ML20148K426
| ML20148K426 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/30/1986 |
| From: | Barnes W, Hickman O, Stafford A VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20148K377 | List: |
| References | |
| NUDOCS 8801270616 | |
| Download: ML20148K426 (22) | |
Text
. _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _
SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION JANUARY 01, 1986 TO JUNE 30, 1986 I l
l PREPARED BY: /M dImW8 William C. Barnes, III Assistant Supervisor Health Physics {
(Count Room & Environmental)
REVIEWED BY: d [ ; a.
O. E 'Hickman, Jrl/1 Supverisor Health Mysics (Technical Services)
REVIEWED BY: I
~A.
H. St<)f/Ord Superintendent Health ics APPROVED BY:
E. Wayne Harrel 7 Station Manag /
Ock$$@
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T 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 Company, 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 l JANUARY 01,1986 T0 JUNE 30,1986 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 1 Attachment 7 Unplanned Releases . . . . . . . . . . . . . . . . . . . 10
)
Page 1 1.0 PURPOSE AND SCOPE The Semi-Annual Radioactive Effluent Release Report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, "Measuring,' Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents of Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data sumarized on a quarterly -
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 00CM 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 Specificaiton 6.14.
Major changes to radioactive liquid, gaseous and solid waste treatment 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 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 Specificaiton 3.3.3.10.b and 3.3.3.11.b a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitors is provided in this report.
i 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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Page 2 Technical Specification' 3.11.2.1.b requires that the dose rate for iodine-131', for tritium, and for all radionclides in particulate form with
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half lives 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 specification 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 or 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 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 liquid effluents to unrestricted veas 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 1
x 10 microcuries/ml. j l
Percent of technical specification calculations are based on the total '
gaseous or liquid effluents released for that respective quarter.
Unplanned releases presented in Attachment 7 are defined according to l
the criteria presented in 10 CFR Part 50.73. Gaseous unplanned releases are those radioactive releases that exceed 2 times the applicable concentrations I 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
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_ limiting combined Maximum Permissible Concentration (MPC) specified in Appendix B,-Table II, of 10 CFR Part' 20 in unrestricted areas for all radionucl_ ides except tritium and dissolved noble gases, when averaged over a time period of one_ hour.
3.0 SUPPLEMENTAL INFORMATION There are no inclusions for the time period covered by this report.
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l ATTACHMENT 1 EFFLUENT RELEASE DATA 1/86 - 6/86 i
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This attachment includes a sunrnary of the quantities l l
of radioactive liquid and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21. ,
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TABLE lA EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1986)
CASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES NORTH ANNA POWER STATION EST. TOTAL UNITS 1st QUARTER 2nd QUARTER % ERROR A. Fission and Activation Gases:
- 1. Total Release Ci 4.01E+3 5.43E+2 1.5E+1
- 2. Average Release Rate for Period pCi/sec 5.16E+2 6.91E+1 B. Iodines:
- 1. Total Iodine-131 Release Ci 1.71E-3 8.51E-4 1.5E+1
- 2. Average Release Rate for Period: uCi/sec 2.20E-4 1.08E-4 C. PARTICULATES (Th < 8 days):
- 1. Total Particulate (Th < 8 days) Release Ci 1.04E-3 1.09E-4 1.5E+1
- 2. Average Release Rate for Period uci/sec 1.34E-4 1.39E-5
- 3. Gross Alpha Radioactivity Release Ci 7.26E-6 1.52E-5 D. Tritium:
- 1. Total Release Ci 7.47E0 1.35E+1' l.5E+1
- 2. Average Release Rate for Period pCi/sec 9.61E-1 1.72E0 E. Percentage of Technical Specification Limits:
- 1. Total Body Dose Rate % 3.20E-1 3.33E-2
- 2. Skin Dose Rate % 1.24E-1 1.30E-2
- 3. Critical Organ Dose Rate % 2.84E-3 2.23E-3
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TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1986)
LIQUID EFFLUENTS-SUMMAT10iY OF ALL RELEASES NORTH ANNA POWER STATION EST. TOTAL UNIT lst QUARTER 2nd QUARTER % ERROR A. Fission & Activation Products
- 1. Total release (not including tritium, gases, alpha) Ci 2.93E-1 1.52E-1 1.5E+1
- 2. Average diluted concentration during period uCi/ml 5.96E-10 2.07E-10
- 3. Percent of applicable limit (T.S.) % 1.91E-2 1.18E-2 B. Tritium
- 1. Total release activity. Ci 2.91E+2 3.94E+2 1.5E+1
- 2. Average diluted concentration during period. UCi/ml 5.91E-7 5.38E-7
- 3. Percent of applicable limit (T.S.) % 1.97E-2 1.79E-2 C. Dissolved and entrained gases
- 1. Total release activity. Ci 6.60E-1 3.62E-1 1.5E+1
- 2. Average diluted concentration during period. UCi/ml 1.34E-9 4.94E-10
- 3. Percent of applicable limit (T.S.) % 6.71E-4 2.47E-4 D. Cross Alpha Radioactivity
- 1. Total release activity. Ci *
- 1.5E+1 E. Volume of waste released (prior to dilution) Liters 6.52E+7 6.50E+7 F. Volume of dilution water used during period Liters 4.92E+11 7.33E+11
- Less than lower limits of detection
2 f
o R E
1 T R
e A g U a Q * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
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E n D 2 O
M H
C T R A E B T R 6 6 7 7 8 8 7 8 6 6 7 6 5 A - - - - - - - - - - - - -
U E E E E E E E E E E E E E Q *
- 2 4 0 8 * * * * * * * *
- 2 6
- 9 *
- S 7 9 7 7 * * * * *
- 6 4 5 6 4 2 1 4 2 0 7 8 6 2 t
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9 1
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T R R O E P T E R 3 2 3 2 2 3 4 2 4 3 4 1 R A - - - - - - - - - - - -
U E E E E E E E E E E E E L Q *
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- 8 * * * * * * *
- 4
- 7 *
- 8 * * * *
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E DI U E E E E E E E E E E E E E E E E E LH Q *
- 2 7 6 4 5 9
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- 8
- 8 0
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S O s 9 2 2 1 3 6 1 1 4 9 4 1 5 2 4 2 1 2 A N 1 W
D N
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n 1 1 1 5 6 - m m 1 1 e 2 5 I - 1 1 1 1 1 - s a _
S a m m 9 5 e - m u u m p m 5 m u r h _
E u u - - - - - 5 6 m s u n i - u - S - - - y - - - - u - $ y u r o t _
D n i i u e m i e t n ( n i n i o f _
I o t t m m e t t - - i n u n d e m a m m t r o e e e e r m - o n h s _
L i n n u u n l l m s i o b n u h u r u l e m n n n n u u m e p l s _
C s o o i i i a a n e o g b c y h i t i e i a v i i i i i l i n i h s a e U s r r s s d b b o n r n o r l c r n r h d b l t d d d d l s o t t o t L N i t t e e o o o r i h a i i o e a a e t o o i n o o o o e e r n u h o _
F S S C C I C C 1 Z C M N Z M T B L C O S C S A I I I I T C I A R P T
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U E E E E Q
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ELFO I R LAEP T E BS N T AODA O R 1 2 3 5 1 2 TPI N C A - - - - - +
SUN U E E E E E _
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- 8 0 1
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D v - - ( - - f m _
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/~ l TABLE 3 (1/86 - 6/86)
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-MONTH EST. TOTAL
- 1. Type of Waste UNIT PERIOD F.RROR, %
- a. Spent resins, filter sludges, m3 1.06E+2 1.0 E+1 evaporator bottoms, etc. Ci 1.41E+2 1.0 E+1
- b. Dry compressible waste, m3 2.01E+2 1.0 E+1 contaminated equipnent, etc. Ci 2.37E+2 1.0 E+1
- c. Irradiated components, control m3 . E . E rods , etc. Ci . E , E
- d. Other(describe) m3 1.42E+1 1.0 E+1 Absorbed Oil C1 1.30E-3 1.0 E+1
- 2. Estimate of major nuclide composition (by type of waste)
- a. Ni 63 21.00% 1.0 E+1 Co 58 20.50% 1.0 E+1 H 3 15.02% 1.0 E+1 Cs 137 10.70% 1.0 E+1 Fe 55 9.97% 1.0 E+1 Co 60 9.61% 1.0 E+1 Cs 134 4.83% 1.0 E+1 C 14 3.99% 1.0 E+1 Cm 244 2.68% 1.0 E+1 Pu 241 1.20% 1.0 E+1 Mn 54 0.72% 1.0 E+1
. % E
% . E
- b. Fe 55 62.37% 1.0 E+1 Ni 63 11.02% 1.0 E+1 Co 60 8.41% 1.0 E+1 H 3 6.95% 1.0 E+1 Cs 137 3.79% 1.0 E+1 Cs 134 1.54% 1.0 E+1 Tc 99 1.36% 1.0 E+1 Sr 90 1.36% 1.0 E+1 0 14 0.98% 1.0 E+'
I 129 0.97% 1.0 E+1 Co 58 0.76% 1.0 E+1 Mn 54 0.44% 1.0 E+1
% . E
- c. None % . E
. % E
% . E
% . E
TABLE 3-CONTINUED P/,GE 2
- 2. Estimate of major nuclide composition (by type of waste)
- d. Fe 55 70.75 % 1.0 E+1 Ni 63 18.13 % 1.0 E+1 Co 60 8.03 % 1.0 E+1 C 14 1.10 % l.0 E+1 Cs 137 1.09 % 1.0 E+1 Tc 99 0.32 % 1.0 E+1 Sr 90 0.32 % 1.0 E+1 Cs 134 0.30 % 1.0 E+1
% . E
% . E
% . E
% . E
% . E
% . E
% . E
% . E
% . E
% . E
% . E
% . E l
% E
{
. E
% . E
-~
% . E l
% E l
% E j
% . E l
% . E i
% . E
% . E
% . E
% . E
% . E l
- 3. Solid Waste Disposition .
NUMBER 0F SHIPMENTS MODE OF TRANSPORTATION DESTINATION 22 Private Vehicle Barnwell, SC ,
1 Private Vehicle Richland, WA l B. IRRADIATEDFUELSHIPMENTS(Disposition)
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION None
Page 5 ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (1/86 - 6/86)
No attachment required for this semi-annual radioactive effluent release report, per Technical Specification 6.9.1.9.
l l
l 1
' ' '~
L;T *i:_ _ . ,
.. ,, q,,-
s-
. Page 6 C
ATTACHMENT 3
'(1/86 - 6/86)
' REVISIONS TO 0FFSITE DOSE CALCULATION.
- MANUAL (0DCM)
As required by Technical Specification 6.15, revisions to the'0DCM for the time period covered by;this report'are synopsized.
below.- Supporting documentation and affected-pages of the.0DCM are.
attached.
2-28-86: Revisions were made to the ODCM to clarify projected ganna dose calculations, and to reference the correct Technical Specification requiring submittal of the; Semiannual Report.
~
3-20-86: Revisions were made to the 00CM to. reflect a new method of distributing revised sections.
T
) t
, - , , , , , , -~i,
ADM-$.4 A t ta clu:en t .'
QP.TH ANNA POWER STATION Page 1 of '
P 'ED1'RE ROUTING SLIP 'll-25-85
!NSTRUCTIONS: When vou hate completed the action for which this proceduro was sent to you, date and initial, then forward,the procedure.to the next person or department .
DO NOT. REMOVE this routing slip.
UNIT /M PROCEDURE NO. [)/)/1 /// NON-SAFETY NEW PROCEDURE DELETION REQUIRED APPROVAL DATE J-JS-ff REQUIRED DISTRIBUTION DATE N
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ORDER TITLE INITIALS DATE* ORD5R TITLE INITIALS DATE g COGNIZANT SUPV. g g.,/pff SUPT.- TECH. SERV.
ASST STATION MANAGER SUPT.- PROJECTS OSM ASST STATION MANAGER SUPT. - HEALTH PHYSICS' NS&L h Ed'N MANAGER, QUALITY ASSURANC g SUPV. ADM. SERVICES SUPT. - OPERATIONS SUPV. - PLANNING SUPT. - TRAINING SUPT. - MAINTENANCE RETURN TO COGNIZANT DEPARTMENT THIS PROCEDURE IS BEING REQ"D FROM FORWARDED T0/FOR: PROOFING ACTION COMPLETED CHECK DATE DATE INITIAL Cognizant Supervisor for Review / Approval ~
or SNSOC Reviev/ Approval Tvpine. First ~i~e
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,e-Co gn i .:a n t Dept: Proot Reading (I) ,
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NORTH ANNA POWER STATION Attachnent 3 l "IRGINIA POWER Page 1 of 1 l 11-25-85 j TO .EP ER"ISOR F.EJPf' :S 13Li F0E FOLLOWING PEOCEDURE l ABNORMAL CU""E B00E OPERATING WELDING l ADMINISTRAT!VE EMERGENCY PERIOD!r TEST ANNUNCIATOR IN-SERVICE INSPECTION GiEALTH PilYSICS)
CALIBRATION MAINTENANCE SPECIAL TEST l CllEMISTRY NON-DESTRUCTIVE TEST START-UP TEST l PROCEDURE NO: 2 UNIT NO: 3 REVISION DATE: 4 006M H2 n-n-8s _.
l 6;&A lim 6/adda6n, #/ama/ '
CHANGES f4 QUESTED: (GIVE STEP NUMBER, EXACT SUGGESTED WORDING, AND LIST REFERENCES, STAPLE 6 COPY OF PROCEDURE WITH SUGGESTED CHANGES MAREED TO THIS FORM.)
/
. 6 A /)2 Y2 l 2 r f j
REFERENCES:
g REASON FOR CHANGES: , i m- r> m osem. + r n CHANGE REQUESTED BY: .// f 8 DATE: Y
$. M V & N')' - N$Wb $
YY$ww 6.M/S2. J. : d! w o & d rea k e ODAlla.L- di)Aff5EEN% Wdnc.p__ M/ssjh2$Esex J dd) Al A J ~~ OJL$nn12SNw o L} [ f _- DOES THIS CHANCE THE OPERATING METHCDS AS DESCRIBED IN THE UFSAR? - YES QiDJ DOES THIS CHANGE INVOLVE ~ A CHANGE TO THE TECH. SPECS? YES @ DOES THIS CHANGE INVOLVE A POSSIBLE UNREVIEWED SAFETY QUESTION? IF AI.L "NO", NO "SAFETY ANALYSIS" IS REQUIRED. YES @ . I F ANY "YES", A "S AFETY At'ALYSIS" IS REQUIRED.
/lCCFR50.59) yp,' e s q v s = r3 ~; q APP'iOVED COPY TO P.F PROVIDED TO LICENSING C00FD. FO' INCLPSION IN V:':UAL s,g.- 3 4,
b;gA:m wly? rs 3 -erED"3F Cpr TE SY: (':' 'r" I UN! ';?F 0/ ' SOR) a D.:d ' ' ' h 5'0 12 DATFi :;
$. ftL&M ] $YhS RE"I EWED FOR QUAL TTY ASSUFA'K/'./ REQUIREMENTS : -y -
V CHANGES MADE: YES NO ! !. m r // / C ~ g /d (( REVIEWElf BY SM( NUCLEAR SAFETY AND OPERATING C0FS11TTEE: ' 17 [ DISAPPROVED APPROVED AS MODIFIED BY COSS!ITTEE ' PPRO'!ED] CHAIR!W SIGNATUP: N F'. PROC r.i)CE E t.' E V i .w i U?. i, A i r. : d&P ' 18 DATE:
.3-2 o - 8C,19 20 I l
1 l At i t o:i to.w Lt. i r.o i. . zi o A i r. : . l
e* PROCEDURE ADM-5.4 REVIEW Attachment 4 CHECKIiST ' Page 1 of 1 11-25-85 PROC. NO:[)/)d/J7 CURRENT REY: / DATE: /,7-/</ -' {[ ()1 PROCEDURE TITLE: [ FOR NEW OR PER'NIC REVIEW: (3) (Y/N) Procedure format correct (ref: ADM-5.10 through 5.27 for appropriate format) Procedure references correct and current HUMAN FACTOR ITEMS No multiple actions per step Precautions and Notes precede af fected step
- Precautions and Notes do not include actions steps
- Sign off and QC Hold as required
- Second or independent verification requirements as required ALARA and personnel safety considered Procedural step progression is technically sound Commitments met by the procedure are identified as required by ADM-5.4 Reportability fot off-nornal results specified Calculation or basis for numerical inputs required and available Acceptance criteria specified and clear Walkdown or checkout made ;
I Valve position / lineup verified by operability test (if applicable) ' Incorporation of previous vendor and engineering recommendations, if appropriate Post maintenance testing requirements are included, if appropriate Verification of no vital or prot,ected area boundary degradation Verification of no EQ as Appendix R design basis degradation Foi ':H!c:';ES : ' Li:o :- re".,." of exist ire prece ur.' 'd Y Changes and location of their placenent clear Y Deletions do not remove connitted material /information I Additions clearly portray equipment, readings, data, etc. Setpoint and/or acceptance criteria changed STEP NO REFERENCE (5) IF NO Review Con lettd By: Date: De at:nenp: , (or
$. $~$$b '
( -
. M.,
- H.P.-0DCM Page 1 of 3 12-19-85 VIRGINIA POWER f NORTH ANNA POWER STATION 1
0FFSITE DOSE CALCULATION MANUAL UNITS 1 AND 2 l l 1 I
\
l l l l RECOnntNDED APPR0vit: /M&/ d APPROVED BY: 6 .Nh' Dhh- - . CHAIRMAN STATION NUCLEAR SAFETY AND OPERATING COMMITTEE DATE: 12-19-85 SA.,-Y R.tA"..) . .
- l I 1 I H.P.-0DCM l Page 2 of 3 12-19-85 I NORTH ANNA POWER STATION j OFFSITE DOSE CALCULATION MANUAL
REFERENCES:
- 1. North Ann'a Power Station Technical Specifications.
- 2. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Rev. 1, U.S. Nuclear i Regulatory Commission, October 1977.
- 3. Regulatory Guide 1.111. "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors," Rev. 1, U.S. Nuclear Regulatory Commission, July 1977.
- 4. U.S. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"
NUREG-0133, October 1978.
- 5. U.S. Nuclear Regulatory Commission, "XOQD0Q, Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," !CIREG-0324, September 1977.
- 6. U.S. Nuclear Regulatory Commission, "User's Guide to GASPAR Code,"
NUREG-0597, June 1980.
- 7. North Anna Power Station Radioactive Release Reports for 1979, 1980, and 1981.
- 8. Virginia Electric and Power Company, North Anna Power Station, Units 1 and 2, Final Safety Analysis Report.
- 9. Virginia Electric and Power Company, Applicant's Environmental Report Supplement, North Anna Power Station, Units 1 and 2, March 15, 1972.
IMPLEMENTATION: The provisions in the North Anna Offsite Dose Calculation Manual will be implemented upon approval of the North Anna Power Station Radiological Effluent Technical Specifications by the NRC.
, H.P.-0DCM Page 3 of 3 03-20-86 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL INDEX References / Implementation -Date Section No.
- 1. Introduction 12-19-85
- 2. Liquid Effluent Radiation Monitor Setpoints 12-19-85
- 3. Liquid Effluent Concentration Limit 12-19-85
- 4. Liquid Effluent Dose Limits 12-19-85
- 5. Liquid Effluent Dose Projection 12-19-85
- 6. Gascous Effluent Radiation Monitor Setpoints 12-19-85
- 7. Gaseous Effluent Release Rates 12-19-85
- 8. Noble Gas Effluent Air Dose Limits 12-19-85
- 9. Iodine - 131, Tritium, and Radionuclides in Particulate Form Gaseous Effluent Dose Limits 12-19-86
- 10. Gaseous Effluent Dose Projection 02-28-86
- 11. Total Dose 12-19-85
- 12. Semiannual Radioactive Effluent xelease Report 02-28-86
- 13. Radiological Environmental Monitoring Locations 12-19-85
- 14. Interlaboratory Comparison Program 12-19-85 Appendix A:
Section A1 - Meteorological Analysis 03-20-86 Section A2 - Liquid Pathway Analysis 03-20-86 Section A3 - Gaseous Pathway Analysis 03-20-86 Appendix B: Regulatory Guide 1.109; Revision 1, October 1977 03-20-86
.. .. .~.. ,.- .. - .. . . . . . . - . .. . . . - .. -. . . - . --
.H.P.-0DCM-A- '
Page 1 of 1 03-20-86 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL-Appendix A Section A1. Meteorological Analysis , A2. . Liquid Pathway Analysis A3. Gaseous Pathway Analysis 9 I P I i l
. . _ . = . _ _-_, . . _ . . _ - _ . . ._. . . . . . . -. .-. , . . . _ . .__
'H.P.-0DCM-B Page 1 of 1 03-20-86 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL APPENDIX B U.S. . Nuclear Regulatory Connission Regulatory Guide 1.109: CALCULATION OF ANNUAL DOSES TO MAN FROM ROUTINE RELEASES OF REACTOR EFFLUENTS FOR THE PURPOSE OF EVALUATING COMPLIANCE WITH 10 CFR PART 50, APPENDIX I 9
.4 e
o
- p. .
ADM-5.4 q C Attachment 2 NORTH ANNA POWER STATION Page 1 of 1 t'ROCEDURE ROUTI NG SL :P 11-25-85 INSTRUCTIONS: When you have enpleted the action for which this procedure was sent to you, date and initial, then forward the procedure to the next person or department. DO NOT REMOVE this routing slip. UNIT l Y 2, PROCEDURE NO. Mf- CDcm - / 0 @ SAFETY NON-SAFETY NEW PROCEDURE S REVISION DELETION REQUIRED APPROVAL DATE ) .27- f[, REQUIRED DISTRIBUTION DATE h /7-86 COMMITMENT DATE f.,2f f6 (X through the routing order if no routing required.) ORDEL TITLE INITIALS DATE ORDER TITLE INITIALS DATE
@ COGNIZANT SUPV. gg j,,g,g S UPT . - TECH. SERV.
ASST STATION MANAGER SUPT.- PROJECTS O&M ASST STATION M/d:AGER S S st. O' SUPT. - HEALTH PHYSICSAd~~
@ MANAGER, QUALITi ASSUTa':CE gjj2Mhi
/
/ S"PV. ADM. SERVICES SUPT. - OPEPATIONS SUPV - PLANNING
, SUPT. - TRAINING SUPT. - MAINTEANCE l RETURN TO COGN!ZA':T DEPARTMENT l l TFIS PROCEDURE IS BEING REC"D FROM , FORWARDED T0/FOR: PROOFING ACTION C0".PLETED l CHEC:: DATE DATE I N IT I. _ C,'-ira.: uperviser for Review / Approval
- - - ^^- . .- /Apprera; T- n- rire- T itr e
. , c. .c r t . . cntire pr<Tc..ru Caerizant Dept Proof Reading (1)
Typing Corrections (I) Co cni::an t Dept: Proef Reading (II) Typir g Corrections (IIT Cocnizant Dept: Proof Reading (III) T;. .ing Corrections (I!!) C Nnicant Dcp: Proc: ,2nding (IV) Drafting Ccgnizant Dept: Proof Reading-Drafting Stetion Records, for Processing and Distribution SPECIAL NOTES / INSTRUCTIONS: ORIGINATOR: gr/, N O
REQUEST TO CHANGE PROCEDURE ADM-S.4 NORTH ANNA POWER STATION A t t a chr,c n t 3 VIRGINIA POWER I'a u 1 o f 1 11-25-95 TO SUPERVISOR RESPONSIBLE FOR FOLLOWit;G Ph0CEDURE: 1 ABNORMAL CURVE BOOK OPERATING WELDING ADMINISTRATIVE EMERGENCY @ PERIODIC TEST ANNUNCIATOR IN-SERVICE INSPECTION HEALTH PHYSICS CALIBRATION MAINTENANCE SPECIAL TEST CHEMISTRY NON-DESTRUCTIVE TEST START-UP TEST PROCEDURE NO: 2 UNIT NO: 3 REVISION DATE: 4
)U'- CDc m - 10 /1' .L p.s -o3 - d L/
T1TLE: 64'< rn AMA R*"5 C SinTo" ct=Fsort 45C CAL Ce & # 1* /* " #7^ </ " A 4 S 644 N to I CA S<o n s & FFLu a W A)c, ss /%h M.s CHANGES REQUESTED: (GIVE STEP NUMBER. EXACT SUGGESTED WORDING AND LIST REFERENCES, STAPLE 6 COPY OF PROCEDURE WITH SUGGESTED CHANGES MARKED TO THIS FORM.) S ee A M < LJ #2.s s W &M
'I
REFERENCES:
REASON FOR CHANGES: - C,+w M f<'e % s .u sw a e m -f 4, NAs*3 2 A C u d.V d o. #- 6'r- 7 L 41,4.: . #e. T . '
/ /
4 CHANGE REQUESTED BY: 8 DATE: T Yfd C . &<m*- h /5 - /b d C' ACTION TATES: 10 DOES THIS CHANCE THE OPERATING METHODS AS DESCRIBED IN THE UFSAR? YES h DOES THIS CHANGE INVOLVE A CHANCE TO THE TECH SPECS? YES 6 DOES THIS CHANCE INVOLVE A POSSIBLE U:: REVIEWED SAFETY QUESTION? IF A: 1 "':0", NO "SAFETV ANALYS S" I S E E0'.' IRED. IF ANY "YEE", A "F YES O AFE Y ara: (F: '" !? RIC flRE*: ( i OC F';56. 5 9 ) APPFM/F* COPY TO F,F FRCVIDE'J TO LICESSINC C00F3 FOR SC Li'F :0': ' ' 'J AI. ? ? ?O R - tyco" - Pr7 ccT;eN. ~
. PPh0VED DISAPPROVED DOES THIS ?WCF.~" -
SY: ( C' 'F " Ah S,UP R\ISOR) 0A DOCD:F::-' C .
! .: DA:r- ti
\ - - . REVIEWED FOR QUAI.ITY ASSURA!fC.. REQUIREMENTS: S/3'-K l CHANGES MADE: YES 14 EY: pg 15 DATE g 16 REVIEWED BY STATION Nt. R SAFETY AND OPERATING COMMITTEE: 17 DISAPPROVED APPROVF.D AS MO3IFIED BY CO."MITTEE CHAIRMAN SIGNATUFE: N E'. PROCEDUP.I. E EV161W. DAl t.: F/ n 18 DATT: 2-2e as Ic-
' 20 AL410h L UM r u t. i t.v t,i ;
il v A 4 .. . ;.
FROCEDURF ADM-5.4 REvtru At t a c h:uen t 6 l CllTCKLIST rap 1 of 1 11-25-M PROC. NO: /,//.cx,n.io CURRENT REV: i- DATE: 0.r-0.t-en/ (l) PROCEDURE TITI.E-
"# ' '" ^ ')
.5< s M se c/.s e r er s A f s t. u a ,-i- Ao s t t', cop n w.a FOR NEW OR PERIODIC REVIEW: (3)
(Y/N) Procedure format correct (ref: ADM-5.10 through 5.27 for appropriate format) Procedure references correct and current HLY.AN FACTOR ITEMS
- No multiple actions per step
- Precautions and Notes precede affected step
- Precautions and Notes do not include actions steps
- Sign off and QC Ho'd as required Second or independent verification requirements as required A1. ARA and personnel safety considered Procedurcl step progression is technically sound Connitments net by the procedure are identified as required by ADM-5.4 Reportability for off-normal results specified
( Calculation or basis for numerical inputs required and available Acceptance criteria specified and clear Walkdown or checkout nade Valve position / lineup verified by operability test (if applicableS Incorporation of previous vendor and engineering reconnendations, if appropriate Post mainter.ance testing requirements are included, if appropriate Verification of no vital or protected area boundary degradatien Verification of no TO rn Appendix F design basir. degradatien r, r,i . ;c;c : . Y tr u t : evi n ier. of :istint pre eduto used f Chan;os and locatier, of their placement clear f Deletions do not reneve committed material /information f Additions clearly portray equipment, readings, data, etc.
#fA Setpoint and/or acceptance criteria changed STEP NO REFERENCE (5)
- IF NO Review Completed by: Date: Departnent: .oi ffgd 2 /,2 /3- 34~ //u /M . .rs N
H.P.-0DCM-10 Page 1 of 5 02-28-86 NORTH ANNA POL'ER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 10 GASEOUS EFFLUENT DOSE PROJECTIONS Part Subject Page
'l Technical Specification Requirement 2 ;
I 2 Projected Gamma Dose l 2 3 Projected Beta Dose 2 4 Projected Maximum Exposed MEMBER OF THE PUBLIC Dose , 2 5 Example 3
- - J
H.P.-0DCM-10 Page 2 of 5 02-28-86
- 1. TECHNICAL SPICIFICATION REQUIREMENT Technical Specification 3.11.2.4 requires that: "The GASEOUS MADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site to areas at or beyond the SITE BOUNDARY (see Figure 5.1-1) would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation over 31 days. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) would exceed 0.3 mrem to the critical organ over 31 days".
- 2. PROJECTED GAMMA DOSE 2.1 Determine Dg = the 31 day gamma air dose in the previous 31 day period calculated according to HP-0DCM-8.
2.2 Estimate Rg = ratio of the estimated volume of gaseous effluent in the present 31 day period to the volume released during the previous 31 day period. 2.3 Estimate Fg = ratio of the estimated noble gas effluent activity in the present 31 day period to the noble gas effluent activity during the previous 31 day period (pCi/ml). 2.4 Determine PD = projected 31 day gamma air dose S PD =D 8 8 (Rg F)g
- 3. PROJECTED BETA DOSE 3.1 Detemine D b = the 31 day gamma air dose in the previous 31 day period, calculated according to HP-0DCM-8.
3.2 Estimate R and F as in steps 2.2 and 2.3 above. 8 8 3.3 Determine PD g = projected 31 day period beta air dose PDb=Db (R g gF)
- 4. PROJECTED MAXIMUM EXPOSED MEMBER OF THE PUBLIC DOSE 4.1 Determine D = the 31 day maximum exposed MEMBER OF THE PUBLIC dose in tfe* previous 31 day period, calculated according to HP-0DCM-9.
4.2 Estimate F = ratio of the estimated activity from I-131, radio-active materials in particulate form with half-lives greater than 8 days, and tritium in the present 31 day period to the activity of
~H.P.-0DCM-10 Page 3 of 5 02-28-86 I-131, radioactive materials in particulate fo rm with half-lives greater than 8 days, and tritium in the previous 31 day . period (pCi/ml).
4.3 Dete rmine PD = projected 31 day maximum exposed MIMBER OF THE PUBLIC dose.*** PD max max ( g i} NOTE: Historical data pertaining to the volumes and radioactive concentrations of ga s'eous effluents released in connection to specific station functions, such as containment purges, shall be used in the above estimates as appropriate.
- 5. EXAMPLE 5.1 Compilation of data from release records for the process vent in a 31 day period provides the following information:
Noble Gas Radionuclide Concentration Released (pCi/ml) Xe-133 5.58E-05 Xe-135 2.00E-07 Xe-131m 6.00E-08 Xe-133m 3.41E-08 5.2 Compilation of data from release records for the ventilation vents in a 31 day period provides the following information: Noble Gas Radionuclide Concentration Released (pCi/ml) Xe-133 1.23E-06 l Xe-135 4.43E-09 i Xe-131m 1.32E-09 I Xe-133m 7.50E-10 ' 5.3 The air dose for gamma radiation is calculated according to HP-0DCM-8 from: D, = 3.17E-08 I (M gyy Qgyy + Mgpy Qgp y] The appropriate values of M gyy and M gy p are obtained from Tables j 7.0 and 7.1. 5.4 The average flow rate for a 31 day period for the process vent is 295 CFM, and for the ventilation vents 120,000 CFM, Determine the total activity in Curies released for a 31 day period:
.- - . . ----l
H.P.-0DCM-10 Page 4 of -5 02-28-86 Process Vent: Concentration Noble Gas Released IE-06 3.63E+11 Total Radionuclide (pCi/ml) x (Ci/pCi) x (ml) = Curies Released Xe-133 5.58E-05 x IE-06 x- 3.63E+11 = 2.08E+01 Xe-135 2.00E-07 x IE-06 x 3.63E+11 = 7.47E-02 Xe-131m 6.00E-08 x IE-06 x 3.63E+11 = 2.24E-02 Xe-133m 3.41E-08 x IE-06 x 3.63E+11 = 2.24E-02 Ventilation Vents: Concentration Noble Gas Released IE-06 1.52E+14 Total Radionuclide (pCi/ml) x (Ci/pCi) x (ml) = Curies Released Xe-133 1.23E-06 x IE-06 x 1.52E+14 = 1.87E+02 Xe-135 4.43E-09 x 1E-06 x 1.52E+14 = 6.73E-01 Xe-131m 1.32E-09 x IE-06 x 1.52E+14 = 2.01E-01 Xe-133m 7.50E-10 x 1E-06 x 1.52E+14 = 1.14E-01 5.5 Calculating Dg: Noble Gas M d
* (mrad-sec)
Radionuclide (mrad /yrpkEVCurie/sec) x (CbEYe) yr Xe-133 3.28E+03 x 1.87E+02 = 6.13E+05 Xe-135 1.7.9E+04 x 6.73E+01 = 1.20E+04 Xe-131m 1.45E+03 x 2.01E-01 = 2.91E+02 Xe-133m 3.04E+03 x 1.14E-01 = 3.47E+02 IM gyy Q 1yy
- = 6.26E+05 i
NoblJ 9as M 6 * (mrad-sec) Radionuclide (mrad /yrpeEVCurie/sec) x (CuSYe) yr Xe-133 4.24E+02 x 2.08E+01 = 8.82E+03 Xe-135 2.30E+03 x 7.47E-02 = 1.72E+02 Xe-131m 1.87E+02 x 2.24E-02 = 4.19E+00 Xe-133m 3.92E+02 x 1.27E-02 = 4.98E+00 IM gy p 6 gy p
= 9.00E+03 d mrad-'
Dg=3.17E-08ffe(6.26E+05"#i~,'** j
+ 9.00E03 r
l Dg = 2.01E-02 mrad
H.P.-0DCM-10 Page 5 of 5 02-28-86 5.6 Total volume of gaseous effluent released in 31 day period is: 31 day average flow 31 day average flow rate [ rate (CFM) for 4.46E+04 *i"31 day
+ (CFM) for ventilation ] x process. vent vents A and B i
Total Volume (ft ) = (295 CFM + 120,000 CFM) x 4.46E+04 3 Total Volume (ft ) = 5.37E+09 Estimated total volume in 31 day period = 4.46E+09 (ft3) Therefore, Rg = 4.46E+09 = 0.83 5.37E+09 i 5.7 The average concentration released in 31 day period.is: 31 day process vent 31 day ventilation vent [ average concentration + A and B average concentration ] (pCi/ml) (pC1/ml) Average concentration released = (5.61E-05 pCi + 1.24E-06 pCi) ml ml Average concentration released = 5.73E-05 pCi/ml. Estimated concentration to be released = 1.98E-06 pCi/ml. l 1.98E-06 = 3.46E-02 1 Therefore, Fg = 5.73E-05 1 5.8 The projected 31 day gamma air dose is: PDg = Dg (R F ) gg PDg = 2.01E-02 mrad x 0.83 x 3.46E-02 PDs = 5.77E-04 1 1 (
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ADM-5.4 NORTH ANNA POWER STATION
.g' Attachnent 2 Page 1 of 1 PROC EDl'R1 Rot'T1NG SL1P 11-25-85 INSTRUCTIONS: When you have completed the action for which this procedure was sent to you, date and initial, then forward the procedure to the next person or departraent.
DO NOT REMOVE this routing slip. UNIT /1' l- PROCEDURE NO. ,. # -- # D c e " - / A M SAFETY NON-SAFETY NEW PROCEDURE M REVISION DELETION REQUIRED APPROVAL DATEf-)f gf REQUIRED DISTRIBUTION DATE ~3 - d .Ib COMMITMENT DATE J JJ'-//. (X through the routing order if no routing required.) ORDER TITLE ISITIALS DATE ORDER TITLE ISITIALS DATE
@ COGNIZANT SUPV. g gjy.g SUPT.- TECH. SERV.
ASST STATION MANAGER SUPT.- PROJECTS O&M ASST STATION MANAGER SUPT. - HEALTH PHYSICS NSLL & /W Ub
@ liANAGER, QUALITY ASSlTaNCE f[h 7 :
% St'PV . ADM. SERVICES SUPT. - OPEPATIONS SUPV. - PLANPING SUPT. - TRAINING SUPT. - MAINTE';ANCE RETURN TO COGNIZA'iT DEPARTMENT THIS PROCEDl7,E IS BEING REQ"D FROM FORWARDED 70/FOR: _
PROOFING ACTION CO:!PLETED CHECR DATE DATE INITIAL C mizant Supervisor for Review / Approval c- "':P s' r.e i ./ App cral
~ . - ir.. Fire: ire t i:- t. ar.ent 3 if entire precedure
- ru t :c N 3 Co.:nizant Dept: Proof Reading (1)
Typing Corrections (1) Copni: ant Dept: Proof P,eading (II) Typing Corrections (II) Co s:nizan t Dept: Proof Reading (III) Ty;.inf. Cerrect ions (I!!) C c ,:n i::a n t Deptt Proof Reading (IV) - Drafting Cogni: ant Dept: Proof Reading-Drafting Station Records, for Processing and Distribution l SPECIAL NOTES /1NSTRUCTIONS: I ORIG 1NATOR: /gst7i'f4MC l l
REQUEST TO CHANGE PROCEDURE ADM-5.4 NORTH ANNA POWER STATION Attachrent 3 VIRCINIA POWER Page 1 et I ll-25-F5 TO SUPERVISOR RESPONSIBLE FOR FOLLOWING PROCEDURE: 1 ASSOD!AL CURVE BOOK OPERATING WELDING ADMINISTRATIVE EMERGENCY PERIODIC TEST ANNUNCIATOR IN-SERVICE INSPECTION 5 HEALTH PHYSICS CALIBRATION MAINTENANCE SPECIAL TEST CHEMISTRY NON-DESTRUCTIVE TEST START-UP TEST PROCEDURE No: 2 UNIT NO: 3 REVISION DATE: 4 Nt#- C'bc' arr - /.z, //A try-os ;;y T1TLE: prerry swa Prwrx s 7srs e J ern.sirr pr.ur c!s: cwcars,~ arr m .- 5 ha),es s.a - Scor*- sta a,.s. b4:a sa r;se r ys. wear & / m c te,,. .er ,cy,,c ,r m r-CHANGES REQUESTED: (GIVE STEP NUMBER, EXACT SUGGESTED WORDING, AND LIST REFERENCES, STAPLE t) COPY OF PROCEDURE WITH SUGGESTED CHANGES MARKED TO THIS FOUi.) 1.< M d ./ Aa.d cw i
REFERENCES:
1 REASON FOR CHA' GES: ~ l
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CHANGE REQUESTED BY: 8 DATE- T k r,,f h t. k cn n f ,4:7 -/3 .*,3 ACTION TAKEN: 10 DGES THIS CHANCE THE OPEFATING METHODS As DESCRIEED IN THE UFSAR? YES v DOES THIS CHANGE INVOLVE A CHA','CE TO THE TEC1!. SPECS? Y F.S
- POES THIS CHANCE INVOLVE A POSSIBLE UNEEVIE'.s'ED SAFETY QUESTION?
IF A:' "gr,", no "gryr "< ; y3; g" i s p gn.j p r-YES 7 7 Ag , "ygge , A "gAyg;y ..: ec- "c tr, r~
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""CLEAR S AFETY AND 0,FEFATING COFDi1TTEE. 4, AF ROVED plSAPPROVED APPROVF.D AS M0?IFIED BY COPMITTEE CHAIRMAN SIGNATUPE:
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.A PROCEDURE ADM-5.4 REVIEW A t t a c hmer.t 4 CitECKLIST Pop 1 of I 11-05-85 PROC. NO: p// cocm-s t CURRENT REY: v' DATE: #f-o3-BV (1)
" # '## ~ '" # # ' #" ' #' * " N '- 4 *- (2)
PROCEDURE TITLE: # # SFm- wwa L (EA's , a e ris $ AFF w ar~ M w sc DmT S<. n .a a!
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FOR NEW OR PERIODIC REVIEW: (3)-
.(Y/N)
Procedure format correct (ref: ADM-5.10 through 5.27 f or appropriate f ormat) Procedure references correct and current HUMAN FACTOR ITEMS
- No multiple actions per step Precautions and Notes precede affected step Precautions and Notes do not include actions steps Sign off and QC Hold as required Second or independent verification requirements as required ALARA and personnel safety considered Procedurcl step progression is technical 3y sound Con =itments net by the procedure are identified as required by AD.M-5.4 Reportability f or of f-norr.al results specified
( Calculation or basis for numerical inputs required and available Acceptance criteria specified and clear Walkdovn or checkout made Valve position / lineup verified by operability test (if applicable) Incorporation of previous vendor and engineering recommendations, if appropriate Post maintenance testing requirenents are included, if appropriate Verification of no vital or protected area boundary degradatien Vc rification of no E0 ar. Appendi: K design basic degradation y, egy. cgg: , V t r. - revisier. o f .:ist ir r pro:+ dura used f Changes and locatien of their placement clear f' Deletions de not reneve committed material /information l 8 Additions clearly portray equipment, readings, data, etc. 1 654, , Setroint and/or acceptance criteria changed . I STEP NO REFERENCE (5) !
' IF NO '
l I Review Com Acted By: Date: Department: .es l hn (l $. / 2 ~/3 - l'Y /&/4 /%,wis
H.P.-0DCM-12 Page 1 of 2 02-28-86 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 12 Semiannual Radioactive Efflu'ent Release Report Dose Assessment Part Subject M 1 Technical Specification Requirement 2 2 Dose Assessment 2
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. 1 H.P.-0DCM-12 Page 2 of 2 02-28-86 l
- 1. TECHNICAL SPECIFICATION REQUIREMENT.
Technical Specification 6.9.1.9 requires that the Semiannual Radioactive Release Report submitted within 60 days af ter January 1 of ) each year include, in part, an assessment of the radiation doses to ; individuals due to the radioactive liquid and gaseous effluents from the station during the previous calendar year, and assessment of the radiation doses to the maximum exposed MEMBER OF THE PUBLIC from' reactor releases and radiation.
- 2. DOSE ASSESSMENT .
- 1. The radiation doses to individuals due to the radioactive liquid and gaseous effluents from the station during the previous calendar year shall be calculated using the methodology presented in this Manual or in Regulatory Guide 1.109 (Revision 1), October 1977, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I" (see Appendix B). Population doses are not to be included in the dose assessment.
- 2. The dose to the maximum exposed MEMBER OF THE PUBLIC due to the radioactive liquid and gaseous effluents from the station shall be incorporated with the dose assessment performed above. If the dose.
to the maximum exposed MEMBER OF THE PUBLIC exceeds twice the limits of Specifation 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, the dos'e assessment shall include the contribution from direct radiation. U.S. Nuclear. Regulatory Commission NUREG-0543, February 1980, "Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40CFR Part 190)", states "There is reasonable assurance that sites with up to four operating reactors that have releases within Appendix I design objective values are also in conformance with the EPA Uranium Fuel Cycle Standard, 40CFR Part 190".
- 3. The meteorological conditions during the previous calendar year or historical annual average atmospheric dispersion conditions shall be used for determining the gaseous pathway doses.
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A Page 7 t ATTACHMENT 4-
-(1/86 - 6/86); o REVISIONS T0' PROCESS CONTROL PROGRAM (PCP) i As required by Techr':51 Specification 6.14, revisions to
-to the' PCP for the time period covered'by this report are synopsized .
below. Supporting documentation and affected.pages of the PCP are attached. No revisions to the PCP were required for the time period covered by this report.
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- Page 8 ATTACHMENT 5
- (1/86 - 6/86)
MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASE0US,-AND SOLID-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. I i J l l
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, .' s ATTACHMENT _6'-
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RADI0 ACTIVE LIQUID AND Gl.SEOUS~ EFFLUENT MONITORING INSTRUMENTATION IN0PERABLE: r
'No radioactive effluent monitors'were declared inoperable, as defined according to the criteria presented.in Technical Specification ;.J.3.10.b and 3.3.3.11.b, for the time period covered by this report, P
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Page 10 ATTACHMENT 7 (1/86 - 6/86) 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 report. l}}