _
. . =_ .- .
+ Page.l.4 of 27 11-27-85 4.1.3 Dewatering Ion Exchange Media Loaded'Into Pressure' Vessels
. --On-Site t
Spent ion exchange media from the High Level Liquid Waste System may be removed from service when they are chemically depleted or become fouled. Once they are removed frod service, the media is transfered to an applicable liner for dewatering for j- transportation and burial. The liner shall be dewatered in l accordance with 1-OP-20.6, which specifies a series of minimum periods for dewatering pump operation and shut down and provides a miniaua time period for sample collection. The procedure is tested for compliance in dewatering to less than the specified l percentage as required by Chem-Nuclear Systems, Inc., State of j South Carolina Radweste Material license No. 97.
4.1.4 Dewatering Spent Powdered Resin From Spent Powdered Resin Holdup Tank Spent powdered resins from the condensate polishing domineralizer system are transfered to the spent powdered resin holdup tank for storage. The spent powdered resin recirculation pump will recirculate the tank providing suction pressure to 1-LW-P-18 which pumps the resin into a dewatering container. As the dewatering container is filled, a dewatering pump removes excess water. The resin filled container is dewatered in accordance with the station approved dewatering procedure 1-OP-20.7 for mo dewatering CNSI 14-195 or smaller liners containing Ecodex, Powdex resin, or diatomaceous earth. This procedure specifies a series of minimum periods for dewatering pump operation and shutdown and provides a minimus time period for sample collection. The procedure has been casted for compliance in
I Process Control Program Page 15 of 27 11-27-85 dewatering to less than the specified percentage as required by Chen-Nuclear System, Inc., State of South Carolina Radwaste material License #97.
The approved procedure must be strictly followed and the documentation required by the above' procedure must be completed.
4.2 Spent Filter Cartridge Disposal When used High Level Liquid Waste cartridge- filters are to be removed from service, the vessels drained, and the elements removed. [ Note: The wound-type elements used do not contain void spaces which can trap liquid in pockets.] In accordance with Health Physics Department -
5 Procedures, a sample of the element will be removed for radioassay following removal of the element from the filter vessel. The element will be allowed to air dry. T'e ='--- t -ill i. c... J...J ;e :;;;;ir.
-- .k-- e,5! f.- -ar. Avn. warar uh.. 4. --- ;. pi:--d : - ,1..n A 7-l l pl :;ic _t;;; f:: : _lui. a of f err her:: rrf. rhrr : : red. *k-71 2:*i-
- i;. o. f.:: 1 * ,r id .
Er r -e 143"<a e---;,, ... ;h: - 4,. the filter a1--__. .111 c ^a
- 4 n ge de he piec.J en : ' y aface of 9 1 ==ede f;r f..a h;; ines;;::t- "nr4t,
-'-- t'e el-- t ir : r:;;J I.v. 6', y12:ti- ec f--- l'q"id r---4n=_nn
- k- plestie. Drying of the elements may be assisted by placing the elements in a flow of warm, dry air or any other means which meets station RP procedures for control of airborne particulates. However.
-;L. ivu. L..- dryness verification shall occur with no drying air flow present. Contractors may use mechanical filters for this service that would be controlled by contractor procedures.
Process Control Program Page 16 of 27 11-27-85 J
4.3 Solidification There is no permanently installed, operating soldification system on site. In the event contractor services are utilized for solidification, the contractor will be required to provide to Virginia Power system operating procedures. The system operating procedures aust define the process control parameters which assure the proper proportioning and mixing of waste and solidification agents. The operating procedures shall also specify minimum data logging requirements to document system operation within the specified ranges.
The system operating procedures will be subject to Virginia Power ;
a review and acceptance and once accepted, will be incorporated by reference into this Process Control Program. The solidification system system will not be operable until the system operating procedures are f~ accepted by Virginia Power.
l l Presently accepted procedures for use are:
X'AX Chem-Nuclear Systems Inc. procedure SD-OP-eff, " Operating XX Procedure for CNSI Portable Cement /011 So ification Unit No. f )' Q C :lGLi-C-Lf;~
M " ..l.e. ",je;; ;, IuG~jir6cedure SD-OP-026. " Process Cuntsvi.
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l
."....__. f;r C;_ us/Gil vlidifica non; ana ~
Chem-Nuclear Systems, Inc. procedure SD-OP-003, " Process Control Program for CNSI Cement So ification Units."
4.4 Absorption l Radioactively contaminated waste oil will be processed in accordance I
with Health Physics Department procedure (s). The process parameters, acceptance criteria, and packaging requirements are specified in the l
applicable procedure (s).
Process Control Program Page 17 of 27'
_j;( 11-27-85 5.0 COLLECTION AND ANALYSIS OF SAMPLES 5." 1 General Requirements 5.1.1 Definitions 5.1.1.a Batch - The amount of waste which fills one disposable
~
liner or drum.
j.
l 5.1.1.b Transfer - The delivery of liquid or sluiced radioactive vaste to a so ification or disposable container.
There any be several transfers made from several sources that compose a batch. If the transfers are made from the same source and the contents of the source are known .
not to change during the time of the transfers, the i
volume of each transfer need not be known. If the transfers are made from several different sources, the volume of each transfer must be known. If several transfers are made from one source which has inputs to that source during the duration of the transfers, the volume of each transfer must be known.
5.1.1.c Sample - A portion of a transfer or batch that represents the contents of that transfer or batch.
5.1.1.d Composite - A mixture of samples proportional by volume
' to the individual transfers making up a batch, thus resulting in the test specimen being representative of the batch.
5.1.1.e Direct In-container Sample - A sample removed from the dispoJable container after the container has been i filled; the contents of which are a composite of samples taken from various positions within the container.
4 Process Control Program Page 18 of 27 11-27-85
-.-.~ ;
5.1.2 Frequency of Samples 5.1.2.a Dewatered Resins - A sample for radioassay. purposes shall be taken from each batch. The sample may be a representative sample taken at the source (when the source remains unchanged during the transfer of a
^
batch), a composite sample composed of samples collected at the source, or a direct in-container sample.
5.1.2.b Spent Filter Cartridges A sample of each spent filter cartridge shall be obtained for radioassay purydgses.
5.1.2.c Solidification / Absorption i
A sample of at least every tenth batch of each type of liquid or sluiced radioactive waste (e.g., boric acid solutions, spent resins, evaporator bottoes) shall be used to demonstrate solidification / absorption .
If any test specimen fails to solidify or absorb, the I batch under test shall be suspended until such time as additional test specimens can be obtained, alternative
! e so ification/ absorption parameters can be determined in accordance with the procedures incorporated by reference into this Process Control Program, and a subsequent test l
verifies so'dification/ absorption. Processing of a 17 .
batch may then be resumed using the aj rnate parameters i
determined.
.I i
w-,. m v.~ , - _ - - -- . - - . - . . _ - - - . . - - - - - . . . _ . . _ _ .---.w-,_, ,__~...-4 ,# , ,.,,.-.v.----------r .m - v n y -.mv-------,y,-r,
Process Control Program Page 19 of 27 11-27-85 If the initial test specimen from a batch of waste fails acceptance criteria, representative test specimens shall be collected from each successive batch of the same type of waste until three (3) consecutive initial test specimens demonstrate solidification / absorption. The i
operating procedure (s) incorporated by reference into this Process Control Progras shall be modified, as required, to assure solidification / absorption of subsequent batches of waste.
- 5.1.3 ALARA Considerations 3.1.3.a Prior to obtaining any samples or performing any waste transfers, a Radiation Work Permit (RWP) will be
- obtained. All activities shall be in compliance with l the conditions of the RWP. The Health Physics Department will stipulate protective clothing requirements and protective measures to be implemented 4
to maintain doses ALARA.
! 5.1.3.b For high activity wastes where handling of samples could
! result in personnel radiation exposures which are inconsistent with the ALARA principle, representative diluted samples will be tested / assayed or representative non-radioactive samples will be tested (for so ification/ absorption verification only).
I f
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l Process Control Prograa
'~~
.. Page 20 of 27 11-27-85 5.2 Dewatered Resins 5.2.1 Sample Collection Representative sample (s) shall be taken of each batch of spent powdered or bead resins. Samples may be taken from the sample tap on the Spent Resia Racirculation pump discharge line or as a direct in-container sample from the disposable container. For samples taken at the recirculation pump discharge, the tank l contents shall be recirculated to provide a minimum of one tank t
contents changeover prior to obtaining a sample. The design of the direct, in-container sample probe assures a representative sample sad, therefore, no aizing requirements esist when direct g, in-container sampling is used. Samples shall be taken in accordance with approved Health Physics Department procedures / instructions.
5.2.2 Saanle Analysis The spent resia sample shall be analysed by radioassay techniques i
in accordance with approved procedures in the station Health l Physics Procedures Manual. A sample of output data documenting a I
radioassay is provided in Appendis A. )
I 5.2.3 Accootence Criteria l l
The results of the radioassay are considered acceptable when it l has been verified and documented that the spent resins are packaged in a container which is acceptable for transportation I and burial, considering the radioactivity concentrations which esist in the waste. Standard containers are acceptable for waste containing less than 1 uCi/gm activity when devatored to less than 0.5% water. High Integrity Containers are required for wastes containing more than 1 uCi/gm activity and aust be dewatered to less than 1.0% water.
1
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1 Process Control Program Page 21 of 27 11-27-85 5.3 Spent Filter Cartridaes
- 5. 3.1 Sample Collection i
A sample of the cartridge filter element asterial shall be
)
removed from the filt,or element. This sample shall be removed in accordance with a Realth Physics Department procedure / instruction 5.3.2 Sample Analysis !
l The cartridge filter sample shall be analyzed by radioassay l techniques in accordance with approved procedures contained in
, the Esalth Physics Procedures Manual, Section 3. A sample of an output data sheet documenting a radioassay is provided in j Appendix A.
5.3.3 Accostance Criteria The results of the radioassay are considered acceptable when it has been verified and documented that the spent filter cartridge is packaged in a container which is acceptable for transportation and burial, considering the radioactivity concentration which exist in the waste. Standard liners and drums are accepta9e for wasta containing less than 1 pC1/sm activity and High Integrity Containers are required for wasta containing more than 1 uCi/sm activity.
---n--- w- v ~vme w we--- n - - - , , , - _ _ -- - - - - - - - - - , - - + - - - - - -
4 Process Control Program Page 22 of 27
--J 11-27-85 5.4 Liquids for Solidification There is no permanently installed, operating solidification system on-site. In the event contractor services are utilized for solidification, the contractor or Virginia Power shall provide procedures for sample collection and sample analysis. The sample i collection and sample analysis procedures shall be for both radioactivity determiantion and solidification verification.
These procedures will be subject to Virginia Power review and acceptance and once accepted, will be incorporated into this Process Control Program by reference (See Section 4.3). The solidification a i
system will not be operable until the sample collection and analysis i
procedures are accepted by Virginia Power.
(' All chemicals used to condition or solidify waste or simulated waste in so Iification tests shall be representative of the actual chemicals to i
be used in full scale solidification. If chemicals of a different type or from a different manufacturer are used, the new material shall be tested to verify it produces a solid product prior to full scale solidification.
5.5 Wasta 011 Absorption 5.5.1 Sample Collection l Representative samples shall be taken of each batch of t
radioactively contaminated waste oil. Samples may be taken from the recirculation pump discharge line.
5.5.2 sample Analysis The oil samples shall be analyzed by radioassay techniques in accordance with approved procedures in the Health Physics Procedures Manual.
l l
. . . - . . - , - . . . _ . _ . ~ ~ - - _ _ , _ _ _ . , , . .
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Page 23 of 27
'J 11-27-85 5.5.3 Acceptance Criteria ,
Any activity indentified in the oil samples greater than Minimus Detectable Activity (MDA) shall deem the oil radioactively contaminated, thus requiring processing and disposal in accordance with approved Health Physics Procedures. 1 1
6.0 STATION RECORDS Station records shall be maintained for sample radioassay, verification of :
1 dewatering per applicable procedure, filter element dryness, so ification/ absorption, so ification system c?arations within specified I process parameters, and documentation of packaged container weight and '
.?
( packaged container survey results. Table 6.1 specifies the forms to be used ,
I for the above data, references the samples provided in Appendix A. and stipulates whether the form is a sample or mandatory. Where forms are a sample only, any form may be used provided it contains the minimum information provided on the sample.
l l
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Process Control Program Page 24 of 27
__. J 11-27-85 TABLE 6.1 SUle(ARY OF FORMS REQUIRED TO IMPLEMENT THIS PROCESS CONTROL PROGRAM Form Sample #
Data In appendix A Manda to ry Sample Radioassay 1 No Verification of Spent Resin Dewatering 2 through 5* Yes*
Verification of Filter NA (Procedure
- Element Dryness sign-offs) Yes Vecification of None - To Be Provided NA So ification By Solidificaiton Contractor h None - To Be Provided Verifica44en of Solidification NA System Operation Within By Solidification Specified Process Parameters Contractor Verification of Absorption 7 Yes Documentation of Packaged 6 Yes l
Container Weight Documentation of Packaged 6 Yes Container Survey
- Applicable form based upon devatering procedure utilized.
7.0 INTERFACES BE1VEEN STATION AND CONTRACTOR SERVICES 7.1 Dewatering Spent Resins 7.1.1 Station Responsibilities 7.1.1.a RWP preparation and issue.
! 7.1.1.b RP coverage, including determiation of special protective measures and shielding requirements.
7.1.1.c Resin sample collection.
Process Control Program Page 25 of 27 11-27-85' 7.0 (cont.)
4 7.1.1.d Resin sample radioassay.
7.1.1.a Transfer of spent resins from the Spent Resin Holdup Tank to the devatoring container.
7.1.1.f operation of the dewatering equipment in accordance with
- I approved procedures. l 7.1.1 3 Verification (QA/QC) of operation in accordance with approved procedures.
I 7.1.1.h Weighing the filled waste container when ready for l shipment. l i 4 ,
7.1.1.1 Surveying the filled waste container when ready for i shipment.
7.1.1.j Prepare and maintain all records.
7.1.2 Contractor Responsibilities 7.1.2.a Operate contractor provided treatment system in accordance with approved procedures.
7.1.2.b Place fresh domineraliser vessels in service and take spent domineralizer vessels out of service.
=7,1 3 2 ,,
n- ---
-ticif-f o----i. so, av.7,--1, 7.1.3 Physical Interfaces 7.1.3.a Process Fluids
- 1. High Level Liquid Waste Tank Discharge: 5-25 gpa at 30-150 psig; maximum temperature-125F: 1-1/2", 150
{
i
).
psi hose with Kam-Lock fitting.
- 2. Filter Atmospheric Vent Hose: 1/2" tygon hose connected to a 1/2" needle valve (150 psi rating) l connected to a Kam-Lock fitting.
4
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Process Control' Program Page 26 of 27 J, 11-27-85 7.0 (cont.)
- 3. Domineralized Water Discharge: 5-25 spa at 150 psig; 1-1/2", 150 psi hose with Kam-Lock fitting.
- 4. Resin Transfer: 1-1/2", 150 psi hose; 25 spa sax at 150 psi anx; quick disconnect fitting at disposable liner fill head.
- 5. Dewatering Line 1-1/2" hose connection at disposable liner fillhead; quick disconnect fitting.
- 6. Crane Services for loading and unloading vessels.
- 7. Protective clothing and dosimetry devices for .
contractor operators.
- 8. Shielding.
7.2 Filter Cartridaes A
The utility is resp Qsible for removing the cartridges from the filter housing. All actions following cartridge removal are utility actions;
- therefore, there are no additions 1 interfaces.
1
, 7.3 Solidification There is no permanently installed, operating solidification system on-l i
' site. In the event contractor services are utilized for solidification, the contractor will be required to provide a list of physical interfaces, services required, and breakdown of utility / contractor responsibilities. These documents will be subject to Virginia Power review and acceptance and once accepted, will be incorporated into this Process Control Program by reference (See Section 4.3). The l
solidification system will not be operable until the definition of physical interfaces, services required, and utility / contractor responsibilities are accepted by Virginia Power.
. 1 Process Control Program Page 27 of 27 11-27-85
-l 7.4 Absorption l I
The utility is responsible for all activities pertaining to processing of radioactively contaginated waste oil using the absorption technique.
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4 Process Control Prograu Append.tx A
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Page 3 of 10
.-~ 11-27-85 NUCLIDE IDENTIFICAT!0H SYSTEN (REVrt/84) .
SUMMARY
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Process Control Program Appendix A Page 4 of 10 11-27-85 VIRGINIA POWER NORTH ANNA POWER STATION UNIT 1 DEWATERING DATA SHEET FOR 24 INCH DIAMETER
, PRESSURE VESSEL CONTAINING ACTIVATED CARBON VESSEL SERIAL NUMBER SHIPPING NUMBER STEPS DATE TIME INITIALS l 4.5 - Start Dewatering Pump 4.6 Stop Dewatering Pump l 4.7 Start Dewatering Pump 4.8 Stop Dewetering Pump 4.9 Start Dewatering Puay 4.10 Stop Dewatering Pump 4.12 Start Dewatering Pump 4.13 Stop Dewatering Pump Volume Water Collected m(1s 6.14 Start Dewatering Pump 4.15 Stop Dewatering Pump Volume Water Collected m(1s 4.16 Start Dewatering Pump 4.17 Stop Dewatering Pu: p Volume Water Collected m{ls SAMPLE 2
Process Control Program Appendix A Page 5 of 10 11-27-85 DEWATERING DATA SHEET FOR 24 INCR DIAMETER PRESSURE VESSEL CONTAINING ACTIVATED CARBON (CONTINUED)
STEPS DATE TIME INITIALS 4.18 Start Dewatering Pump 4,19 Stop Dewatering Pump Volume Water Collected $1a i
1 COMMENTS: ;
i l
SAMPLE 2
Proc 30s Control Program Appendix A Page 6 of 10
- . . 11-27-85
.4 VIRGINIA POWER NORTH ANNA POWER STATION UNIT 1 DEWATERING DATA SHEET FOR 24 INCH DIAMETER PRESSURE VESSEL CONTAINING ION EXCHANGE RESINS VESSEL SERIAL NUMBER SHIPPING NUMBER STEPS DATE TIME INITIALS 4.5 Start Dewatering Pump 4.6 Stop Dewatering Pump 4.8 Start Dewatering Pump Z.
4.9 Stop Dewatering Pump Volume Water Collected als 4.10 Start Dewatering Pump l 4.11 Stop Dewatering Pump Volume Water Collected als l
1 COMMENTS:
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S AMPLE 3
Process Control Program Appendix A Page 7 of 10
_-- 11-27-85 VIRGINIA POWER NORTH ANNA POWER STATION UNIT 1 DEWATERING DATA SHEET FOR CHEM-NUCLEAR 14-195 OR SMALLER LINER LINER SERIt.L NUMBER SHIPPING NUMBER DEWATERED TO 0.5% / 1.0% (CIRCLE ONE)
STEPS DATE TIME INITIALS 4.5 Start Dewatering Pump 4.6 Stop Dewatering Pump E 4.7 Start Dewatering Pump _
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4.8 Stop Dewatering Pump l
l 4.11 Start Dewatering Pump 4.12 Stop Dewatering Pump Volume Of Water Collected gal If Necessary 4.14 Start Dewatering Pump 4.15 Stop Dewatering Pump Volume Of Water Collected gal 4.16 Start Devataring Pump 4.17 Stop Dewatering Pump Volume Of Water Collected gal SAMPLE 4 q' W' e 9-w- -y'a---- -- ,,p _, , _ ,
Process Control Program Appendix A Page 8 of 10 11-27-85 STEPS DATE TDG INITIALS
~4.18 Start-Dewatering Ptsap 4 19 Stop Dewatering Pump Volume Of Water Co,11ected gal COMMENTS:
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. SAMPLE 4
Process Control Program Appendix A
~
_f Page 9 of 10 11-27-85
. VIRGINIA POWER NORTH ANNA POWER STATION UNIT 1 DEWATERING DATA SHEET FOR CHEM-NUCLEAR 14-195 OR SMALLER LINER CONTAINING ECODEX, POWDEX, OR DIATOMACEOUS EARTH LINER SERIAL NUMBER SHIPPING NUMBER ,
STEPS INCH Hg DATE TIME INITIALS 4.7 Start Dewatering 4.8 Close Valve #4 ..
3 4.9 Close Valve #3 4.10 Close Valve #2 4.11 Close Valve il 4.13 Start Dewatering l
Close Valve #4 Close Valve #3 Close Valve #2 Close Valve il 4.15 Start Dewatering, l .
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- Close Valve #2!
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GENERATOR NAME VIRGINIA POWER BARNWELL WASTE MANAGEMENT FACILITY (4) CARRIER:TRI-STAIE MUTOR I CAN'il l ADDOESSINURTH ANNA POWER STATION OPERATED Bif t CHEM-NUCLEAR SYSTEMS, INC. ADDRESS:
CITY:P.O. BOX 402 MINERAL, VA P.O. BOX 726, stARNWELL, SOUTH CAROLINA 29812 TELEPHONE BsX>-641-7500 CONTACT: CARL DRADLEY .(803)259-1781 SHIPPING DATE 11/14/06
- PHONE 703-894-5151X291 RADIOACTIVE SHIPMENT MANIFEST FORM- SHIPMENT TYPE: USA /9176/A CONSIGNED TO: SHIPMENT SURFACE EXPOSURE: . . . . . . . . .MiueIN CEM-NUCLEAR SYSTEMS, INC. (3) USE THIS NUMBER ON VOLUME ALLOCATION No. PAGE 1' CASK IDENTIFICATION NO.................'.
P.O. BOX 7261 OSBORN ROAD ALL CONTINUATION PAGES 11-86-149-S- 0F 2 SHIPMENT NO.38637 LINER SERIAL NO.......
BARNWELL, SOUTH CAROLINA 29012 DRIVER SIGNATURES............DA1Es......
TOTAL FOR EA.CLASSIPROPER SHIPPINS NAME & HAZARD CLASS ID. NO.lte) SHIPMENT TOTALS I 3).PKGES IWEIGHT (LB) I '(PER 49 CFR 172.101) , 8 DISP. ITOTAL NO.I ACTIVITY (10CFR20.311) MILLICURIES 1
.......l..........lRADIDACTIVE MATERIAL, EMPTY PACKAGES UN2908 t VOLUME 10F PKSS. I ALL I I I .
I I I IRADIDACTIVE MATERIAL, FISSILE,N.D.S. I CU.FT.I IISOTOPESITRITIUM I C-14 I TC-99 l I-129 8
.......l..........I -RADIDACTIVE MATERIAL UN2918 1.......l.........l........l........l........l........j........I 1 1 7000.0 IRADIDACTIVE MATERIAL,L.S.A.,N.O.S.
.......l......... 1 -RADI0 ACTIVE MATERIAL I 193.0 1 1 11.25E+0517.60E+0115.81E+011 LLD.
UN2912 8.......l.........I........l........l........l........l....... 1 llLLD. 1 I IRADIDACTIVE MATERIAL,N.O.B. l
.......l..........I -RADIDACTIVE MATERIAL UN2992 l(7) TOTAL SNM -l 1 SOURCE I I IRADIDACTIVE MATERIAL,LTD.ONTY.,N.O.S. I ISOTOPE I U-233 I U-235 I TOTAL i I (LBS) I
..... .l..........! -RADIOACTIVE MATERIAL UN2910 l I N.A. I N.A. I N.A. 1 I N.A. 1 1 1RADIDACTIVE MATERIAL, SPEC. FORM,N.O.S. I GRAMS 1.........l.........l.........I 1........l
.......l......... 8 -RADIDACTIVE MATERIAL UN2974 I i 1RADIDACTIVE MATERIAL INST.& ARTICLES 1(8) TOTAL PALLET (9) MINIMUM FILL % FOR
.......l..........I -RADIOACTIVE MATERIAL UN2911 1 VOLUPE (CU. FT. ): .O STABILIZATION PROCESS: 85.0
...'....l..........IOTHER (SPECIFY)............................. 1 1 I ..
0 WASTE DESCRIPTION: ' (11) PHYSICAL FORM / SOLIDIFICATION (12) CHEMICAL FORM AND NAME AND % (13) WASTE FORM CLASS:
DEWATERED BEAD RESIN AGENT: SOLID /NDE CELATING AGENTS: METAL OXIDES [ 3AU [ ]AS [X]D E 3C 0[ 3YES [ 3NO THIS VEHICLE IS CONSIGNED EXCLUSIVE USE. LOADING (16)*" CERTIFICATION IS HEREBY MADE TO THE SOUTH CAROLINA DEPART-AND UNLOADING MUST BE ACCOMPLISHED BY CONSIGNOR OR CONSIGEE, ENT OF M ALTH AND ENVIRONMENTAL CONTROL THAT THIS SHIPMENT OR HIS/HER DESIGNATED AGENT. OF LOW-LEVEL RADIOACTIVE WASTE HAS BEEN INSPECTED IN ACCORD-ANCE WITH TE REQUIREENTS OF SOUTH CAROLINA RADIOACTIVE 9IMPORTANT "THIS IS TO CERTIFY THAT THE 'ABOVE NAMED MATERI ALS MATERIAL LICENSE NO. 097 AS AE NDED, AND THE NUCLEAR REGULA-ARE PROPERLY CLASSIFIED, DESCRIBED, PACKAGED, MARKED, AND TORY C0fetISSION'S LICENSE NO. 12-13536-01 AS AMENDED,AND NE LADELED, AND ARE IN PROPER CONDITION FOR TRANSPORTATION AC- EFFECTIVE BARNMELL SITE DISPOSAL CRITERIA WITHIN 48 HOURF.
CORDING TO THE APPLICABLE REGULATIONS OF THE DEPARTMENT OF PRIOR TO SHIPENT, AND FURTHER CERTIFICATION IS MADE TS%f TRANSPORTATION." . ! THE INBPECTION REVEALED NO ITEMS OF NON-COPFLI ANCE WTH ALL i APPLICABLE LAWS, RULES, AND RESULATIONS."
SIGNATURES.......................'.........................
DATES...........BYs.........................................
COMPANY:................................ DATES............. TITLE AND ORGANIZATIONS.....................................
TELEPHONE NO. .............................................. .
.................................======....======== CNSI USE ONLY ===========================================================
THIS MATERIAL MEETS ALL LICENSE REQUIREMENTS. ARRIVAL DATES.......... ARRIVAL SURVEY N0.s.............
THIS MATERIAL WAS DISPOSED OF IN ACCORDANCE WITH DATE/ TIME BURIEDs...........H.P. INITIAL:
LICENSE.
, DISCREPANCY:...................................... TRENCH Nos................ LOCATION CODES...............
, FORM
................................................ NO. WASTE CLASS CODES......................................
l CNS-201 i ................................................ .......................................................
AulHORIZED SIGNATURES........................... (11-85) PERSONNEL EXPOSURES.................................,,,
fliLE.........................DATE:............
I
, FORM HP - 3.2.15 Attachment 1 Page 1 of-1 11-27-85 l
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IN#EuuoN RiiULTS HEALTH PHYSICS QC INSPECTOR BATCE ID # SAT UNSAT DATE/ SIGNATURE DATE/ SIGNATURE i
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Page 8 .
4 ATTACHMENT 5 (7/86 - 12/86)
MAdORCHANGESTORADI0ACTIVELIQUID, GASEOUS,ANDSOLID WASTE TREATMENT SYSTEMS No major changes to the radioactive liquid, gaseous, and solid waste treatment systems were made for the time period covered by this report.
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g-Page 9 ATTACHMENT 6 (7/86-12/86)
RADI0 ACTIVE LIQUID AND GASE0US EFFLUENT MONITORING INSTRUMENTATION INOPERABLE No radioactive effluent monitors were declared inoperable, as defined according to the criteria presented in Technical Specification 3.3.3.10.b and 3.3.3.ll.b,'for the time period.
covered by this report.
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-,7, -- - - . , _ , _---,e%r-,. 7-,,-%g-_., y-, w --, -----. -- --.. -- .- mcg y. -- w- - --r w +&-,,-- --ww-.- w.--- -.y yer. - . - --,pp-
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C ATTACHM'NT E 7 (7/86'-112/86)
UNPLANNED RELEASES No unplanned releases, as defined according to the criteria presented in 10 CFR Part 50.73, occurred during the time period covered by this L
report. ,
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.g-- y VINGINIA ELECTRIC AND Powna COMI%NY Hics Moxn,VinoinnA 202G1 W. L. Stawaar Vsem PanssoswT NUcLEAm oramarsons March 2, 1987 United States Nuclear Regulatory Commission' Serial No.87-088
' Attention: Document Control Desk N0/RCB:jmj Washington,-D.C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4
. NPF-7 Gentlemen:
VIRCINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the North Anna Power Station Semi-Annual Radioactive Effluent Release Report for July 1, 1986 through December 31, 1986. The report, submitted pursuant to North Anna Station Technical Specification 6.9.1.9, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the previous six months, as outlined in Regulatory Guide 1.21, Revision 1, June 1974.
Very truly yours, r
t u W. L. Stewart u
Enclosure l
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///
{,,
W i-cc: - U.~-~ S. Nuclear Regulatory Comunission
-101 Marietta Street. N.W.
-Suite 2900.
Atlanta, GA 30323 Mr. J.-L.'Caldwe11
'NRC Senior Resident Inspector North Anna Power Station l
i