ML20217P998
| ML20217P998 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/28/1997 |
| From: | Clark J, Krieger R SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13319A870 | List: |
| References | |
| PROC-970528, NUDOCS 9805070173 | |
| Download: ML20217P998 (209) | |
Text
UNITS 2/3 OFFSITE DOSE CALCULATION MANUAL REVISION 30 SAFETY EVALUATION l EFFLUENT MONITORING INSTRUMENTATION - CHANNEL FUNCTIONAL TEST l
(
gpproved by: James [ Winslow 6 3hh Date
( Statior) Technical S~ ' Ib ' 17 eviewe by: James Beece Date Maintenance h h/ ) Y'?
Reviewecfay: Daryl Dick ' Da'te Effluent Engineering I I$Y > ^ff?ofW Repwed by: Catdy Yhip ' Ddte P&E/ Licensing
- B P P d R P3 4 *J o 6 R PDR
l UNITS 2/3 OFFSITE DOSE CALCULATION MANUAL REVISION 30 SAFETY EVALUATION EFFLUENT MONITORING INSTRUMENTATION - CHANNEL FUNCTIONAL TEST Introduction Criterion 60 of Appendix A to 10CFR50 requires licensees to control radioactive releases to the environment. To implement this regulation, NUREG-1301 "Offsite Dose j
Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors", dated 4/91, and prior revisions of San Onofre's Radiological Effluent Technical Specifications (RETS) stipulate testing requirements for radiation monitors !
and their associated equipment. For all liquid and certain (batch) Urborne release {
points, the ability of the radiation monitor on the discharge path to automatically !
terminate the release prior to exceeding the limits of 10CFR20 is one of the mechanisms for controlling radioactive effluents. ,
1 Tables 4-2 and 4-4 of the Units 2/3 Offsite Dose Calculation Manual (ODCM) provide a i detailed listing of the monitors and their associated equipment, define the necessary ;
testing, and establish the frequency at which those tests must be performed. One of those tests to demonstrate that the radiation monitor is capable of performing its design !
function is the channel functional test (CFT). Channel functional tests are required to i be performed once a quarter and are used to verify that the automatic termination !
function will occur and that the control room is notified under specific conditions. j This revision of the ODCM will modify the channel functional test so that the effluent path isolation signal is verified once per quarter and the effluent path isolation closure i is verified once per refueling period. Downscale testing is also being eliminated as a test condition due to the design of the radiation monitors at San Onofre.
j Discussion i Note 1 to Table 4.3-8 and 4.3-9 of NUREG 1301 states:
The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation occur if any of the following conditions exists:
- a. Instrument indicates measured levels above the Alarm / Trip setpoint, or
- b. Circuit failure, or
- c. Instrument indicates a downscale failure, or
- d. Instrument controls are not set in operate mcde.
Safety Evaluation: Effluent Monitoring instrumentation - Channel Functional Test Page 2 of 8
Note 1 to Tables 4-2 and 4-4 of the Units 2/3 ODCM rev 29 states: ,
The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation closure and control room alarm annunciation if any of the following conditions exist:#
- a. Instrument indicates measured levels above the alarm / trip setpoint
- b. Circuit failure
- c. Instrument indicates a downscale failure.
- If the instrument controls are not set in the operate mode, procedures shall call for declaring the channelinoperable.
The following changes are being made:
- 1. Note 1 to Tables 4-2 and 4-4 is revised to reduce the frequency of verification of effluent path isolation closure to once per refueling interval. Concurrent with that change, effluent path isolation signals will be required once per quarter as part of the Chhnnel Functional Test.
l Testing of the effluent path isolation sianalinstead of the effluent path isolation closure once per quarter will result in everything up to the actual isolation valve being tested at the recommended frequency. As such, the change to a refueling j interval surveillance period only applies to the actuated components and not to !
the initiating device.
{
A review of maintenance orders using the San Onofre Maintenance Management System (SOMMS) from 1983 to 1997 was performed for the following release points:
RELEASE POINT MONITOR ISOLATION VA'LVE Liquid Radwaste Effluent Line 2/3RT7813 2/3 HV4642 Blowdown Neutralization Sump / Full 2(3)RT7817 2(3) HV3773 ,
Flow Condensate Polisher Effluent Line I Turbine Plant Sump Effluent Line 2(3)RT7821 2(3) HV5849 Steam Generator Blowdown Bypass 2(3)RT6753 2(3) TV4090 Effluent Line 2(3)RT6759 Waste Gas Discharge Header 2/3RT7808 2/3 HV7202 2(3)RT7865*
Containment Purge 2(3)RT7828 2(3) HV9948 2(3)RT7865** 2(3) HV9951 2(3) HV9821 2(3) HV9825 when aligned to the Plant Vent Stack when aligned to Containment Purge Safety Evaluation: Effluent Monttoring Instrumentation Channet Functional Test Page 3 of 8
r This review demonstrated that, excluding startup problems (circa 1983) with 2(3)HV3773, there have been no failures of the support system actuation by radiation monitoring instrumentation. The most probable modes of failure for the valves in the system is either a loss of air to valve actuator, or, a loss of electrical power to the instrument controlling the actuated component. In response to these modes of failure, the actuated device will fail in its closed or deenergized position, isolating the effluent pathway. The maintenance history for these valves show that the system has proven to be highly reliable with no failures of the actuation logic or actuated components that could compromise their ability to perform their ODCM effluent isolation function.
Technical Specification 3.6.3 requires the 42" containment isolation valves to be ;
sealed closed in Modes 1-4 (SR 3.6.3.1). This prevents any testing of the valves during these modes of operation. The valves are Local Leak Rate Tested (LLRT) and locked closed after refueling. As such, they are not a credible release path during normal 1-4 modes of operation. This change now requires the Main Purge valves be tested for verification of effluent path isolation / closure by the respective monitors (2(3)RT7828 and 2(3)RT7865] on a once per refueling interval prior to performirig initial reactor core alterations. This change clarifies that the mini purge valves need only be tested for verification of effluent path isolation / closure by the respective monitors (2(3)RT7828 and 2(3)RT7865] on a once per refueling interval. No additional purge valve testing is required for mid-cycle outage purge operation. It should also be noted that these valves are tested once per refueling interval as part of the Engineered Safety Feature Actuation System (ESFAS) based on the " Application of Reliability Centered Maintenance for Surveillance l Interval Extension, San Onofre Nuclear Generating Station, Units 2 and 3" as presented at the June 1990 American Nuclear Society Annual Meeting.
l Testing the automatic termination function of the radiation monitors is performed '
consistent with the guidance of IEEE 279 " Criteria for Protection Systems for i Nuclear Power Generating Stations" (1971). Verification of effluent path isolation l once per refueling outage is acceptable given the established performance of the radiation monitors and their associated plant components.
- 2. The requirement for verifying effluent path isolation closure and annunciation in the control room whenever the instrument indicates a downscale failure is being deleted due to the design limitations of the monitors and administrative controls.
Downscale failure is properly defined as the loss of indication due to a high radiation condition at the detector. There are currently three manufacturers of radiation monitors at SONGS: NMC, Victoreen, and Sorrento Electronics. None of I
the radiation monitors at San Onofre lose indication during high radiation conditions due to different design features and administrative controls. The specifics are discussed below by manufacturer:
Safety Evaluawn: Effluent Monitoring Instrumentauon - Channel Functional Test Page 4 of 8
}
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Three of the liquid radiation monitors [2/3RT7813,2(3)RT7817, and 2(3)RT7821]
and the monitor on the common Plant Vent Stack (2/3RT7808) were manufactured by NMC. (The air ejector monitor,2(3)RT7818 is also an NMC monitor but does not have an automatic termination function.) During linearity testing in 1990, it was identified that no downscale failure tendency occurred at count rates of up to 1E8 cpm. Since the monitors exhibited non-linearity above 1E6 cpm, an administrative limit was implemented to restrict setpoints to 1E6 cpm. Non-Conformance Report (NCR) 2-2349 documents this problem and provides administrative limits of 1E6 cpm for all NMC radiation monitor alarm setpoints.
Testing conducted in conjunction with NCR 2-2349 has shown that the monitors have linear response and the monitor will not be saturated at this level. Testing of the alarm at the ODCM setpoint, never set above 1E6 cpm, satisfies the downscale failure requirements.
There are two Victoreen monitors,2(3)RT6753 and 2(3)RT6759, both on the steam generator blowdown bypass. Calculation J-SPA-129 specified the Technical Specification limit steam generator blowdown concentration to be 8.32E-2 pCi/ml, assuming 1% failed fuel. The range of these monitors is 1E-6 pCi/ml to 1E-1 pCi/mi and the response is linear over the entire range of the instrument indication. The monitor does not exhibit downscale failure within the indicating range of the instrument. Within the Technical Specification leakage constraints, these monitors are capable of adequately monitoring steam generator activity and performing any required isolation functions. Should plant conditions ever deteriorate to accident levels, Main Steam isolation Signal (MSIS) would activate safe shutdown actions. One such action is the isolation of steam generator blowdown, whether through the flash tank or through the bypass. The condenser air ejector radmonitor,2(3)RT7870 is relied upon to give early warning of a steam generator tube leak before any ESFAS actuation would occur. These monitors have installed setpoints sufficiently low to insure a release to the outfall, would be terminated prior to the monitor failing from excessive radiation. Removal of the " Instrument indicates a downscale failure" from the table notation, only provides clarification of the actual testing performed on the monitors.
The Sorrento Electronics Wide Range Gas Monitors (2(3)RT7865] have multiple channels which provide for detection, alarm, and actuation at concentrations up to 1ES pCi/cc. These monitors are used for three effluent release points: plant vent stack, waste gas decay tanks (batch releases), and containment purges (batch releases). The automatic termination function is only required when the monitors are used for either the waste gas decay tank releases or containment purge. The monitors are designed to cover the range of credible source terms considered in NUREG-0737 and Regulatory Guide 1.97. The existence of a source term above 1ES pCi/cc concentration is not considered credible and therefore downscale >
failure response was not required for these monitors.
Safety Evaluation: Emuent Monstonng instrunientation Channel Functional Test Page 5 of 8
The other radiation monitors used for containment purge (2(3)RT7828] are also Sorrento Electronics. These monitors will detect, alarm, and provide actuation at radiation levels approximately 2 decades greater than its indicating range.
2(3)RT7828 was not designed for use under accident conditions; those conditions prompted the installation of 2(3)RT7865. The ODCM setpoint, used to ensure compliance with the limits of 10CFR20, is always on scale (less than 1E-1 pCi/cc).
These monitors were factory tested for downscale failure and do not exhibit this phenomenon below 1E-1 pCi/cc. Calculation J-SPA-059 noted that the containment airborne concentration for a 1% failed fuel and a 1 gpm RCS leak to be 2.14E-2 Ci/cc. This value is below the tested level for downscale failure.
Therefore, the conclusion can be made that for normal operation and any anticipated operational occurrence, 2(3)RT7828 will adequately monitor the containment atmosphere and perform all its required termination functions. For releases under accident conditions 2(3)RT7865 is used. Testing of the monitors at the ODCM setpoint satisfies the downscale failure requirements.
Conclusion l
This revision of the ODCM will change the required frequency for verifying that the effluent path is isolated from once per quarter to once per refueling interval based on reliability-centered maintenance. Verification that the signal to isolate the effluent path 3 is generated will continue to be performed once per quarter. Additionally, one of the 1 testing conditions, downscale failure, is being deleted due to design limitations of the radiation monitors at SONGS. Administrative controls have been successfully implemented since 1990 to compensate for the design limitations. Given the proven ;
performance of the instrumentation and administrative controls, the proposed changes do not constitute an unreviewed safety question nor will they adversely affect the health and safety of the public.
- 1. May the proposed activity increase the probability of occurrence of an accident evaluated previously in the safety analysis report?
Response: No.
The liquid system radiation monitors provide an automatic signal for the isolation of its respective system, as listed earlier in this evaluation. All systems are provided for isolation closure in the unlikely event of an ODCM limit challengirg inadvertent release. The isolation valves themselves are not credited in the UFSAR accident analyses for ODCM functions. They are not credible initiators of any accident therefore the proposed activity cannot increase the probability of-occurrence of an accident evaluated previously in the safety analysis report. )
Safety Evaluation: Effluent Monitoring instrumentation . Channel Functional Test Page 6 of 8
2/3RT7808 and 2(3)RT7865 provide an automatic signal for the isolation of the waste gas header isolation valve 2/3HV7202. 2(3)RT7828 and 2(3)RT7865 provide an automatic signal for the isolation of the air operated, outside containment purge valves. All systems are provided for isolation closure in the l unlikely event of an ODCM limit challenging, inadvertent release. The j Conts ament Purge Isolation System (CPIS) is credited in the UFSAR chapter 15 accident analysis. The CPIS system is actuated by Safety Related radiation j monitors 2(3)RT7804 and 2(3)RT7807, which are physically separate and I electrically isolated from the Containment Purge External Air Operated valve actuation functions of the ODCM monitors 2(3)RT7828 and 2(3)RT7865. The i ODCM isolation functions are not credited in the UFSAR accident analysis. They are not credible initiators of any accident therefore the proposed activity cannot increase the probability of occurrence of an accident evaluated previously in the safety analysis report.
- 2. May the proposed activity increase the conse quences of an accident evaluated previously in the safety analysis report?
Response: No.
Neither the monitors or isolation valves referenced earlier in this evaluation are credited in any postulated UFSAR chapter 15 accident. Therefore this activity cannot increase the radiological consequences of an accident evaluated previously in the safety analysis report. )
- 3. May the proposed activity increase the probability of occurrence of a malfunction of equipment important to safety evaluated previously in the safety analysis report?
Response: No. !
The failure modes of the monitors and their isolation functions are bounded by the safety analysis reports and are independent systems. The ODCM actuation /
isolation function is important to safety, but the failure of each Individual system is bounded by the UFSAR. The non-safety related portions of the monitors are physically separated and electrically isolated from other equipment. Therefore i this activity cannot increase the probability of a malfunction of equipment important to safety evaluated previously in the safety analysis report. l i
Safety Evaluation: Effluent Monitoring instrumentation - Channel Functional Test Page 7 of 8
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- 4. May the proposed activity increase the consequence of a malfunction of ,
equipment important to safety evaluated previously in the safety analysis report?
Response: No.
The failure modes of the monitors and their isolation functions are bounded by the !
I safety analysis reports and are independent systems. Therefore this activity cannot increase the consequence of a malfunction of equipment important to I safety evaluated previously in the safety analysis report. l S. May the proposed activity create the possibility of an accident of a different type ,
than any evaluated previously in the safety analysis report? 3
)
Response: No.
t The radiation monitors and their respective isolation functions are not modified by l this activity and therefore can not create the possibility of an accident of a different I type than any evaluated previously in the safety analysis report.
- 6. May the proposed activity create the possibility of a malfunction of equipment important to safety of a different type than any evaluated previously in the safety analysis report?
Response: No.
The radiation monitors and their respective isolation functions are not modified by this activity. The failure modes of the equipment is bounded by the safety analysis reports and as independent instruments cannot create the possibility of a malfunction of equipment important to safety of a different type than any evaluated previously in the safety analysis report.
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Safety Evaluation: Effluent Monitonng Instrumentation - Channel Functonal Test Page 8 of 8
May 28,1997
SUBJECT:
(
Units 2/3 OFFSITE DOSE CALCULATION n \
Incorporated into this revision e n are 1) chang anual(ODCM).
Use Censuses, 2) changed various. calibration 95 and 1996 Landconstants and deleted two gas and requirements for downscale failure, and n enance item Environmental Protection's Annual Report. ased on No safety evaluations were performed for implementing ch 1996 Land Use Census (LUC). These changes reflect result fan as such do not constitute a modification in methodology for deter released from the site and subsequent u n dose ng activityto a member o dataLUC 1995 washave not been ableincorporated.
to be included.
The into LUC r, any for changes revision
- c. The 1995 LUC 1996 due cor to the 29 Howe X/Q and D/O values.
rected several distances and DCP 6926; 2(3)RT-7818B. ,o On r the e on-going work ofyear, cali resulted in slight changes to the calibration constants The new v1I ues are listed.
isolation closure surveillance. The system or performing system isolat demonstrating downscale failure was for deleted d o, the requirement controls. An approved safety evaluation covering both items has bo change.
een provided for this Section 5, Table 5-2 " Reporting Levels for Radioactivity Co Environmental Samples" and Table ncentrations 5-3 " Detection in Capabilities f Sample Analysis"were changed slightly toor make them mor Environmental 1301. These changes include makingr- LLD for Ba-140 and Z 95e c more restrictive. The concurrence.
their June P.K Chang. 7,1996 Guidance memo " Revision of from Tables roup Health ro ection's for is Environ provided in Physics a mental Sample Analyses"to t Section 1.4 has been re-formatted and edited. One blank pa ge is being deleted.
fccilitate dispensation ofinformation. o etter Pages with containing change bars, do not force a new page revision e ype changes, while correction of typographical errors. Par NRC Generic letter 89 u re or performed for the 1 of 8 RECEIVED 0DM MAY Z 81997 SlTEFILECOPY
v Revised page numbers of the tables due to reformatting sections 1 and 2.
This is an administrative change.
1-5 Deleted outdated Technical Specification references.
1-6 Deleted outdated Technical Specification references. l i
1 -8
- Reformatted Section 1 from this page onward. One blank page was )
thru removed and sections were reformatted changing the total number of i 1-26 pages.
1 -8
- Added note describing relationship between F and R and moved three paragraphs from page 1-9 here.
1 -9
- Revised section on administrative factors and added an explanation of their i use. Also removed phrase suggesting CCW heat exchanger releases through the SWC system. This is not a credited release point. Also one paragraph was moved here from page 1-8.
1-10* corrected a typographical error and moved one paragraph off this page onto page 1-9. These are administrative changes. j 1-11
- Converted the previous step 3 into steps 3 and 4 since two distinct actions were described. Reformatted definition under equation 1-4.
1-12* Corrected typographical error on name of admin factor for RW and reformatted the listing of pump flow rates.
1-13* Revised the note (which had been on page 1-14) making it more generic and removing specific component numbers, as Operations uses the instruments in their procedures. Also moved the paragraph discussing admin factors to a different page. Also reformatted two definitions.
1-14
- Moved the note to page 1-13 and deleted the first paragraph on administrative factors which is explained if fuller detail now elsewhere in section 1. This page is intentionally left blank.
1-15* Moved note to this page and revised it making it more generic and removing specific component numbers, as Operations uses the instruments in their procedures Also deleted paragraph discussing admin factors which was moved to a different page and added some definitions under equation 1-8.
1-16* Added " weekly" in definition of C, as tritium composites are typically analyzed weekly for continuous release. Moved definitions to this page from page 1-17.
1-17* Added definitions under equation 1-10. Moved step 3 here from page 1-18 and created step 4 out the previous step 3. Definitions for equation 1-9 were moved to page 1-16.
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1-18* Moved step 3 to page 1-17. This page left intentionally blank.
1-19* Moved and revised the note (from page 1-20) making it more generic and removing specific component numbers, as Operations uses the instruments in their procedures. Also moved paragraph discussing admin to a different page. Added definitions under equations 1-11 and 1-12.
1-20* Moved note to page 1-19. This page then left intentionally blank.
1-21
- Expanded definitions under equations 1-13 thru 1-16.
1-22
- Revised the note making it more generic and removing specific component numbers, as Operations uses the instruments in their procedures. Also moved paragraph discussing admin factors to a different page. Some l definitions from equations 1-13 through 1-16 were expanded and put on this page.
1-23* Revised the note making it more generic and removing specific component f numbers, as Operations uses the instruments in their procedures, Also added and expanded definitions under equations 1-17 and 1-18.
1-24
- The paragraph describing administrative factors and the note were both moved from this page and placed elsewhere in this section. This is an i administrative change and did not warrant a page revision.
.The old page 1-25 was blank and has been removed from the ODCM.
1-25 Changed calibration constants for various monitors.
2-4 Corrected a typographical error by adding Cs-137 to footnote g.
2-5 Deleted outdated Technical Specification references.
2-6 Deleted outdated Technical Specification references.
2-7 Deleted outdated Technical Specification references.
2-19* Corrected typographical error in equation 2-7a.
2-20* Corrected typographical error on definition of A..
2-22* Corrected typographical error.in definition of A_ under equation 2-8.
2-24 Deleted 2 and 3 RT-78188 from the table as these two channels have been removed from the air ejector system.
2-26 Modified definition of X/Q (under equations 2-11 and 2-12) to include the '
addition of the South Yard Facility monitors.
2-27 Modified definitions of Wu (under equation 2-13) to include the addition of the South Yard Facility monitors.
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l 2-28 Modified definition of X/O (under equations 2-14 and 2-15) to include the addition of the South Yard Facility monitors.
2-30 Modified definitions of LR.W and R. (under equation 2-18) to include the addition of the South Yard Facility monitors.
2-31 Modified definitions of X/Q and D/Q under "Wu" (under equation 2-18) to account for the addition of the South Yard Facility monitors.
2-32 Modified definition of R., (under equation 2-19) to include the addition of the South Yard Facility monitors.
2-35 6 Three locations and CLF values for all locations were changed as a result of the 1995 and 1996 Land Use Census.
2-36 6 Sector P-Surf Beach / Life Guard occupancy factor was increased from 667 hrs to 2000 hrs. X/Q, D/Q, and distance were changed. Also, all R, values except infant were changed.
6 2-37 Sector P-Cotton Point Estates with Garden X/O and D/Q values were chanced Per LUC.
2-38
- Changed "51 Area Beach check-in" from sector Q to sector P due to more accurate mapping during the 1996 LUC. Changed X/Q and D/Q. R, values and distance remained the same.
6 2-39 Sector Q: Name changed from "51 Area Beach Trailers" to " Rec Building Staff". Distance, X/Q, D/Q, and R, values were changed.
2-40 6 Sector Q-San Onofre Mobile Homes: Changed the distance, X/Q and D/Q.
R, values remained the same.
2-41* Sector Q-State Park Office Trailer: Changed X/Q and D/Q. R, values remained the same 6
2-42 Sector Q-Surf Beach / Guard Shack: Changed X/Q and D/Q and child and ;
teen inhalation values.
2-43* Sector Q-51 Area Beach / Campground: Changed X/Q and D/Q and distance. R, values remained the same 2-44 6 Sector Q: This page was left blank as there are no longer any sheep grazing at this location.
2-4 56 Sector Q: The garden at location " San Clemente Resident" has been eliminated. As a result, R i values were changed. Distance, X/Q, and D/Q were also changed .
2-46
- Sector Q-San Clemente Ranch (No Residents): Changed X/Q and D/Q. Ri values remained the same.
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2-47 6 Sector Q-San Clemente Ranch Adm Offices: Changed the distance and Adult food and ground pathway per the LUC. The garden fraction was deleted in the LUC.
6 2-48 Sector R-San Onofre Mobile Homes: Changed distance, X/Q and D/Q. R i.
values remained the same.
2-49
- Sector R-San Clemente Ranch (No Residents): Changed X/Q and D/Q. R i values remained the same.
2-50 6 Sector R-SC Ranch Packing: Changed D/Q. R, values were changed due to the occupancy factor being increased. The name was changed to reflect no residents at this location.
b 2-51 Sector R This page was left blank as there are no longer any sheep grazing at this location.
2-52 b Sector R: This page was left blank as there is no longer deer hunting at this location 6
2-53 Sector A- Camp San Mateo: Changed X/Q per the LUC.
b 2-54 Sector A: This page was left blank as there are no longer any sheep i
~9 zing at this location i 2-55* Sector A- Deer Consumer / Hunter: Changed X/Q, D/Q and distance per the LUC. R ivalues remained unchanged b
2-56 - Sector B: This page was left blank as there is no longer any sheep grazing at this location 2 676 Sector B- Deer Consumer / Hunter: Changed X/Q, D/Q and distance per the LUC. R, values remained unchanged 2-58 6 Sector B- Sanitary Landfill: Changed X/Q and D/O per the LUC. R, values remained unchanged '
2-59 6 Sector C- Camp San Onofre: Changed X/Q and D/Q per the LUC. R, values remained unchanged 6
2-60 Sector C- Camp San Onofre Fire Station: Changed X/Q, D/Q and distance per the LUC. R, values remained unchanged 6
2-61 Sector C- Sewage Facility: Changed X/O per the LUC.
6 2-62 Sector C This page was left blank as there is no longer any sheep grazing at this location 4
6 2-63 Sector C- Deer Consumer / Hunter: Changed X/Q and D/Q per the LUC. Ri values remained unchanged 6 of 8
b 2-64 Sector D- Camp San Onofre: Changed X/Q, D/Q and distance per the LUC.
Ri values remained unchanged 2-65* Sector D: This page was left blank as there is no longer any sheep grazing at this location 2-66* Sector D- Deer Consumer / Hunter: Changed X/Q, D/Q and distance per the LUC. R ivalues remained unchanged 2-67
- Sector E- Camp Horno: Changed X/Q, D/O and distance per the LUC. R i values remained unchanged b
2-68 Sector E- Sheep (Meat)/ Shepherd: Changed X/Q, D/O and distance per the LUC. R, values remained unchanged b
2-69 Sector E- Deer Consumer / Hunter: Changed X/Q, D/Q and distance per the LUC. R ivalues remained unchanged j 2-70
- Sector F- San Onofre State Park / Guard Shack: Changed X/O and D/Q per the LUC. R, values remained unchanged 2-71
- Sector F ' der Patrol Checkpoint: Changed X/Q and D/Q per the LUC.
Ri values nained unchanged b
2-72 Sector F- Sheep (Meat)/ Shepherd: Changed X/0, D/Q and distance per the LUC. R, values remained unchanged 2-73 b Sector F- Deer Consumer / Hunter: Changed X/Q, D/Q and distance per the LUC. R ivalues remained unchanged 2-74 6 Sector G- San Onofre State Beach Campground: The occupancy factor for the adult was increased from 2000 hrs /yr to 8760 hrs /yr. As a result, Ri l values were changed. Distance, XIQ and D/Q were changed.
2-756 Sector G- Highway Patrol Weigh Station: Changed X/O and D/O per the LUC. R, values remained unchanged 2-76
- Sector G: This page was left blank as there is no longer any sheep grazing at this location 2-77 6 Sector G: This page was left blank as there is no longer any deer hunting in this area.
d 4-5 Revised CFT testing on path isolation verification and downscale failure.
Relocated footnote into approprate table note.
d 4-14 Revised CFT testing on path isolation verification and downscale failure.
Relocated footnote into approprate table note.
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1 4-15 d New page added to handle the carryover from page 4-14 due to additions to l that page. Corrected typographical error and moved the footnote to previous page. These are both administrative changes.
4-16 d Page numbers increased by one to account for the added page 4-15.
thru 4-19 5-1 Deleted outdated Technical Specification references 5-2 Deleted outdated Technical Specification references. ;
5-7 6 Table 5-2 was revised to account for there not being a drinking water pathway at the site. The footnotes were made to reflect NUREG-1301. ,
Corrected the name of Zr-95 and Ba-140.
5-8 6 lodine footnote was changed from "b" to "d". Ba-140 and Zr-95 LLDs were !
changed to more restrictive values. Also the footnotes were moved to page 5-10.
l 5-9 The last paragraph on footnote on LLD were moved to this page from page j 5-10. Alc. mleted reference (3) as it is no longer applicable.
5-10 6 Moved revised footnotes "b" and "d" to this page from page 5-8. The notes were changed to reflect NUREG-1301. Added footnote "d". Moved the top paragraph to page 5-9 as well as the footnotes for LLD.
5-11 Deleted outdated Technical Specification references. i 6
5-19 Revised the location of the Oceanside " Control", local crop #2, as the exact location will vary depending on where the sample is obtained. A footnote is also added to explain this. Deleted drinking water locations 1 (Tri-Cities Municipal Water District Reservoir) and 2 (San Clemente golf Course Well).
Added drinking water location 4. The two remaining drinking water locations are the Control location and the closest location.
5-20 6 Modified distance of non-migratory marine animals at the Units 2 and 3 outfall from 1.7 miles to 1.5 miles.
6-9 Deleted outdated Technical Specification references.
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0FFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION UNITS 2 AND 3 i
i RECEIVEDCDM S023-00CM Revision 30 MAY 2 81997 05-28-97 SITERLECOPY
ODCM l TABLE OF CONTENTS Paae l LIST OF FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . iv LIST OF TABLES ........................... v-vi i
INTRODUCTION ............................ vii l
1.0 LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . 1-1 thru l-29 lF 1.1 Concentration . . . . . . . . . . . . . . . . . . . . . . . 1-1 i 1.1.1 Specification . . . . . . . . . . . . . . . . . . . 1-1 1.1.1.1, 1.1.1.2 Surveillances .............. 1-1 1.2 Dose ........................... 1-5 1.2.1 Specification . . . . . . . . . . . . . . . . . . . 1-5 1.2.1.1 Surveillance ................... 1-5 j 1.3 Liquid Waste Treatment .................. 1-6 1.3.1 Specification . . . . . . . . . . . . . . . . . . . 1-6 1.3.1.1, 1.3.1.2, 1.3.1.3 Surveillances . . . . . . . . . . 1-6 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation . . 1-8 Q, 1.4.1 Batch Release Setpoint Determination . . . . . . 1-10 1.4.2 Continuous Release Setpoint Determination . . . . 1-16 l 1.5 Dose Calculations for Liquid Effluents . . . . . . . . . 1-26 F
1.6 Representative Sampling . . . . . . . . . . . . . . . . . 1-29 i 2.0 GASE0US EFFLUENTS ....................... 2-1 thru 2-91 [F 2.1 Dose Rate . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 1
2.1.1 Specification . . . . . . . . . . . . . . . . . . . . 2-1 2.1.1.1, 2.1.1.2 Surveillances .............. 2-1 2.2 Dose - Noble Gas ..................... 2-5 2.2.1 Specification ................... 2-5 2.2.1.1 Surveillance ................... 2-5 2.3 Dose - Radiciodines, Radioactive Materials in Particulate Form and Tritium ..................... 2-6 2.3.1 Specification ................... 2-6 2.3.1.1 Surveillance ................... 2-6 r
5023-0DCM l Revision 30 l 1 05-28-97 !
1 l
ODCM TABLE OF CONTENTS (Continued)
Pace 2.4 Gaseous Radwaste Treatment ................ 2-7 2.4.1 Specification . . . . . . . . . . . . . . . . . . . . 2-7 2.4.1.1 Surveillance ................... 2-7 2.4.1.2, 2.4.1.3 Surveillances .............. 2-8 2.5 Total Dose ........................ 2-9 2.5.1 Specification . . . . . . . . . . . . . . . . . . . . 2-9 2.5.1.1 Surveillance ................... 2-9 2.6 Gaseous Effluent Monitor Setpoints ............ 2-11 2.6.1 Plant Stack . . . . . . . . . . . . . . . . . . . . 2-11 2.6.2 Condenser Evacuation System . . . . . . . . . . . . 2-15 2.6.3 Contai nment Purge . . . . . . . . . . . . . . . . . 2-18 2.6.4 Waste Gas Header ................. 2-21 2.7 Gaseous Effluent Dose Rate ................ 2-25 2.7.1 Nobl e Ga s es . . . . . . . . . . . . . . . . . . . . 2-25 2.7.2 Radiciodines and Particulates . . . . . . . . . . . 2-26 2.8 Gaseous Effluent Dose Calculation . . . . . . . . . . . . . 2-28 2.8.1 Nobl e Ga s es . . . . . . . . . . . . . . . . . . . . 2-28 2.8.1.1 Historical Meteorology ......... 2-28 2.8.1.2 Concurrent Meteorology ......... 2-29 p 2.8.2 Radiciodines and Particulates . . . . . . . . . . . 2-30 2.8.2.1 Historical Meteorology ......... 2-30 2.8.2.2 Concurrent Meteorology ......... 2-31 2.9 Total Dose Calcul ations . . . . . . . . . . . . . . . . . . 2-78 2.9.1 Total Dose to Most Likely Member of the Public .. 2-78 2.9.1.1 Annual Total Organ Dose . . . . . . . . . 2-78 2.9.1.2 Annual Total Whole Body Dose ...... 2-79 2.9.1.3 Annual Total Thyroid Dose . . . . . . . . 2-80 3.0 PROJECTED DOSES ........................ 3-1 thru 3-1 ,
3.1 Liquid Dose Projection .................. 3-1 3.2 Gaseous Dose Projection . . . . . . . . . . . . . . . . . . 3-1 S023-0DCM Revision 25 11 02-28-92 l .
00CM TABLE OF CONTENTS (Continued)
ILag 4.0 EQUIPMENT ........................... 4-1 thru 4-19 p 4.1 Radioactive Liquid Effluent Monitoring Instrumentation .. 4-1 I 4.1.1 Specification . . . . . . . . . . . . . . . . . . . . 4-1 4.1.1.1, 4.1.1.2 Surveillances .............. 4-1 4.2 Radioactive Gaseous Effluent Monitoring Instrumentation . . 4-6 4.2.1 Specification . . . . . . . . . . . . . . . . . . . . 4-6 4.2.1.1 Surveillance ................... 4-6 4.3 Operability of Radioactive Waste Equipment ........ 4-16 lP 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ............. 5-1 thru 5-26 5.1 Monitoring Program .................... 5-1 5.1.1 Specification .................. 5-1 5.1.1.1 -Surveillance . . . . . . . . . . . . . . . . . . . 5-2 5.2 Land b;e Census . . . . . . . . . . . . . . . . . . . . . . 5-11 5.2.1 Specification .................. 5-11 5.2.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 5-11 5.3 Interlaboratory Comparison Program ............ 5-12 5.3.1 Specification .................. 5-12 5.3.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 5-12 5.4 Annual Radiological Environmental Operating Report .... 5-13 5.5 Sample Locations ..................... 5-14 6.0 ADMINISTRATIVE . . . . . . . . . . . . ............ 6-1 thru 6-16 6.1 Definitions . . . . . . . . . . . . . . . . . . . . . . . . 6-1 6.2 Admi ni s t ra t i ve Con t rol s . . . . . . . . . . . . . . . . . . 6-7 6.3 Major Changes to Radioactive Waste Treatment Systems (LiquidandGaseous) ................... 6-9 6.4 Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-10 S023-0DCM Revision 25 iii ,02-28-90
i ODCM l
1 LIST OF FIGURES Fiaure Title Paae
'I 1-2 Site Boundary for Liquid Effluents . . . . . . . . . . . . . . . . 1-7 l
2-2 Site Boundary for Gaseous Effluents ............... 2-10 j 4-5 SONGS 2 and 3 Radioactive Liquid Waste Treatment Systems . . . . . 4-17 j i
F 4-6 SONGS 2 and 3 Radioactive Gaseous Waste Treatment Systems .... 4-18 l i
4-7 Solid Waste Handling . . . . . . . . . . . . . . . . . . . . . . . 4-19 !
5-1 Radiological Environmental Monitoring Sample Locations j 2 Mile Radius .......................... 5-23 5-2 Radiological Environmental Monitoring Sample Locations 10 Miles Radius .......~.................. 5-24 5-3 Radiological Environmental Monitoring Sample Locations Orange County .......................... 5-25 5-4 Radiological Environmental Monitoring Sample Locations San Diego County . . . . . . . . . . . . . . . . . . . . . . . . . 5-26 S023-0DCM .
iv Revision 28 12-21-95
ODCM LIST OF TABLES Table Title Paae 1-1 Radioactive Liquid Waste Sampling and Analysis Program . . 1-2 1-3 Liquid Effluent Radiation Monitors Calibration Constants . . . . . . . . . . . . . . . . . . 1-25 1-4 Dose Commitment Factors A i , . . . . . . . . . . . . . . . 1-27 2-1 Radioactive Gaseous Waste Sampling and Analysis Program . 2-2 2-3 Gaseous Effluent Radiation Monitor Calibration Constants ................. . 2-24 2-4 Dose Factors for Noble Gas and Daughters . . . . . . . . . 2-33 2-5 Dose Parameters Pa . . . . . . . . . . . . . . . . . . . 2-34 2-6 Controlling Location Factors . . . . . . . . . . . . . . . 2-35 2 Dose Parameters iR for Sector P . . . . . . . . . . . . . 2-36 p 2-8 Dose Parameters Ri for Sector Q . . . . . . . . . . . . . 2-39 2-9 Dose Parameters iR for Sector R . . . . . . . . . . . . . 2-48 2-10 Dose Parameters iR for Sector A . . . . . . . . . . . . . 2-53 2-11 Dose Parameters iR for Sector B . . . . . . . . . . . . . 2-57 2-12 Dose Parameters iR for Sector C . . . . . . . . . . ... . 2-59 2-13 Dose Parameters Ri .for Sector D . . . . . . . . . . . . . 2-64 2-14 Dose Parameters R, for Sector E . . . . . . . . . . . . . 2-67 2-15 Dose Parameters iR for Sector F . . . . . . . . . . . . . 2-70 2-16 Dose Parameters Ri for Sector G . . . . . . . . . . . . . 2-74' 2-17 SYF Controlling Location F3ctors . . . . . . . . . . . . . 2-81 2-18 SYF Dose Parameters Ri for Sector D . . . . . . . . . . . 2-82 2-19 SYF Dose Parameters Ri for Sector E . . . . . . . . . . . 2-83 2-20 SYF Dose Parameters Ri for' Sector F . . . . . . . . . . . 2-84 2-21 SYF Dose Parameters Ri for Sector G . . . . . . . . . . . 2-88 S023-0DCM Revision 28 v 12-21-95
l 0DCM LIST OF TABLES (Continued) l Table Title Paae 4-1 Radioactive Liquid Effluent Monitoring Instrumentation . . 4-2 4-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . 4-4 4-3 Radioactive Gaseous Effluent Monitoring Instrumentation . 4-7 !
4-4 Radioactive Gaseous Effluent Monitoring Instrumentation ,
Surveillance Requirements . . . . . . . . . . . . . . . . 4 !
5-1 Radiological Environmental Monitoring Program . . . . . . 5-3 5-2 Reporting Levels for Radioactivity Cc9centrations in j Environmental Samples . . . . . . . . . . . . . . . . . . 5-7 1 5-3 Maximum Values for the Lower Limits of Detection (LLD) . . 5-8 5-4 Radiological Environmental Monitoring Sample Locations . . 5-15 5-5 PIC Radiological Environmental Monitoring Locations . . . 5-21 5-6 Sector and Direction Designation for Radiological Environmental Monitoring Sample Location Map . . . . . . . 5-22
.6-1 Operational Modes . . . . . . . . . . . . . . . . . . . . 6-5 l l
6-2 Frequency Notation . . . . . . . . . . . . . . . . . . . . 6-6 q i
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S023-0DCM Revision 25 l vi 02-28-92 l j
7 INTRODUCTION The 0FFSITE DOSE CALCULATION MANUAL (0DCM) is a supporting document of the i RADIOLOGICALEFFLUENTTECHNICALSPECIFICATIONS(NUREG0472). The ODCM enumerates dose and concentration specifications, instrument requirements, as well as describes the methodology and parameters to be used in the calculation of offsite doses from radioactive liquid and airborne effluents. In order to meet release limits, it additionally provides calculations for liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. The environmental section contains a list of the sample locations for the radiological environmental monitoring program.
The ODCM will be maintained at the Site for use as a document of Specifications and acceptable methodologies and calculations to be used in implementing the Specifications. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents current methodology.
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S023-0DCM Revision 21 vii ,02-15-90
1.0 LIQUID EFFLUENTS 1.1 CONCENTRATION SPECIFICATION 1.1.1 The concentration of radioactive material released from the site (see Figure 1-2) 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 10-8 microcuries/mltotalactivity.
AePLICABILITY: At all times I
ACTION:
- a. With the concentration of radioactive material released from the tite exceeding the above limits, immediately restore the concentration to within the above limits.
SURVEILLANCE RE0VIREMENTS
.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 1-1.
.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in Section 1.4 to assure that the concentrations at the point of release are maintained within the limits of Specification 1.1.1.
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/
S023-0DCM 1-1 Revfsfon 22 08-02-90 l
i TABLE 1-1 l RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)
Type Frequency Frequency Analysis (yCi/ml)'
A. Batch Waste P P Principal Gamma 5x10-'
Release d Each Batch Each Batch Emitters' I-131 1x10' P M Dissolved and 1x105 OneBatch/M Entrained Gases 3 (Gamma emitters) i P M H-3 1x105 Each Batch Composite b l P Q Sr-89, Sr-90 5x10 8
6 Each Batch Composite Fe-55 1x10-8 NOTE BATCH RELEASE POINTS: Primary Plant Makeup Storage Tanks, Radwaste Primary Tanks, Radwaste Secondary Tanks, Miscellaneous Waste Condensate Monitor Tanks, ;
BlowdownProcessingSump,FFCPDsumps(highconductivity,lowconductivity)and holduptank,ComponentCoolingWaterSump,StorageTankAreaSump,S/GBlowdown.
B. Continuous D W Principal Gamma 5x107 Releases', Grab Sample Composite
- Emitters I-131 1x10-5 l M M Dissolved and 1x10-5 Grab Sample Entrained Gases (Gamma emitters)
D M H-3 1x105 Grab Sample Composite
- Gross Alpha 1x10' D Q Sr-89, Sr-90 5x10-8 Grab Sample Composite
- Fe-55 1x10 '
NOTE CONTINU0US RELEASE POINTS: Turbine Plant Sump *, Blowdown Processing Sump", S/G Blowdown Bypass Line*", S/G Blowdown, Auxiliary Building Sump.*
S023-0DCM 1-2 Revision 28
. 12-21-95
TABLE 1-1 (Continued)
TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely -
concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
1 4.66 s, i 6
E = V e 2.22 x 10
- Y = exp (-AAt) where:
LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),
s,is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume),
2.22 x 10' is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
{
The value of si used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
Typical values of E, V, Y and At should be used in the calculation.
It should be recognized that the LLD is defined as an A Driori (before the fact) limit representing the capability of the measurement system and not as a Dosteriori (after the fact) limit for a particular measurement.'
'For a more complete discussion of the LLD, and other detection limits, see the following:
HASLProceduresManual,HASL-300(revisedannually).
. Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40,586-93(1968).
(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques,"
Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).
S023-0DCM 1-3 Revision 26 12-20-93
TABLE 1-1 (Continued)
TABLE NOTATION
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
- c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
- d. A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.
- e. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.
- f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. I Administrative controls shall ensure that only one continuous release point is discharging through a discharge path at any given time. The normal continuousreleasepointvia2(3)RT-7821istheturbineplantsump.
The first sump when transferring outlying sumps shall be treated as a batch release.
Sampling of this flow is not required if at least once per 31 days blowdown bypass isolation valve (S21301MV618 for Steam Generator 2E088, S21301MU619 for Steam Generator 2E089, S31301MU618 for Steam Generator 3E088 and S31301MU619 for Steam Generator 3E089) is verified locked shut.
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l S023-0DCM i 1-4 Revision 26 .
12-20-93 !
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1.0 LIQUID EFFLUENTS (Continued) I 1.2 D_Q1E SPECIFICATION 1.2.1 The dose or dose connitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 1-2) shall be limited:
- a. During any ca?endar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any 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 mrem to any organ.
APPLICABILITY: At all times ACTION:
- a. With calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section R 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section !
5.7.2 and LCS 5.0.104.2, a Special Report which identifies the i cause(s) for exceeding the limit (s).and defines the corrective R actions taken to reduce the releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 1.2.1.
SURVEILLANCE RE0VIREMENTS
.1 Dose Calculation. Cumulative dose contributions from liquid effluents shall be determined in accordance with Section 1.5 at least once per 31 days.
S023-0DCM 1-5 Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued) 1.3 LIOUID WASTE TREATMENT f
SPECIFICATION 1.3.1 The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the ,
radioactive materials in liquid wastes prior to their discharge !
when the projected doses due to the liquid effluent from the site (see Figure 1-2) when averaged over 31 days, wou 0.06mremtothetotalbodyor0.2mremtoanyorganldexceed i
APPLICABILITY: At all times ACTION:
- a. With radioactive liquid waste being discharged without I treatment and in excess of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, pre]are and submit to the Commission within 30 g, days pursuant to Tec1nical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
SURVEILLANCE RE0VIREMENTS
.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with Section 3.1.
.2 Duringplantoperation(Mode 1-4),theappropriateportionsofthe liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatmer,t system equi) ment for at least 15-minutes at least once per 92 days unless tie liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.
.3 Inplantshut-down(Mode 5,6),theappropriateportionsofthe liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 15-minutes prior to processing licuids unless the appropriate liquid radwaste system has been utilizec to process radioactive liquid effluents during the previous 92 days.
- Per reactor unit 5023-0DCM 1-6 Revision 30 05-28-97
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- O OO = ^
- + ,
- Ed
=g - \ ..
"lLa f
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/
ss yag,4y
.4T ,$>O % . _
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SITE B0UNDARY FOR LIOUID EFFLUENTS FIGURE 1-2 S023.0DCM 1-7 fievision 29 07-31-96
1.0 LIQUID EFFLUENTS (Continued) 1.4 LIOUID EFFLUENT MONITOR METHODS OF SETPOINI CALCULATION Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 at the release point to the unrestricted area. To meet this specification and for the
.nurposeofimplementationofSpecification1.1.1,thealarm/ trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:
f C,R ' (1-1)
F+R j s MPC'"
y where:
C, = setpoint, representative of a radionuclide concentration for the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release, yCi/mi R = permissible waste effluent flow rate at the radiation monitor location, in volume per unit time in the same units as for F F = dilution water flow in volume per unit time, p
= 185,000 gpmpercirculatingwaterpump(4 total)*
= 17,000 gpm per saltwater pump (2 total)
The design flowrate of each circulating water pump is 205,000 gpm. The value used in the determination of F takes into account factors such as frictional losses, pump inefficiency, and tidal flow, and provides reasonable assurance that the radioactive release concentration is not underestimated.
NOTE: Since the values of R are much smaller than F, the term (F + R) in p equation (1-1) may be replaced by F. j 1
S023-0DCM 1-8 Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued) I 1.4 LIOUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION (Continued)
MPC,,,= effective effluent maximum concentration permissible limit (Ci/ml)atthereleasepointtotheunrestrictedareaforthe i radionuclide mixture being released: )
/ i '
1 (1-2) F
=
n F' I E l t
i'l s
MPC,,, [
l n =
number of radionuclides identified in sample analysis Fi = fractional concentration of the ih radionuclide as obtained by t
sample analysis l
)
MPC, = MPC of the ith radionUClide (10CFR20, App B, Table II, Column 2)
I Administrative values are used to reduce each setpoint to account for g j the potential activity released simultaneously from the following release points:
RWsui = Radwaste Effluent discharge SGaa.: = Unit 2 Steam Generator E-088 SG3 ,.: = Unit 2 Steam Generator E-089 SGu.3 = Unit 3 Steam Generator E-088 SG 89 .3 = Unit 3 Steam Generator E-089 Br = Unit 2 Neutralization Sump B3 = Unit 3 Neutralization Sump Tr = Unit 2 Turbine Plant Sump T3 = Unit 3 Turbine Plant Sump The sum of the administrative values is limited to 1.0 to ensure that the total concentration from all release points to the plant discharge will not result in a release exceeding the limits of 10CFR20, Appendix B, Table II, Column 2 from Units 2 and 3. The administrative values shall be assigned such that:
(RW78i3 + SGas-r + 89SG 2 + SGa.3 + SG,9 32 + B + B + T, + T 3 3
) 5 1.0.
The administrative values shall be periodically reviewed based on actual q release data and revised as necessary.
S023-0DCM 1-9 Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION IF The waste flow (R) and monitor setpoint (C,) are set to meet the lR.
condition of equation (1-1) for the MPC,7, limit. The method by which this is accomplished is as follows:
STEP 1: Theisotopicconcentrationforeachbatchtank(or sump) to be released is obtitined from the sum of the measuredconcentrationsinthetank(orsump)as determined by analysis.
C = % Cy ] + (C,) + (C,) + (C,) + (Cre ) II-3) where:
C =
total concentration in each batch tank, C1/ml ,
l IC, iy
= sum of the measured concentrations for each radionuclide, i, in the gamma spectrum, Ci/ml I Cr.
Fe-55 concentration as determined in the previous quarterly composite sample, C1/mi C, = gross alpha concentration determined in the previous monthly composite sample, Ci/ml C,
Sr-89 and Sr-90 concentrations as determined in the previous quarterly composite sample, Ci/mi Ci = H-3 concentration as determined in the previous monthly composite sample, or as measured in the sample taken prior to release, pCi/;.;l l l
S023-03CM 1-10 Revision 27 12-21-94
10 0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETP0 INT DETERMINATION (Continued)
STEP 2: The effective MPC (MPC,,r) for each batch tank (or sump) is determined using:
1 (1-4)
MPC'" =
'C,/C' ' C,/C ' ' C,/C ' 'C,/C' 'Cre/C' r' y MPC,,
y MPC,,
MPC,,
MPC,,
M P C,, ,
where:
MPCyi ,
MPC,,
MPC,, E MPCr.,
MPC a =
the limiting concentrations of the appropriate radionuclide from 10CFR20, Appendix B, Table II, Column 2 NOTE: For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 Ci/mltotalactivity.
STEP 3: The setpoint, C, ( Ci/ml) for each batch release radioactivity monitor may now be specified based on the respective values of C, I ciyi, F, MPC,rr, and R to provide compliance with the limits of 10CFRP.0, Appendix B, Table II, Column 2. @-
STEP 4: The setpoint, cpm, may be derived using the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor limit C., C1/ml.
S023-0DCM 1-11 Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETP0 INT DETERMINATION (Continued) 1.4.1.1 RA0 WASTE DISCHARGE LINE MONITOR (2/3RT7813)
The value for C , the concentration limit at the detector, is determined by using:
(RWm3) (F) (C,,,) (1-5) A C, s , ,
C* C"
@i + . . . + R,) +...+
( eff! effn j where:
{
RWni3
Radwaste Effluent discharge administrative value F
dilution water flow in volume per unit time A l
=
185,000 gpm per circulating water pump (4 total)
=
17,000 gpm per saltwater pump (2 total)
C. ,, = effective gamma isot)pic concentration at the monitor for the tank combination to be released (equal to I iy c, for single tank releases)
(1-6) 4
. R (1,C 3 y ,), +2R iy(I C ,) + . . . + Rg,C y ,), '
R3 + R, + . . . + R, (I iCyi )i, l (Z C )r>
i yi etc. = total gamma isotopic concentration of first tank,secondtank,etc.(Ci/ml) n =
number of tanks to be released R,i R,2 etc. =
typical effluent flow rate from first tank, second tank, etc. Values of R for each tank are as follows:
Radwaste Primary Tanks = 140 gpm (per pump)
Radwaste Secondary Tanks = 140 gpm (per pump) g Primary Plant Makeup Tank = 160 gpm (per pump)
Condensate Monitor Tanks = 100 gpm (per pump)
S023-0DCM 1-12 Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3RT7813) (Continued) ,
lb ,
l C,
i Cr.
etc. =
values of C, total concentration, from equation (1-3) for the first tank, second tank, etc., in Ci/ml p M P C,,,i ,
MPCe rrre etc. =
values of MPC,,, from equation (1-4) for first tank, second tank, etc.
lF NOTE: If C,5 C.,,, then no release is possible. To increase C , increase the administrative value RWrais, and/or increase dilution flow F (by running more dilution pumps in the applicable discharge structure), and/or S decrease the effluent flow rates Ri , R2 , etc., and recalculate C, using the new RW sis, F, R as applicable and equation (1-5).
i l
S023-0DCH 1-13 Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued) .
l 1
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(
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S023-00CM 1-14 Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued) 1.4.1.2 NEUTRALIZATION SUMP / FULL FLOW CONDENSATE POLISHER DEMINERALIZER JFFCPD) SUMP DISCHARGE LINE MONITOR (8ATCH) (2RT7817. 3RT7817)
The value for Cr (Unit 2) or C (Unit 3), the concentration limit 3 p.
at the Unit 2 or Unit 3 detector, is determined by using:
i C' s '
(R) (C/MPC,,,)
C' s (R) (C/MPC,,,)
where:
Cr
=
instantaneous concentration at detector 2RT7817 in pCi/cc C3 =
instantaneous concentration at detector 3RT7817 in ::Ci/cc B, = Unit 2 Neutralization Sump administrative value B3 = Unit 3 Neutralization Sump administrative value F = dilution water flow in volume per unit time
= 185,000 gpm per circulating water pump (4 total)
= 17,000 gpm per saltwater pump (2 total)
I iy c , = total gamma isotopic concentration, Ci/ml,(STEP 1) (( !
l R = Typical release flow rates:
Neutralization Sump = 500 gpm FFCPD High Conductivity Sump = 500 gpm FFCPD Low Conductivity Sump = 600 gpm FFCPD Holdup Tank = 1000 gpm C = total concentration in each batch sample, Ci/ml lR.
MPC,,, = value of MPC,,, from equation (1-4) for the sample analysis lb NOTE: If C, or C 5 I,C yi, then no release is possible. To increase C, or C ,
3 3 increase the administrative value Br or 8, and/or increase dilution 3
g, flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate Cr or C using the new D, or B , F, R as 3 3 applicableandequation(1-7)or(1-8).
S023-0DCM 1-15 '
Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued) 1.4.2 CONTINU0US RELEASE SETPOINT DETERMINATION The waste flow (R) and monitor setpoint (C,) are set to meet the condition of equation (1-1) for the effective MPC (MPC,,,) limit.
Tne method by which this is accomplished is as follows:
STEP 1: The isotopic concentration for the continuous releases are obtained for each release stream (steam generator blowdown, steam generator blowdown bypass, blowdown neutralization sump and turbine plant sump) from the sum of the respective measured concentrations as determined by analysis:
C = % Cy ] + (C,) + (C,) + (C,) + (Cp ,) (1-9) where:
=
C totalconcentration(Ci/ml)
EC;y =
total gamma activity associated with each radionuclide, 1, in the weekly composite analysis for the release stream, pC1/ml p
=
C, total measured gross alpha concentration determined from the previous monthly composite analysis for the release stream, Ci/ml
=
Cr. total Fe-55 concentration as determined in the previous quarterly composite sample for the release stream, Ci/ml C, =
total measured H-3 concentration determined from the previous weekly or monthly composite analysis for the lR.
, release stream, Ci/ml C, =
total measured concentration of Sr-89 and Sr-90 as determined from the previous quarterly composite analysis f for the release stream, Ci/ml SG23-0DCM 1-16 Revision 30 05-28-97
Ic0 LIQUID EFFLUENTS (Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION (Continued)
$_TEP 2: The effective MPC (MPC,,,) for each release stream (steamgeneratorblowdown,blowdownneutralization sump,orturbineplantsump)isdeterminedusing:
1 (1-10)
MPC'" =
r' 'C /C' g
MPCg,
' C,/C' MPC,,
' C,/C '
MPC,,
'C,/C' MPC,
' C,,/C '
MPCp ,,
! where:
MPC yi ,
MPC,, A MPCe, MPCr.,
MPC a =
the limiting concentrations of the appropriate radionuclide from 10CFR20, Appendix B Table II, Column 2 STEP 3: The setpoint, C, ( Ci/ml) for each continuous release radioactivity monitor may now be specified based on the respective values of C, I Ci yi, F, MPC,,r, and R to R provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2.
STEP 4: The setpoint, cpm, may be derived using the applicable calibration constants given in Table 1-3 to correspond d, to the calculated monitor limit C,, C1/ml.
S023-0DCM 1-17 Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued)
THIS PAGE LEFT INTENTIONALLY BLANK F
i S023-0DCM 1-18 Revision 30
, 05-28-97
i 1.0 LIQUID EFFLUENTS (Continued) 1.4.2.1 NEUTRALIZATION SUMP DISCHARGE LINE MONITORS (2RT7817. 3RT7817) l The value for 2C (Unit 2) orc (Unit 3), the concentration limit 3 [L at the Unit 2 or Unit 3 detector, is determined by using:
Cs ' .
2 (R) (C/MPC,,,)
' Y' Cs3 (R) (C/MPC,,,)
where:
Cr
=
instantaneousconcentrationatdetector2RT7817inpCi/cc C3 =
instantaneousconcentrationatdetector3RT7817inpCi/cc B2 = Uqit 2 Neutralization Sump administrative value 83 = Unit 3 Neutralization Sump administrative value A
F = dilution water flow in volume per unit time j
= 185,000 gpm per circulatang water pump (4 total)
= 17,000 gpm per saltwater pump (2 total)
ICi yi
= total gamma isotopic concentration, Ci/ml,(STEP 1)
R =
effluent flow rate, gpm, (STEP 1), (maximum of 500 gpm) i C = total concentration, C1/ml i
MPC,,, = value of MPC,,, from equation (1-4) for the sample analysis )
[F NOTE: If C, or C 5 I Ci yi, then no release is possible. To increase C, or C ,
3 3 increase the administrative value B or B , and/or increase dilution 2 3 flow F (by running more dilution pumps), and/or decrease the effluent S flow rate, R, and recalculate Cr or C using the new B, or B , F, R as 3 3 applicable and equation (1-11) or (1-12).
S023-0DCM 1-19 Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued)
THIS PAGE INTENTIONALLY LEFT BLANK l
P l i
l l
l l
l l
S023-0DCM 1-20 Revision 30 05-28-97
100 LIQUID EFFLUENTS (Continued) 1.4.2.2 1 TEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT6753, 2RT6759. 3RT6753. 3RT6759)
The value for Cs,.r, Cs3 2, Cs,.3 or Cs3 3, the concentration limit at the Unit 2 or Unit 3 detectors, is determined by using:
(SG88-2) (f) (E i Cy ,) D-13)
C"'2 s (R) (C/MPC,,,)
C s
2
53'2 (R) (C/MPC,,f)
C" ~3 s (R) (C/MPC,f,)
1 89-3 1 yt 53 -3 (R) (C/MPC,f,)
where: l l
C5 ,,, = instantaneous concentration at detector 2RT6759 in yCi/ml l Cs3.r = instantaneous concentration at detector 2RT6753 in Ci/ml Cs,.3 = instantaneous concentration at detector 3RT6759 in Ci/ml Cs3 3 = instantaneous concentration at detector 3RT6753 in Ci/mi SGas. = Unit 2 E088 Steam Generator Blowdown administrative value g S G,,. = Unit 2 E089 Steam Generator Blowdown administrative value SG 38 .3 = Unit 3 E088 Steam Generator Blowdown administrative value SG3 ,.3 = Unit 3 E089 Steam Generator Blowdown administrative value F = dilution water flow in volume per unit time
= 185,000 gpm per circulating water pump (4 total)
= 17,000 gpm per saltwater pump (2 total)
S023-0DCM 1-21 Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT6753. 2RT6759. 3RT6753. 3RT6759) (Continued) i ICi yi
= total gamma isotopic concentration, Ci/ml,(STEP 1) j l
R = maximum blowdown bypass effluent flowrate per steam generator, 200 gpm, (STEP 1) k l C = total concentration, Ci/mi MPC ,, = value of MPC,,, from equation (1-4) for the sample analysis F
NOTE: If Cs,.2, Cs3r, C 5 ,.3, or C 33 .3 5 I Ci yi (for the respective steam generator),
then no release is possible. To increase C 3 ,.2, C 53 .3, C ,.3 or C 33 .3, 3
increase the administrative value SG ee .2, SG ,.2, SG88 3 or SGe,.3, and/or increase dilution flow F (by running more dilution pumps), and/or k decrease the effluent flow rate R and recalculate C ,.r. C 53 .3, C ,.3 or Cs3 3 5 3 using the new values of SGa9.r, SG 88 r, SGe,.3 or SG 88 -3, F, R as applicable and equation (1-13), (1-14), (1-15) or (1-16).
l l
S023-00CM 1-22 Revision 30 05-28-97
100 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT7821. 3RT7821)
The value for C (Unit 2) or C (Unit 3),theconcentrationlimit 2 3 IR at the Unit 2 or Unit 3 detector, is determined by using:
C' s (R) (C/MPC,,,)
Cs '
- 3 (R) (C/MPC,,,)
where:
=
Cr instantaneous concentration at detector 2RT7821 in Ci/cc R
C3 =
instantaneous concentration at detector 3RT7821 in Ci/cc Tr
= Unit 2 Turbine Plant Sump administrative value T3 = Unit 3 Turbine Plant Sump administrative value A
F = dilution water flow in volume per unit time
= 185,000 gpmpercirculatingwaterpump(4 total) ,
= 17,000gpmpersaltwaterpump(2 total) '
IC i yi
= total gamma isotopic concentration, Ci/ml,(STEP 1)
R =
effluent flow rate, gpm, (STEP 1), typically flow rate:
= 100gpm(perpump) g I
C = total concentration, Ci/ml l MPC,,, = value of MPC,,, from equation (1-4) for the sample analysis NOTE: If C, or C3 s I,C yi, then no release is possible. To increase C, or C , 3 ,
increase the administrative value T, or T , and/or increase dilution 3
g flowF(byrunningmoredilutionpumps),and/ordecreasetheeffluent flow rate, R, and recalculate C, or C using the new Tr or T , F, R as 3 3 applicable and equation (1-17) or (1-18).
S023-0DCM 1-23 Revision 30 05-28-97 ,
{
1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT7821. 3RT7821) (Continued)
{F Use of a temporary discharge path from the Turbine Plant Sump is !
allowed providing the radiation monitor, 2(3)RT7821, in service and l the normal discharge path is used concurrently. Temporary pumps facilitate faster discharge when draining the condenser to the outfall via this pathway. The following conditions shall be met:
)
l
- a. The release permit shall account for the entire volume of 1 j water discharged from the Turbine Plant Sump.
- b. The alarm setpoint for the monitor shall be adjusted to take
! into account the entire discharge flow through both the normal and temporary paths.
- c. Procedures shall require the immediate termination of the discharge via the temporary path if the monitor on the normal path alarms.
l l
f I
S023-0DCM 1-24 Revision 21
,02-15-90
Table 1-3 Liquid Effluent Radiation Monitor Calibration Constants (*)
(Ci/cc/ cpm)
MONITOR Co-60 Ba-133 Cs-137 2RT6753 2.08E-8 1.93E-8 2RT6759 1.85E-8 1.90E-8 R j 3RT6753 2.00E-8 1.93E-8 1
3RT6759 2.02E-8 1.99E-8 2/3RT7813 2.27E-9 3.16E-9 4.81E-9 2RT7817 2.37E-9 3.29E-9 4.84E-9 2RT7821 2.32E-9 3.20E-9 4.80E-9 3RT7817 2.38E-9 3.24E-9 5.26E-9 3RT7821 2.32E-9 3.18E-9 4.72E-9 l
5
. i
(*) This table provides typical (* 20%) calibration constants for the liquid effluent radiation monitors.
S023-0DCM 1-25 Revision 30 05-28-97
1.0 LIQUID EFFLUENTS (Continued) 1.5 DOSE CALCULATION FOR LIOUID EFFLUENTS The liquid releases considered in the following dose calculations are described in Section 1.4. The dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing Specification 1.2.1 using the following expression.
D, = I, A,, I,(At 3 C,3 F{
3 (1-19) where:
A,, =
Site-related adult ingestion dose commitment factor to the total body or an organ, T, for each identified principal gamma and beta emitter,1, from Table 1-4 in mrem /hr per Ci/ml.
Cu =
average concentration of radionuclide, i, in the undiluted liquid effluent during time period, At , in C1/ml.
3 D, =
dose commitment to the total body or an organ, T, from the liquid effluent for the time period, At , in mrem.
3 F3 =
near field average dilution factor (actually mixing ratio) for Cy during the time period, At . This factor is the ratio of 3
the maximum undiluted liquid waste flow during time period, At , to the average flow from the site discharge structure to 3
unrestricted receiving waters, maximum liquid radioactive waste flow '
I
, discharge structure exit f_ low ,
At 3
=
length of the j" time period over which Cu and F are averaged 3
for all liquid releases, in hours.
S023-00CM 1-26 Revision 26
,12-20-93
TABLE-1-4 DOSE COMMITMENT FACTORS *, An (mrem /hrper Ci/ml)
Radio- Total nuclide Bone 1.1ver Body Thyroid Kidney Lung GI-LLI H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 Cr-51 5.58E+0 3.34E+0 1.23E+0 7.40E+0 1.40E+3 Mn-54 7.06E+3 1.35E+3 2.10E+3 2.16E+4 Mn-56 1.78E+2 3.15E+1 2.26E+2 5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 1.97E+4 2.03E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 5.30E+4 6.32E+5 Co-57 1.42E+2 2.36E+2 3.59E+3 Co-58 6.03E+2 1.35E+3 1.22E+4 Co-60 1.73E+3 3.82E+3 3.25E+4 Cu-64 2.14E+2 1.01E+2 5.40E+2 1.83E+4 Zn-65 1.61E+5 5.13E+5 2.32E+5 3.43E+5 3.23E+5 Br-84 9.39E-2 7.37E-7 Rb 1.79E+0 9.49E-1 2.47E-11 Sr-89 4.99E+3 1.43E+2 8.00E+2 Sr-90 1.23E+5 3.01E+4 3.55E+3 Sr-91 9.18E+1 3.71E+0 4.37E+2 Sr-92 3.48E+1 1.51E+0 6.90E+2 Y-90 6.06E+0 1.63E-1 6.42E+4 Y-91m 5.73E-2 2.22E-3 1.68E-1 Y-92 5.32E 1.56E-2 9.32E+3 Zr-95 1.59E+1 5.11E+0 3.46E+0 8.02E+0 1.62E+4 Zr-97 8.81E-1 1.78E-1 8.13E-2 2.68E-1 5.51E+4 Nb-95 1.84E+0 1.03E+0 5.51E-1 1.01E+0 6.22E+3 l Nb-95m 1.84E+0 1.03E+0 5.51E-1 1.01E+0 6.22E+3
)
Nb-97 1.55E-2 3.91E-3 1.43E-3 4.56E-3 1.44E+1 j Mo-99 1.28E+2 2.43E+1 2.89E+2 2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 NOTE: where no value is given, no data are available.
- Source: Reg. Guide 1.109, Table E-11, Table A-1 l USNRC NUREG-0172, Table 4 ICRP-30, Part 3, Supplement A Methodology: USNRC NUREG-0133, Section 4.3.1 S023-0DCM 1-27 Revision 26 12-20-93
I TABLE 1-4 (Continued)
DOSE COMMITMENT FACTORS ^, An (mrem /hrper Ci/ml)
Radio- .
Total nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI Ru-103 1.07E+2 4.60Et1 4.07E+2 1.25E+4 Ru-106 1.59E+3 2.01E+2 3.06E+3 1.03E+5 Ag-110m 1.42E+3 1.32E+3 7.82E+2 2.59E+3 5.37E+5 Sn-113 2.26E+5 Sn-117m 2.26E+5 Sb-124 2.76E+2 5.22E+0 1.09E+2 6.70E-1 2.15E+2 7.84E+3 Sb-125 1.77E+2 1.97E+0 4.20E+1 1.79E-1 1.36E+2 1.94E+3 Te-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 4.69E+3 Te-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 I-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 8.23E+1 I-132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 5.35E+0 1-133 7.45E+1 1.30E+2 3.95E+1 1.90Ew. 2.26E+2 1.16E+2 1-134 5_.ji6E+0 1. 5.1 E+1 5.40E+0 2.62E+2 2.40E+1 1.32E-2 I-135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 6.87E+1 Cs-134 6.84E+3 1.63E+4 1.33E+4 5.27E+3 1.75E43 2.85E+2 Cs-136 7.! E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+0 1.20E+1 5.94E+0 8.81E+0 8.70E-1 5.12E-5 Ba.139
. 7.85E+0 5.59E-3 2.30E-1 5.23E-3 3.17E-3 1.39E+1 i Ba-140 1.64E+3 2.06E+0 1.08E+2 7.02E-1 1.18E+0 3.38E+3 I La-140 1.57E+0 7.94E-1 2.10E-1 5.83E+4 Ce-141 3.43Et0 2.32E+0 2.63E-1 1.08E+0 8,86E+3 Ce-143 6.04E-1 4.46E+2 4.94E-2 1.97E-1 1.67E+4 Ce-144 1./9E+2 7.47E+1 9.59E+0 4.43E+1 6.04E+4 Nd-147 3.96J+0 4.58E+0 2.74E-1 2.68E+0 2.20E+4 W-187 9. lie +0 7.66E+0 2.68E+0 2.51E+3 Np-239 3.53E-2 3.47E-3 ,_1.91E-3 1.08E-2 7.11E+2 NOTE: where no value is given, no data are available.
- Source: Reg. Gui. 1. D. Tatle E-11, Table A-1 UShRC NI' 4 . ',2, Table 4
( ICE 3r a rt 3, Supplement A Methodology: iJSNRC NtJREG-0133, Section 4,1 1 S023-00CM 1-20 Revision 26 8
12-20-93
1.0 LIQUID EFFLUENTS (Continued) 1.6 Representative Sampling i
Prior to sampling of a batch release, each batch shall be thoroughly mixed to assure representative sampling in accordance with the requirements of Regulatory Guide 1.21 and NUREG-0800, Section 11.5. The methodology for mixing and sampling is described in S0123-III-5.11.23,
" Units 2/3 Liquid Effluent Release Permit" and S0123-III-5.2.23,
" Units 2/3 Liquid Effluent Sample Collection".
S023-0DCM 1-29 Revision 21 02-15-90 i
2.0 GASE0US EFFLUENTS 2.1 DOSE RATE SPECTFICATION i
2.1.1 The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site (see Figure 2-2) shall be limited to the following:
- a. For noble gases: Lessthanorequalto500 mrem /yrtothe total body and less than or equal to 3000 mrem /yr to the skin, and
- b. For all-radiciodines, tritium and for all radioactive materials 4 in particulate form with half lives greater than 8 days: Less j than or equal to 1500 mrem /yr to any organ.
APPLICABILITY: At all times ACTION: l
- a. With dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s).
SURVEILLANCE RE0VIREMENTS i
l .1 The dose rate due to noble gases in gaseous effluents shall be detern.ined to be within the above limits in accordance with l Section 2.7.
.2 The dose rate due to radiciodines, tritium and radioactive l materials in particulate form with half lives greater than 1 8 days in gaseous effluents shall ba determined to be within the above limits in accordance with Section 2.7 by obtaining '
, representative samples and perfonning analyses in accordance with l the sampling and analysis program specified in Table 2-1.
4 I
S023-0DCM 2-1 Revision 21 02-15-90
l l
TABLE 2-1 l
RADI0 ACTIVE GASE0VS WASTE SAMPLING AND ANALYSIS PROGRAM i Gaseous Minimum Type of Lower Limit Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (pC1/ml)' j Batch P P Principal Gama Emitters' 1x10~'
Waste Gas Each Tank Each Tank Decay Tank Grab Sample ,
I Incinerated Each Batch' Each Batch' Principal Gama Emitters' 5x10'7 6
011 Grab Sample Continuous *
- Principal Gama Emitters' 1x10 I Tritium 1x10
d W I-131 1x10'22 l Continuous' Charcoal Sampler Sample I-133 1x10 4 d
W Continuous' Particulate Principal Gama Emitters' 1x10 "
Sampler Sample (I-131 and Otners)
M Continuout' Composite Gross Alpha 1x10'"
Sampler Particulate Satple Q
Continuous' Composite Sr-89 and Sr-90 1x10'"
l Sampler Particulate Sample I Continuous' Noble Gas Noble Gases 1x10
Monitor Monitor Gross Beta or Gama
- Sampling frequencies for noble gases and tritium are: ];
CONTINLOUS PATHWAYS: Containment Purge - 42" : Each Purge6
- Containment Purge - 8" : Monthly Grab 6 Condenser Air Ejector : Monthly Grab 6 Plant Vent Stack : Weekly Grab **'
South Yard Facility : Particulate and Iojine sampling only d S023-0DCM 2-2 Revision 27 12-21-94 j
TABLE 2-1 (Continued)
TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
Foraparticularmeasurementsystem(whichmayincluderadiochemical separation):
LLD =
E = V = 2.22 x 106 = Y = exp (-Aot) where:
LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),
s, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume),
2.22 x 10' is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between nidpoint of sample collection and time f of Gunting (for plant effluents, not environmental samples).
The value of s, used in the calculation of the LLD for a particular I measurement system shall be based on the actual observed variance of the '
background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
Typical values of E, V, Y and At should be used in the calculation.
I It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of the measurement system and not as a Dosteriori (after the fact) limit for a particular measurement.*
1
- For a more ccmplete discussion of the LLD, and other detection limits, see the followuc: )
HASL Procedures Manual, HASL-300 (revised annually).
Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).
(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques,"
Atlantic Richfield Hanford Company Report ARH-2537 (June 22,1972).
S023-00CM 2-3 Revision 26 12-20-93
l TABLE 2-1 (Continued)
TABLE NOTATION
- b. Analyses shall also be performed following shutdown, startup, or a THERMAL l POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1-hour period. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more l than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. I
- c. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded. .
1
- d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 l days following each shutdown, startup, or a THERMAL POWER change exceeding 15 l percent of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses shall be completed i within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. This requirement does not apply if: )
(1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the I reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding ;
LLDs may be increased by a factor of 10. l
- e. Tritium grab samples shall be taken at least one per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
- f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 2.1, 2.2, 2.3.
- g. The principal gamma emitters for which the LLD specification A.oplies exclusively are the following radionuclides: Kr-87, Kr-88, Xe 133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. 0-This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported,
- h. Incinerated oil may be discharged at points other than the plant vent stack.
Release shall be accounted for based on pre-release grab sample data,
- i. Samples for incinerated oil releases shall be collected from representative samples of filtered oil in liquid form.
J. Radioactive airborne effluents only expected to be particulate and iodine.
S023-0DCM 2-4 Revision 30 05-28-97
2.0 6ASE0US' EFFLUENTS-(Continued) 2.2 DOSE - N0BLE GASES SPECIFICATION 2.2.1 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 2-2) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
- b. During any calendar year: Less than or equal to 10 mrad for gama radiation and less than or equal to 20 mrad for beta radiation.
APPLICABILITY: At all times i
ACTION:
- a. With calculated air dose from radioactive noble gases in l gaseous effluents exceeding any of the above limits, in lieu of 1 any other report required by Technical Specification Section i 5.7.1 and LCS 5.0.104, prepare and submit to the Comission within 30 days, pursuant to Technical Specification Section 8 5.7.2 and LCS 5.0.104.2, a Special Report which identifies the j cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with Specification 2.2.1.
SURVEILLANCE RE0VIREMENTS
.1 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.
S023-0DCM 2-5 Revisien 30 05-28-97
2.0 GASEOUS EFFLUENTS (Continued) 2.3 DOSE - RADI0I0 DINES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM SPECIFICATION 2.3.1 The dose to an individual from tritium, radioiodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the Site (see Figure 2-2) shall be limiced to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any orgaa and,
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
- c. Less than 0.1% of the limits of 2.3.1 (a) and (b) as a result of burning contaminated oil.
APPLICABILITY: At all times ACTION:
- a. With the calculated dose from the release of tritium, radiciodines, and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS l 5.0.104, prepare and submit to the Commission within 30 days pursuant to Technical Specification Section 5.7.2 and LCS g, 5.0.104.2, a Special Report which identifies the cause(s) for l exceeding the limit and defines the corrective actions taken to reduce releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 2.3.1.
SURVEILLANCE RE0VIREMENTS
.1 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.
5023-0DCM 2-6 Revision 30 05-28-97
e 2.0 GASEOUS EFFLUENTS (Continued) 2.4 GASE0US RADWASTE TREATMENT l l
SPECIFICATION '
2.4.1 The GASE0US RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be operable. The appropriate portions of the GASE0US RADWASTE 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 the site (see Figure 2-2), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radM tion. The appropriate portions of the VENTILATION EXHAUS1 IREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to effluent releases from the site (see Figure 2-2)gaseouswhen averaged over 31 days would exceed 0.3 mrein to any organ.*
APPLICABILITY: At all times !
ACTION:
- a. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other raport required by Technical Specification Sec. tion 5.7.1 and LCS 5.0.104, preparc and submit to the Commission within 30 days, S pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged )
without treatment, identification of the inoperable i equipment or subsystems and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and i
- 3. Summary description of action (s) taken to prevent a recurrence. '
SURVEILLANCE RE0VIREMENTS
.1 Doses due to gaseous releases from the site shall be projected at least'once per 31 days, in accordance with Section 3.2.
'These doses are per reactor unit.
I I
S023-0DCM 2-7 Revision 30 05-28-97
200 GASEOUS EFFLUENTS (Continued) 2.4 ,GASE0US RADWASTE TREATMENT (Continued)
SURVEILLANCE RE0VIREMENTS (Continued) l 1
2.4.1.2 During plant operation (Modes 1-4), the applicable portions of the i GASE0US RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT !
SYSTEM shall be demonstrated OPERABLE by operating the GASE0US i RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once
)
I per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.
.3 In plant shut-down (Mode 5, 6), the applicable portions of the i GASE0US RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT l SYSTEM shall be demonstrated OPERABLE by operating the GASE0US '
RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15-minutes prior to ]
processing gases unless the appropriate gaseous radwaste system has been utilized to process radioactive gaseous effluents during the previous 92 days.
l 5023-0DCM 2-8 Revision 22 08-02-90
I 200 GASEOUS EFFLUENTS (Continued) 2.5 TOTAL DOSE SPECIFICATION 2.5.1 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the th be limited to less than or equal to 75 mrem)overyroid, which shall 12 consecutive months.
APPLICABILITY: At all times ACTION:
1
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 1.2.1.a, 1.2.1.b, 2.2.1.a, 2.2.1.b, 2.3.1.a. or 2.3.1.b in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 30 days, which l defines the corrective action to be taken to reduce subsequent '
releases to prevent recurrence of exceeding the limits of Specification 2.5.1. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including l all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dose (s) exceeds the limits of Specification 2.5.1, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the s 3ecified infortnation of paragraph 190.11(b). Submittal of tie report is considerN a timely request, and a variance is granted ur.til staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed elsewhere in this ODCH.
SURVEILLANCE RE0VIREMENTS
.1 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with surveillance 1.2.1.1, 2.2.1.1, and 2.3.1.1.
S023-0DCM 2-9 Revision 21 02-15-90 l
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I 2.0 GASEOUS EFFLUENTS (Continued) 2.6 Methods of Calculation for Gaseous Effluent Monitor Setpoints Administrative values are used to reduce each setpoint to account for the potential activity in other releases. These administrative values shall be periodically reviewed based on actual release data and revised as required. The sum total of all these administrative values for the site shall be less than or equal to 1.0.
2.6.1 PLANTVENTSTACK-2/3RT-7808,2RT-7865-1,3RT-7865-1 2.6.1.1 2/3RT-7808 - Plant Vent Stack Monitor For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for r.oble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion j factor.
Total Body i The concentration at the detector corresponding to a 500 mrem /yrtotalbodydoserateattheexclusionareaboundary is determined by: (2-1) l cfm ' 3 (0.38) 2120 ( 500 mrem /yr)(10~5 m/cc) where: C = ' m /sec, det r 3<
3 (Flow rate, cfm)(X/Q, sec/m ) E, K,,
mmm/yr ' b 3
Ci/m , Ct ,, , ,
C,,, = the instantaneous concentration at the detector, Ci/cc 0.38 =
an administrative value used to account for potential activity from other gaseous release pathways l
i S023-00CM 2-11 Revision 26 12-20-93
2.0 GASEOUS EFFLUENTS (Continued) 2.6.1 PLANT ','ENT STACK - 2/3RT-7808, 2RT-7855-1, 3RT-7865-1 (Continued)
Ki = total body dose conv?rsion factor from Table 2-4 for the 1" gamma emitting noble gas, mrem /yrper C1/m 3 C, = concentration of the 1" noble gas as determined by sample analysis, Ci/cc C,,, = total concentration of noble gases as determined by sample analysis, Ci/cc=IC ii Flow Rate = plant vent flow rate, cfm
= 82,000cfm/ fan (xno.offanstoberun) 2120 = conversion constant, cfm per m'/sec 500 mrem /yr = total body dose rate limit, as specified by Specification 2.1.1.a
=
X/Q historical annual average disp'ersion factor foranylandwardsector,sec/m ,
=
4.8E-6 sec/m' !
Skin i i
The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by: )
(2-2) l cfm (0.38) 2120 ( 3000 mrem /yr)(10 m3 /cc)
= ' m /sec, C
det i t C, i '
(Flow rate, cfm) (X/Q, sec/m') E, L, + 1.1M,, mrem /yr 3
Ci/m , , C ,,, ,
l S023-0DCM 2-12 Revision 24 08-31-91 r
2.0 GASEOUS EFFLUENTS (Continued) 2.6.1 PLANTVENTSTACK-2/3RT-7808,2RT-7865-1,3RT-7865-1 (Continued) where:
=
Li skin Dose Conversion Factor from Table 2-4 for the i" noble gas, mrem /yr per Ci/m' t
=
Mi air Dose Conversion Factor from Table 2-4 for the i th noble gas, mrem /yr per pCi/m 3 1.1 = conversion factor to convert gamma air dose to skin dose 3000 mrem /yr =
skin dose rate limit as specified by Specification 2.1.1.a Other values in equation (2-2) are defined in equation (2-1).
The smaller of the values of C,,, from equations (2-1) or (2-2) is to be used in the determination of the maximum permissible monitoralarmsetpoint(cpm),asfollows:
l Themaximumpermissiblealarmsetpoint(cpm)isdetermined l usingthecalibrationconstantfor2/3RT-7808givenin Table 2-3. The maximum permissible alarm setpoint is the value " cpm" corresponding to the concentration, C,,, (the smaller value from equation (2-1) or (2-2)). The calibration constant used is based on Kr-85 or on Xe-133, whichever yields a lower detection efficiency (the largest value in terms of Ci/cc/ cpm).
The alarm setpoint will be maintained at a value not greater than the maximum permissible alarm setpoint.
S023-0DCM 2-13 Revision 21 02-15-90
2.0 GASEOUS EFFLUENTS (Continued) 2.6.1.2 2RT-7865-1 and 3RT-7865-1 Widt Ranae Gas Monitors The maximum release rate ( Ci/sec) for Wide Range Gt; Monitors is determined by converting the concentration at the detector, ,
C.,llows fo :( Ci/cc) to an equivalent release rate in Ci/sec,as
( C,,, , Ci/cc)(flowrate, cc/sec) (2-3) where: A,, =
2
=
A,,,, maximum permissible release rate, Ci/sec C ,, =
smaller of the values of C,,4 obtained from equations (2-1)or(2-2).
Flow Rate =
flow rate,'cc/sec
=
(3.87 x 10 cc/sec per fan) (number of fans) ,
i 2= a factor to compensate for the split flow between Unit 2 and Unit 3 plant vent stacks lj j
The release rate setpoint will not be set greater than the maximum release rate determined above, when this monitor is being used to meet the requirements of Specification 2.1.1.
l l
i S023-0DCM 2-14 Revision 26 12-20-93
2.0 GASEOUS EFFLUENTS (Continued) 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 2.6.2.1 2RT-7818 and 3RT-7818 Condenser Air E.iector Monitors For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.
The concentration at the detector corresponding to a total body doserateof500 mrem /yrattheexclusionareaboundaryis determined by using:
Total Body (2-4) !
f i cfm (0.1)(0.5) 2120 ( 500 mrem /yr) (10~8 m3 /cc)
C = ' m /sec, det / i 3
(Flow rate, cfm)(X/Q, sec/m ) 3 I, K,,
3
, Ci/m , C,,,,
The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by using:
Skin (2-4a)
C*
(0.1)(0.5) 2120 3
( 3000 mren/yr) (10~6 m3 /cc) g = 1 m/seC, det f i' (Flow rate, cfm)(X/Q, sec/m ) 3 L, + 1.1M, , * **!# '
I, r pCi/m' , C tat , _
S023-00CM 2-15 Revision 26 12-20-93
2.0 GASEOUS EFFLUENTS (Continued) 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 (Continued) where:
0.1 is an administrative value used to account for potential activity from other gaseous release pathways. 0.5 is an administrative value used to account for releases fro,a both SONGS 2 and SONGS 3 condenser air ejectors simultaneously.
Other parameters are specified in 2.6.1.1, and 2.6.2.2.
The smaller of the values Co,t from equations (2-4) or (2-4a) is to be used in determining the maximum permissible monitor alarmsetpoint(cpm),asfollows:
The maximum permissible alarm setting (cpm) is determined by using the calibration constant for the corresponding Condenser Evacuation System Monitor given in Table 2-3. The maximum permissible alarm setpoint is the cpm value corresponding to the concentration, C,,,, [ smaller value from equation (2-4) or (2-4a)].
The calibration constant used is based on Kr-85 or on Xe-133, whichever yields a lower detection efficiency (higher value in terms of C1/cc/ cpm). The alarm setpoint will not be set greater than the maximum permissible alarm setting determined above.
S023-0DCM 2-16 Revision 21 02-15-90
200 GASEOUS EFFLUENTS (Continued) 2.6.2.2 2RT-7870-1 and 3RT-7870-1 Wide Ranae Gas Monitors The maximum release rate ( C1/sec) for Wide Range Gas Monitor is determined by converting the concentration at the detector, C ,1 (pCi/cc), to an equivalent release rate in pC1/sec.
A, = ( C,,, , Ci/cc) (flow rate, cc/sec) where:
A., = maximum permissible release rate, Ci/sec Co., = smaller value of C,,,, as obtained from equations (2-4) and (2-4a) flow rate =
flow rate of the condenser air ejector, cc/sec
= 4.719E5 cc/sec (conservatively assumed as design flow rate) l S023-0DCM 2-17 Revision 26 12-20-93
i I
2.0 GASE0US EFFLUENTS (Continued) .
l 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865, 3RT-7865 For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.
The concentration at the detector corresponding to a. total body doserateof500 mrem /yrattheexclusionboundaryisdetermined j by using: l Total Body e 3 (2-6) cfm (0.38) (P,) 2120 ( 500 mrem /yr)(10-6 m3 /cc) 3 m /sec, det2 _ y 3 f i, (Flow rate, cfm)(X/Q, sec/m 3) I, K,,
, pCi/m' , ,Ctot , _
< s (2-7) cfm (0.38)(P3 ) 2120 ( 500 mrem /yr) (10 m3 /cc)
= ' m,/sec, C ,
det3 3 r 3-7 (Flow rate, cfm)(X/Q, sec/m 3) I, K,,
3 s
pCi/m , s C,,, ,
The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by using:
Skin r 3 (2-6a) cfm (0.38)(P,) 2120 ( 3000 mrem /yr) (10-6 m3 /cc) t m,/seC j gdet2 = r i*
(Flow rate, cfm)(X/Q, sec/m ) 3 I, L, + 1.1M, , * **!#
3 s Cf/m , C ,,, ,
5023-00CM 2-18 Revision 22 08-02-90
2.0 GASEOUS EFFLUENTS (Continued) l 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865, 3RT-7865 (Continued)
(2-7a) ,
f i cfm (0.38)(P3 ) 2120 3
( 3000 mrem /yr) (10~6 m/cc) 8-g _ <
m,/seCj det3 f r C, 3 -
(Flow rate, cfm)(X/Q, sec/m ) 3 I, L, + 1.1M,, m em/yr '
, pCi/m 3 , C,,,,
where:
Co.tr
=
instantaneous concentration of the Unit 2 detector, Ci/cc.
C,,,3 =
instantaneous concentratiun of the Unit 3 detector, C1/cc.
0.38 is an administrative value used to account for potential activity from other gaseous release pathways.
Pr and P3 are aoministrative values used to account for simultaneous purges of both SONGS 2 and SONGS 3. The fractions P, l
and P will be assigned such that P + P 51.0.
3 2 3 Flow rate =
observed maximum flowrate in cfm from the unit specific monitor 7828. Default values will be the following conservative measured flows- i
)
= 50,000 cfm full purge
= 3,000 cfm mini-purge (The above values replace the smaller design flowrates.)
Other parameters are as specified in 2.6.1.1 above. The smaller of the values of maximum permissible Co.tr from equation (2-6) or l 1
(2-6a)andCo,i3 trom equations (2-7) or (2-7a) is to be used in determining the maximum permissible monitor alarm setpoints.
1 S023-0DCM 2r19 Revision 28
, 12-21-95
l .
2.0 GASEOUS EFFLUENTS (Continued) m.".3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT /865, 3RT-7865 (Continued) 2.6.3.1 Maximum Permissible Alarm Settina (RT-7865) l The maximum permissible alarm setting for the Wide Range Gas Monitor expressed as a maximum release rate ( C1/sec) is determined by converting the concentration at the detector, C,,,
( Ci/cc),to an equivalent release rate in pCi/sec.
A., = ( C,,, , Ci/cc) (flow rate, cc/sec) where:
A., = maximum permissible release rate, Ci/sec S.
C ,, = smaller value of Co.,, as obtained from equation (2-6, 2-6a) for Unit 2 or (2-7, 2-7a) for Unit 3.
s flow rate = flowrate,cc/sec
= 1.416E6 cc sec for mini-purge.
= 2.360E7 cc sec for main purge.
.2 Maximum Permissible Alarm Settina (RT-7828)
The maximum permissible alarm setting for RT-7828 is in C1/cc and is the smaller of the values of Co., ( C1/cc) from equations (2-6) and (2-6a) for Unit 2 or equations (2-7, 2-7a) for j Unit 3.
l l
1 S023-0DCM 2-20 Revision 26 12-20-93
2.0 GASE0US EFFLUENTS (Continued) 2.6.4 WASTEGASHEADER-3RT-7865,2/3RT-7808 for the purpose of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent
. flow rate and the meteorological dispersion factor. Since the waste gas header discharges to the plant vent stack, either 3RT-7865or2/3RT-7808maybeusedtomonitorwastegasheader releases.
The concentration at the detector corresponding to*a total body dose rate of 500 mrem /yr or a skin dose rate of 3000 mrem /yr at t!e exclusion area boundary is determined by using equations (2-1) or (2-2) with sample concentration (C i) and (C,1) being t
obtained from the waste gas decay tank to be released.
The smaller of the values of maximum permissible concentration (C,,,) from equation (2-1) or (2-2) is to be used in determining the maximum permissible monitor alarm setpoint.
I 2/3RT-7808 The maximum permissible alarm. setting (cpm) is determined by using the calibration constant for plant vent stack monitor 7808 given in Table 2-3. The maximum permissible setroint is the cpm value corresponding to the concentration C.t. (smaller value from equation (2-1) or (2-2)).
S023-0DCM 2-21 Revision 21 02-15-90
3 2.0 GASE0US EFFLUENTS (Continued) 2.6.4 WASTEGASHEADER-3RT-7865,2/3RT-7808 (Continued) 3RT-7865 The maximum permissible alarm setting is expressed as a maximum release rate ( Ci/sec) and is determined by converting the concentration at the detector, C,,,, to an equivalent release rate in Ci/secbyequation(2-8).
l (C o ,t, C1/cc)(flowrate,cc/sec) (2-8)
A = l m
where:
Am =
the maximum permissible release rate, pCi/sec (t.
C ,, =
the smaller value of C equation (2-1)or(2-27.e,asobtainedfrom flowrate = flowrate, cc l
=
7.74E7cc/se/secc for 2 fan operation or
3.87E7cc/secfor1fanoperation 2
correction for 3-7865 viewing only 1/2 the total Plant Vent Stack Flow.
.1 A release from the waste gas header is not possible if:
, (2-9) h iC,) -
> co ,,
where:
ICi i
= total concentration in waste gas holdup tank to be released f = waste gas header effluent flow rate, cfm F = plant vent stack flowrate in cfm (164,000 cfm for 2 fan operation; 82,000 for 1 fan operation)
C,,, = smaller of the values of C,,, from equation (2-1) or (2-2) with C, being obtained from the waste gas holdup tank to be released SC23-0DCM 2-22 Revision 24 08-31-91
2.0 GASE0US EFFLUENTS (Continued) 2.6.4 WASTEGASHEADER-3RT-7865,2/3RT-7808 (Continued) 2.6.4.1 (Continued)
If a release is not possible, adjust the waste gas header flow by determining the maximum permissible waste gas header effluent flow rate corresponding to the Vent Stack Monitor setpoint in accordance with the following:
f < (0.9)(C,,,)(F) (2-10) l I, C, '
where:
f = waste gas header effluent flow rate (cfm)
F = plant vent stack flow rate (cfm) used in equation (2-1) or(2-2)
C,,, = smaller of the value of Co., from equation (2-1) or (2-2)
IC=
ii total gamma activity ( Ci/cc) of the waste gas holdup tank to be released, as determined from the pre-release sample analysis.
The 0.9 is an administrative value to account for the potential activity from other releases in the same release pathway.
4 S023-0DCM 2-23 Revision 24
')8-31-91
)
l l
1 Table 2-3(a)
Gaseous Effluent Radiation Monitor Calibration Constants (Ci/cc/ cpm)
MONITOR Kr-85 Xe-133 2/3RT-7808C 4.43E-8 4.81E-8 2RT-7818A 4.27E-8 6.86E-8 1D 3RT-7818A 3.73E-8 5.12E-8 1D l
l I
(8)This table provides typical (*20%) calibration constants for the gaseous effluent radiation monitors.
5023-0DCM 2-24 Revision 30 05-28-97
2.0 GASE0US EFFLUENTS (Continu'i) 2.7 Gaseous Effluent Dose Rate The methodology used for the purpose of implementation of Specification 2.1.1 for the dose rate above background to an individual in an unrestricted area is calculated by using the following expressions:
2.7.1 FOR N0BLE GASES:
, , (2-11) '
D 3 =I, K,(X/Q)Q, "I (2-12)
D, t (li + 1.1M,) (X/Q) Q, 1
wnere:
Dr.
total body dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem /yr D,
skin dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem /yr Ki =
the total body dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrem /yr per Ci/m 3 l
S023-0DCM 2-25 Revision 21 i 02-15-90
2.0 GASE0US EFFLUENTS (Continued) 2.7.1 FOR N0BLE GASES: (Continued)
Li =
skin dose factor due to the beta emissions from Table 2-4 for each identified noble gas radionuclide,1, in mrem /yr per yCi/m 3 M, = air dose factor due to gamma emissions from Table 2-4 for each identified noble g'as radienuclide,1, in mrad /yr per pC1/m (conversion constant of 1.1 mrem / mrad converts air dosetoskindose.)
Qi
= measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, in C1/sec ,
(X/Q) = Maximum annual average atmospheric dispersion factor for any landward sector or distance at or beyond the unrestricted area boundary.
=
4.8E-6 sec/m' for Units 2 and 3 R
= 8.0E-5 sec/m' for South Yard Facility lA '
2.7.2 FOR ALL RADIOI0 DINES. TRITIUM AND FOR ALL RADI0 ACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS:
. . (2-13) 0, =
I, I,(P,,ii,)Q, where:
D.
= organ dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem /yr S023-0DCM 2-26 Revision 30 05-28-97 !
l s
2.0' GASEOUS EFFLUENTS (Continued) 2.7.2 FOR ALL RADI0I0 DINES. TRITIUM AND FOR ALL RADI0 ACTIVE l
MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS: (Continued) l Qi
= measurea or calculated release rate of radionuclide,1, for either continuous or batch gaseous effluents,
, pCi/sec
( Pri =
dose parameter for radionuclide, i, for pathway, k, from Table 2-5 for the inhalation pathway in mrem /yr I
per pCi/m'. The dose factors are based on the critical individual organ and the child age group. l
%= highest calculated annual average dispersion (TfQ) or deposition (D7Q)factorforestimatingthedosetoan individual at or beyond the unrestricted area boundary for pathway k.
= (T/Q), 4.8E-6 sec/m' for Units 2/3 for the inhalation R -
pathway. The. location is the unrestricted area in the NW sector.
= (T/Q), 8.0E-5 sec/m' for South Yard Facility for the inhalation pathway. The location is the unrestricted A area in the E sector.
= (D7Q), 4.3E-8 m.: for Units 2/3 for the food and ground lR plane pathways. The location is the unrestricted area in the E sector.
= (D7Q), 8.0E-7 m-r for South Yard Facility for the food and ground plane pathways. The location is the h unrestricted area in the E sector.
I L
l l
l S023-0DCM 2-27 Revision 30 05-28-97
2.0 GASEOUS EFFLUENTS (Continued) ,
2.8 Gaseous Effluent Dose Calculation 2.8.1 DOSE FROM N0BLE GASES IN GASE0US EFFLUENTS l
The gaseous releases considered in the following dose calculations are described in Section 2.6. The air dose in unrestricted areas due to noble gases released in gaseous ;
i effluents is calculated using the following expressions:
2.8.1.1 For historical meteorolo_qy:
~
Dy = 3.17x10 -8 y , g, '(X/Q)Q, j D, = 3.17x10-8 I, N, (X/Q)Q, (2-15) where:
Dy = total gamma air dose from gaseous effluents, mrad D, = total beta air dose from gaseous effluents, mrad 3.17x10 8 = inverse seconds per year M, = air dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide,1, in mrad /yr per pCi/m' Ni =
air dose due to beta emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad /yr per 3
C1/m (X/Q) = Maximum annual average atmospheric dispersion factor for any landward sector or distance at or beyond the unrestricted area boundary.
=
4.8E-6 sec/m' for Units 2 and 3 P_
= 8.0E-5 sec/m for South Yard Facility 3
[A Qi = amount of noble gas radionuclide,1, released in gaseous effluents, Cf.
S023-0DCM 2-28 Revision 30 05-28-97
i 2.0 GASE0_US EFFLUENTS (Continued) 2.8.1.2 For meteoroloav concurrent with release:
NOTE: Consistent with the methe ' logy provided in Regulatory Guide 1.109 and the following equations, RRRGS (Radioactive Release Report Generating System) software is used to perform the actual calculations.
l Dg = 1.14x10 -' I , M, I,(At, (X/Q)3e ) (2-16)
D oe = 1.14x10 -' I , N, I)(At3 (X/Q)je Q ) (2~l7) g l
l l where:
Dg = total gamma air dose from gaseous effluents in sector 6, mrad D g8 = total beta air dose from gaseous effluents in sector e, mrad l
1.14 x10-* = inversehours/ year i
M, = air dose factor due to gamma emissions from Table 2-4 for each identified noble g'as radionuclide, i, in mrad /yr per Ci/m Ni =
air dose factor due to beta emissions from i
' Table 2-4 for each identified noble g'as radionuclide,i,inmrad/yrperyCi/m l At 3
= length of the j" time period over which (X/Q)38 and Qu are averaged for gaseous releases in hours l
l (X/Q)38
= atmospheric dispersion factor for time period l At3 at exclusion boundary location in I landward sector e determined by concurrent meteorology,sec/m' Qu
= average release rate of radionuclide,1, in gaseous effluents during time period, At ,3 Ci/sec S023-0DCM 2-29 Revision 28 12-21-95 1
2.0 GASE0US EFFLUENTS (Continued) 2.8.2 DOSE FROM TRITIUM. RADIOI0 DINES AND RADI0 ACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS IN GASE0US EFFLUENTS The dose to an individual from tritium, radiciodines and radioactive materials in particulata form with half lives greater than eight days in gaseous effluents released to unrestricted areas is calculated using the following expressions:
2.8.2.1 For historical meteoroloav:
(2-18)
= 3.17x10 -8 y , y t D, g g
where:
D, = total projected dose from gaseous efflur.nts to an individual, mrem 3.17x10'8 = year /second Qi
= amount of each radionuclide, i, (tritium, i radioiodine, radioactive material in ) articulate '
form with half lives greater than eig1t days),
released in gaseous effluents, pCi IgR aW ie
= sum of all pathways, k, for radionuclide, 1, of the R W product, in mrem /yr per yC1 i The I R,,W, 6
value for each radionuclide, 1, /sec.
is given in Table 2-6 for Units 2/3 and Table 2-17 for South (t
, Yard Facility. The value given is the maximum I Ri aW, for all locations and is based on the most restrictive age groups. ,
Rgi
= dose factor for each identified radionuclide,1, for mrem /pathwayk,(fortheinhalationpathwayinyr per pC1 plane pathways in m*-mrem /yr per C1/sec),atthe controlling location. The Rn's i for each controlling location for each age group are given in Tables 2-7 thru 2-16 for Units 2/3 and Tables 2-18 through 2-21 for South Yard Facility. A Data in these tables are derived using the NRC code, PARTS. (See the annual updete of revised R i parameters based on changes in the Land Use Census provided by Corporate Health Physics and Environmental.)
S023-0DCM Revision 30 2-30 05-28-97
2.0 GASE0US EFFLUENTS (Continued) 2.8.2.1 For historical meteoroloav: (Continued)
W, =
annualaveragedispersion(T[Q)ordeposition(D7Q) factor for estimating the dose to an individual at the controlling location for pathway k.
= (T/Q) for the inhalation pathway in sec/m'. l The (T/Q) for each controlling location is given in Tables 2-7 thru 2-16 for Units 2/3 and Table 2-18 g through 2-21 for South Yard Facility. !
= (D7Q) for the food and ground plane pathways in m-2 The (D/Q) for each controlling location is given in Tables 2-7 thru 2-16 for Units 2/3 and Tables 2-18 ft through 2-21 for South Yard Facility.
2.8.2.2 for meteoroloav concurrent with releases:
NOTE: Consistent with the methodology provided in Regulatory Guide 1.109 and the following equations, RRRGS (Radioactive Release Report Generating System) software is used to perform the actual calculations.
1mn r, s. (2-19)
D, = 1.14 x 10-' III (At,)(Rne)(Wne) ijk A Q'J>.
where: ,
De
= total annual dose from gaseous effluents to an individual in sector e, mrem.
At 3 =
length of the j" period over which W e3 and Qu are averaged for gaseous released, hours Qu
= average release rate of radionuclide,1, in gaseous effluents during time period At , C1/sec 3
S023-0DCM Revision 30 2-31 .
05-28-97
2.0 GASEOUS EFFLUENTS (Continued) {
2.8.2.2 For meteorolooy concurrent with releases: (Continued) f l
Rae = dose factor for each identified radionuclide i, for pathway k for sector e (for the inhalation pathway in 8
mrem /yrper Ci/m and for the food and ground plane 2
pathways in m mrem /yr per C1 location. A listing of Rn for/sec) at the controlling the controlling locations in each landward sector for each group is given in Tables 2-7 thru 2-16 for Units 2/3 and g Tables 2-18 through 2-21 for South Yard Facility. The e is determined by the concurrent meteorology.
W,=
3 dispersion (T/Q) or deposition (D7Q) factor for the time period At for each pathway k for calculating the 3
dose to an individual at the controlling location in sector e using concurrent meteorological conditions.
=
(T/Q) for the inhalation pathway, sec/m'
=
(D7Q)forthefoodandgroundplanepathways,m-r 1
1 1
S023-0DCM 1 Revision 30 1 2-32 05-28-97
TABLE 2-4 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS **
Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose Factor K i Factor L i Factor M i Factor N i Radio- (mrem /yr (mrem /r (mrad /r (mrad /r Nuclide per Ci/m') per pCi m') per pCi m') per pC1 m')
Kr-85m 1.17E+3 1.46E+3 1.23E+3 1.97E+3 Kr-85 1.61E+1 1.34E+3 1.72E+1 1.95E+3 Kr-87 5.92E+3 9.73E+3 6.17E+3 1.03E+4 Kr-88 1.47E+4 2.37E+3 1.52E+4 2.93E+3 Xe-131m 9.15E+1 4.76E+2 1.56E+2 1.11E+3 Xe-133m 2.51E+2 9.94E+2 3.27E+2 1.48E+3 Xe-133 2.94E+2 3.06E+2 3.53E+2 1.05E+3
! Xe-135m 3.12E+3 7.11E+2 3.36E+3 7.39E+2
) Xe-135 1.81E+3 1.86E+3 1.92E+3 2.46E+3 Xe-138 8.83E+3 4.13E+3 9.21E+3 4.75E+3 Ar-41 8.84E+3 2.69E+3 9.30E+3 3.28E+3
- Source: USNRC Reg. Guide 1.109, Table B-1 1
S023-0DCM 2-33 Revision 21 j 02-15-90 )
I
TABLE 2-5 DOSE PARAMETER Pa*
CHILO AGE GROUP CRITICAL ORGAN I
Radionuclide (mrem /yrperInhalation C1/m Pathway)
Radionuclide (mrem /yr perInhalation C1/m Path I
H-3 1.1E+3 I -131 -
1.6E+7 Cr-51 1.7E+4 I -132 1.9E+5 Mn-54 1.6E+6 I -133 3.8E+6 Co-57 5.1E+5 I -134 5.1E+4 i Co-58 1.1E+6 I -135 7.9 E+ 5 l Co-60 7.1E+6 Cs-134 1.0E+6 Sr-89 2.2E+6 Cs-136 1.7E+5 Sr-90 1.0E+8 Cs-137 9.1E+5 l Zr-95 2.2E+6 Ba-140 1.7E+6 Nb-95 6.1E+5 Ce-141 5.4E+5 Ru-103 6.6E+5 Ce-144 1.2E+7 i Te-129m 1.8E+6
- Source: USNRC NUREG-0133, Section 5.2.1.1 S023-0DCM 2-34 Revision 23 02-28-91
TABLE 2-6 CONTROLLING LOCATION FACTORS I RuW t
Radionuclide mrem /yrper,pC1/sec Use:
H -3 8.97E-4 Q: San Onofre Mobil. Homes Cr-51 3.00E-2 Q: San Onofre Mobil. Homes Mn-54 6.00E+0 Q: San Onofre Mobil. Homes Co-57 1.53E+0 Q: San Onofre Mobil Homes Co-58 2.15E+0 Q: San Onofre Mobil. Homes Co-60 7.86E+1 Q: San Onofre Mobil. Homes Sr-89 4.65E+1 Q: SCRanch(No.Res.)
Sr-90 1.95E+3 Q: SC Ranch (No. Res.)
Zr-95 2.69E+0 Q: San Onofre Mobil. Homes Nb-95 1.07E+1 E: Deer Consumer Hunter Ru-103 1.69E+1 E: Deer Consumer Hunter g Te-129m 8.35E+0 E: Deer Consumer Hunter j Cs-134 3.60E+1 Q: SC Ranch (No. Res.) l Cs-136 6.26E-1 Q: San Onofre Mobil. Homes Cs-137 3.45E+1 Q: SC Ranch (No. Res.) l Ba-140 1.45E+0 Q: San Onofre Mobil. Homes Ce-141 6.15E-1 Q: SCRanch(No.Res.)
Ce-144 1.80E+1 Q: SC Ranch (No. Res.)
I -131 1.39E+1 P: Cotton Point Gardens I -132 1.35E-1 Q: San Onofre Mobil. Homes I -133 2.63E+0 Q: San Onofre Mobil.Homs I -134 3.67E-2 Q: San Onot.'e Mobil. Homes j I -135 5.53E-1 Q: San Onofre Mobil. Homes 1 UN-ID 3.75E+0 Q: SC Ranch (No. Res.) l l
l Footnote: These values to be used in manual calculations are the maximum !
I,RuW, for all locations based on the most restrictive age group.
l S023-0DCM 2-35 Revision 30 05-28-97
TABLE 2-7 DOSE PARAMETER R FOR SECTOR P Page 1 of 3 Pathway =SurfBeach/ Lifeguard Distance = 0.5 miles X/Q=1.3E-6sec/m' D/Q=5.5E-9m'2 Infant Child Teen Adul t Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 7.8E+0 4.2E+1 2.9E+2 Cr-51 1.2E+2 3.2E+4 6.9E+2 1.5E+5 3.3E+3 1.1E+6 Mn-54 1.1E+4 9.5E+6 6.5E+4 4.5E+7 3.EE+5 3.2E+8 Co-57 3.5E+3 2.4E+6 1.9E+4 1.1E+7 8.4E+4 7.8E+7 Co-58 7.6E+3 2.6E+6 4.4E+4 1.2E+7 2.1E+5 8.7E+7 Co-60 4.9E+4 1.5E+8 2.9E+5 7.0E+8 1.4E+6 4.9E+9 h Sr-89 1.5E+4 1.5E+2 7.9E+4 7.1E+2 3.2E+5 4.9E+3 Sr-90 7.0E+5 3.5E+6 2.3E+7 Zr-95 1.5E+4 1.7E+6 8.8E+4 8.2E+6 4.0E+5 5.7E+7 Nb-95 4.2E+3 9.4E+5 2.5E+4 4.5E+6 1.2E+5 3.1E+7 l Ru-103 4.6E+3 7.5E+5 2.6E+4 3.6E+6 1.2E+5 2.5E+7 Te-129m 1.2E+4 1.4E+5 6.5E+4 6.4E+5 2.6E+5 4.5E+6 Cs-134 7.0E+3 4.7E+7 3.7E+4 2.2E+8 1.9E+5 1.6E+9 Cs-136 1.2E+3 1.0E+6 6.3E+3 4.9E+6 3.3E+4 3.4E+7 Cs-137 6.3E+3 7.1E+7 2.8E+4 3.4E+8 1.4E+5 2.3E+9 Ba-140 1.2E+4 1.4E+5 6.6E+4 6.7E+5 2.9E+5 4.7E+6 Ce-141 3.8E+3 9.4E+4 2.0E+4 4.5E+5 8.3E+4 3.1E+6 Ce-144 8.2E+4 4.8E+5 4.4E+5 2.3E+6 1.8E+6 1.6E+7 I -131 1.1E+5 1.2E+5 4.8E+5 5.6E+5 2.7E+6 3.9E+6 I -132 1.3E+3 8.5E+3 4.9E+3 4.1E+4 2.6E+4 2.8E+5 I -133 2.7E+4 1.7E+4 9.5E+4 8.0E+4 4.9E+5 5.6E+5 I -134 3.5E+2 3.1E+3 1.3E+3 1.5E+4 6.8E+3 1.0E+5 I -135 5.5E+3 1.7E+4 2.0E+4 8.2E+4 1.0E+5 5.8E+5 UN-ID 6.9E+3 5.1E+6 4.1E+4 2.4E+7 2.0E+5 1.7E+8 Inhalation Pathway, units = p* 7#
Food & Ground Pathway, units = i* }Imrem/vr) pC l
S023-0DCM 2-36 Revision 30 05-28-97
TABLE 2-7 DOSE PARAMETER R, FOR SECTOR P Page 2 of 3 Pathway = Cotton Point Esf.ates with Garden Distance = 2.8 miles X/Q = 1.0E-7 sec/m' D/0 = 3.0E-10 m-2 l R.
Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 4.0E+3 1.3E+3 2.6E+3 1.3E+3 2.2E+3 Cr-51 1.3E+4 4. 7E+ 6 1.7E+4 1.1E+7 2.1E+4 1.4E+7 1.4E+4 1.5E+7 Mn-54 1.0E+6 1.4E+9 1.6E+6 2.0E+9 2.0E+6 2.3E+9 1.4E+6 2.3E+9 Co-57 3.8E+5 3.4E+8 5.1E+5 5.8E+8 5.9E+5 6.6E+8 3.7E+5 6.2E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 7.4E+8 1.3E+6 9.5E+8 9.3E+5 9.7E+8 .
Co-60 4.5E+6 2.2E+10 7.1E+6 2.4E+10 8.7E+6 2.5E+10 6.0E+6 2.5E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 3.5E+10 2.4E+6 1.4E+10 1.4E+6 9.4E+9 l Sr-90 4.1E+7 1.0E+8 1.4E+12 1.1E+8 8.2E+11 9.9E+7 6.6E+11 Zr-95 1.8E+6 2.5E+8 2.2E+6 1.1E+9 2.7E+6 1.5E+9 1.8E+6 1.4E+9 Nb-95 4.8E+5 1.4E+8 6.1E+5 4.2E+8 7.5E+5 5.7E+8 5.0E+5 5.9E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 4.9E+8 7.8E+5 6.6E+8 5.0E+5 6.4E+8 l Te-129m 1.7E+6 2.0E+7 1.8E+6 2.8E+9 2.0E+6 1.7E+9 1.2E+6 1.4E+9 (
Cs-134 7.0E+5 6.8E+9 1.0E+6 3.2E+10 1.1E+6 2.3E+10 8.5E+5 1.7E+10 Cs-136 1.3E+5 1.5E+8 1.7E+5 3.5E+8 1.9E+5 3.0E+8 1.5E+5 3.0E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 3.5E+10 8.5E+5 2.4E+10 6.2E+5 1.9E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.7E+8 2.0E+6 2.1E+8 1.3E+6 2.5E+8 Ce-141 5.2E+5 1.4E+7 5.4E+5 4.0E+8 6.1E+5 5.3E+8 3.6E+5 4.9E+8 Ce-144 9.8E+6 7.0E+7 1.2E+7 9.9E+9 1.3E+7 1.3E+10 7.8E+6 1.0E+10 I -131 1.5E+7 1.7E+7 1.6E+7 4.1E+10 1.5E+7 2.7E+10 1.2E+7 3.2E+10 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 6.9E+8 2.9E+6 3.9E+8 2.2E+6 4.5E48 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 1 -135 7.0E+5 2.5E+6 7.9E+5 1.1E+7 6.2E+5 7.4E+6 4.5E+5 8.1E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 3.4E+9 1.2E+6 2.6E+9 8.6E+5 2.0E+9 ,
l l
Inhalation Pathway, units = mre r p jm' Food & Ground Pathway, units = I*
C1/sc S023-0DCM 2-37 Revision 30 05-28-97 l
TABLE 2-7 DOSE PARAMETER R FOR SECTOR P g l
Pathway = 51 Area Beach Check-In Distance = 1.4 miles X/Q=6.9E-7sec/m' D/Q=3.3E-9m' g Infant Child Teen Adul t Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.2E+2 Cr-51 3.7E+3 1.2E+6 Mn-54 3.6E+5 3.6E+8 Co-57 9.5E+4 8.8E+7 i Co-58 2.4E+5 9.8E+7 Co-60 1.5E+6 5.5E+9 l Sr-89 3.6E+5 5.5E+3 l Sr-90 2.5E+7 Zr-95 4.5E+5 6.5E+7 Nb-95 1.3E+5 3.5E+7 Ru-103 1.3E+5 2.8E+7 Te-129m 3.0E+5 5.1E+6 Cs-134 2.2E+5 1.8E+9 Cs-136 3.8E+4 3.9E+7 Cs-137 1.6E+5 2.6E+9 Ba-140 3.3E+5 5.3E*6 Ce-141 9.3E+4 3.5E+6 Ce-144 2.0E+6 1.8E+7 I -131 3.1E+6 4.4E+6 I -132 2.9E+4 3.2E+5 I -133 5.5E+5 6.3E+5 I -134 -G- 7.7E+3 1.2E+5 I -135 1.2E+5 6.5E+5 UN-ID 2.2E+5 1.9E+8 InhalationPathway, units =p"[e yr Food & Ground Pathway, units = I* I rem r)
Cij5 c S023-0DCH 2-38 Revision 30 05-28-97
TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 1 of 8 Pathway = Rec. Bldg Staff Distance = 1.2 miles 3
X/Q=8.9E-7sec/m D/Q=4.4E-9m'2 0-Infant Child Teen Adul t Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.9E+2 Cr-51 3.3E+3 1.1E+6 Mn-54 3.2E+5 3.2E+8 Co-57 8.4E+4 7.8E+7 Co-58 2.1E+5 8.7E+7 Co-60 1.4E+6 4,9E+9 Sr-89 3.2E+5 4.9E+3 Sr-90 2.3E+7 Zr-95 4.0E+5 5.7E+7 Nb-95 1.2E+5 3.1E+7 Ru-103 1.2E+5 2.5E+7 Te-129m 2.6E+5 g
4.5E+6 Cs-134 1.9E+5 1.6E+9 Cs-136 3.3/+4 3.4E+7 Cs-137 1.4E+5 2.3E+9 Ba-140 2.9E+5 4.7E+6 Ce-141 8.3E+4 3.1E+6 Ce-144 1.8E+6 1.6E+7 I -131 2.7E+6 3.9E+6 I -132 2.6E+4 2.8E+5 I -133 4.9E+5 5.6E+5 I -134 6.8E+3 1.0E+5 I -135 1.0E+5 5.8E+5 UN-ID 2.0E+5 1.7E+8 1
m InhalationPathway, units =p[emyr Food & Ground Pathway, units = * " "
Ci/sc I
S023-0DCM 2-39 Revision 30 05-28-97 i
I
TABLE 2-8 DOSE PARAMETER R FOR SECTOR Q Page 2 of 8 Pathway = San Onofre Mobile Homes Distance = 1.4 miles X/Q=6.9E-7sec/m' D/Q = 3.3E-9 m-r A
Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7 E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 3.8E+5 3.4E+8 5.1E+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 4.1E+7 1.0E+8 1.1E+8 9.9E+7 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4 E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 7.0E+5 6.8E+9 1.0E+6 6.8E+9 1.1E+6 6.8E+9 8.5E+5 6.8E+9 Cs-136 1.3E+5 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 i
Inhalation Pathway, units = p* [#
mrem /vr)
Food & Ground Pathway, units = (* }p(C I
S023-0DCM 2-40 Revision 30 05-28-97
TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 3 of 8 Pathway = State Park Office Trailer Distance = 0.6 miles 3
X/Q=2.5E-6sec/m D/Q = 1.4E-8 nr' Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 5.8E+1 Cr-51 6.6E+2 2.1E+5 Mn-54 6.4E+4 6.3E+7 Co-57 1.7E+4 1.6E+7 Co-58 4.2E+4 1.7E+7 Co-60 2.7E+5 9.8E+8 Sr-89 6.4E+4 9.9E+2 Sr-90 4.5E+6 Zr-95 8.1E+4 1.1E+7 Nb-95 2.3E+4 6.2E+6 Ru-103 2.3E+4 5.0E+6 Te-129m 5.3E+4 9.0E+5 Cs-134 3.9E+4 3.1E+8 Cs-136 6.7E+3 6.9E+6 Cs-137 2.8E+4 4.7E+8 Ba-140 5.8E+4 9.4E+5 Ce-141 1.7E+4 6.2E+5 Ce-144 3.6E+5 3.2E+6 I -131 5.4E+5 7.9E+5 I I -132 5.2E+3 5.7E+4 I -133 9.8E+4 1.1E+5 I -134 1.4E+3 2.1E+4 I -135 2.0 E+4 1.2E+5 UN-ID 3.9E+4 3.4E+7
)
m yr Inhalation Pathway, units = p Food & Ground Pathway, units = I* " "
Ci/sc l
l 5023-0DCM 2-41 Revision 30 05-28-97
TABLE 2-8 D0SE PARAMETER Ri FOR SECTOR Q Page 4 of 8 Pathway = Surf. Beach /GuardShack Distance = 0.7 miles 3
X/Q=2.0E-06sec/m D/Q = 1.1E-08 m-2 l g, )
Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & i Radio- tion Ground tion Ground tion Ground tion Ground 1 Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway l H -3 7.8E+0 4.2E+1 2.2E+2 '
Cr-51 1.2E+2 3.2E+4 6.9E+2 1.5E+5 2.5E+3 8.0E+5 ;
Mn-54 1.1E+4 9.5E+6 6.5E+4 4.5E+7 2.4E+5 2.4E+8 j Co-57 3.5E+3 2.4E+6 1.9E+4 1.1E+7 6.3E+4 5.9E+7 Co-58 7.6E+3 2.6E+6 4.4E+4 1.2E+7 1.6E+5 6.5E+7 Co-60 4.9E+4 1.5E+8 2.9E+5 7.0E+8 1.0E+6 3.7E+9 Sr-89 1.5E+4 1.5E+2 7.9E+4 7.1E+2 2.4E+5 3.7E+3 Sr-90 7.0E+5 3.5E+6 1.7 E+7 Zr-95 1.5E+4 1.7E+6 8.8E+4 8.2E+6 3.0E+5 4.3E+7 Nb-95 4.2E+3 9.4E+5 2.5E+4 4.5E+6 8.6E+4 2.3E+7 Ru-103 - 4.6E+3 7.5E+5 2.6E+4 3.6E+6 8.6E+4 1.9E+7 l
Te-129m 1.2E+4 1.4E+5 6.5E+4 g
6.4E+5 2.0E+5 3.4E+6 Cs-134 7.0E+3 4.7E+7 3.7E+4 2.2E+8 1.5E+5 1.2E+9 Cs-136 1.2E+3 1.0E+6 6.3E+3 4.9E+6 2.5E+4 2.6E+7 Cs-137 6.3E+3 7.1E+7 2.8E+4 3.4E+8- 1.1E+5 1.8E+9-Ba-140 1.2E+4 1.4E+5 6.6E+4 6.7E+5 2.2E+5 3.5E+6 Ce-141 3.8E+3 9.4E+4 2.0E+4 4.5E+5 6.2E+4 2.3E+6 )
Ce-144 8.2E+4 4.8E+5 4.4E+5 2.3E+6 1.3E+6 1.2E+7 I -131 1.1E+5 1.2E+5 4.8E+5 5.6E+5 2.0E+6 2.9E+6 I -132 1.3E+3 8.5E+3 4.9E+3 4.1E+4 2.0E+4 2.1E+5 I -133 2.7E+4 1.7E+4 9.5E+4 8.0E+4 3.7E+5 4.2E+5 I -134 3.5E+2 3.1E+3 1.3E+3 1.5E+4 5.1E+3 7.7E+4 I -135 5.5E+3 1.7E+4 2.0E+4 8.2E+4 7.7E+4 4.3E+5 l UN-ID 6.9E+3 5.1E+6 4.1E+4 2.4E+7 1.5E+5 1.3E+8
)
m yr Inhalation Pathway, units = p Food & Ground Pathway, units = I* IIrrrem/vr)
C i
S023-0DCM 2-42 Revision 30 !
05-28-97
I TABLE 2-8 DOSE PARAMETER Ri FOR SECTOR Q Page 5 of 8 Pathway =51AreaBeach[ Campground Distance = 1.2 miles X/Q=9.8E-07sec/m D/Q=5.0E-09m b Infant Child Teen Adult Inhala- Food & Inhala- Food & tnhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 8.0E+01 1.4E+02 1.6E+02 1.6E+02 Cr-51 1.6E+03 5.7E+05 2.1E+03 5.7E+05 2.6E+03 5.7E+05 1.8E+03 5.7E+05 Mn-54 1.2E+05 1.7E+08 1.9E+05 1.7E+08 2.4E+05 1.7E+08 1.7E+05 1.7E+08 Co-57 4.7E+04 4.2E+07 6.3E+04 4.2E+07 7.2E+04 4.2E+07 4.6E+04 4.2E+07 Co-58 9.6E+04 4.7E+07 1.4E+05 4.7E+07 1.7E+05 4.7E+07 1.1E+05 4.7E+07 i Co-60 5.6E+05 2.7E+09 8.7E+05 2.7E+09 1.1E+06 2.7E+09 7.4E+05 2.7E+09 '
Sr-89 2.5E+05 2.7E+03 2.7E+05 2.7E+03 3.0E+05 2.7E+03 1.7F+05 2.7E+03 Sr-90 5.0E+06 1.2E+07 1.3E+07 1.2E+07 l Zr-95 2.2E+05 3.1E+07 2.8E+05 3.1E+07 3.3E+05 3.1E+07 2.2E+05 3.1E+07 '
Nb-95 5.9E+04 1.7E+07 7.6E+04 1.7E+07 9.3E+04 1.7E+07 6.2E+04 1.7E+07 Ru-103 6.8E+04 1.3E+07 8.2E+04 1.3E+07 9.7E+04 1.3E+07 6.2E+04 1.3E407 Te-129m 2.1E+05 2.4E+06 2.2E+05 2.4E+06 2.4E+05 2.4E+06 1.4E+05 2.4E406 Cs-134 8.7E+04 8.4E+08 1.3E+05 8.4E+08 1.4E+05 8.4E+08 1.0E+05 8.4E+08 Cs-136 1.7E+04 1.9E+07 2.1E+04 1.9E+07 2.4E+04 1.9E+07 1.8E+04 1.9E+07 Cs-137 7.5E+04 1.3E+09 1.1E+05 1.3E+09 1.0E+05 1.3E+09 7.7E+04 1.3E+09 Ba-140 2.0E+05 2.5E+06 2.1E+05 2.5E+06 2.5E+05 2.5E+06 1.6E+05 2.5E+06 Ce-141 6.4E+04 1.7E+06 6.7E+04 1.7E+06 7.6E+04 1.7E+06 4.5E+04 1.7E+06 Ce-144 1.2E+06 8.6E+06 1.5E+06 8.6E+06 1.6E+06 8.6E+06 9.6E+05 8.6E+06 I -131 1.8E+06 2.1E+06 2.0E+06 2.1E+06 1.8E+06 2.1E+06 1.5E+06 2.1E+06 I -132 2.1E+04 1.5E+05 2.4E+04 1.5E+05 1.9E+04 1.5E+05 1.4E+04 1.5E+05 I -133 4.4E+05 3.0E+05 4.7E+05 3.0E+05 3.6E+05 3.0E+05 2.7E+05 3.0E+05 I -134 5.5E+03 5.5E+04 6.3E+03 5.5E+04 4.9E+03 5.5E+04 3.7E+03 5.5E+04 I -135 8.6E+04 3.1E+05 9.8E+04 3.1E+05 7.7E+04 3.1E+05 5.5E+04 3.1E+05 UN-ID 8.0E+04 9.2E+07 1.2E+05 9.2E+07 1.5E+05 9.2E+07 1.1E+05 9.2E+07 m yr Inhalation Pathway, units = g Food & Ground Pathway, units = I* IImrem/vri pC 5023-0DCM 2-43 Revision 30 05-28-97
TABLE 2-8 DOSE PARAMETER R FOR SECTOR Q i
l D
1 THIS PAGE INTENTIONALLY LEFT BLANK 1
l i l S023-0DCM 2-44 Revision 30 05-28-97
r i
TABLE 2-8 1
DOSE PARAMETER R FOR SECTOR Q Page 6 of 8 Pathway = S. C. Resident Distance = 4.1 miles X/Q = 1.4E-7 sec/m 3
D/Q = 4.7E-10 mr R Infant Child Teen Adult ,
Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0 E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 3.8E+5 3.4E+8 5.1E+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 l Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 4.1E+7 1.0E+8 1.1E+8 9.9E+7 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8 E+ 6 2.5E+8 Nb-95 4.8E+5 1.4 E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 b Cs-134 7.0E+5 6.8 E+9 1.0E+6 6.8E+9 1.1E+6 6.8E+9 8.5E+5 6.8E+9
! Cs-136 1.3E+5 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 ;
I -131 1.5E+7 1.7E+7 1.6E+7 1.7 E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1. 5 E+ 5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5Et5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 Inhalation Pathway, units = p" 7" Food & Ground Pathway, units = I* IImrem/vr) pC 1
?
S023-0DCM 2-45 Revision 30 05-28-97
TABLE 2-8 l
DOSE PARAMETER R FOR SECTOR Q Page 7 of 8 Pathway = San Clemente Ranch (No Residents) Distance = 2.2 miles X/Q = 3.5E-7 sec/m' D/Q=1.5E-9m'2 lg Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.8E+3 2.4E+3 1.9E+3 Cr-51 4.8E+6 7.4E+6 6.7E+6 Mn-54 6.1E+8 8.3E+8 8.0E+8 Co-57 2.2E+8 2.9E'8 2.4E+8 Co-58 3.3E+8 5.1E+8 4.7E+8 Co-60 2.0E+9 3.0E+9 2.7E+9 Sr-89 3.1E+10 1.2E+10 7.2E+9 Sr-90 1.3E+12 7.7E+11 5.8E+11' Zr-95 7.8E+8 1.1E+9 9.1E+8 Nb-95 2.4E+8 3.5E+8 3.1E+8 Ru-103 3.3E+8 4.5E+8 3.8E+8 Te-129m 2.3E+9 1.4E+9 9.5E+8 Cs-134 2.4E+10 1.5E+10 9.2E+9 Cs-136 9.0E+7 5.7E+7 3.6E+7 Cs-137 2.3E+10 1.3E+10 7.8E+9 Ba-140 1.1E+8 6.8E+7 5.3E+7 Ce-141 , . 3.3E+8 4.1E+8 3.2E+8 Ce-144 9.2E+9 1.2E+10 9.0E+9 I -131 4.1E+9 2.1E+9 1.4E+9 I -132 6.0E-36 2.6E-36 1.7E-36 1 -133 4.0E-11 1.7E-11 1.1E-11 I -134 6.1E-37 2.7E-37 1.7E-37 I -135 7.0E-35 3.1E-35 1.9E-35 UN-ID 2.5E+9 1.7E+9 1.1E+9 Inhalation Pathway, units = p* 7" Food & Ground Pathway, units = rem "
Cij c S023-0DCM 2-46 Revision 30 05-28-97 l
7 TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 8 of 8 Pathway = San Clemente Ranch Adm. Offices Distance = 2.6 miles lR X/Q=2.7E-7sec/m' D/Q=1.1E-9m'2 Infant Child Teen Adul t Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 4.3E+02 Cr-51 4.9E+03 1.6E+06 Mn-54 4.8E+05 4.7E+08 Co-57 1.3E+05 1.2E+08 Co-58 3.2E+05 1.3E+08 Co-60 2.0E+06 7.4E+09 Sr-89 4.8E+05 7.4 E+03 Sr-90 3.4E+07 Zr-95 6.1E+05 8.6E+07 Nb-95 1.7E+05 4.7E+07 Ru-103 1.7E+05 3.7E+07 Te-129m 4.0E+05 6.7E+06 Cs-134 2.9E+05 2.3E+09 p, Cs-136 5.0E+04 5.1E+07 Cs-137 2.1E+05 3.5E+09 Ba-140 4.4E+05 7.0E+06 Ce-141 1.2E+05 4.7E+06 Ce-144 2.7E+06 2.4E+07 I -131 4.1E+06 5.9E+06 I -132 3.9E+04 4.2E+05 I -133 7.4E+05 8.4E+05 I -134 1.0E+04 1.5E+05 I -135 1.5E+05 8.6E+05 UN-ID 3.0E+05 2.6E+08 l Inhalation Pathway, units = p"C Food & Ground Pathway, units =
- rem r)
Cij5 c S023-0DCM 2-47 Revision 30 05-28-97
TABLE 2-9 DOSE PARAMETER R FOR SECTOR R Page 1 of 3 Pathway = San Onofre Mobile Homes Distance = 1.3 miles X/Q=5.2E-7sec/m' D/Q=3.0E-9m 4 b l
Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & I Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 l Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 I Co-57 3.8E+5 3.4 E+8 5.1E+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E+8 !
Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 l Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 l Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 4.1E+7 1.0E+8 1.1E+8 9.9E+7 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 i Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 l Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 7.0E+5 6.8E+9 1.0E+6 6.8E+9 1.1E+6 6.8E+9 8.5E+5 6.8E+9 Cs-136 1.3E+5 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 l Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 l Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 l I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 l I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 l I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 Inhalation Pathway, units = p*C Food & Ground Pathway, units = I* "
C1/sc S023-0DCM 2-48 Revision 30 05-28-97
TABLE 2-9 DOSE PARAMETER R. FOR SECTOR R Page 2 of 3 Pathway = San Clemente Ranch (No Residents) Distance = 2.3 miles 3
X/Q=2.1E-7sec/m D/Q = 1.1E-9 m-r g, Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Naclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.8E+3 2.4E+3 1.9E+3 Cr-51 4.8E+6 7.4E+6 6.7E+6 I Mn-54 6.1 E+8 8.3E+8 8.0E+8 Co-57 2.2E+8 2.9E+8 2.4E+8 Co-58 3.3E+8 5.1E+8 4.7E+8 Co-60 2.0E+9 3.0E+9 2.7E+9 Sr-89 3.1E+10 1.2E+10 7.2E+9 Sr-90 1.3E+12 7.7E+11 5.8E+11 Zr-95 7.8E+8 1.1E+9 9.1E+8 Nb-95 2.4E+8 3.5E+8 3.1E+8 Ru-103 3.3E+8 4.5E+8 3.8E+8 Te-129m 2.3E+9 1.4E+9 9.5E+8 Cs-134 2.4E+10 1.5E+10 9.2E+9 Cs-136 9.0E+7 5.7E+7 3.6E+7 Cs-137 2.3E+10 1.3E+10 7.8E+9 Ba-140 1.1E+8 6.8E+7 5.3E+7 Ce-141 3.3E+8 4.1E+8 3.2E+8 Ce-144 9.2E+9 1.2E+10 9.0E+9 I -131 4.1E+9 2.1E+9 1.4E+9 I -132 6.0E-36 2.6E-36 1.7E-36 I -133 4.0E-11 1.7E-11 1.1E-11 I -134 6.1E-37 2.7E-37 1.7E-37 I -135 7.0E-35 3.1E-35 1.9E-35 UN-ID 2.5E+9 1.7E+9 1.1E+9 Inhalation Pathway, units = p* 7" Food & Ground Pathway, units = I* }Imrem/vr)
C
)
S023-0DCM 2-49 Revision 30 05-28-97
TABLE 2-9 DOSE PARAMETER Ri FOR SECTOR R Page 3 of 3 Pathway = SC Ranch Packing Distance = 2.6 miles X/Q=1.7E-07sec/m 3
D/Q=8.4E-10m-r R Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & I Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway l
H -3 5.0E+2 l Cr-51 5.8E+3 1.9E+6 Mn-54 5.6E+5 5.5E+8 Co-57 1.5E+5 1.4E+8 Co-58 3.7E+5 1.5E+8 Co-60 2.4 E+6 8.6E+9 Sr-89 5.6E+5 8.6E+3 Sr-90 4.0E+7 Zr-95 7.1E+5 1.0E+8 Nb-95 2.0E+5 5.5E+7 b Ru-103 2.0E+5 4.3E+7 l Te-129m -G- 4.6E+5 7.9E+6 Cs-134 3.4E+5 2.7E+9 Cs-136 -C- 5.8E+4 6.0E+7 Cs-137 2.5E+5 4.1E+9 Ba-140 5.1E+5 8.2E+6 Ce-141 1.4E+5 5.5E+6 Ce-144 3.1E+6 2.8E+7 I -131 4.8E+6 6.9E+6 I -132 4.6E+4 5.0E+5 I -133 8.6E+5 9.8E+5 I -134 1.2E+4 1.8E+5 I -135 1.8E+5 1.0E+6 UN-ID 3.5E+5 3.0E+8
=
m yr Inhalation Pathway, units = p mrem /vr) food & Ground Pathway, units = (* }y(C S023-0DCM 2-50 Revision 30 05-28-97 .
l l
TABLE 2-9 00SE PARAMETER R FOR SECTOR R l'
o ,
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TABLE 2-9, DOSE PARAMETER R, FOR SECTOR R b
l THIS PAGE INTENTIONALLY LEFT BLANK l
I I
S023-0DCM 2-52 Revision 30 05-28-97
TABLE 2-10 DOSE PARAMETER R, FOR SECTOR A Page 1 of 2 Pathway = Camp San Mateo Distance = 3.6 miles X/Q=7.2E-8sec/m' D/Q = 4.1E-10 m r g, Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 l Ru-103 5.0E+5 1.1E+8 )
Te-129m 1.2E+6 2.0E+7 j Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 4 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 l UN-ID 8.6E+5 7.5E+8 1
m yr Inhalation Pathway, units = p Food & Ground Pathway, units = I" }(mrem /vr)
C S023-0DCM 2-53 Revision 30 05-28-97
(
TABLE 2-10 DOSE PARAMETER R FOR SECTOR A t
i i
t l I
D l
l l
\
THIS PAGE INTENTIONALLY LEFT BLANK l
l l
l l
i I
S023-0DCM 2-54 ' Revision 30 05-28-97
TABLE 2-10 DOSE PARAMETER R, FOR SECTOR A Page 2 of 2 Pathway =DeerConsumer/ Hunter Distance = 4.2 miles l X/Q=5.7E-8sec/m 3
r &
D/Q=3.1E-10m Infant Child Teen Adult l Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground t%n Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway ya wv Pathway l I H -3 2.8E+1 2.3E+1 3.501 3.9E+1 i Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5
! Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 l
Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2. 5 E+4 4.7E+7 Co-60 3.6E47 7.2E+7 1.6E+5 7.2E+8 l Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9
, Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7 5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 l Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3- 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 l
Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 9- 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4 E+ 4 1.4E+8 <
I l
l m yr Inhalation Pathway, units = p Imrem/vr)
Food & Ground Pathway, units = (*}pC i S023-0DCM
! 2-55 Revision 30 05-28-97
TABLE 2-11 DOSE PARAMETER R FOR SECTOR B D
i
)
THIS PAGE INTENTIONALLY LEFT BLANK S023-00CM 2-56 ~ Revision 30 05-28-97
TABLE 2-11 00SE PARAMETER R F0P. SECTOR B Page 1 of 2 Pathway =DeerConsumer/ Hunter Distance = 3.8 miles g 3
X/Q=6.8E-8sec/m D/Q = -5.1E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0Et4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9
, Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = p* [#
Food & Ground Pathway, units = "" !Vr)
Ci/sec S023-0DCM 2-57 Revision 30 1 05-28-97 i j
TABLE 2-11 DOSE PARAMETER R FOR SECTOR B Page 2 of 2 Pathway = Sanitary Landfill Distance = 2.1 miles 3
X/Q=1.3E-7sec/m D/Q=1.1E-9m'2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.9E+2 Cr-51 3.3E+3 1.1E+6 Mn-54 3.2E+5 3.2E+8 Co-57 8.4E+4 7.8E+7 Co-58 2.1E+5 8.7E+7 Co-60 1.4E+6 4.9E+9 Sr-89 3.2E+5 4.9E+3 Sr-90 2.3E+7 Zr-95 4.0E+5 5.7E+7 Nb-95 1.2E+5 3.1E+7 Ru-103 1.2E+5 2.5E+7 Te-129m 2.6E+5 4.5E+6 Cs-134 1.9E+5 1.6E+9 Cs-136 3.3E+4 3.4E+7 Cs-137 1.4E+5 2.3E+9 3 Ba-140 2.9E+5 4.7E+6 l Ce-141 8.3E+4 3.1E+6 l Ce-144 1.8E+6 1.6E+7 I -131 2.7E+6 3.9E+6 I -132 2.6E+4 2.8E+5 I -133 4.9E+5 5.6E+5 I -134 6.8E+3 1.0E+5 I -135 1.0E+5 5.8E+5 UN-ID 2.0E+5 1.7E+8 m yr Inhalation Pathway, units = p Food & Ground Pathway, units = I* }Imrem/vr) pC S023-0DCM 2-58 Revision 30 05-28-97 i
TABLE 2-12 DOSE PARAMETER R, FOR SECTOR C Page 1 of 4 Pathway = Camp San Onofre Distance = 2.6 miles 3
X/Q=9.7E-8sec/m D/Q=8.9E-10m' lg Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 i Ce-144 7.8 E+ 6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 m yr Inhalation Pathway, units = p Food & Ground Pathway, units = I* IImrem/vr) pC S023-0DCM 2-59 Revision 30 05-28-97
TABLE 2-12 DOSE PARAMETER R, FOR SECTOR C i Page 2 of 4 Pathway = Camp San Onofre Fr. Stn Distance = 2.5 miles X/Q=1.0E-7sec/m' D/Q=9.4E-10m.: F Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 5.2E+2 Cr-51 5.9E+3 1.9E+6 Mn-54 5.8E+5 5.7E+8 Co-57 1.5E+5 1.4E+8 Co-58 3.8E+5 1.6E+8 Co-60 2.5E+6 8.8E+9 Sr-89 5.8E+5 8.9E+3 Sr-90 4.1E+7 Zr-95 7.3E+5 1.0E+8 Nb-95 2.1E+5 5.6E+7 i Ru-103 2.1E+5 4.5E+7 i Te-129m 4.8E+5 8.1E+6 i Cs-134 3.5E+5 2.8E+9 Cs-136 6.0E+4 6.2E+7 Cs-137 2.6E+5 4.2E+9 Ba-140 5.2E+5 8.4E+6 Ce-141 1.5E+5 5.6E+6 Ce-144 3.2E+6 2.9E+7 I -131 4.9E+6 7.1E+6 I -132 4.7E+4 5.1E+5 I -133 8.8E+5 1.0E+6 I -134 1.2E+4 1.8E+5 I -135 1.8E+5 1.0E+6 UN-ID 3.6E+5 3.1E+8 m yr Inhalation Pathway, units = p m mrem /M Food & Ground Pathway, units =
Ci/sec S023-0DCM 2-60 Revision 30 05-28-97
i l
TABLE 2-12 DOSE PARAMETER R, FOR SECTOR C Page 3 of 4 Pathway = Sewage Facility Distance = 2.2 miles 3
X/Q=1.3E-7sec/m D/Q=1.2E-9m g Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.9E+2 Cr-51 3.3E+3 1.1E+6 Mn-54 3.2E+5 3.2E+8 Co-57 8.4E+4 7.8E+7 Co-58 2.1E+5 8.7E+7 Co-60 1.4E+6 4.9E+9 Sr-89 3.2E+5 4.9E+3 Sr-90 2.3E+7 Zr-95 4.0E+5 5.7E+7 Nb-95 1.2E+5 3.1E+7 Ru-103 1.2E+5 2.5E+7 Te-129m 2.6E+5 4.5E+6 Cs-134 1.9E+5 1.6E+9 Cs-136 3.3E+4 3.4E+7 Cs-137 1.4E+5 2.3E+9 Ba-140 2.9E+5 4.7E+6 Ce-141 8.3E+4 3.1E+6 Ce-144 1.8E+6 1.6E+7 I -131 2.7E+6 3.9E+6 I -132 2.6E+4 2.8E+5 I -133 4.9E+5 5.6E+5 I -134 6.8E+3 1.0E+5 1 -135 1.0E+5 5.8 E+ 5 UN-ID 2.0E+5 1.7E+8 InhalationPathway, units =p*F'*[7" Food & Ground Pathway, units = " "
Ci/s i S023-0DCM 2-61 Revision 30 05-28-97
TABLE 2-12 DOSE PARAMETER Ri FOR SECTOR C D
THIS PAGE INTENTIONALLY LEFT BLANK S023-0DCM 2-62 Revision 30 05-28-97
TABLE 2-12 DOSE PARAMETER R FOR SECTOR C Page 4 of 4 Pathway =DeerConsumer/ Hunter Distance = 1.0 miles 3
X/Q=4.0E-7sec/m D/Q = 4,6E-9 m-4 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway l
H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4- 4.1E+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 l~
Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 i Ru-103 4.2E+8 7.5E+8 1.4E+4' 1.3E+9 Te-129m - 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 l Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 i Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 .0- 4.2E+6 3.5E+4 7.4E+6 Ce-141- 1.5E+6 2.4E+6 9.9E+3 4.2E+6 i Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 )
I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 I
l Inhalation Pathway, units = p* 7" Food &GroundPathway, Units ='*y'Ci/sjc S023-0DCM 2-63 Revision 30 05-28-97
TABLE 2-13 DOSE PARAMETER R FOR SECTOR D Page 1 of 2 Pathway = Camp San Onofre Distance = 3.0 miles X/Q=6.9E-8sec/m' S D/Q=7.2E-10m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 Zr-95 1.8 E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I.-134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units = p* 7" Food & Ground Pathway, units = I* "
Ci/sc S023-0DCM 2-64 Revision 30 05-28-97
}
TABLE 2-13 DOSE PARAMETER R, FOR SECTOR D f
I l
l D THIS PAGE INTENTIONALLY LEFT BLANK l
S023-0DCM
- 2-65 Revision 30 l 05-28-97
TABLE 2-13 DOSE PARAMETER R FOR SECTOR D Page 2 of 2 Pathway =DeerConsumer/ Hunter Distance = 0.8 miles X/Q=5.3E-7sec/m' D/Q=7.3E-9m.: 9 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 ,
Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 l Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 )
Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 i Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 !
Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 {
Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 2
Ba-140 l5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 'l1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 n. -0 I1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1 E+8 9.4E+7 2.4E+4 1.4E+8 l
l l
Inhalation Pathway, units = ["
Food & Ground Pathway, units = I* IImrem/vr)
C S023-0DCM 2-66 Revision 30 05-28-97
l TABLE 2-14 I
DOSE PARAMETER R FOR SECTOR E Page 1 of 3 Pathway = Camp Horno Distance = 4.1 miles X/Q=7.5E-8sec/m' D/Q=7.2E-10m b Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 l 1 -131 1.2E+7 1.7E+7 l I -132 1.1E+5 1.2E+6 i I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8
{
l m yr Inhalation Pathway, units = p Food & Ground Fathway, units = I*
Ci/sc S023-00CM l
2-67 Revision 30 l 05-28-97 i
TABLE 2-14 DOSE PARAMETER R FOR SECTOR C Page 2 of 3 Pathway = Sheep (Meat)[ Shepherd Distance = 5.0 miles X/Q=5.6E-8sec/m D/Q=5.0E-10m.: 6 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 Cr-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 0- 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 ,
Sr-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 l Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 !
Zr-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.1E+3 4.3E+3 8.1 E+ 2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 6.3E+2 6.8E+3 I I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4. 2 E+6 Inhalation Pathway, units = p* 7" Food & Ground Pathway, units = *' "
Ci/sc S023-0DCM 2-68 Revision 30 05-28-97
TABLE 2-14 DOSE PARAMETER R FOR SECTOR E Page 3 of 3 Pathway =DeerConsumer/ Hunter Distance = 0.8 miles X/Q=8.5E-7sec/m' D/Q=1.3E-8m'2 S Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 i Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 ?
Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4 E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 l Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = p* 7" Food & Ground Pathway, units = '* "
Ci/s S023-0DCM 2-69 Revision 30 05-28-97
1 TABLE 2-15 DOSE PARAMETER R FOR SECTOR F Page 2 of 4 Pathway = Border Patrol Checkpt. Distance = 1.8 miles -
X/Q=2.8E-7sec/m' D/Q=2.1E-9m'2 g g, Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.6E+2 Cr-51 4.1E+3 1.3E+6 Mn-54 4.0E+5 3.9E+8 Co-57 1.1E+5 9.8E+7 Co-58 2.6E+5 1.1E+8 Co-60 1.7E+6 6.1E+9-Sr-89 4.0E+5 6.2E+3-Sr-90 2.8E+7 Zr-95 5.0E+5 7.2E+7 Nb-95 1.4E+5 3.9E+7 Ru-103 1.4E+5 3.1E+7 Te-129m 3.3E+5 5.6E+6 Cs-134 2.4E+5 1.9E+9 Cs-136 4.2E+4 4.3E+7 Cs-137 1.8E+5 2.9E+9 Ba-140 3.6E+5 5.9E+6 Ce-141 1.0E+5 3.9E+6 Ce-144 2.2E+6 2.0E+7 I -131 3.4E+6 4.9E+6 I -132 3.3E+4 3.5E+5 I -133 6.1E+5 7.0E+5 I -134 8.5E+3 1.3E+5 I -135 1.3E+5 7.2E+5 UN-ID 2.5E+5 2.1E+8 t
Inhalation Pathway, units = p* ["
Food & Ground Pathway, units = I* IImrem/vr) pC S023-0DCM 2-71 Revision 30 05-28-97
TABLE 2-15 DOSE PARAMETER R FOR SECTOR F P.9e 3 of 4 Pathway = Sheep (Meat)[ Shepherd Distance = 5.0 miles X/Q=6.2E-8sec/m D/Q = 3.3E-10 m-r R Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 Cr-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 '3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 ~3.1E+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E&4 1.1E+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 Cs-137' 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I I -131 6.6E+5 4.4 E+5 6.6E+4 7.0E+5 I -132 6.3E+2 6.8E+3 I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 l
1 Inhalation Pathway, units = p* E mr /vr)
Food & Ground Pathway, units = (* }p(C S025-0DCM 2-72 Revision 30 05-28-97
TABLE 2-15 DOSE PARAMETER R FOR SECTOR F Page 4 of 4 Pathway =DeerConsumer/ Hunter Distance = 1.5 miles g_
X/Q = 3.6E-7 sec/m' D/Q=2.8E-9m-r l
Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
i Radio- tion Ground tion Ground tion Ground tion Ground l Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway l H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 i Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 l Mn-54 7.7E+5 1.4E+6 3.8 E+4 4.IE+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E47 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2. 7 E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 i Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 l I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 I
l Inhalation Pathway, units = p* 7" Food & Ground Pathway, units = * "
Ci/sc l
l i
S023-0DCM 2-73 Revision 30 05-28-97 L
TABLE 2-16 DOSE PARAMETER R FOR SECTOR G Page 1 of 2 Pathway = San Onofre State Beach Campground Distance = 0.9 miles 3 g j X/Q=6.6E-7sec/m D/Q=3.3E-9m'2 1
Infant
~
Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 8.0E+1 1.4E+2 1.6E+2 1.3E+3 Cr-51 1.6E+3 5.7E+5 2.1E+3 5.7E+5 2.6E+3 5.7E+5 1.4E+4 4.7E+6 Mn-54 1.2E+5 1.7E+8 1.9E+5 1.7E+8 2.4E+5 1.7E+8 1.4E+6 1.4E+9 Co-57 4.7E+4 4.2E+7 6.3E+4 4.2E+7 7.2E+4 4.2E+7 3.7E+5 3.4E+8 Co-58 9.6E+4 4.7E+7 1.4E+5 4.7E+7 1.7E+5 4.7E+7 9.3E+5 3.8E+8 Co-60 5.6E+5 2.7E+9 8.7E+5 2.7E+9 1.1E+6 2.7E+9 6.0 E+6 2.2E+10 Sr-89 2.5E+5 2.7E+3 2.7E+5 2.7E+3 3.0E+5 2.7E+3 1.4E+6 2.2E+4 Sr-90 5.0E+6 1.2E+7 1.3E+7 9.9E+7 Zr-95 2.2E+5 3.1E+7 2.8E+5 3.1E+7 3.3E+5 3.1E+7 1.8E+6 2.5E+8 Nb-95 5.9E+4 1.7E+7 7.6E+4 1.7E+7 9.3E+4 1.7E+7 5.0E+5 1.4E+8 Ru-103 6.8E+4 1.3E+7 8.2E+4 1.3E+7 9.7E+4 1.3E+7 5.0E+5 1.1E+8 Te-129m 2.1E+5 2.4E+6 2.2E+5 2.4E+6 2.4E+5 2.4E+6 1.2E+6 2.0E+7 p Cs-134 8.7E+4 8.4E+8 1.3E+5 8.4E+8 1.4E+5 8.4E+8 8.5E+5 6.8E+9 Cs-136 1.7E+4 1.9E+7 2.1E+4 1.9E+1 2.4E+4 1.9E+7 1.5E+5 1.5E+8 Cs-137 7.5E+4 1.3E+9 1.1E+5 1.3E+9 1.0E+5 1.3E+9 6.2E+5 1.0E+10 Ba-140 2.0E+5 2.5E+6 2.1E+5 2.5E+6 2.5E+5 2.5E+6 1.3E+6 2.1E+7
- Ce-141 6.4E+4 1.7E+6 6.7E+4 1.7E+6 7.6E+4 1.7E+6 3.6E+5 1.4E+7 Ce-144 1.2E+6 8.6E+6 1.5E+6 8.6E+6 1.6E+6 8.6E+6 7.8E+6 7.0E+7 l 1 -131 1.8E+6 2.1E+6 2.0E+6 2.1E+6 1.8E+6 2.1E+6 1.2E+7 1.7E+7 j I -132 2.1E+4 1.5E+5 2.4E+4 1.5E+5 1.9E+4 1.5E+5 1.1E+5 1.2E+6 I -133 4.4E+5 3.0E+5 4.7E+5 3.0E+5 3.6E+5 3.0E+5 2.2E+6 2.4E+6 I -134 5.5E+3 5.5E+4 6.3E+3 5.5E+4 4.9E+3 5.5E+4 3.0E+4 4.5E+5 I -135 8.6E+4 3.1E+5 9.8E+4 3.1E+5 7.7E+4 3.1E+5 4.5E+5 2.5E+6 UN-ID 8.0E+4 9.2E+7 1.2E+5 9.2E+7 1.5E+5 9.2E+7 8.6E+5 7.5E+8 l
l m yr Inhalation Pathway, units = p Food & Ground Pathway, units =
C1/sc S023-0DCM 2-74 Revision 30 05-28-97
TABLE 2-16 DOSE PARAMETER R FOR SECTOR G !
Page 2 of 2 I Pathway = Hwy Patrol Weigh Station I Distance = 2.0 miles '
X/Q=1.9E-7sec/m' D/Q=8.0E-10mr Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.0E+2 Cr-51 3.4E+3 1.1E+6 Mn-54 3.3E+5 3.3E+8 Co-57 8.8E+4 8.1E+7 Co-58 2.2E+5 9.0E+7 Co-60 1.SE+6 5.1E+9 l Sr-89 3.3E+5 5.1E+3 l Sr-90 2.4E+7 1 Zr-95 4.2E+5 6.0E+7 l
Nb-95 1.2E+5 3.2E+7 Ru-103 1.2E+5 2.6E+7 Te-129m 2.8E+5 4.7E+6 Cs-134 2.0E+5 1.6E+9 Cs-136 3.5E+4 3.6E+7 Cs-137 1.5E+5 2.4E+9 i Ba-140 3.0E+5 4.9E+6 Ce-141 8.6E+4 3.2E+6 Ce-144 1.8E+6 1.7E+6 I -131 2.8E+6 4.1E+6 I -132 - 2.7E+4 2.9E+5 I -133 5.1E+5 5.8E+5 I -134 7.1E+3 1.1E+5 I -135 1.1E+5 6.0E+5 UN-ID 2.1E+5 1.8E+8 1
Inhalation Pathway, units = p*C Food & Ground Pathway, units = (m )(mrem /vr)
C1/sec S023-0DCM 2-75 Revision 30 05-28-97
TABLE 2-16 DOSE PARAMETER R FOR SECTOR G D
THIS PAGE INTENTIONALLY LEFT BLANK I
)
l S023-0DCM 2-76 Revision 30 05-28-97
TABLE 2-16 DOSE PARAMETER R, FOR SECTOR G D
THIS PAGE INTENTIONALLY LEFT BLANK i 1
ll S023-0DCM 2-77 Revision 30 05-28-97
2.0 GASEOUS EFFLUENTS (Continued) 2.9 TOTAL DOSE CALCULATIONS 2.9.1 Total Dose to Most Likely Member of the Public The total annual dose or total dose commitment to any member of the public, due to releases of radioactivity and to radiation, from uranium fuel cycle sources within 5 miles of the Site is calculated using the following expressions.
l This methodology is used to meet the dose limitations of 40 CFR 190 per twelve consecutive months. The transportation of radioactive material is excluded from the dose calculations.
The Annual Total Dose is determined monthly for maximum organ (gas & liquid), whole body (gas & liquid) and thyrcid !
(gas & liquid) to verify that the Site total (Units 1, 2 and
- 3) is less than or equal to 25 mrem, 25 mrem, and 75 mrem respectively.
.1 Annual Total Oraan Dose (D or (0))i (2-20) 12 2/3 Dror (0) = I I Dp (0G) + pD (0L) + Dj,.(0G) 1=1 j=1 where:
- NOTE: Df(0G) = 0 for bone i
- All to be summed over the most recent 12 months.
n !
Dp (0G) = K I C,E,R g W, (2-21) !
i=1 l i
i = each i',otope in specific organ category !
j = Units 1, 2 and 3 1 = months 1 - 12**
year- Ci K = 3.1688 E-2 sec-Ci 5023-0DCM 2-78 Revision 21 02-15-90
2.0 GA5E005 EFFLUENTS (Continued) 2.9 TOTAL DOSE CALCULATIONS (Continued) l 2.9.1 Total Dose to Most Likely Member of the Public (Continued) n =
number of isotopes in the specified organ category )
C, = total particulate gas curies released for the month IRaW, = controlling location factors from ODCM Table 2-5, k Unit 1 and lable 2-6, Units 2/3, for all pathways k.
Op (0L) = liquid organ dose for the specified organ in mrem for the month. [ReferenceODCMUnits2/3(1-10), Unit 1 (1-13)]
Df(0G)* = as organ dose form tritium in mrem for the month.
ReferenceODCMUnit1(2-14),ODCMUnits2/3(2-18)]
.2 Annual Total Whole Body Dose Dro7(WB) l 12 2/3 (2-22)
Drot(WB) = I I Dj (WBL)+ Dj,(0G) + 0.9 Dj(y) +D(DIRECT) l 1=1 j=1 ;
where:
j= Units 1, 2 and 3 1= months 1 - 12, to be sunned over the most recent 12 months Dp(WBL) = liquid whole body organ dose in mrem for the whole month.
(1-13)] [ Reference ODCM Units 2/3 (1-19), ODCM Unit 1 Df(0G) = fasorgandosefromtritiuminmremforthemonth, ReferODCMUnits2/3(2-18),ODCMUnit1(2-14)]
Do (y) = gamma air dose in mrad for the month.
0.9 converts mrad to mrem.
[ReferenceODCMUnits2/3(2-14),ODCMUnit1(2-10)]
n (2-23) 4 I 0(bkgd),
D (Direct) = I max [D(beach),]
P"I .0342 q=1 p = for all TLDs per quarter q = for Quarters 1-4 S023-0DCM 2-79 Revision 26 12-20-93 i
2.0 GASE0US EFFLUENTS (Continued) 2.9 TOTAL D0SE CALCULATIONS (Continued) 2.9.1.2 Annual Total Whole Body Dose DrodWDB1 -(Continued)
- Direct Radiation The direct radiation levels are evaluated mest recently using cadmium covered TLDs. The TLDs are placed at 47 locations around the site. The average dose measured by.
TLDs 5 to 50 miles from the site is used as background.
These sites are subject to change.
The background is subtracted from the highest reading TLD within 5 miles of the site (generally numbers 55 through 58). This value is the direct dose but must be prorated by the occupancy factor.
Example: Beachtime(westboundary, seawall)of300 hrs /yr,eastandnorthboundariesof20 hrs /yr, or 8 hrs /yr for the south boundary and west fence of parking lot 1 (top of !
bluff).
Reference:
E. M. Goldin Memorandum for File, " Occupancy Factors at San Onofre Owner Controlled Area Boundaries," dated October 1, 1991.
.3 Annual Total Thyroid Dose Dro r (T) 1 12 2/3 Dm(T) = I I 'Dj (0G) + Dg (0L)'
l=1 j=1 (2-24) where:
-j= Units 1, 2 and 3 1= months 1 - 12, to be summed over the most recent 12 months D3 (0G)
= thyroid organ dose from gaseous iodine for the month in mrem. (from2-21)
D3 (0L) = liquid thyroid organ dose for the month in mrem.
, [Ref " eODCMUnits2/3(1-19), Unit 1ODCM (1-13n S023-0DCM 2-80 Revision 26 12-20-93
TABLE 2-17 SOUTH YARD FACILITY CONTk9LLING LOCATION FACTORS I,R aW i
Radionuclide mrem /yr per ,pCi/sec Use:
H-3 1.31E-03 G: SAN ONOFRE BCH CAMPGD I
Cr-51 4.15E-02 F: SOST.PK./GUARDSHACK Mn-54 9.70E+00 F: SOST.PK./GUARDSHACK l
Co-57 2.41E+00 F: S0ST.PK./GUARDSHACK l Co-58 3.14E+00 F: SOST.PK./GUARDSHACK l Co-60 1.35E+02 F: SOST.PK./GUARDSHACK l Sr-89 1.71E+00 F: DEERCONSUMER/ HUNTER J
! Sr-90 1.04E+02 G: SAN ON0FRE BCH CAMPGD Zr-95 7.26E+00 F: DEERCONSUMER/ HUNTER Nb-95 2.88E+01 F: DEERCONSUMER/ HUNTER
, Ru-103 4.56E+01 F: DEERCONSUMER/ HUNTER Te-129m 2.26E+01 F: DEERCONSUMER/ HUNTER Cs-134 4.28E+01 F: SOST.PK./GUARDSHACK l Cs-136 ,
1.04E+00 F: SOST.PK./GUARDSHACK l Cs-137 6.36E+01 F: SOST.PK./GUARDSHACK Ba-140 1.39E+00 G: SAN ON0FRE BCH CAMPGD Ce-141 .
4.29E-01 G: SAN ONOFRE BCH CAMPGD Ce-144 8.39E+00 G: SAN ON0FRE BCH CAMPGD I-131 2.28E+01 F: DEERCONSUMER/ HUNTER I-132 1.22E-01 G: SAN ON0FRE BCH CAMPGD I-133 2.22E+00 G: SAN ON0FRE BCH CAMPGD I-134 3.24E-02 G: SAN ON0FRE BCH CAMPGD I-135 4.60E-01 G: SAN ON0FRE BCH CAMPGD UN-ID 5.36E+00 F: SOSTPK./GUARDSHACK l
Footnote: These values to be used in manual calculations are the maximum I,R i ,W, for all locations based on the most restrictive age group.
l l
S023-0DCM i
2-81 Revision 28
. 12-21-95
TABLE 2-18 SOUTH YARD FACILITY D0SE PARAMETER R FOR SECTOR D i Page 1 of 1 Pathway = Camp Horno Sewage Trmnt. Distance = 3.0 Miles X/Q = 1.2E-7 sec/m' D/Q = 1.2E-9/m-2 Infant Child Teen Adul t Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground. tion Ground tion Ground-Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway I H-3 2.9E+2 !
CR-51 3.3E+3 1.1E+6 MN-54 3.2E+5 3.2E+8 l
C0-57 8.4E+4 7.8E+7 C0-58 2.1E+5 8.7E+7 i C0-60 1.4E+6 4.9E+9 SR-89 3.2E+5 4.9E+3 l SR-90 2.3E+7 !
ZR-95 4.0E+5 5.7E+7 NB-95 - 1.2E+5 3.1E+7 RU-103 1.2E+5 2.5E+7 TE-129m 2.6E+5 4.5E+6 CS-134 1.9E+5 1.6E+9'
! CS-136 3.3E+4 3.4E+7 l
CS-137 - 1.4E+5 2.3E+9 l BA-140 2.9E+5 4.7E+6 CE-141 8.3E+4 3.1E+6 CE-144 1.8E+6 1.6E+7 I-131 2.7E+6 3.9E+6 ,
I-132 2.6E+4 2.8E+5 I-133 4.9E+5 5.6E+5 I-134 6.8E+3 1.0E+5 I-135 1.0E+5 5.8E+5 UN-ID 2.0E+5 1.7E+8 1'
Inhalation Pathway, units = p* 7" Food & Ground Pathway, units = "
C1/sc i
l I
S023-0DCM l 2-82 Revision 28 12-21-95
TABLE 2-19 SOUTH YARD FACILITY DOSE PARAMETER R, FOR SECTOR E Page 1 of 1 Pathway = Camp Horno Distance = 3.7 Miles 8
X/0 = 6.0E-7 sec/m D/Q = 5.7E-9 /m'2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 1.3E+3 CR-51 1.4E+4 4.7E+6 MN-54 1.4E+6 1.4E+9 C0-57 3.7E+5 3.4E+8 C0-58 9.3E+5 3.8E+8 C0-60 6.0E+6 2.2E+10 SR-89 1.4E+6 2.2E+4 SR-90 9.9E+7 ZR-95 1.8E+6 2.5E+8 NB-95 5.0E+5 1.4E+8 RU-103 5.0E+5 1.1E+8 TE-129M 1.2E+6 2.0E+7 CS-134 8.5E+5 6.8E+9 CS-136 1.5E+5 1.5E+8 CS-137 6.2E+5 1.0E+10 BA-140 1.3E+6 2.1E+7 CE-141 3.6E+5 1.4E+7 .
CE-144 7.8E+6 7.0E+7 l I-131 1.2E+7 1.7E+7 I-132 f 1.1E+5 1.2E+6 1 1-133 2.2E+6 2.4E+6 I-134 3.0E+4 4.5E+5 I-135 4.5E45 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units = p* 7" Food & Ground Pathway, units = "" "
Ci/sjc 1
l S023-00CM 2-83 Revision 28 12-21-95 i
IABLE 2-20 SOUTH YARD FACILITY DOSE PARAMETER R FOR SECTOR F Page 1 of 4 Pathway =SanOnofreStatePark/GuardShack Distance = 0.4 Miles 3
X/Q = 5.4E-6 sec/m D/Q = 3.5E-8 /m2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 2.2E+2 CR-51 2.5E+3 8.0E+5 MN-54 2.4E+5 2.4E+8 C0-57 6.3E+4 5.9E+7 C0-58 1.6E+5 6.5E+7 C0-60 1.0E+6 3.7E+9 SR-89 2.4E+5 3.7E+3 SR-90 1.7E+7 ZR-95 3.0E+5 4.3E+7 NB-95 8.6E+4 2.3E+7 RU-103 8.6E+4 1.9E+7 TE-129M 2.0E+5 3.4E+6 CS-134 1.5E+5 1.2E+9 CS-136 2.5E+4 2.6E+7 CS-137 1.1E+5 1.8E+9 BA-140 2.2E+5 3.5E+6 CE-141 6.2E+4 2.3E+6 CE-144 1.3E+6 1.2E+7 I-131 2.0E+6 2.9E+6 I-132 2.0E+4 2.1E+5 I-133 3.7E+5 4.2E+5 I-134 5.1E+3 7.7E+4 I-135 7.7E+4 4.3E+5 l UN-ID 1.5E+5 1.3E+8 Inhalation Pathway, units = p* 7#
Food & Ground Pathway, units = "
C1/sc S023-0DCM 2-84 Revision 28
. 12-21-95
TABLE 2-20 SOUTH YARD FACILITY DOSE PARAMETER R. FOR SECTOR F Page 2 of 4 Pathway = Border Patrol Checkpt. Distance = 1.4 Miles 2
X/Q = 1.2E-6 sec/m D/Q = 8.2E-9 /m-r Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 3.6E+2 l CR-51 4.1E+3 1.3E+6 MN-54 4.0E+5 3.9E+8 C0-57 1.1E+5 9.8E+7 C0-58 2.6E+5 1.1E+8 l C0-60 1.7E+6 6.1E+9 l SR-89 4.0E+5 6.2E+3 i SR-90 2.8E+7 !
ZR-95 5.0E+5 7.2E+7 l NB-95 1.4E+5 3.9E+7
! RU-103 1.4E+5 3.1E+7 l TE-129M 3.3E+5 5.6E+6 CS-134 2.4E+5 1.9E+9 I
CS-136 4.2E+4 4.3E+7 CS-137 1.8E+5 2.9E+9 BA-140 3.6E+5 5.9E+6~
i CE-141 1.0E+5 3.9E+6 l CE-144 2.2E+6 2.0E+7 I-131 3.4E+6 4.9E+6 I-132 3.3E+4 3.5E+5 I-133 6.1E+5 7.0E+5 I-134 8.5E+3 1.3E+5 I-135 1.3E+5 7.2E+5 UN-ID 2.5E+5 2.1E+8 l
Inhalation Pathway, units = pmremyr Food & Ground Pathway, units = I"IImrem/vr)
C l-l l
l l
S023-0DCM 2-85 Revision 28 l 12-21-95
l TABLE 2-20 l SOUTH YARD FACILITY DOSE PARAMETER R, FOR SECTOR F Page 3 of 4 Pathway = Sheep (Meat)[ Shepherd Distance = 0.3 Miles X/Q = 7.2E-6 sec/m D/0 = 4.5E-8 /m-r Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 CR-51 5.1E+1 1.0E4 2 7.9E+1 2.6E+4 MN-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 C0-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 C0-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 C0-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 SR-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 j SR-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 ZR-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 )
NB-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 l RU-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 I
( TE-129M 6.0E+5 4.5E+5 6.4E+3 7.6E+5 CS-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 ,
CS-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 l CS-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 {
BA-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 j CE-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 l CE-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 {
I-131 6.6E+5 4.4E+5 6.6E44 7.0E+5 j I-132 6.3E+2 6.8E+3 j I-133 1.6E+2 8.7E+3 1.2E+4 1.3E+4 I-134 1.6E+2 2.5E+3 I-135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units = p* 7" mrem /vr) food & Ground Pathway, units = (* }y(C l
I S023-0DCM 2-86 Revision 28 12-21-95
l TABLE 2-20 SOUTH YARD FACILITY DOSE PARAMETER R FOR SECTOR F Page 4 of 4 Pathway =DeerConsumer/ Hunter Distance = 0.4 Miles 3
X/Q = 5.4E-6 sec/m D/Q = 3.5E-8 /m-Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 CR-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 MN-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 C0-57. 4.6E+6 8.0E+6 1.0E+4 2.3E+7 C0-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 C0-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 SR-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 SR-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 ZR-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 NB-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 RU-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 TE-129M 5.9E+8 4.5E+8 3.2E+4 6.4E+8 CS-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 CS-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 CS-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 BA-140 - 5.0E+6 4.2E+6 3.5E+4 7.4E+6 CE-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 CE-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I-131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I-132 3.1E+3 3.4E+4 I-133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I-134 8.2E+2 1.2E+4 I-135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = p* 7" Food & Ground Pathway, units = I* IImrem/vr) pC S023-00CM 2-87 Revision 28
. 12-21-95
TABLE 2-21 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR G Page 1 of 4 Pathway = San Onofre Bch Campgd Distance = 0.4 Miles X/Q = 4.5E-6 sec/m' D/Q = 1.8E-8 /m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 8.0E+1 1.4E+2 1.6E+2 2.9E+2 CR-51 1.6E+3 5.7E+5 2.1E+3 5.7E+5 2.6E+3 5.7E+5 3.3E+3 1.1E+6 MN-54 1.2E+5 1.7E+8 1.9E+5 1.7E+8 2.4E+5 1.7E+8 3.2E+5 3.2E+8 C0-57 4.7E+4 4.2E+7 6.3E+4 4.2E+7 7.2E+4 4.2E+7 8.4E+4 7.8E+7 C0-58 9.6E+4 4.7E+7 1.4E+5 4.7E+7 1.7E+5 4.7E+7 2.1E+5 8.7E+7 C0-60 5.6E+5 2.7E+9 8.7E+5 2.7E+9 1.1E+6 2.7E+9 1.4E+6 4.9E+9 SR-89 2.5E+5 2.7E+3 2.7E+5 2.7E+3 3.0E+5 2.7E+3 3.2E+5 4.0E+3 SR-90 5.0E+6 1.2E+7 1.3E+7 2,3E+7 ZR-95 2.2E+5 3.1E+7 2.8E+5 3.1E+7 3.3E+5 3.1E+7 4.0E+5 5.7E+7 NB-95 5.9E+4 1.7E+7 7.6E+4 1.7E+7 9.3E+4 1.7E+7 1.2E+5 3.1E+7 RU-103 6.8E+4 1.3E+7 8.2E+4 1.3E+7 9.7E+4 1.3E+7 1.2E+5 2.5E+7 TE-129M 2.1E+5 2.4E+6 2.2E+5 2.4E+6 2.4E+5 2.4E+6 2.6E+5 4.5E+6 CS-134 8.7E+4 8.4E+8 1.3E+5 8.4E+8- 1.4E+5 8.4E+8 1.9E+5 1.6E+9 CS-136 1.7E+4 1.9E+7 2.1E+4 1.9E+7 2.4E+4 1.9E+7 3.3E+4 3.4E+T CS-137 7.5E+4 1.3E+9 1.1E+5 1.3E+9 1.0E+5 1.3E+9 1.4E+5 2.3E+9 BA-140 2.0E+5 2.5E+6 2.1E+5 2.5E+6 2.5E+5 2.5E+6 2.9E+5 4.7E+6 CE-141 6.4E+4 1.7E+6 6.7E+4 1.7E+6 7.6E+4 1.7E+6 8.3E+4 3.1E+6 CE-144 1.2E+6 8.6E+6 1.5E+6 8.6E+6 1.6E+6 8.6E+6 1.8E+6 1.6E+7 I-131 1.8E+6 2.1E+6 2.0E+6 2.1E+6 1.8E+6 2.1E+6 2.7E+6 3.9E+6 I-132 2.1E+4 1.5E+5 2.4E+4 1.5E+5 1.9E+4 1.5E+5 2.6E+4 2.8E+5 I-133 4.4E+5 3.0E+5 4.7E+5 3.0E+5 3.6E+5 3.0E+5 4.9E+5 5.6E+5
.I-134 5.5E+3 5.5E+4 6.3E+3 5.5E+4 4.9E+3 5.5E+4 6.BE+3 1.0E+5 I-135 8.6E+4 3.1E+5 9.8E+4 3.1 E+5 7.7E+4 3.1E+5 1.0E+5 5.8E+5 UN-ID 8.0E+4 9.2E+7 1.2E+5 9.2E+7 1.5E+5 9.2E+7 2.0E+5 1.7E+8 Inhalation Pathway, units = p*I'* 7" Food & Ground Pathway, units = I"IImrem/vri pC S023-0DCM 2-88 Revision 28 12-21-95
TABLE 2-21 SOUTH YARD FACILITY DOSE PARAMEiER R FOR SECTOR G Page 2 of 4 1 Pathway r Highway Patrol Weigh Station Distance = 1.6 Miles X/Q = 4.2E-7 sec/m' D/Q = 1.7E-9 /m-r Infant Child Teen Adult ,
inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & l Radio- tion Ground tion Ground tion Ground tion Ground l Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 3.0E+2 CR-51 3.4E+3 1.1E+6 MN-54 3.3E+5 3.3E+8 C0-57 8.8E+4 8.1E+7 C0-58 2.2E+5 9.0E+7 C0-60 -0< 1.4E+6 5.1E+9 SR-89 3.3E+5 5.1E4 3 SR-90 2.4E+7 ZR-95 4.2E+5 6.0E+7 NB-95 1.2E+5 3.2E+7 RU-103 '
1.2E+5 2.6E+7 TE-129M 2.8E+5 4.7E+6 CS-134 2.0E+5 1.6E+9 CS-136 3.5E+4 3.6E+7 CS-137 1.5E+5 2.4E+9 BA-140 3.0E+5 4.9E+6 CE-141 8.6E+4 3.2E+6 CE-144 1.8E+6 1.7E+7 I-131 2.8E+6 4.1E+6 I-132 2.7E+4 2.9E+5 I-133 5.1E+5 5.8E+5 I-134 7.1E+3 1.1E+5 I-135 1.1E+5 6.0E+5 UN-ID 2.1E+5 1.8E+8 i
l l
mrem /vr Inhalation Pathway, units = pC1/m' i
Food & Ground Pathway, units = (m )(mrem /vr) -
Ci/sec S023-0DCM 2-89 Revision 28 12-21-95
~
l l
TABLE 2-21 SOUTH YARD FACILITY DOSE PARAMETER R, FOR SECTOR G Page 3 of 4 Pathway = Sheep (Meat)[ Shepherd Distance = 2.3 Miles X/Q = 2.4E-7 sec/m D/Q = 9.2E-10 /m Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 CR-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 MN-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 C0-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 C0-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 C0-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 SR-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 SR-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 ZR-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 NB-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 RU-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 TE-129M 6.0E+5 4.5E+5 6.4E+3 7.6E+5 CS-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 CS-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 CS-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 BA-140 1 5.1E+3 4.3E+3 7.0E+3 1.2E+5 CE-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 CE-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I-131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I-132 6.3E+2 6.8E+3 I-133 1.6E+2 8.7E+3 1.2E+4 1.3E+4 I I-134 1.6E+2 2.5E+3 1-135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID .
1.1E+5 9.5E+4 4.8E+3 4.2E+6 l
Inhalation Pathway, units = p* 7" Food & Ground Pathway, units = I* }Imrem/vr)
C 5023-0DCM 2-90 Revision 28 12-21-95
TABLE 2-21 SOUTH YARD FACILITY DOSE PARAMETER R, FOR SECTOR G Page 4 of 4 Pathway =DeerConsumer/ Hunter Distance = 2.9 Miles 3
X/Q = 1.8E-7 sec/m D/Q = 6.4E-10 /m'8 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 CR-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 MN-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 C0-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 C0-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 C0-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 SR-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 SR-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 ZR-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 NB-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 RU-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 TE-129M 5.9E+8 4.5E+8 3.2E+4 6.4E+8 CS-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 CS-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 CS-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 BA-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 CE-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 CE-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I-131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I-132 3.1E+3 3.4E+4 I-133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I-134 8.2E+2 1.2E+4 I-135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8
[I Inhalation Pathway, units = p*
Food & Ground Pathway, units = (m mremM C1/sec S023-0DCM i 2-91 Revision 28 12-21-95
3.0 PROJECTED DOSES 3.1 Liquid Dose Projection The methodology used for projecting a liquid dose over 31 days for Specification 1.3.1 is as follows:
1 1
- 1. Determine the monthly total body and organ doses resulting )
I from releases during the previous twelve months. l
- 2. Projected dose = Previous 12 months' dose divided by 12 for the total body and each organ.
3.2 Gaseous Dose Projection The methodology used for projecting a gaseous dose over 31 days for Specification 2.4.1 is as follows:
- 1. Determine the monthly gamma, beta and organ dose resulting ,
i from releases during the previous twelve months.
- 2. Projected dose = Previous 12 months' dose divided by 12 for the gamma, beta and organ doses.
S023-00CM 3-1 Revision 22 08-02-90
1 4.0 EOUIPMENT 4.1 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION f SPECIFrCATION 4.1.1. The radioactive liquid effluent monitoring instrumentation channels shown in Table 4-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 1.1.1 are not exceeded. Thealarm/ trip setpoints of these channels shall be determined in accordance with Section 1.4.
APPLICABILITY: At all times ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm conservative than required by/ trip setpoint the-above less specification, j immediately suspend the release of radioactive liquid i effluents monitored by the affected channel or declare the channel inoperable. !
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 4-1. Exert best efforts to l
return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain l inoperable for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the
- inoperability was not corrected in a timely manner.
- c. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-1 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-2, an INVESTIGATIVE REPORT shall be prepared which identifies the cause(s) for the event and defines the corrective actions to be taken to preclude recurrence of the event.
SURVEILLANCE RE0VIREMENTS
.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK.
SOURCE CHECK, CHANNEL CALIBRATION and' CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-2.
.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all pumps required to be providing dilution to meet the site radioactive effluent concentration limits of Specification 1.1.1 shall be determined to be operating and i providing dilution to the disc. je structure. l i
S023-0DCM 4-1 Revision 26 12-20-93
5 2
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L (s l u1 o o L (s o o A i iS2 l l i l l 0 t nl x 8 B B S t nl B B I S n e
wo ur7 E n wo D R oP Ae- ) ) C e oP ) ) _
O u d ,t 8 9 I u d 8 9 A
R T l we aR T8 8 V l we 8 8 I f ot sW) 0 0 E f ot 0 0 N f l a p 3 E E D f l a E E OE E Bs mg( (9 (3 E Bs ( (
MS n un2 5 5 T n A e re Si r7 r7 N e re r r YE t od l - o6 o6 E t od o o TL s t n toe tT tT M s t n t t IE a w
ao non aR r) aR E a ao a a VR rC aCi r) R w rC r r I d e l L e3 e3 U d e e e TF a nw Pt n( n( S a nw n n CO A
R eo nt e2 e2 A E
R eo e e Gl een G G Gl G G
- 0N d F nne - - M d F T IO i m iou m m i m m m N DI u al b pl ae ae E u al a a E AT q el rmf en en T q el e e M RA i tu uof ti ti A i tu t t U N L SF TCE SL SL R L SF S S R SI _
T SM W S OR O N RE . . . . . L . . . .
I GT a b c d e F a b c d 1 2
TABLE 4-1 (Continued)
TABLE NOTATION Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become-inoperable (i.e., feedback signal). As long as the monitor has indication, alarmcapability(ifapplicable),
requirements)andisolationfunction propif(erresponse(baseduponsurveillance applicable), the loss of the recorder does not render the monitor inoperable.
ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Specification 1.1.1 and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculation and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 29 - With~ the number of channels OPERABLE less than required by the Minimum Channels OPERABLE recuirement, effluent releases via this pathway may continue providec grab samples are analyzed for gross radioactivity (beta or gamma) at a 11mit of detection of at least 10-7 microcuries/ gram:
- a. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant.is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131;
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal' to 0.01 microcuries/gramDOSEEQUIVALENTI-131;or
- c. Lock closed valve HV-3773 and divert flow to T-064 for processing as liquid radwaste.
ACTION 30 - With the number.of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of collection time for gross radioactivity (beta or gamma) at a limit l of detection of at least 10-' microcuries/ml or lor.k closed valve S2(3)2419MUO77 ors 2(3)2419MUO78anddivertflowtotheradwaste sump for processing as liquid radwaste.
ACTION 31 - With the number of channels OPERABLE less than required by the l Minimum Channels OPERABLE requirement, effluent releases via this ~
pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used ,
to estimate flow.
S023-0DCM 4-3 Revision 22 08-02-90 1
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U NA - af un af L ON rE Ba n n rE n n F MI e t T w w t w w F M n ur y o o e ur o o E YR i ee re d d n ee a d TE L Nh (s
a g1 w9 w i Nh w w D IT V s ia2 o5 o L (s o o I i l r8 l7 l i l l U IC t nl io7 B6 B S t nl B B O TI n wo xt - - E n wo I CT e oP uST )T ) C e oP ) )
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TGS E iR u
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- SIE T SVR W N OO O E RRF . . . . . L . . . .
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I 1 2
TABLE 4-2 (Continued)
TABLE NOTATION l
Monitor Recorders are not required for the Operability of the monitor, l providing the inoperable recorder does not cause the monitor to become l inoperable (i.e., feedback signal). As long as the monitor has indication, l alarm capability (ifisolation applicable), propif (er responsethe (based upon {
requirements) and function applicable), loss of the surveillance !
recorder does not render the monitor inoperable.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent I path isolation actuation signal, automatic patf4 -
solation, and Control g. {
Room alarm annunciation if any of the followint ,'tions exist:
j
- 1. Instrument indicates measured levels abov: larm/tripsetpoint.
- 2. Circuit failure.
g Automatic pathway isolation is tested on a once per refueling period. [4 !
Down scale failure testing is bounded by administrative limitation on monitor setpoint which ensure monitor alarm and release termination occur prior to A reaching the level of monitor saturation.
If the instrument controls are not in the operate mode, procedures shall p require that the channel be declared inoperable.
(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Stanheds and Technology or using standards that have been obtained from su)phers that participate in measurement assurance activities with NIST. T1ese standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONS, sources that have been related to the initial calibration shall be used.
(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
I i
S023-0DCM l 4-5 Revision 30 05-28-97
)
l 4.0 E0VIPMENT 4.2 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.2.1 The radioactive gaseous effluent monitoring l
1 instrumentation channels shown in Table 4-3 shall be OPERABLEwiththeiralarm/tripsetpointssettoensure that the limits of Specification 2.1.1 are not exceeded.
The alarm / trip setpoints of these channels shall be determined in accordance with ODCM.
APPLICABILITY: At all times '
ACTION:
- a. With a radioactive gaseous effluent monitoring ;
instrumentation channel alarm !
conservative than required by/ the trip abovesetpoint less specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.
l b. With less than the minimum number of radioactive gaseous l
effluent monitoring instrumentation channels OPERABLE, l take the ACTION shown in Table 4-3. Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain inoperable for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the l inoperability was not corrected in a timely manner.
I
- c. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-3 not taken
, or the necessary surveillances not performed at the l l specified frequency prescribed in Table 4-4, an i INVESTIGATIVE REPORT shall be prepared which identifies !
, the cause(s) for the event and defines the corrective actions to be taken to preclude recurrence of the event.
I SURVEILLANCE RE0VIREMENTS l .1 Each radioactive gaseous effluent monitoring instrumentation l channel shall be demonstrated OPERABLE by performance of the l CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-4.
S023-00CM 4-6 Revision 26 l 12-20-93
N O
I 56 70066 70066 80066 7 T 33 34433 34433 34433 2 C M A Cn4 Do9 0i -
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v e e v e e Y l E l S i p l t R i p l t _
( t r m p a A t m p a c a m R c r a m R _
Y A e S a N A e S a T
e l
e S w O l S w I p o I e p e o L t m t d l T t m t d l I a a a e F A a a a e F C l S l t N l S l t
- A u u a s I u u a s
- F c e c i s M c e c i s
- i n i c e A i n i c e T D t i t o c T t i t o c N R r d r s o N r d r s o E A a o a s r O a o a s r M Y P I P A P C P I P A P U E R H D T T S U F N O . . . . . Y . . . . .
I S a b c d e S a b c d e 5 6
TABLE 4-3 (Continued)
TABLE NOTATION At all times.
MODES 1-4 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.
Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based upon surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.
(1) 2(3)RT-7818isnotequippedtomonitorprocessflow. If another means of continuously monitoring process flow is not available, then comply with ACTION 36.
(2) 2/3RT-7808 is not equip)ed to monitor process flow. If 2RT-7865 and 3RT-7865 are not availa)le to continuously monitor plant vent stack flow, then comply with ACTION 36.
(3) .Due to unequal mixing in the Plant Vent Stack, both 2RT-7865 and 3RT-7865
~
are required to be operable when 2/3RT-7808 is inoperable.
(4) With only one channel operable, channel may be sampled so long as the time that the channel is shut down is one hour or less. Ref: Memorandum for File. " Units 2/3 - Clarification No.14", by G. T. Gibson, dated June 30, 1983. I I
ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend releases of radioactive effluents via this pathway.
ACTION 36 - With the number of channels OPERABLE less than required by the Minimum ,
Channels OPERABLE requirement, effluent releases via this pathway may l continue provided the flow rate is estimated at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. System design characteristics may be used to estimate flow.
S023-0DCM 4-9 Revision 27 12-21-94
TABLE 4-3 (Continued)
TABLE NOTATION ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.
ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 2-1.
1 S023-00CM 4-10 Revision 26 12-20-93
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TABLE NOTATION At all times.
Modes 1-4 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.
Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based upon surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation actuation signal, automatic pathway isolation, and Control @. I Room alarm annunciation if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
lD l Automatic pathway isolation is tested on a once per refueling interval. The main containment purge isolation valves are required to be tested in Mode 5 prior to performing initial core alterations. Containment purge valves are not required to be tested for automatic isolation in the event of a mid- A cycle outage.
Down scale failure testing is bounded by administrative limitation on monitor setpoints which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation.
If the instrument controls are not set in the operate mode, procedures shall F call for declaring the channel inoperable.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:#
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure. gg j Down scale failure testing is bounded by administrative limitation on monitor setpoints which ensure monitor alarm and release termination occur A prior to reaching the level of monitor saturation.
If the instrument controls are not set in the operate mode, procedures shall p call for declaring the channel inoperable.
S023-0DCM 4-14 Revision 30 05-28-97
l l
TABLE 4-4 (Continued)
TABLE NOTATIQ3 (Continued) i i
l (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONS, sources that have f-been related to the initial calibration shall be used.
(4) Prior to each release and at least once per month.
(5) Daily checks only required during times of building occupation.
F S023-0DCM 4-15 Revision 27 12-21-94
4.3 OPERABILITY OF RADI0 ACTIVE WASTE EQUIPMENT The flow diagrams defining the treatment paths and the components of the radioactive liquid, gaseous and solid waste management systems are shown in Figures 4-5 thru 4-7.
S023-0DCM 4-16 Revision 21 02-15-90
r FIGURE 4-5 SONGS 2 & 3 RADI0 ACTIVE LIQUID WASTE TREATMENT SYSTEMS I l
l l
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( 088 -l l .
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Condensate Monitor Tanks .l2/3AT-7813 l (Batch) Intake Out"all
,l l l Radiation Monitor NOT[I Monitor pathways are unit specific unless indicated to be coanon to Units 2 and 3.
S023-0DCM 4-17 Revision 28 12-21-95
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5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Monitorina Proaram SPECIFICATION 5.1.1 The radiological environmental monitortra program shall be conducted as specified in Table 5-1. The requirements are applicable at all times.
APPLICABILITY: At all times ACTION:
- a. Should the radiologica1' environmental monitoring program not be conducted as specified in Table 5-1, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the R.
Commission, in the Annual Radiological Environmental Operating Report (see Section 5.4), a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
l b. Should the level of radioactivity in an environmental sampling medium exceed the reporting levels of Table 5-2
- when averaged over any calendar quarter, in lieu of any I
other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the g Commission, within 30 days from the end of the affected calendar quarter a Report pursuant to 10 CFR 50.73. When more than one of the radionuclides in Table 5-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) + . . 2 1.0 limit level (1) limit level (2)
- c. When radionuclides other than those in Table 5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or year limits of Specification (greater than the calendars) 1.2.1, 2.2 appropriate. This report is not required if the measured level of radioactivity was not the result of plant l effluents; however, in such an event, the condition shall l be reported and described in the Annual Radiological Environmental Operating Report (see Section 5.4).
S023-0DCM 5-1 Revision 30 i
, 05-28-97 l
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued)
ACTION: (Continued)
- d. With fresh leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table 5-1, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the commission g, within 30 days, pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples.
The locations from which samples were unavailable may then be deleted from those required by Table 5-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.
SURVEILLANCE RE0VIREMENTS
.1 The radiological environmental monitoring samples shall be collected pursuant to Table 5-1 from the locations given in Tables 5-4 and 5-5 and Figure 5-1 and shall be analyzed pursuant to the requirements of Tables 5-1 and 5-3.
I S023-00CM 5-2 Revision 30 05-28-97
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- TABLE 5-3 (Continued)
TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
l 4.66 s b l LLD =
l E . V . 2.22 x 10 . Y . exp (-AAt) 8 j
where l l
LLD is the "a priori" lower limit of detection as defined above (as {
microcurie per unit mass or volume),
i s is the standard deviation of the background counting rate or of tIie counting rate of a blank sample as appropriate (as counts per minute),
i E is the counting efficiency (as counts per transformation),
V is che sample size (in units of mass or volume),
2.22 x 10' is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
l A is the radioactive decay constant for the particular radionuclide, and At is the elaased time between midpoint of samale collection or end of the collection environmental samples, period and time of counting (for notplanteffluents).
The value of so used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the i LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E,V,Y and At shall be used in the calculations.
It should be recognized that the LLD is defined as an a priori (before the I fact) limit representing the capability of the measurement system and not as l A posteriori (after the fact) limit for a particular measurement.* p
- For a more complete discussion of the LLD, and other detection limits, see the following:
(1) HASLProceduresManual,HASL-300(revisedannually).
(2) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968). lb S023-0DCM 5-9 Revision 30 05-28-97
TABLE 5-3 (Continued)
TABLE NOTATION P
- b. Ifnodrinkingwaterpathwayexists,avalueof3000pC1/1maybeused. [q
- c. Other peaks which are measurable and identifiable, together with the radionuclides in Table 5-3, shall be identified and reported.
- d. Ifnodrinkingwaterpathwayexists,avalueof15pCi/lmaybeused. A h
S023-0DCM 5-10 Revision 30 05-28-97
- n. -
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.2 LAND USE CENSUS SPECIFICATION 5.2.1- A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden
- of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.
APPLICABILITY: At all times ACTION:
- a. Withalandusecensusidentifyingalocation(s)which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification -
2.3.1, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days, pursuant to R.
Technical Specification Section 5.7.2 and LCS 5.0.104.2, a I Special Re> ort which identifies the new location (s).
Identify tie new locations in the next Annual Radioactive Effluent Release Report.
- b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment via the same exposure pathway 20 percent greater than at a location from which samples are currently being obtained in accordance with Section 5.1, in lieu of an~y other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days, R pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control station i location, having the lowest calculated dose or dose ;
commitment via the same exposure pathway may be deleted '
from this monitoring program after October 31 of the year in which this land use census was conducted.
SURVEILLANCE RE0!)IREMENTS
.1. The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.
be performed at the site boundary in the
- direction Broad leaf vegetation sector sampling with the highest D may /Q in lieu of the garden census.
S023-0DCM 5-11 Revision 30 05-28-97
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.3 INTERLABORATORY COMPARIS0N PROGRAM SPECIFICATION 5.3.1 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.
APPLICABILITY: At all times ACTION:
- a. With analyses not being performed as required above, report the corrective actions taken to prevant a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
SURVEILLANCE RE0VIREMENTS
.1 A summary of the results obtained as part of the above required Interlaboratory Comparison Program and its accordance with Section 5.4.1 of this document shall be included in the Annual Radiological Environmental Operating Report (see Section 5.4).
l I
i S023-0DCM 5-12 Revision 22 l 08-02-90
]
1 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 5.4.1 The annual radiological environmental operating reports 1 shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Section 5.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports I shall irclude summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be .
submitted noting and explaining the reasons for the missing ,
results. The missing data shall be submitted as soon as '
possible in a supplementary report.
The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and-directions from the mid-point of reactor Units 2 and 3; and the results of licensee participation in the Interlaboratory Comparison Program, required by Section 5.3.
A single submittal may be made for a multi)1e unit station, combining those sections that are common to all units at tie station. !
S023-0DCM 5-13 Revision 21 02-15-90 1
1
_j
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.5 SAMPLE LOCATIONS The Radiological Environmental Monitoring Sample Locations are identified in Figure 5-1. These sample locations are described in Tables 5-4 and 5-5 and indicate the distance in miles and the direction, determined from degrees true north, from the center of the Units 2 and 3 building complex. Table 5-6 gives the sector and direction designation for the Radiological Environmental Monitoring Sample Location on Map, Figure 5-1.
l l
i I
I l
l l
l 1
S023-0DCM i 5-14 Revision 21 02-15-90 l
)
Page 1 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- l TYPE OF SAMPLE AND SAMPLING LOCATION *** (miles) DIRECTION
- l Direct Radiation 1 CityofSanClemente(FormerSDG&EOffices) 5.6 -NW l 2 CampSanMateo(MCB,CampPendleton) 3.5 N l 3 Camp San Onofre (MCB, Camp Pendleton) 2.6 NE 4 Camp Horno (MCB, Camp Pendleton) 4.5 E l
! 6 OldRoute101(East-Southeast) 3.0 ESE 8 Noncommissioned Officers'. Beach Club 1.5 NW 10 Bluff (Adjacent to PIC #1) 0.7 WNW 11 Former Visitors' Center 0.3** NW 12 South Edge of Switchyard 0.2** E 13 Southeast Site boundary (Bluff) 0.4** SE 14 Huntington Beach Generating Station 37.0 NW 15 Southeast Site Boundary (Office Building) 0.2** SE 16 East Southeast Site Boundary 0.4** ESE i
17 Transit Dose - -
18 Transit Dose - -
19 San Clemente Highlands 5.0 NNW 22 Former U.S. Coast Guard Station - San Mateo Point 2.7 WNW 23 San Clemente General Hospital 8.2 NW i
Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north. i Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.
- MCB - Marine Corps Base PIC - Pressurized Ion Chamber Locations previously deleted and removed: 5, 7, 9, 20, 21, 24, 25 through 30, 32, 37, 39,.42, 43, 45, 48, 51, 52.
I S023-0DCM 5-15 Revision 28 12-21-95
(
I Page 2 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION *** (miles) DIRECTION
- Direct Radiation (Continued) 31 Aurora Park-Mission Viejo 18.7 NNW 33 Camp Talega (MCB, Camp Pendleton) 5.7 N 34 San Onofre School (MCB, Camp Pendleton) 1.9 NW 35 Range 312 (MCB, Camp Pendleton) 4.7 NNE 36 Range 208C (MCB, Camp Pendleton) 4.2 NE 38 San Onofre State Beach Park 3.3 SE 40 SCE Training Center - Mesa (Adjacent to PIC #3) 0.7 NNW 41 Old Route 101 - East 0.4** E 44 Fallbrook Fire Station 18.0 E l 46 San Onofre State Beach Park 1.0 SE 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 SE l
1 1
Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
- Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all l sectors) and not required by Technical Specification.
- MCB - Marine Corps Base PIC - Pressurized Ion Chamber Locations previously deleted and removed: 5, 7, 9, 20, 21, 24 25 through 30, 32, 37, 39, 42, 43, 45, 48, 51, 52.
S023-0DCM 5-16 Revision 28 12-21-95
Page 3 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION *** (milesl DIRECTION
- Direct Rt.diation (Continued) 49 CampChappo(MCB,CampPendleton) 12.8 ESE 50 Oceanside Fire Station (CONTROL) 15.5 SE l 53 San Diego County Operations Center 45.0 SE i l 54 Escondido Fire Station 32.0 ESE l
55 SanOnofreStateBeach(Unit 1,WestSouthwest) 0.2** WSW 56 SanOnofreStateBeach(Unit 1, Southwest) 0.1** SW j
, 57 SanOnofreStateBeach(Unit 2) 0.1** SSW I 58 SanOnofreStateBeach(Unit 3) 0.1** S 59 SONGS Meteorological Tower 0.3** WNW l 60 Transit Control Storage Area - -
l 61 Mesa - East Boundary (Adjacent to PIC 74) 0.7 N l l 62 MCB - Camp Pendleton (Adjacent to PIC f5) 0.6 NNE l 63 MCB - Camp Pendleton (Adjacent to PIC #6) 0.6 NE i 64 MCB - Camp Pendleton (Adjacent to PIC #7) 0.5 ENE 65 MCB - Camp Pendleton (Adjacent to PIC #8) 0.7 E 66 San Onofre State Beach (Adjacent to PIC #9) 0.6 ESE l 67 Former SONGS Evaporation Pond (Adjacent to PIC #2) 0.6 NW L 68 Range 210C (MCB, Camp Pendleton) 4.3 ENE 73 South Yard Facility 0.05** NE i
Transit Control A - -
L Transit control B - -
Fader (Co-Located with TLD f 54)**** 32.0 ESE Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.
MCB - Marine Corps Base PIC - Pressurized Ion Chamber
- For fading correction due to significant increase in temperature.
Locations previously deleted and removed: 5, 7, 9, 20, 21, 24, 25 through 30, 32, 37, 39, 42, 43, 45, 48, 51, 52.
S023-0DCM 5-17 Revision 28 12-21-95
Page 4 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION
- Airborne 1 City of San Clemente (City Hall) 5.5 NW 2 CampSanOnofre(CampPendleton) 1.8 NE 3 Huntington Beach Generating Station (CONTROL) 37.0 NW 5 Units 2 and 3 Switchyard 0.13** NNE 7 AWS Roof 0.18** NW 9 State Beach Park 0.6 ESE 10 Bluff 0.7 WNW 11 Mesa E0F 0.7 NNW 12 Former SONGS Evaporation Pond 0.6 NW 13 Marine Corps Base (Camp Pendleton East) 0.7 E Soil Samples 1 Camp San Onofre 2.5 NE 2 Old Route 101 - East Southeast 3.0 ESE 3 BasiloneRoad/I-5FreewayOfframp 2.0 NW 4 HuntingtonBeachGeneratingStation(CONTROL) 37.0 NW 5 Former Visitor's Center 0.2** NNW Ocean Water A Station Discharge Outfall - Unit 1 0.5 SSW B Outfall - Unit 2 0.7 SW C Outfall - Unit 3 0.7 SW D NewportBeach(CONTROL) 30.0 NW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
- Distances are within the Units 2 and 3 Site boundary (0.4 mile in all ,
sectors) and not required by Technical Specification. ,
l l
l S023-0DCM 5-18 Revision 26 12-20-93 j
I Page 5 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION
- Drinking Water 1 Deleted 2 Deleted b 3 Huntington Beach (CONTROL) 37.0 NW 4 Camp Pendleton Drinking Water Reservoir 2.2 NNW lA 1
Shoreline Sediment (Beach Sand) 1 San Onofre State Beach (0.6 mile Southeast) 0.6 SE l 2 San Onofre Surfing Beach 0.9 NW 3 San Onofre State Beach (3.1 miles Southeast) 3.1 l SE 4 Newport Beach (North End) (CONTROL) 30.0 NW Local Crops 1 San Mateo Canyon (San Clemente Ranch) 2.6 NW 2 Oceanside (CONTROL)** 15 to 25 SE to ESE R-
- 3. Cotton Point Estates Gardens (Casa Pacifica) 2.8 WNW 1
l l
l Distance (miles) and Directior. (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
Control location should be in Section G or F,15 to 25 miles from site. The 4 control location will be selected based on sample availability. The exact g I location shall be noted in the Annual Radiological Environmental Operating l Report.
l i S023-0DCM 5-19 Revision 30 05-28-97 l )
l J
Page 6 of 6 ,
TABLE 5-4 f RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION
- Non-Migratory Marine Animals A Unit 1 Outfall 0.9 WSW B Units 2 and 3 Outfall 1.5 SSW lA C LagunaBeach(CONTROL) 18.2 NW Kelp A San Onofre Kelp Bed 1.5 S !
B San Mateo Kelp Bed 3.8 WNW C Barn Kelp Bed 6.3 SSE D LagunaBeach(CONTROL) 15.6 NW Ocean Bottom Sediments A Unit 1 Outfall (0.5 mile West) 0.6 W B Unit 1 Outfall (0.6 mile West) 0.8 SSW j C Unit 2 Outfall 1.6 SW D Unit 3 Outfall 1.2 SSW E Laguna Beach (CONTROL) 18.2 NW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
i S023-0DCM l 5-20 Revision 30 l 05-28-97 i
TABLE 5-5 PIC - RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Theta DISTANCE
- PRESSURIZED ION CHAMBERS (Dearees)* Meters miles DIRECTION / SECTOR
- S1 San Onofre Beach 298* 1070 0.7 WNW P S2 SONGS Former Evap. Pnd 313* 890 0.6 NW Q S3 Japanese Mesa 340 1150 0.7 NNW R S4 HCB - Camp Pendleton 3* 1120 0.7 N A SS MCB - Camp Pendleton 19 1050 0.6 NNE B S6 MCB - Camp Pendleton 46 940 0.6 NE C S7 MCB - Camp Pendleton 70* 870 0.5 ENE D 4 S8 MCB - Camp Pendleton 98" 1120 0.7 E E S9 San Onofre State Beach 121* 940 0.6 ESE F 4
- Distance (meters / miles) and Direction (sector) are nieasured relative to l Units 2 and 3 midpoint. Theta direction is determined from degrees true north.
I l
S023-0DCM 5-21 Revision 21 02-15-90
TABLE 5-6 SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATION MAP l
DEGREES TRUE NORTH FROM SONGS 2 AND 3 MID-POINT NOMENCLATURE .
Sector Center Sector 22.5*
Limit Line Limit Sector
- Direction j 348.75 0 & 360 11.25 A N l 11.25 22.5 33.75 B NNE 33.75 45.0 56.25 C NE-56.25 67.5 78.75 D ENE 78.75 90.0 101.25 E E 101.25 112.0 123.75 F ESE 123.75 135.0 146.25 G SE 146.25 157.0 168.75 H SSE 168.75 180.0 191.25 J S 191.25 202.5 213.75 K SSW 213.75 225.0 236.25 L SW 236.25 247.5 258.75 M WSW 258.75 270.0 281.15 N W 281.25 292.5 303.75 P WNW 303.75 315.0 326.25 Q NW 326.25 337.5 348.75 R NNW I
Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true North.
i S023-0DCM 5-22 Revision 21 02-15-90 1
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.x 1.i r . :.M , .,r ; Ib "; .y,g. S023-0DCM i
JB .-
$,'h,+.fP.g d) 1 figure 5-4 P. 5-26 WD.,n i4b Revision 28
.,n
- , . ' ' ,m:. . . - " :f" h,
-. ,, _..n.....
12-21-95
6.0 ADMINISTRATIVE 6.1 DEFINITIONS -
The defined terms of this section appear in capitalized type and are applicable through these Specifications.
ACTION 6.1.1 ACTION shall be that part of a specification which prescribes remedial measures required under designated conditions.
CHANNEL CALIBRATION 6.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of tha carameter which the channel monitors. The CHANNEL 1 CAddRATION shall encompass the entire channel, including !
the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK 6.1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of thechannelindicationand/orstatuswithother indicationsand/orstatusderivedfromindependent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST 6.1.4 A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog channels - the injection of a simulated signal into channel as close to the sensor as verify OPERABILITY, including alarmorand/ trippracticable to functions.
- b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY, includingalarmand/ortripfunctions.
- c. Digital computer channels - the exercising of the digital computer hardware using diagnostic programs and the injection of siniulated process data into the '
channel to verify OPERABILITY. l l
l S023-0DCM 6-1 Revision 21 l 02-15-90
)
6.0 ADMINISTRATIVE (Continued) l DOSE E0VIVALENT I-131 6.1.5 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/ gram) which alone would produce the same i thyroid dose as the quantity and isotopic mixture of I- l 131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be tnose listed in Table III of TID-14844, l
" Calculation of Distance Factors for Power and Test l Reactor Sites." '
FRE0VENCY NOTATION 6.1.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 6.2.
GASE0US RADWASTE TREATMENT SYSTEM 6.1.7 A GASE0US RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
INVESTIGATIVE REPORT 6.1.8 The group responsible for the missed ACTION or surveillance shall perform an evaluation which covers the root cause(s), corrective action, and recommendations to preclude recurrence of the event. Copies of the resulting repor' shall be provided to Effluent Engineering and the Unit Superintendent with the original sent to CDM-SONGS for retention.
MEMBERS OF THE PUBLIC 6.1.9 MEMBER (S) 0F THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal associatior. with the plant. This category shall include nonemployees of the licensee who are permitted to use portions of the site for recreational, occupational, or purposes not associated with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.
l S023-0DCM 6-2 Revision 23 02-28-91
l i
l 6.0 ADMINISTRATIVE (Continued)
OPERABLE - OPERABILITY 6.1.10 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performingitsspecifiedfunction(s),andwhenall necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are recuired for the system, I subsystem, train, component or cevice to perform its function (s) are also capable of performing their related supportfunction(s).
PURGE - PURGING 6.1.11 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
SITE B0UNDARY 6.1.12 The SITE B0UNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.
SOLIDIFICATION 6.1.13 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
SOURCE CHECK 6.1.14 A SOURCE CHECK shall be the qualitative assessment of ]
channel response when the channel sensor is exposed to a radioactive source, j THERMAL POWER 6.1.15 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
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l S023-0DCM 6-3 Revision 23 02-28-91 ,
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6.0 ADMINISTRATIVE (Continued)
VENTILATION EXHAUST TREATMENT SYSTEM 6.1.16 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbersand/orHEPAfiltersforthepurposeofremoving I iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).
Engineered Safety Feature (ESF) atmospheric cleanup ;
systems are not considered to be VENTILATION EXHAUS 1 TREATMENT SYSTEM components.
VENTING l
6.1.17 VENTING is the controlled process of discharging air or l gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent used in system names does not imply a VENTING process.
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S023-0DCM 6-4 Revision 25 02-28-92 1
TABLE 6-1 OPERATIONAL MODES REACTIVITY % OF RATED AVERAGE COOLANT OPERATION MODE CONDITION. K,r, THERMAL POWER
- TEMPERATURE
- 1. POWER OPERATION t 0.99 > 5% 1 350*F
- 2. STARTUP > 0.99 < 5% 1 350*F
- 3. HOT STANDBY < 0.99 0 t 350*F
- 4. HOT SHUTDOWN <JD.99 0 350*F> T,,,>200*F
- 5. COLD SHUTDOWN < 0.99 0 < 200*F
- 6. REFUELING ** < 0.95 0 < 140*F
- Excluding decay heat.
- Fuel in the reactor vessel with the vessel head closure bolts less than fully ,
tensioned or with the head removed. '
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S023-0DCM 6-5 Revision 21 02-15-90
TABLE 6-2 FRE0VENCY NOTATION NOTATION FRE0VENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W At least once per 7 days M At least once per 31 days Q At least once per 92 days SA At least once per 184 days R At least once per 18 months
- S/U Prior to each reactor startup P Completed prior to each release N.A. Not applicable Refueling Not to exceed 24 months Interval
- A month is defined as a 31-day period.
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l S023-0DCM 6-6 Revision 22 08-02-90
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6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT *
]
6.2.1 Routine radioactive effluent release reports covering the o)eration of the unit during the previous calendar year '
)
s1all be submitted before May 1 of each year.
. 6.2.2 The radioactive effluent release reports shall include a
! summary of the quantities of radioactive liquid and l gaseous effluents and solid waste released from the unit i as outlined in Regulatory Guide 1.21 " Measuring, l Evaluating, and Reporting Radioactivity in Solid Wastes
! and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, " Revision 1, June 1974, with data summarized on a l quarterly basis following the format of Appendix B l thereof.
l l The radioactive effluent release report shall include an l annual suanary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an !
assessment of the radiation doses due to the radioactive !
liquid and gaseous effluents released from the unit or station during the previous calendar year. This same l
report shall also include an assessment of the radiation j doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the
- SITE B0UNDARY (Figure 1-2 and 2-2) during the report i
All assumptions used in making these assessments p(eriod.i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of
. radioactive materials in gaseous effluents (as determined l by sampling frequency and measurement) shall be used for .
determining the gaseous pathway doses. The assessment of )
radiation doses shall be performed in accordance with the i 0FFSITE DOSE CALCULATION MANUAL (0DCM). l
- A single submittal may be made for a multiple unit station. The sutmittel should combine those sections that are cosmon to all units at the Station; however, for units with separate redweste systems, the submittal shall specify the releases of radioactive material from each unit.
S023-0DCM 6-7 Revision 26 12-20-93
6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS (Continued) 6.2.2 (Continued)
The radioactive effluent release report shall also include an assessment of radiation doses to the likely most ex)osed MEMBER OF THE PUBLIC from reactor releases and ot1er nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from licuid and
' gaseous effluents are given in Regulatory Guice 1.109, Rev. 1.
The radioactive effluents release shall include the following information for each ty offsite during the report period:pe of solid waste shipped
- a. Container volume,
- b. Total curie quantity (specify whether determined bymeasurementorestimate),
- c. Principal radionuclides (specify whether determined by measurement or estimate),
- d. Type of waste (e.g., spent resin, compacted dry waste,evaporatorbottoms),
- e. Type of container (e.g., LSA, Type A Type B, large Quantity), and
- f. SolidificationAgent(e.g., cement, urea formaldehyde).
The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.
The radioactive' effluent release re) orts shall include any changes to the PROCESS CONTROL PROGIAM (PCP) made during the reporting period.
1 S023-0DCM 6-8 Revision 26 12-20-93 a
1 6.0 ADMINISTRATIVE (Continued) j 6.3 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, & j Gaseous)
Licensee initiated major changes to the radioactive waste systems (liquid & gaseous):
- 1. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was performed pursuant to Quality Assurance Program Description g (SCE-1-A), Subsection 17.2.20.3.1.1. The discussion of each change shall contain:
- a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
- c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;
- d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license application and amendments thereto;
- e. An evaluation of the change which shows the' expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;
- f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents to the actual release for the period prior to when the changes are to be made;
- g. An estimate of the exposure to plant operating personnel i as a result of the change; and
- h. Documentation of the fact that the change was reviewed and found acceptable pursuant to Quality Assurance Program (2.
Description (SCE-1-A), Subsection 17.2.20.3.1.1.
- 2. Shall become effective upon review and acceptance pursuant to g QualityAssuranceProgramDescription(SCE-1-A), Subsection 17.2.20.3.1.1.
5023-0DCM 6-9 Revision 30 05-28-97 w D
a 6.0 ADMINISTRATIVE (Continued) 6.4 BASES LIOUID EFFLUENTS CONCENTRATION (1.1) 6.4.1 This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B Table II, Column 2. This limitation provides I additional assurance that the levels of radioactive i materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix limits I,10 20.106(e of 10 CFR CFR 50,)to an individual, to the population.and The(2) the concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water l using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
DOSE (1.2) 6.4.2 This specification is provided to implement the require- l ments of Section II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation '
implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such '
that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ecuations specified in the ODCM for calculating the doses cue to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in 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," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
S023-0DCM Revision 21 6-10 02-15-90 L J
6.0 ADMINISTRATIVE (Continued) 6.4 JLAlfJi (Continued)
LIOUIDWASTETREATMENT.(1.3) 6.a.3 The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
!' GASEE S EFFLUENTS l 00SERATE(2.1) 6.4.4 This specification is provided to ensure.that the dose at i any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits s)ecified in Appendix B, Table II of 10 CFR Part 20 ,
2 art 20.106(b)). For individuals who may at times (10 CFR be within the site boundary, the occupancy of the
,. individual will be sufficiently low to compensate for any L
increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits '
restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem /yeartotheskin. These release rate limits also ;
, restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem;' year.
This specification applies to the release of gaseous l effluents from all reactors at the site. For units with
! shared radwaste treatment systems, the gaseous effluents
-from the shared system are proportioned among the units sharing that system.
S023-0DCM Revision 21 6-11 02-15-90
r 6.0 ADMINISTRATIVE (Continued) 6.4 p_AH A 1 (Continued)
DOSE - N0BLE GASES (2.2) 6.4.5 This specification is provided to implement the requirements of Sections II.B. III.A and IV.A of Appendix I, 10 CFR Part 50. The Limitin implements the guides set forth]in Section II.B ofCondition for Operation Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses ~due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in 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,"
Revision 1, October 1977 and Regulatory Guide 1.111,
" Methods for Estimating Atmospheric Transport and Dis)ersion of Gaseous Effluents in Routine Releases from Lig1t-Water Cooled Reactors," Revision 1, July 1977. For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. For MEMBERS OF THE PUBLIC who traverse the SITE B0UNDARY via highway I-5, the residency time shall be considered negligible and hence the dose "0". The ODCM equations provided for determining the air doses at the SITE BOUNDARY are based upon the historical average atmospheric conditions.
DOSE - RADI0 IODINES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRI7IUM-(2.3) 6.4.6 This specification is provided to implement the requirements of Sections II.C. III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.
The ACTION statements provide the required o)erating flexibility and at the same time implement t1e guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents ;
will be kept "as low as is reasonably achievable." The '
ODCM calculational methods specified in the Surveillance Requirements implement the 1
S023-0DCM f 6-12 Revision 22 08-02-90
_ _ _ _ _ _ - - _ . /
6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational rethods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in 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," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.
These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radiciodines, radioactive materials in particulate form and tritium are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
GASE0USRADWASTETREATMENT(2.4) 6.4.7 The OPERABILITY of the GASE0US RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents requ!re treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
S023-0DCM 6-13 Revision 21 02-15-90
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l 1 6.0 ADMINISTRATIVE (Continued) 6.4 DAlgi (Continued)
TOTALDOSE(2.5) 6.4.8 This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective ~ doses of Ap)endix I. For sites containing up to 4 reactors, it is hig11y unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors j remain within the reporting requirement level. The Special Report will describe a course of action which 3 should result in the limitation of dose to a member of the '
public for 12 consecutive months to within the'40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of' the public is estimated to exceed the requirements of 40 CFR 190, the Special Re) ort with a request for a variance in accordance wit 1 the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected.
An individual is not considered a member of the public duringanyperiodinwhichhe/sheisengagedincarrying.
out any operation which is part of the nuclear fuel cycle.
RADI0ACTIVELIOUIDEFFLUENTINSTRUMENTATION(4.1) 6.4.9 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM toensurethatthealarm/tripwilloccurpriorto exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of-Appendix A to 10 CFR Part 50.
5023-0DCM 6-14 Revision 21 02-15-90 L __
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6.0 ADMINISTRATIVEM(Continued) 6.4 BASES (Continued)
RADI0 ACTIVE GASE0US EFFLUENT INSTRUMENTATION (4.2) 6.4.10 The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumenta-tion also includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
MONITORING PROGRAM (5.1) 6.4.11 The radiological monitoring program required by this specification provides measurements of radiation and of .
radioactive materials in those exposure pathways and for i those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of ,
radioactive materials and levels of radiation are not '
I higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial o)eration. Following this period, program changes may )e initiated based on operational experience.
The detection capabilities required by Table 5-1 are ,
state-of-the-art for routine environmental measurements in l industrial laboratories. It should be recognized that the l LLD is defined as an a orfori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Opercting Report.
S023-0DCM 6-15 Revision 22 08-02-90
6.0 ADMINISTRATI (Continued) 6.4 BASES (Continued)
LANDUSECENSUS(5.2) 6.4.12 This specification is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quant'ty (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used,
- 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2)avegetationyieldof2kg/squaremeter.
INTERLABORATORY COMPARIS0N PROGRAM (5.3) 6.4.13 The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
S023-0DCM 6-16 Revision 22 08-02-90 l 1
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