ML20235U784
| ML20235U784 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/31/1988 |
| From: | Keuter D SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| AGM-NPP-89-085, AGM-NPP-89-85, NUDOCS 8903090372 | |
| Download: ML20235U784 (191) | |
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l' l SEMIANNUAL RADIO ACTIVE EFFLUENT RELEASE REPORT h JULY - DECEMBER 1988 1
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L RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 INTRODUCTION Rancho Seco. Nuclear Generating Station (RSNGS) Unit No. 1 is located in Sacramento County, California approximately 25. miles southeast of Sacramento and 26 miles north-northeast of Stockton.-
Rancho Seco Unit No. 1 began commercial operation on April 17, 1975. The single unit on the Rancho Seco site is'a pressurized l water reactor supplied by Babcock and Wilcox. The rated capacity is 963 gross megawatts electrical.
This Semiannual- Radioactive Effluent Release Report (SRERR) provides a summary of gaseous and liquid effluent releases made I
I from Rancho Seco . Unit No. 1 during the period July 1 through December 31, 1988. Also presented in this report is the projected radiological impact-from these releases and a summaryz of solid radwaste shipments.
This report has been prepared by the Sacramento Municipal Utility-l District to meet the requirements of Rancho Seco Technical l
Specification 6.9.2.3. It is presented in accordance with the format of USNRC Regulatory Guide 1.21. The radiation . doses l: reported in this SRERR are calculated for a hypothetical I individual who receives the maximum possible exposure at or beyond the Site Boundary.
f l-Releases of. radioactivity in gaseous and liquid effluents during this report period did not exceed the limits of 10 CFR 20 or the numerical guidelines of 10 CFR 50, Appendix I. A 40 CFR 190 dose evaluation is not required because radioactive effluent releases did not exceed twice' the numerical guidelines of 10 CFR 50, Appendix I.
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RSNGS SIMIANNUAL RADIOACTIVE EFFIDENT REI. EASE REPORT JULY - DECEMBER 1988 2&EE OF CKNENTS PAGE I. SUPPIDENIAL INFORMATION 3 1
A. Regulatory Limits & Gii@ines for Effluent Releases 3 B. Maximum Permissible Can.=ittations 4 l C. Meastu==st Methods for 'Ibtal Radioactivity 5
D. Batch Releases (via acnitored pathways) 6 E. Unplanned Gaseous Effluent Relaam 7 F. Unplanned Liquid Effluent Releases 9 G. Effluent and Water Manimf==>L Project 10 H. Radioactive Effluent Monitorirn Instrumentation Inoperable for Greater than 30 Days 11 I
II. CMANGES 'IO 'IHE PCP, ODCM, REMP MANUAL, AND RADWASIE TREAIMENT SYSTEMS 12
! A. Process Control Ptupam (PCP) Changes 12 B. Offsite Dose Calculation Marmal (ODCM) Changes 12
- C. Radiological Envisumustal Monitoring Pt% tam (REMP) l Manual Changes 15 D. Major Change to a Gaseous Radwaste Treatment System 16 III. ESTIMATION OF ERROR 18 IV. GASEQUS EFFIUDTPS 19 Table IV-A f aws Effluents - Sumation of All Releases 21 Table IV-B Gaseous Effluents - Ground Imvel Releases 22 Table IV-C t:awis Effluents - Typical Iower Limits of Detection 23 Table IV-D Radiological Impact on Man Due to fia w s Effluent Releases 24 l
! V. LIQUID EFFIUDTPS 25 Table V-A Liquid Effluents - Sutumation of All Releases 26 Table V-B Liquid Effluents 27 Table V-C Liquid Effluents - Typical Iower Limits of Detection 28 Table V-D Radiological Impact on Man Due to Liquid I Effluent Releases 29 VI. SOLID WASTE 30 VII. ME?TEDROI.OGICAL DATA 32 1
RSNGS SDUANNUAL RADIOACTIVE EFFIIENT RELEASE REPORT JULY - DECEMBER 1988 7
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l ADDDER 'IO PREVIOUS SDENDEL REPORTS
'A. Corrected Doses for Semiannual Reports frm Jarmary 1980 through June 1988 B. rweimmioning of ABGLV mswus Effluent Manitor R-15546A as a 'Ibch Spec Monitor During the Sauniarinual Report 1%riod fra Jarmary -
l C+ +_r 1987 C. Major Changes to the Liquid Effluent Radwaste Treatment System Durirg the Followirg Semiannual Report Periods:
1 July - Eer e 1987-January - June 1988 ATTACHMENTS l A. Offsite Dose Calculation Manual (Procedure AP.310, Rev. 6) l.
l B. Radiological Enviwima d1L1 Manitoring F u cuu Manual Revision 2 l
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l I 1 RSNGS SEMIAMUAL RADIOCHVE EFMUDE RELEASE RENRP j JULY - IECEMBER 1988 Y
I. SUPP2 MEND %L INFGMLTICN l
A. EDITLATORY LIMITS & GUIDELINES IVR EFFIUDE REIZASES
- 1. . naaanus Effluents ]
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- a. Ncble Gas dose rate limit at or beyond the Exclusion Area Boundary (Technical Specification 3.18.1):
500 mrm Vyear to the total body 3000 mre Vyear to the skin ;
- b. Noble Gas air dose limit at or beyond the Site Boundary ]
(Technical Specificatical 3.18.2, numerical guidelines of 1 10 CFR 50, Appendix I):
5 mrad per calendar quarter for gama radiation 10 mrad per calendar quarter for beta radiation 10 mrad per calendar year for gama radiation 20 mrad per calendar year for beta radiation y
- c. Dose rate limit at or beyard the Exclusion Area Boundary for Iodine-131, Iodine-133, Tritium, and radioactive material in particulate form with half-lives greater than 8 days (Technical n=r ification 3.18.1):
I 1500 mrueVyear to any organ l
- d. Dose otzmitment to a member of the public at or beyond the i
Site Boundary frun Iodine-131, Iodine-133, Tritium, and radioactive material in particulate form with half-lives greater than 8 days (Technical Specification 3.18.3,
- l. numerical guidelines of 10 CFR 50, Appendix I):
)
7.5 mrun per calendar quarter to any organ
! 15 mrem per calendar year to any organ l
- 2. Liquid Effluents
- a. The cm rukation of radioactive material in liquid effluents released beyond the Site Boundary shall not avr,aad the limits of 10 CFR 20, Appendix B, Table II, Column 2. '!his applies to all radionuclides except dissolved or entrained noble i gases (TW:hnical Specification 3.17.1) .
- b. The total m au n ation of dissolved or entrained noble gases
> shall not ernaca 2.0E-04 pCi/ml (Technical Specification 3.17.1).
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b RSNGS SEMIANNUAL RADIOACTIVE EFFIDENT RELEASE REPORP
- JULY - IECEMBER 1988
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- c. Dose otamnitment to a member of the public at or beyorx1'the Site Boundary from radioactive materials in liquid effluents
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shall- be limited to (Technical Specification 3.17.2, t numerical guidelines of 10 CFR 50, Appendix I):
1.5 mean per calendar quarter to the total body 5 mran per calendar quarter to any catgan 3 mran per calendar year to the total body 10 mran per calendar year to any organ l B. MAXIMM PERMISSIBLE CONCENIRATICES 3 ..
- 1. naawus Effluents
'Ibe u.=m.=>^uations listed in 10 CFR 20, Appendix B, . Table II, Column 1 (air) are not directly used in calculations for -
determining pam4==ible rpaama effluent release rates. 'Ihe annual dose limits of 10 CFR 20 for unrestricted areas.are the th== maaeciated with the canoentrations of 10 CER .20, '
Appendix B, Table'II, Colunn 1~. Te &nical Specification dose
- 2 rate limits (arenVyr) for rpaeus affluents are provided to -
ensure that the dose rate frun rpasnia effluents at any time
( at the Exclusion Area Boundary will be within the annual dose limits' of 10 CFR 20 for. unrestricted areas.. 'these dose rate limits (listed abcne in part A) are used for' determining L
i paminaible rpaania effluent release rates.
) 2. Liquid Effluents l
'Ihe u -. 'uation values' listed in -10 CFR 20, Appendix B, Table II, Column 2 are used in calculations - to determine pami ==ible liquid dis &arge flow rates. . Ihe most conservative MFC value for end radionuclides detected in the-liquid effluent sanple (excluding dissolved or entrained
(. noble gases) is used in the calculations.
I For dissolved or entrained noble ry==aa, the total allowable I ccec=>uation in the liquid at the point of offsite dis &arge
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i is limited to 2.0E-04 pCi/ml.
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RSNGS SDEANNUAL RADIOACTIVE EFFIDENT REGASE REPORT JULY - IECEMBER 1988 7
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C. MEASUREMENT MCIfDDS FOR TOIAL RADIOACTIVITY
- 1. Fission and Activation Gases
> Gama SWLtunehy (HPGe) i Liquid Scintillation (H-3) i
- 2. Iodines Gama S-WLu=ky (HFGe)
- 3. Particulate i.
Gama SWLumby (HPGe)
Beta FJ.pdional (Sr*89, Sr-90, gross beta)
Alpha Proportional (gross alpha)
-4. Liquid Effluents Gama SWLu=Ly (HPGe)
Liquid Scintillation (H-3) l l
Beta F1.edianal (Sr-89, SMO, gross beta)
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Alpha F1. y 1.tional (gross alpha)
(Note: HPGe refers to Hyper-Pure Germnium) i
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f I RSNGS SIMIANNUAL RADIOACTIVE EFFLUDIT REIEASE REKRP JULY - IECEMBER 1988
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D. BA2UI RELEASES (via Inonitored pathways) 3rd 4th
- 1. meic (Rx Bldg Purge, Rx Bldg Equalization, Ouarter Ouarter Hydrogen Blower, NGDT)
- a. Number of batcil releases 6 10
- b. 7btal time period for batcil relaaman (hours) 553.47 1000.93
- c. Mavimnn time period for a batd1 release (hours) 168.00 335.58
- d. Average time period for a batd1 release (hours) 92.24 100.09
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- e. Mininum time period for a batd1 release (hours) 1.02 3.23
- 2. Liquid (RHUT Releases)
[ a. Number of batch releases 33 32
- b. Ibtal time period for batch releases (hours) 173.41 159.44 l-
- c. Maximum time period for a batd1 release (hours) 11.90 12.33
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- d. Average time period for a batch release (hours) 5.25 4.98
- e. Minimum time period for a batch release (hours) 1.25 1.42
- 3. Liquid (Retention Basin Discharges)
- a. Number of batch releases 18 22 j
- b. 7btal time period for batch releases (hours) 218.63 217.23 l c. Maxinum time period for a batch release (hours) 19.83 20.75 h
- d. Average time period for a batch release (hours) 12.15 9.87
- e. Minhum time period for a batch release (hours) 6.93 5.48
- f. Average stream flow during periods of release of effluent into a flowirg stream (cfs) 16.96 20.35 NOTE: The Regenerant Holdup Tanks (RHUrs) are released to the Retentico Basins. The Retention Basins are discilarged offsite. All 10 CFR 50, p Appendix I dose calculations are based on the RHUT releases. All 10 CPR 20 calculations are based on the Retention Basin discharges.
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RSNGS SDEANNUAL RADIOACTIVE EFFIDEKI REMASE REPORT JULY - IECEMBER 1988 E. UNPIANNED GASEQUS EFFIDENT REIEASES i
- 1. During respirator cleaning on 8/7/88, 8/8/88, 8/9/88, 8/10/88, 8/11/88, 8/12/88, 10/17/88, 10/26/88, 10/27/88, 10/28/88, 11/1/88, t 11/2/88,' 11/7/88, 11/16/88, 12/14/88, 12/16/88, and 12/17/88, air
- sanples were taken at the exhaust of the respirator cleaning facility (trailer) . 'Ihe r}aamaic release volume frun all of these mini-rela ==a= taken collectively was approximately 2.24E11 oc.
'Ihe total activity relanae=1 offsite was calmlated to be:
I-131 1.06E-05 Ci
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I-133 1.31E-06 Ci
'Ihe calculated mav4== organ dose due to these mini-relaaaan was 1.07E-02 mrem. 'Itchnical Specification dose / dose rate limits for gaseous effluents were not eynaariari as a result of these mini-relaaaac. Actions taken to prevent recurrence involve evaluation of this release point for possible li - y, ration into the ODN as I
a " planned" release point.
- 2. 'Ihe reactor tripped on 10/14/88, arrl the autanatic shutdown
)- resulted in the lifting of one Atamperic Dunp Valve and seven Code Safety Relief . Valves. Approximately 1.00E07 oc of rymaania effluent (steam) was released to the an -@sre. 'Ihe activity relanaevi offsite was calculated to be:
H-3 5.28E-05 Ci Xe-133 5.19E-07 Ci Xe-135 2.22E-07 Ci L
'Ihe calculated rinaac for this release included: =av4== organ dose of 1.50E-07 mrem, ganna air dose of 4.06E-10 mrad, and beta air dose of 7.26E-10 mrad. Technical Specification dose / dose rate l' limits for gaseous effluents were not avnaariari as a result of this release. Actions taken to prevent recurrence are not applicable because this release was a m=aq rer,yise to the reactor trip i incident.
- 3. Due to failure of a steam relief valve, a release of saturated steam fran the 2A Feedwater Heater eiW on 12/5/88.
Approximately 1.17E10 cc of rymaania effluent (steam) was relaneari to the atmosphere. 'Ibe activity relaaaari offsite was calculated to be:
H-3 8.61E-02 Ci Xe-133 1.43E-03 Ci Xe-135 1.84E-04 Ci 7
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RSNGS SDilANNUAL RADIOACTIVE EFFIIIENT RELEASE REKRP JULY - DECDEER 1988
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We calculated th:aa for this release included: mav4== organ dose of 2.45E-04 mrem, gama air dose of 5.71E-07 mrad, and beta air dose of 1.30E-06 mrad. Technical Specification dose / dose rate limits for gaces effluents were not avnaariai as a result of this release. Actions taken to prevent recurrence involved maintenance on the relief valve.
- 4. %e ventilation system of the Interim Onsite Storage N41 ding was operated on 11/4/88, 11/15/88, 11/16/88, and 12/12/88 through 12/22/88. Sanples of the exhaust on these dates showed detectable levels of I-131. Approximately 3.68E12 oc of ga-= effluent was i
relaaaai to the ah W a e, based on release data taken on all of l these dates. %e activity released offsite was calculated to be .
4.96E-07 Ci of I-131. Se calculated mavi== organ dose for these cambined releases was 5.00E-04 mrem. Technical Specification dose / dose rate limits for gaamic effluents were not evnaariari as a .'
result of this release. Actions taken to prevent recurrerce involve evaluation of this release point for possible in wrporation into the OD N as a " planned" release point.
- 5. As a result of a reactor trip on 12/9/88, several secondary .
j system relief valves actuated. Both widersier air ejectors !
l (hoggers) were in operation during the ent -h aaquent restart.
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Approximately 9.06E07 cc of gaaela effluent (steam) was released to the atmosphere. %e activity relanaai offsite was calculated M M:
Kr-85M 9.97E-06 Ci
) Xe-133 6.93E-04 Ci L
Xe-135 8.07E-05 Ci 1-131 2.84E-06 Ci Cs-137 6.22E-06 Ci I H-3 7.58E-04 Ci I
%e calculated doses for this release included: raxinum organ
! dose of 2.99E-03 mrum, gama air dose of 2.74E-07 mrad, ard beta I air dose of 6.30E-07 mrad. 'Ibchnical Specification th:a/ dose rate limits for gaseous effluents were not avnaariari as a result of this release. Actions taken to prevent recurrence are not applicable because this release was a n-amy r w aie to the trip incident.
- 6. An evaluation of the dose contribution frun mianallaneous steam releases with a contaminated secordary system was performed for calendar year 1988. % e estimated release volume was 3.0E09 oc of games effluent. me activity released offsite hami on the nest conservative results of "A" Steam line and "B" Steam line sanples was calculated to be:
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RSNGS SDGAINUAL RADIOACTIVE EFFIUDfr REIEASE REPORP
- i. JULY - IECEMBER 1988
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'H-3 2.01E-02 Ci 1
'Xe-133 1.26E-03 Ci- i Xe-135 3.96E-04 Ci L 'Ihe calculated cirwa= for this release included:- navium cegan dose of 5' 72E-05 nrem, rpmna air dose of 8.02E-07 ared, and beta air dose of 1.53E-06 mrad. Todmical Specification dose / dose rate .
limits for rya-= effluents were not =wmarb=1 as a result of.this release. Actions taken to prevent recurrence are not applicable because this release is the result of routine plant aparation with
[. a contaminated secondary systen.
r F. UNPIANNED I2 QUID EFFIDDfr RE1 EASES
- 1. On 8/12/88 . after use ' of the low point drain of the niLuvus system, approximately one pint of the . water was' inadvertently
<* w'r=ri into the I&C shop sink drain (PDQ #88-1496)' . 'Ihe activity l' relaaaari offsite was calculated to be:
05-134 6.34E-11 Ci L , Os-137 7.00E-10'Ci
'Ibe =vi=wn. total body dose and the =v4== organ dose for this release were calculated to be' 2.18E-07 mrum and 4.29E-07 neum, l'
respectively. Te&nical Specification dose /MPC limits for liquid effluents were not awmariari as a result of this release. Actions taken to prevent recurrence involved investigation into.the source p of contamination and briefing of plant personnel responsible for i this incident.
- 2. On 8/19/88, a valve leak was r4=atved on . the "B" Moisture p Separator Reheater on two separate occasions. Approximately 2.88E05 ml of liquid flowed into an Urm.uhulled drain. '1he activity released offsite was calculated to be:
H-3 1.76E-06 C1 Cs-137 3.34E-09 Ci
'Ihe =v4== total body dose and the =v4== organ dose for this release were calculated to be 7.36E-07 mran and 1.18E-06 mrun, respectively. Tactinical Specification dose /MK: limits for liquid effluents were not exmaariari as a result of this release. Actions taken to prevent recurrence involved routing the leakage to a controlled drain until maintenance pergunel repaired the valve.
- 3. On 8/22/88, a valve leak was r*=avved on the "B" Moisture Separator Reheater. Approximately 7.28E03 al of liquid flowed 9
RSNGS SDEANNUAL RADIC&CTIVE EFFIDDir RETASE REPORP JULY - DECEMBER 1988 into an urmiuulled drain. The activity relmaaad offsite was calculated to be 3.53E-08 Ci of H-3. Se ==v4== total body dose 3 and the =avia= organ dose for this release were both calculated to be 2.97E-10 mrum. Technical Specifimtion dose /MPCLlimits for liquid effluents were not aw=adari as a result of this release.
Actions taken to prevent recurrence involved routing the leakage to a controlled drain until maintenance personnel repaired the valve. .
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- 4. Frcrn 8/13/88 through 9/9/88, liquid leaked fran the Nwilian( l Feedwater Pump Gland Seal into an ur m iuulled drain. !
Approximately 9.89E07 al flowed into the drain. Se activity relaaaad offsite was calculated to be: !
H-3 2.47E-04 Ci Os-137 5.98E-07 Ci The mav4== total body dose and the ==v4== organ dose for this release were calculated to be 1.63E-04 mrem and 3.45E-04 mrum, respectively. Technical Specification dose /MPC limits for liquid effluents were not aw=ariari as a result of this release. Actions y taken to prevent recurrence involved routing the -' leakage to a controlled drain until maintenance pw. mane.1 repaired the seal.
G. EFFIUDTP AND WATER MANAGEMENT PROJECT
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Project was established in March l he Effluent - and Water Managenent 1988. The purpose of this project "Di to: (1) rargrw the possibility
}. of unplanned liquid affluent relaaaac, (2) improve the day-to-day waste
[ water marnf iat process, and (3) improve the site water mas,, it capability to operate with primary to seu Jery leakage.
The project consists of representatives frun Operations, Chemistry, Engineering, .Licensirg and Quality. Se Project Manager coordinates the site-wide effort to reduce the radiological impact to the envisuais t through inproved waste water yv w characterization, plant modifications, proceduru changes, and contingency action plan development. % e effectiveness of the project is measured by tracking a variety of waste water and offsite dose-related parameters.
The Effluent ard Water Mainf i-it Project implemented the following chanjes during this report period:
I 1. Re-routed the turbine deck drains to redtoe the risk of an ur aniuulled liquid release.
- 2. Bailt a curb around the Retention Basins to reduce the volume of solid waste.
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f RSNGS SEMIANNUAL RADIOACTIVE EFTIDENT REI. EASE REFORT JULY - IECEMBER 1988 1 3. RE ' u2tirg. of - drains frm tie dog bane seals and condensate puup l
seal. water to the condenser for volume ra$uction is essentially ocuplete.
I 4. Addition of ski-rs to the turbine steps and RE7ra to reduce the amount of oil in waste uter is essentially ocuplete.
l 5. Replacement of the sunp puups in._the tank farm with %J punps to reduce the risk of an uncontrolled liquid release is essentially emplete.
l' 6. Re-routed the circulation eter instrument drains to the condenser to reduoe.the volume of waste water.
i 7. Re-routing of the CPS /PDS punp seal water frm the sumps to the l s44ers,er to rwtm the volume of waste water is essentially ocuplete.
- 6. A domineralizer and filter were ad$ed to the polisher sluice water line for activity reduction.
- 9. An . enclosure was ocupleted around the RHUr destineralizers to reduce the risk of an unplanned liquid release.
H. RADIOACTIVE EFTIDENT M3tI'ICRING INSTIRMENTATION INOPERABLE FOR GREATER
'IHAN 30 DAYS.
'Ihere were no mm during this report period when r=Mr=Mve effluent monitorirq instrumentation .was irq=gceble for greater than 30 days.
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RSNGS SDiIA100AL RADIGAC.TIVE EFFI1ENT REIEASE REPORT JULY - IECEMBER 1988 l
II. OWG5 'ID EE FT CDCM REMP MERL, MD RADWCIE HEmWP SWEE A. PROCESS CDtTfROL PROGRAM (PCP) CHANGES
'Ihere were no changes to the PCP during this report period.
B. Ornnt DOSE CAIf01ATICE MAIUAL (ODCM) CHAIGES Revision 6 of the ODCM hamma effective on 10/29/88. 'Ihis revision of the ODCH was prepared, reviewed, and impleented by Chemistry Department effluents pael. 'Ihe changes incorporated in this revision will not reduce the accuracy or l
reliability of dose calculations or setpoint determinaticms.
Attachment A of this report contains h=aritation of the fact that all changes have been reviewed and found acceptable by both the Plant Review Ottmittee (PRC) and the Marnfam:=d. Safety Review Otznittee (MSRC) pursuant to RSNGS Technical Specification 6.16.2.
Changes to the followirs Sections / Steps were ira.w W rated in Revision 6 of the ODCM:
4.9 'Ibe term " Safety Factor" was addad to the definition l section. Essentially the same words were used to describe the parameter; however, the arbitrary restriction that the safety factor be less than 10 was j drupped. Usirq a safety factor of greater than 10 does not rurh a the margin of safety or the accuracy cf setpoint determinations. 'Ihroughout the text, all repeated definitions were deleted as well.
L 5.2.1.2 'Ibe definitions for the variables F and r Fe (discharge and dilution flow rates) now include a reference to the I process flow diagram (Figure 5.1) for clarification.
1 5.2.1.3 A caveat was added to this section to allow for l
determining maximum discharge flow rate and minimum
} dilution flow rate without the assistance of the referenced equations provided the criterion of 5.2.1.2 is satisfied (Tech Spec 3.17.1) . Procedurally, the minimum dilution flow is pre-determined and does not need to be calculated on a release-by-release basis.
l 5.2.2.1 'Ihe note did not acx:urately describe the GA 'Ibchnologies nonitors and was therefore deleted.
5.2.2.1 The liquid GA monitors are gama scintillation l
detectors. Consequently, the variable C1 which is used throughout the ODCM to apply to all radionuclides was 12
RSNGS SEMIANNUAL RADIOACTIVE EF7UBir RE2 EASE REECRP JULY - IECEMBER 1988 specifically restricted to gesuna-emitting nuclides ( )
for the; liquid nonitor setpoint calculation.
irun the reliability and accuracy -of setpoint calculations by excluding beta or alpha emittirq reclides that would not be detected by the monitor.
5.2.3 Die reference to volume was deleted har== the equation is only valid if F Die ,
r and Fe are the flw rates.
equation is used to evalusta cmapliance with 10 CFR 20,-
which specifies instantaneous canoentration listits.
Using volume in the equation would ptwide an average concentration which is not applicable to 10 CFR 20. Any I text whi& indicates that volumes _ may be used instead of rates was deleted.
5.3.1.2 Currently, all liquid dose calculations are performed
! using the IADAP ocmputer program provided by the USNRC to inplement Regulatory Guide 1.109. En present l equatien, however, is based on NURED 0133. .'Ihe two equations are algebraically equivalent for applicable pathways, but the present simplified equation was adopted to avoid unnecessary confusion.
l' 5.3.1.3 All referenons to particular versions of IADMP (e.g.,
IADmP-2) beve been ruplaced with just IADmP, with the inference heirs that the unst current and te&nically accurate versian should be used. In addition, the text was expanded to explicitly allow for the use of EMS for' dose calculations. 'Ihe EMS program uses IADmP dose factors.
5.3.2 'Ihis section r%rribes how the NUREG 0133 equation whis calculates dose per release may be adjusted to include multiple batches. 'Ihis part of the di-ion was deleted because it was covered in the sur.=ed change to
- Step 5.3.1.2 which did not change the dose calculation methodology.
Table 'Ibe table was changed to use mav4== design flow rates 5.4-1 rather than ncatinal flow ratas in order to be more ocnservative. 'Ibe values given were determined -in response to Engineering Action ReqM EP 88-021.
5.5 'Ihis section was. zwised to use a reference year or several years of meteorological data for determination of relative a; -- Meric diaparsian and deposition !
factors. Using several years of data will be more impasadative for dose calculations. References L 13 i
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RSNGS SI:MIANNUAL RADIQACnVE DTEDTP REIEASE RElFORP JULY - IECEMBER 1988 throughout - the text to the annual average X/Q were deleted..
5.7.1 The equation for noble gas norsitor' set: point equation was split. to prwide separate. equaties for set: point based on canoentration and cm release rate. The text allows for greater flexibility .for distributing the site limit for activity release among the three release vents, without mwnaading the limits of Tadmical specification 3.18.1.- In addition, release rate estpoint miaulations are added hananaa the alarn/ trip functions are tied to .
the release rate channel of the acnitor. She partition -
factor allows for flexibility without a rdw+ian. in.-
reliability or accuracy.
5.7.2 The text was dim.fm1 to reference the wuact Table A-4 instead of A-3.
5.8 & Both sections were expanded to explicitly allow for the 5.9 use of DE for ry=aama dose m1mlations.
Figure The drawing was amended for clarification to specifi-5.1 - cally show the flows Fr ard Fc used in liquid 10 CTR 20 dose calm 1ations. Also, additional sources of effluent
- (Anviliary Boiler and the Transfamer Alley stem drains) were includod.
Table A note was added to the table to clarify that the 5.4-1 Interim Onsite Stwage (ICS) b2ilding ventilation is not -
a Technical Specification release pathway. The -IOS biilding is not subject to cantimous diar *mges of radioactivity and therefore does not aantribute significantly to the overall site releases. . The ==v4 = =
flow rate of the ventilation system is provided in this table in the event of a release requiring a dose evaluation in accordance with RSNGS abnormal . release procedures. Relanaaa fran the IOS b>ildirig will still be nanitored and evaluated.
Table The table is deleted because it is no langer referenced A-3 in the text. The information contained in Table A-3 was
._ a condensed version of Table A-4 and was eliminated-because it was redundant.
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1 f 'd RS'NGS SEMIANNUAL RADIOACTIVE DTIIENT REIEASE REPORF JULY - DE)CEMBER 1988 i
C. RADIOIDGICAL ENVIRONMENTAL M]N1'IORING PROGRAM (REMP) MANUAL ORNGES
)
Revision 2 of the REMP Manual harma effective on 7/27/88. 'Ihis revision of the REMP Manual was prepared, reviewed, and
! implemented by Envitus-uutl Protection Department perm .el. 'Ihe
[ daarxyes irwiputated in this revision will not reduce the accuracy or reliability of <%se calo11ations or setpoint
, determinations (the REMP Mamal does rrt' address these itens) .
! Attadanent B of this report contains <&rimaritation of the fact I
that all danges have been reviewed and found avveyLible by both the Plant Review rW=ittee (PRC) and the ;". -
A. Safety Review Otanmittee (MSRC) pursuant to Technical Specification 6.16.2.
Changes to the following Sections / Steps were irwtputated in Revision 2 of the REMP Mamal:
0.0 (page 1) Policy statement charged to Joseph F. Firlit, 011ef Executive Officer, Nuclear.
1.0 (page 4), 2.0 (pages 5 & 7), 2.1 (page 7), 2.2 (pages 9 & 10),
2.3 (page 10), 2.5 (pages 11 & 12):
Rewarded various sentences /pawtapas to make the meaning more concise and/or more accurate.
- l. 2.0 (page 6), 2.1 (page 8), 2.4 (page 11), Table 3 (pages 19, 20, 21, 22, & 25):
Corrected various typ wtai aical errors.
i 2.0 Deleted references to pv Mnus HPIP-2001, L (pages 5 & 6) HPIP-2025, HPIP-2080, HPIP-2611, HPIP-2630, HPIP-2631, HPIP-2650, HPIP-2651, and HPIP-2652.-
'Ibese procedures were never otzepleted or were deleted because the TID ptwtam. (except for collection and placement in the field) has been I contracted out effective July 1, 1988.
2.2 (page 9) Replaced minimum flow of 5000 gpn to an average flow of 8500 gpn to mora accurately reflect plant conditions.
2.3 (page 10) Deleted requirement to identify the time and date with the stated sanple identification method because it is not used. 'Ibe time and date are recorded when the samples are collected in the spaces provided in the procedures.
15
)'
l RS!GS SD(IAIRCAL RADIOACTIVE EFTWENT REI. EASE RERET JULY - TtTMBER 1980 2.5 (page 12) Deleted a pa%#i to eliminate redundancy and reference to norMotisting procwures. Also aMad a paragraph to account for three more site gardens (south, east, and west) that are now used as
- indicator sanples.
}
Table 1 AMad an asterisk (*) next to " Runoff Water" and (page 13) defined Runoff Water at the bottom of the page.
Table 3 AMed the locaticn for the ocuposite water sanple (page 17) required by 'Dncti spec 3.22-1, 3a.
Table 3 Deleted well water sanple RHW1.6G0 because it does (page 19) not exist. RWRl.8F0 is the well water sanple taken at the Rancho Seco Reservoir.
)
AMad two more indicator sanple locations for Well Water.
Table 3 Added three more indicator sanple locations for Mud (page 20) and Silt.
AMad the statement " includes species identified as Bass, Sunfish, Perth, Catfish, Carp, or Suckers" adjacent to the title " FISH SAMPIES" to agree with Tecti spec 3.22-1.4b.
Table 3 Added an indicator sanple location for Algae.
-(page 22)
Table 3 AMad eight indicator sanple locations for Soil.
(Page 23)
D. Major Change to a C+e Radwaste Treatment System A 10 CFR 50.59 safety evaluation was prepared to support a pwposed charge to EDAI%306, Enviumsw.uLal Releases of Airborne Radioactivity (currently CAP-OOO9) . 'Ihe pv + M change was implemented to allow for the equalization of the Reactor Buildirg (RB) using the HydwpJi Purge Line. It was determined in the 10 CFR 50.59 evaluation that this is a major change to the radwaste treatment systems as defined in 'Ibctinical Specification 6.17.
'Ibe release point for an RB equalization using the Hydwgi Purge Line is via the Auxiliary pH1dirg Stack (ABS), which is addrh in the USAR. 'Ibe proposed equalization will not result in a situation that is different than has been previously analyzed for 16
f l-RSNGS SDUA'M1AL RADIQACTlVE EFMUENT RE1 EASE REPORP JULY - IEGMBER 1988 the RB purge and/or the RB mini-purge (12" equalizing line) in the l~ USAR. 'Ihe release will be less than or equal to 20 SCFM (normally I 2-3 SCFM) , and it will be monitored by the ABS nmitor R-15045.
The first equalization using the Hyda.m. Purge Line was initiated l- on July 31, 1988.
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RS!GS SWIAlWJAL RADIOACTIVE EFTIDDTP RE1 EASE REPORT JULY - IECEMBER 1988 III. ESTIM@ICH OF ERROR 1
1 1 'Ihe methods for establishing error estimates included review of applicable station procedures, inspection of sanplire aqdynt,
- i. ergineerirg estimates, statistical applications, review of calibration
) setpoint data, and ev=minication with plant personnel. 'Ihe varicus sources of error (o) in reported values of rjac. arum effluents, liquid effluents, and solid waste are ==ai to be ir.' -r---Amt, and thus the total error is calculated accordirg to the formula:
' 'Ibtal Error = 2 2 2 2
( o1 + o2 + o3 + ..... + oi where: oi = relative error associated with u.mp#nt i l
Sources of error for gaseous effluents include waste gas decay tank pressure, fan error (flow), c,rab samplirg, collection, filter efficiency, countirg, and calibration.
Sources of error for liquid effluents include RHUr volume, dilution water flow rate, grab sanplirg, countirg, and calibration.
Sources of error for solid waste include offsite lab mmar analysis, dose rate meter calibration, dose rate meter readirg, Wastetrak dose-to-curie calculation, sample volume maasta=wnL, ganna spec countirg, gama spec calibration, and waste volume determination.
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l BStGS SDdIAIM1AL RADIOACTIVE EFFIDENT REIEASE REPORT l JUIX - DECEMEER 1988 IV. GASKIL EFFIDENPS l
l Table IV-A, awas Effluents - Sumation of All Belme.m, provides a a detailed sumary of emes effluent relme.= per quarter. 'Dris table sumarizes releases of fission and activation rJacm, iodine-131, ,
l particulate with half-lives greater than 8 days, and tritium. 'Ibe {
methodology used to calculate the F=At of 'IWinical Specification 1 limit is as follows:
n I (Fi)(Avg Release Rate)(X/Q)(Dose Factor)
% Tech Spec limit = i=1
- 100%
(Dose Rate Limit)
Were: Fi = the fraction of the total number of Curies of nuclide "i" out of the total Curies in that category for that quarter (unitless)
(Note: Fi always equals 1.0 for I-131 and H-3 because they are the only ruclides in their respective categories)
Avg Rel Rate = (total Curies Der cateaory per cuarter)(1E-06 uCi/Ci)
(# seconds in the quarter)
X/Q = the highest annual average ahnmapheric dispersion factor at the Exclusion Area Boundary, listed in the OIXM (sec/m3)
Dose Factor = the values derived for each rurli+ "i" frun NRC Regulatory Guide 1.109 (K i , I,1+1.1M i , or Raij):
units in (mren/vr)
(pCi/m3)
Dose Rate Limit = 'Ihe 'Ibchnical Specification (i.e., Regulatory) limits for dose rate listed in Section I of this report (mrenVyr).
(Note: Particulate with half-lives less than 8 days are not included in this calculation)
'Ihe methodology used to calculate the Estimated ' Ictal Error (%) in Table IV-A is presented in Section III of this report.
Table IV-B, mels Effluents - Ground Invel Releases, provides a complete quarterly sumary of the anount of radioactivity (Ci) released per radionuclides in each quarter. Data fran both continuous and batch release redes is provided for fission gases, icxiines, particulate, ard 19
RSNGS SD(INNUAL RADICETIVE E"TIUDif r RELEASE ktwRT JULY - DEX2MBER 1988 tritium.
Table IV-C, Gasocus EfflueJ1ts - Typical lower Limits of Detection, prwides a listing of the typical lower limit of detection (LLD) mmd.aations in pCi/ml for various radionuclides.
Table IV-D, Radiological Inpact on Man Due to Gaseous Effluent Releases, prwides a sumary of calculated radiation doses delivered to a maxinum exposed hypothetical indivMm1 at the Site Boundary for gaseous effluents (actual h will be a-W in the 1988 Annual RD4P Report) . 'Ibe maximum calculated organ ckse, gama air dose, and beta air dose are listed for quarter 3, quarter 4, and 1988 (annual) .
'Ihe dose due to direct radiation based cn 'Ibernolhrit Dosimeter (TID) results is also listed. Presented in this table for each category is a ccrparison versus 'IW:hnical Specification dose limits.
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R$NGS SEMIANNUAL' RAD 10 ACTIVE EFFLUENT RELEASE REPOR7 3 JULY - DECEMBER 1988 TABLE IV A ,
GASEOUS EFFLUENTS - SUNNATION OF ALL RELEASE 6 Est. Total gnil Guarter 3 Guarter 4 Error. %
A. : Fission 8 Activation Gases (i.e., Noble Geses)
- 1. Total Release ct 5.02 E+02 9.08 E+02 2.5 E+01
- 2. Average Release Rate for period #Ci/sec 6.31 E+01 1.14 E+02 l 3. Percent of Tech Spec limit % 1.03'E-01 1.77 E-01 B. Iodines
- 1. Total lodine 131 Ci 1.77 E 05 2.22 E-04 2.5 E+01
- 2. Average Release Rate for period #C1/see 2.23 E-06 2.79 E-05
- 3. Percent of Tech Spec limit % 5.53 E 05 6.93'E 04 C. Particulate-
- 1. Particulate with half-lives > 8 days ci 1.95 E 04 6.23 E 06- 2.5'E+01
- 2. Average Release Rate for period #Cl/sec 2.45 E 05 7.84 E 07
- 3. Percent of Tech Spec limit % 6.73 E 05 1.09 E 06
- 4. Gross Alpha radioactivity Ci 5.75 E 13 0.00 E+00
- 0. Tritium
- 1. Total release C1 3.77 E+00 5.76 E+00 2.5 E+01
- 2. Average Release Rate for period pCi/sec 4.74 E 01 7.24 E 01
- 3. Percent _of Tech Spec limit X 8.13 E 04 1.24 E-03 21
l I R$NGS SEQlANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 TABLE IV-B DASEOUS EFFLUENTS - CR0dND LEVEL RELEASES (
CONTINUOUS MODE BATCH M09E Nuclides Released y,n,,i,1 Quarter 3 Quarter 4 cuarter 3 cuarter 4
- 1. Fission Gases (i.e., Noble Cases)
Ar-41 Ci 0.00 E+00 0.00 E+00 6.22 E 03 1.75 E-02 Kr 85 Cl 0.00 E+00 0.00 E+00 1.90 E 01 1.73 E+00 Kr 85m Cl 9.93 E-01 1.92 E+00 3.20 E-03 3.15 E 02 Kr 87 Ci 0.00 E+00 0.00 E+00 3.99 E 04 4.44 E 03 Kr 88 Cl 9.44 E 01 1.41 E+00- 4.02 E-03 2.28 E 02 Xe 131m Cl 1.02 E+01 4.26 E*00 1.83 E 01 6.21 E 01 W Xe-133 Cl 4.06 E+02 8.33 E+02 6.49 E*01 4.88 E+01 Xe-133m Cl 6.05 E+00 3.05 E+00 8.30 E 02 4.67 E 01 1.27 E+01 1.18 E+01 1.78 E-01 6.22 E 01 I Xe 135 C1 Xe 135m Cl 0.00 E+00 0.00 E+00 1.49 E-04 0.00 E+00 unidentified Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Total for Period C1 4.37 E+02 8.55 E+02 6.55 E+01 5.23 E+01
- 2. Iodines 1 131 Ci 5.40 E 06 3.00 E-05 1.16 E 05 1.51 E 04 1-133 Cl 0.00 E+0L 0.00 E+00 7.30 E 07 4.12 E 05 Total for Period Cl 5.40 E-06 3.00 E-05 1.23 E 05 1.92 E 04
- 3. Particulate 1.58 E-06 0.00 E+00 I Sr-85 Rb-88 Mn-54 Ci Ci Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 1.88 E 04 2.18 E-06 1.60 E-06 0.00 E+00 0.00 E+00 6.23 E-06 Cs 137 Cl 0.00 E+00 0.00 E+00 I Co-60 unidentified Cl Cl 1.14 E-06 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Total for Period Cl 1.14 E-06 0.00 E+00 1.93 E 04 6.23 E 06
I - - - _
RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 )
TABLE IV-C !
1 L
i - GASEOUS EFFLUENTS - TYPICAL LOWER LIMITS OF DETECTION CONTINUOUS AND BATCH RADIONUCLIDES Tin (sci /cci
- 2. Fission & Activation Gases:
Argon-41 2.28 E-07 Krypton-85 8.51 E-06 Krypton-85m 2.92 E-08 Krypton-87 2.10 E-07 Krypton-88 1.06 E-07 Xenon-131m 8.58 E-07 Xeren-133 5.58 E-08 Xcron- 13 3m 1.79-E-07 Xenew ".35 2.55 E-08 Xenon-135m 3.28 E-05 Xenon-138~ 9.72 E-05
- 3. Iedines:
Iodine-131 8.30 E-13 Iodine-133 4.15 E-12 Iodine-135 4.39 E-10
- 4. Particulate:
Barium-140 2.14 E-12 Cobalt-58 4.88 E-13 Cobalt-60 1.55 E-12 Cerium-141 5.08 E-13 Cerium-144 1.88 E-12 Cesium-134 7.50 E-13 Cesium-137 1.35 E-12 Iron-59 1.21 E-12 Lanthanum-140 8.59 E-13 Manganese-54 7.22 E-13 Molybdenum-99 8.12 E-12 Niobium-95 8.27 E-13 Strontium-89 2.00 E-15 Strontium-90 5.00 E-15 Technetium-99m 6.40 E-11 Zirconium-95 1.02 E-12 23
RSNGS SDEANNUAL RADIOACTIVE EITIDENT REIEASE REPORT JULY - IECEMBER 1988
'IAME IV-D RADIOLOGICAL IMPACT ON MAN IDE 'IO GASEDUS EFFIDDTT RrrFASES CAICUIATED RADIATION DOSES AT 'IHE SITE 100NDARY FIR GASEDUS EFFIDENTS:
3RD 4'1H 1988 IEIT GUARTER CUARTER ANNUAL A. Tritium, Iodine, Particulate
- 1. Maximum Organ dose urem 3.18 E-02 1.42 E-01 1.82 E-01 (a) (a) (a) l Percent 'Ibch Spec Limit % 4.24 E-01 1.89 E+00 1.21 E+00 1
B. Noble Gas
- 1. Gamma air dose trad 1.20 E-01 2.57 E-01 4.03 E-01 l Percent Tech Spec Limit % 2.40 E+00 5.14 E+00 4.03 E+00 I
- 2. Beta air dose trad 3.16 E-01 6.97 E-01 1.09 E+00 Percent Tech Spec Limit % 3.16 E+00 6.97 E+00 5.45 E+00 l
C. Direct Radiation
- 1. Dose (TID results) mrum 0.00 E+00 0.00 E+00 0.00 E+00 Parcent 'Ibch Spec Limit % N/A N/A N/A (a) Infant 'Ihyroid l NOTE: 'Ibe quarterly doses listed above were calculated via the GASPAR certputer program using source term (ci) and the concurrent meteorological data for each respective quarter. 'Ihe annual doses i listed above are the sumations of doses frun Quarter 1 through l Quarter 4 of 1988.
24
RSMGS SD4IMMEL PADIQACTIVE EFFIUHir RELEASE RERET JULY - DDCEMBER 1988 V. LIOUID EFFIUDfrS Table V-A, Liquid Effluents - Sumation of All Releases, provides a detailed sumary of liquid effluent releases per quarter. 'Ihis table sumarizes releases of fission and activation products, tritium, dissolved and entrained gases, ard gross alpha raMar-tivity. Also listed is the volume of waste released prior to dilution and the volume of dilution water used durirg ead quarter.
'Ihe followirg methodology is used to calculate the Average Diluted Cor,_ud. ration and the Percent of 'Ib&nical Specification Limit in Table V-A:
total curies released in each category Avg Diluted Cbnc = Der cuarter converted to uCi total volume released (part F in Table V-A) converted to ml n
)
% Tech Spec Limit = Z (Ci / E i)
- 100 l
i=1 where: n = the total number of radionuclides identified
! Ci = the average diluted unbiad. ration Ei = the E of the ith radionuclides, frun 10 CFR 20, Appersiix B, Table II, Column 2 l 'Ihe methodology used to calculate the estimated total error in Table V-A is presented in Section III of this report.
t f Table V-B, Liquid Effluents, provides a otmplete quarterly sumary of the anount of radioactivity (Ci) released per radionuclides in each quarter. Data is provided for fission and activation products, and for dissolved and entrained gases. Tritium and gross alpha are not included in this table (they are listed in Table V-A) . Since no continuous releases of liquid radioactive effluent are made frun RStGS, I data is provided only for batch rela .
l Table V-C, Liquid Effluents - Typical Iower Limits of Detection, i provides a listirg of the typical lower limit of detection (IID) concentrations in pCi/ml for various radionuclides.
Table V-D, Radiological Impact on Man Dae 'Ib Liquid Effluent Releases, provides a summary of calculated radiation doses delivered to a raxinum exposed hypothetical individual at the Site Bourdary for liquid effluents (actual doses will be awed in the 1988 Annual RIMP Report). 'Ihe maxitum calculated total body dose and organ dose for quarter 3, quarter 4, ard 1988 (annual) are listed. A cnuparison versus Technical Specification dose limits is also presented.
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R$NGS SEMIANNUAL RA010 ACTIVE EFFLUENT RELEASE REPORT JULY - DECENBER 1988 TABLE V-A QQUfD EFFLUENTS
- SUMMATION OF ALL RELEASES E s t '. Totat' gq11 cuarter 3 Quarter 4 Error. % j A. Fission & Activation Products
- 1. Total Release (not including tritium, gases, alpha) Cl 5.54 E-04 1.58 E 03 2.3 E+01 i
- 2. Average diluted concentration-during period gCl/ml 1.45 E-10 3.45 E 10
- 3. Percent of. applicable limit % 1.14 E-01 1.57 E-01 B. Tritium
- 1. Total Release Cl 6.06 E+01 3.99 E+01 2.3 E+01 2.
Average diluted concentration during period MCl/ml 1.59 E-05 8.71 E-06
- 3. Percent of applicable limit % 5.30 E-01 2.90 E 01 C. Olssolved and Entrained Gases (i.e., Noble Gases) l-
- 1. Total Release ci 1.22 E-05 6.57 E 04 2.3 E+01
- 2. Average diluted concentration during period gCl/ml 3.19 E-12 1.43 E 10
- 3. Percent of applicable limit % 1.60 E 06 7.15 E-05 D. Gross Alpha radioactivity
- 1. Total Release Cl 0.00 E+00 0.00 E+00 N/A E. Volume of waste released (prior to dilution) Liters 1.54 E+07 1.52 E+07 5.0 E+00 F. Volume of dilution water used during period Liters 3.82 E+09 4.58 E+09 1.0 E+01 26
RSICS SDUNCUAL RADIOACTIVE EFTIDDir RELEASE REPORT JULY - DECEMER 1988 TABIE V-B LIOUID EFTIUDfIS Nuclides Released Batch Mode Fission ard activation products Quarter Quarter (excludim tritium, cases, altha) Unit 3 4 Strontium-90 Ci 9.60 E-06 0.00 E+00 W it-58 Ci 0.00 E+00 1.47 E-06 Cobalt-60 Ci 9.91 E-05 2.25 E-05 Cesium-134 Ci 2.06 E-05 7.79 E-05 Cesium-136 Ci 0.00 E+00 3.90 E-06 Ci 2.18 E-04 3.30 E-04
. Cesium-137 Iodine-131 Ci 1.94 E-04 7.06 EM)4 Iodine-133 Ci 1.27 E-05 5.69 E-05
'Ibtal for Deri.od (above) Ci 5.54 E-04 1.20 E-03 l
Dissolved ard entrained emw Xenon-133 Ci 1.22 E-05 6.52 E-04 l- Xenon-135 Ci 0.00 E+00 4.70 E-06 l
l Note: No continuous releases of liquid radioactive effluent are made from Rancho Seco Nuclear Generatirg Station.
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RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 TABLE V-C LIOUID EFFLUENTS - TYPICAL LOWER LIMITS OF DETECTION RADIONUCLIDES BATCH MODE: LLD (uCi/cci
- 2. Particulate & Iodines:
Sodium-24 2.74 E-09 Chromium-51 1.82 E-08 Manganese-54 2.24 E-09 Iron-59 4.04 E-09 Cobalt-57 2.30 E-09 Cobalt-58 2.37 E-09 Cobalt-60 2.78 E-09 Zinc-65 5.02 E-09 Strontium-89 1.00 E-09 Strontium-90 5.00 E-10 Niobium-95 2.37 E-09 Zirconium-95 3.85 E-09 Zirconium-97 3.26 E-09 Molybdenum-99 1.89 E-08 Technectium-99m 5.18 E-09 Ruthenium-103 2.25 E-09 Silver-110m 1.96 E-09 Antimony-124 2.02 E-09 Antimony-125 6.52 E-09 Cesium-134 2.14 E-09 Cesium-136 3.22 E-09 Cesium-137 2.44 E-09 Barium-140 8.21 E-09 Lanthanum-140 2.74 E-09 Cerium-141 4.13 E-09 Cerium-144 1.81 E-08 Iodine-131 2.41 E-09
! Iodine-133 3.06 E-09 i
- 3. Dissolved and Entrained Gases:
)
Krypton-85 2.10 E-06 Krypton-85m 3.11 E-08 Krypton-87 1.51 E-07 I Krypton-88 1.17 E-07 Xenon-131m 5.33 E-07 ,
l Xenon-133 4.48 E-08 f Xenon-133m 1.11 E-07 Xenon-135 1.54 E-08 l-28 l
1
RSNGS SDEANNUAL RADIQACI'D!E EITIUDTT REIEASE REPORT JULY - IEOMBER 1988 i
)
1 TABIE V-D l
,1 RADIOIDGICAL IMPACT CN MAN IUE 'IO LIOUID EFFIDENT PFTFASES CAIGIATED RADIATION DOSES AT 'IEE SITE BOUNDAIU RR IIQUID EFFIUDfIS:
3RD 4'IH 1988 IET GUARTER QBEEB ANNUAL A. 1. Maximum Total Body dose mrem 6.37 E-01 3.73 E-01 1.71 E+00 (a) (a) (b)
- 2. Percent 'Ith Spec Limit % 4.25 E+01 2.49 E+01 5.70 E+01 I B. 1. Maxim 2m Organ dose mrem 7.40 E-01 5.61 E-01 3.06 E+00 (c) (c) (c)
- 2. Percent 'Ith Spec Limit % 1.48 E+01 1.12 E+01 3.06 E+01 y
h (a) Child (b) Adult (c) Child - Liver NOTE: Although the age group that received the highest Tctal Body dose in Quarters 3 ard 4 was the CHIID, the age group that received the highest 'Ibtal Body dose for the entire year (1988) was the ADULT.
l NOTE: 'Ihe quarterly doses listed above were calculated via the IADIAP
) computer pwpcua using the source term (C1) ard the average dilution flow (cfs) for each r=qwtive quarter. 'Ibe annual doses listed above were calculated via IADDP using the source term ard the average dilution flow for the entire year (1988) .
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RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 VI. SOLID WASTE AND IRRADIATED FUEL SHIPMENT A .' SOLID WASTE SHIPPED Ondnt FOR BURIAL OR DISIOSAL (Not irradiated fuel)
- 1. Type of Waste Unit 6-lin dh Est. Total IW_riod Error: %
- a. Spent resins, filter sluijes, m3 2.42 E+02 evaporator bottans, etc. Ci 7.10 E+00 2.5 E+01
- b. Dry ccepressible waste, m3 5.10 E+01 contaminated equignent, etc. Ci 3.61 E+01 3.6 E+01 I c. Irradiated cu @ nents, control rods, etc.
m3 Ci 0.00 E+00 0.00 E+00 N/A
- d. Other: m3 0.00 E+00 Ci 0.00 E+00 N/A I 2. Estimate of major nuclide ca: position (by type of waste)
Ni-63 % 9.86 E+00 Cs-134 % 6.39 E+00 Co-60 % 4.65 E+00
- b. Ni-63 % 3.40 E+01 Fe-55 % 3.35 E+01 Co-60 % 1.58 E+01 i Cs-137 % 1.08 E+01 Cs-134 % 2.88 E+00 C-14 % 1.14 E+00
- c. Not Apolicable % N/A
- d. Not Apolicable % N/A 30 I
I I
RS!K;S SEMIAIEUAL RADIOACTIVE EFFIUENT RELEASE REPORT
_" JULY - DDCEMBER 1988
- 3. Solid Waste Disposition IAznber of Shiments Mode of Trar s ttotion Destination 26 Truck (sole use vehicle) Richland, Washirgton
- 4. Type of (bntainer
- a. one Type B container
- b. all others Strorg Tight Cbntainers
- 5. Solidification Agent
- a. Envirostone used for one container, N/A for all others B. IRRADIATED IUEL SHIIMEtTfS 1Armber of Shirznents Mode of Transportation Destination None N/A N/A I
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l RSNGS SD4IANNUAL RADICACI'IVE EFFWDTI REIEASE REFORT JULY - DECDER 1988 VII. MEIHNOIDGICAL DATA l
'Ihe meteorological data for Rarcho Seco Nuclear Generatirg Station for !
Quarter 3 and Quarter 4 of 1988 is presented in this section. 'Ihe I joint frequency distribution (JED) of wird speed ard wind direction by atmospheric stability class is presented. Each JFD table displays the q number of hours at each wind speed and direction. JFD tables for stability classes A,B,C,D,E,F, ard G are presented for each quarter, alorg with a JED table sumarizing all of the ocabined stability classes.
Continuous release ard batch release meteorology are presented in the follcwing tables. Continuous release data takes into account all hourly averages in the entire quarter. Batch release meteorology takes into account only those hours durirg which batch releases emwred.
Batch release meteorology includes monitored maaeus batch release hours ard abnomal gaseous release hours. 'Ihis explains the discrepancy between the total hours of batch releases in this section versus the value recorded in the "BA'IG REEASES" sumary table (Section I, part D).
'Ibe following meteorological data was Mam%ed in accordan with USNRC Regulatory Guide 1.111, Methods for Estimatirg Atmospheric Transport ard Dispersion of scaem Effluents in Routine Releases from Light Water Cooled Reactors. Meteorological information frun the site meteorological tower was used to <xmplete the data for the JEDs. 'Ibe meteorological data acquisiticris system recovered 96.88% of the data <
for Quarter 3 and 90.72% of the data for Quarter 4 of 1988.
) Measurements frun the meteorological tower have been made in accortimoe With USNRC Regulatory Guide 1.23, Onsite Meteorological Programs.
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)
r
I SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
'l
=
JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: A DT/DZ ELEVATION: GROUND LEVEL RELEASE I .-______--------_---__--_-------__----___----_-_-_ -_----_--___-
WIND WIND SPEED (MPH) AT 10 METER LEVEL DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 1
l ,
N 0 0 0 0 0 0 0 NNE O 4 6 0 0 0 10 i NE O 2 5 0 0 0 7 ENE O O 1 0 0 0 1 E O O 1 0 0 0 1 ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S O 2 3 0 0 0 5 SSW 0 6 17 0 0 0 23 SW 0 8 29 9 0 0 46 WSW 0 15 81 23 0 0 119 W 0 14 125 19 0 0 158 WNW 0 1 16 0 0 0 17 NW 0 0 5 3 3 0 11 NNW 0 0 0 0 0 0 0 PERIODS OF CALM (HOURS): 0 I VARIABLE DIRECTION HOURS OF MISSING DATA:
O 69 I
I
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: B. DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O O O O O O NE O 1 0 1 0 0 2 ENE O O O O O' O O E O O O O O O O ESE O 1 0 0 0 0 1 SE O O O O O O O i
SSE O 1 0 0 0 0 1
)- S 0 1 0 2 0 0 3 i
SSW 0 4 1 0 0 0 5 t
L SW 0 7 5 1 0 0 13
)
WSW 0 10 20 8 0 0 38 W 0 12 13 1 0 0 26 WNW 0 3 3 1 0 0 7 r
NW 1 1 2 3 1 0 8
""* ________________2_____2_____2_____2_ _ _ _ _3_ _ _ _ _3, _ _ _ , 2 I _____
I TOTAL 1 41 44 19 1 0 106 L ______________________________________________________________
PERIODS OF CALM (HOURS) : 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 69 ,
L
' SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER'1988 RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY HOURS Al Z?.0H WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: C DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O 1 0 0 0 1 NE 1 0 0 0 0 0 1 ENE O O O O O O O E O O O O O O O ESE 1 0 0 0 0 0 1 SE O O O O O O O SSE O O O O O O O I S 0 2 1 0 0 0 3 SSW 0 5 3 0 0 0 8 SW 0 7 8 2 0 0 17 WSW 0 11 21 4 0 0 36 W O 8 17 0 0 0 25 WNW 0 3 4 0 0 0 7 NW 0 0 2 7 0 0 9
) NNW O O 2 2 0 0 4 l
______________________________________________________________ l TOTAL 2 36 59 15 0 0 112
) ______________________________________________________________
PERIODS OF CALM (HOURS): 0 t
VARIABLE DIRECTION O f HOURS OF MISSING DATA: 69
h SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988-RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION
! PERIOD OF RECORD = 1988 QUARTER 3
)
STABILITY CLASS: D DT/DZ ELEVATION: GROUJD LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL l
WIND 1 l
y DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 1 0 0 0 0 3 NNE 1 3 0 1 0 0 5 NE 3 1 1 0 0 0 5 1
1 ENE O O O O O O O
)
E 1 0 0 0 0 0 1 l
I ESE 2 1 1 0 0 0 4 SE 9 5 3 0 0 0 17 SSE 3 9 4 0 0 0 16 S 2 10 4 0 0 0 16 f'
SSW 8 31 7 2 0 0 48 I SW 4 31 19 1 0 0 55 WSW 3 61 51 7 0 0 122 l
W 5 70 41 2 0 0 118 WNW 2 20 11 1 0 0 34 NW 4 19 10 4 1 0 38 .
j NNW 4 6 4 2 0 0 16 TOTAL 53 268 156 20 1 0 498 l PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 69 r
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: E DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 12 0 0 0 0 0 12 i
NNE 10 12 0 0 0 0 22 NE 7 3 2 0 0 0 12 ENE 8 2 0 0 0 0 10 i
l E 6 3 0 0 0 0 9 ESE 8 3 0 0 0 0 11 SE 8 30 8 0 0 0 46 SSE 11 32 11 0 0 0 54
! S 9 45 11 0 0 0 65 l
SSW 10 39 12 1 0 0 62 SW 12 42 24 5 0 0 83 WSW 8 48 43 6 0 0 105 i
) W 12 21 4 0 0 0 37 WNW 2 12 3 0 0 0 17 NW 4 10 1 0 0 0 15 2
) """________________* _________2_____2_____!____*_____
l TOTAL 135 312 119 12 0 0 578
(
PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 69
[
SEMIANNUAL. RADIOACTIVE EFFLUENT RELEASE REPORT-JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION
- . BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS
- F DT/DZ GROUND LEVEL RELEASE l ELEVATION:
WIND SPEED (MPH) AT 10 METER LEVEL l i
WIND DIRECTION- 1-3 4-7 8-12 13-18 19-24 >24 TOTAL ;
7 --- --- .---- --_-- ----- --- ----- !
N- 2 4 0 0 0 0 6 !
!. NNE O 1 0 0 0 0 1 4
' l NE 1 3 0 0 0 0 4 l ENE O 1 0 0 0 0 1 E O 1 0 0 0 0 1 l ,
I. ESE 1 0 0 0 0 0 1
, WSW 2 9 6 0 0 0 17 W 3 5 2 0 0 0 10 WNW' 2 2 0 0 0 0 4 f
NW 1 3 3 0 0 0 7 NNW 0 3 4 0 0 0 7 f- --------------------------------------------------------------
TOTAL 22 53 21 0 0 0 96 PERIODS OF CALM (HOURS) : 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 28
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: G DT/DZ ELEVATION: GROUND LEVEL RELEASE-WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 9 3 0 0 0 14
.NNE. 5 12 3 0 0 0 20 NE O 13 0 0 0 0 13 ENE 3 7 0 0 0 0 10 E 1 6 1 0 0 0 8 ESE 2 7 2 O O O 11 SE O 6 3 0 0 0 9 SSE O 3 2 0 0 0 5 I S 2 5 2 0 0 -0 9 L
SSW 0 5 1 0 0 0 6 i-SW 1 1 0- 0 0 0 2 WSW 3 5 2 0 0 0 10
) W 3 0 1 0 0 0 4 WNW 5 2 0 0 0 0 7 NW 0 3 2 0 0 0 5 I NNW 0 4 2 0 0 0 6 TOTAL 27 88 24 0 0 0 139 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O 69
~
HOURS OF MISSING DATA:
L
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: ALL DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l --_ -__ ---- -_ -- --_-- _-- -----
N 18 16 3 0 0 0 37 NNE 19 42 10 1 0 0 72 NE 16 31 8 1 0 0 56 ENE 14 12 1 0 0 0 27 E 11 14 2 0 0 0 27 l
l l ESE 15 23 4 0 0 0 42 SE 19 59 21 0 0 0 99 SSE 19 69 20 0 0 0 108 S 19 79 25 2 0 0 125 SSW 27 113 45 3 0 0 188 SW 24 115 89 18 0 0 246 i
WSW 19 169 236 49 0 0 473 W 24 137 204 23 0 0 388 WNW 12 47 37 2 0 0 98 ,
NW 11 37 26 17 5 0 96 l
! NNW 13 26 12 6 0 0 57 l TOTAL 280 989 743 122 5 0 2139 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 69
p:
[1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
) JULY - DECEMBER 1988 I. RANCHO SECO NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION l- PERIOD OF RECORD = 1988 QUARTER 3 l' STABILITY CLASS: A DT/DZ ELEVATION: GROUND LEVEL RELEASE f WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l --------- --- ---
'- N O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O l S O O O O O O O SSW 0 0 0 0 0 0 0 I SW 0 1 6 1 0- 0 8 WSW 0 4 25 8 0 0 37 W 0 1 21 8 0 0 30 WNW 0 0 3 0 0 0- 3 NW 0 0 1 1 3 0 5 NNW 0 0 0 0 0 0 0 TOTAL 0 6 56 18 3 0 83 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 28 j
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: B DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE 0- 0 0- 0 0 0 0 SSE O O O O O O O
)
i S 0 0 0 2 0 0 2 SSW 0 0 0 0 0 0 0 l
l SW 0 0 1 1 0 0 2
. WSW 0 2 5 1 0 0 8
)
W 0 5 4 0 0 0 9 WNW 0 1 1 1 0 0 3 NW 0 0 0 2 1 0 3 NNW 0 0 0 1 0 0 1 j TOTAL 0 8 11 8 1 0 28 f.
PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 28 1
1 J
. SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 i
RANCHO SECO NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: C DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND
- l. DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O O O O O O j.
NE O O O O O O O ENE O O O O O O O E O O O O O O O l
ESE O O O O O O O L SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 2 0 0 0 2 f 0 0 5 l SW 0 1 3 1 WSW 0 4 7 1 0 0 12 I
W 0 2 5 0 0 0 7 WNW O 1 2 O O O 3 NW 0 0 0 4 0 0 4 NNW 0 0 1 2 0 0 3 TOTAL 0 8 20 8 0 0 36 PERIODS OF CALM (HOURS): . O VARIABLE DIRECTION O HOURS OF MISSING DATA: 28
l I
}
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
-JULY - DECEMBER 1988 i
l' RANCHO SECO NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURf AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: D DT/DZ ELEVATION: GROUND LEVEL RELEASE
\ __-_______ ..______________ .____-____._________________________
! WIND SPEED (MPH) AT 10 METER LEVEL WIND f . .
1 1 0 0 0 0 2 N-NNE O O O O O O O' NE O O O O O O O ENE O O O O O O O
[
E O O O O O O O f.
ESE O O O O O O O l SE 1 1 0 0 0 0 2 SSE 1- 2 2 0. 0 0 5 S 0 2 3 0 0 0 5 f
SSW 3 5 2 1 0 0 11 SW 0 7 5 1 0 0 13 WSW 0 19 23 2 0 0 44 W 0 27 25 0- 0 0 52 WNW 2 11 7 1 0 0 21 NW 0 4 7 2 1 0 14 NNW 3 3 3 2 0 0 11 TOTAL 11 82 77 9 1 0 180 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 28
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT )
JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: E DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10-METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL-N 1 0 0 0 0 0 1 NNE 2 0 0 0 0 0 2 NE 1. 0 0 0 0 0 1 ENE 2 1 0 .0 0 0 3 E 3 3 0 0 0 0 6-ESE O 2 0 0 0 0 2 SE 1 5 3 0 0 0 9 SSE 3 6 3 0 0 0 12 l-S 2 12 3 0 0 0 17 SSW 3 14 0 1 0 0 18 SW 7 11 5 3 0 0 26 WSW 5 15 10 2 0 0 32 I
W 3 5 1 0 0 0 9 WNW 1 4 0 0 0 0 5 NW 1 3 1 0 0 0 5 I' NNW 3 3 0 0 0 0 6
! TOTAL 38 84 26 6 0 0 154 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 28
1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT L JULY - DECEMBER 1988-
! RANCHO SECO NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY'-
HOURS AT EACH WIND SPEED AND DIRECTION' f PERIOD OF RECORD = 1988 QUARTER 3 L . STABILITY CLASS: F DT/DZ ELEVATION: GROUND LEVEL' RELEASE I. ------------ ...------------------------------------------------
f WIND SPEED (MPH) AT 10 METER LEVEL WIND
). -
DIREOTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL
\ ---- ..-- --- --- ---- ----- ----- --- -----
I
.N 2 4 0 0 0 0 6 NNE O 1 0 0 0 0 1 NE 1 3 0 0 0 0 4 ENE O 1 0 0 0 0 -1 E O 1 0 0 0 0 1
) ESE 1 0 0 0 0 0 1 SE 1 4 2 0 0' O 7 SSE 1 4 1 0 0 0 6 S 2 2 1 0 0 0 5 SSW 2 4 0 0 0 0 6 SW 4 7 2- 0 0 0 13 WSW 2 9 6 0 0 0 17 W 3- 5 2 0 0 0 10 WNW 2 2 0 0 0 0 4 NW 1 3 3 0 0 0 7 NNW 0 3 4 0 0 0 7
~
TOTAL 22 53 21 0 0 0 96 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS'OF MISSING DATA: 28
I SEMIANNUAI, RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION l
BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: G DT/DZ ELEVATION: GROUND LEVEL RELEASE l -___________--__-____--____--____----------__----_--___--. -_-_.
WIND WIND SPEED (MPH) AT 10 METER LEVEL DIRECTION 8-12 13-18 19-24 >24 TOTAL I
1-3 4-7 N O 3 3 0 0 0 6 NNE O 4 3 0 0 0 7 NE O 7 0 0 0 0 7 ENE O 1 0 0 0 0 1 E 1 0 0 0 0 0 1 ESE O 2 2 0 0 0 4 SE O 3 1 0 0 0 4 SSE O 1 1 0 0 0 2 S 0 2 1 0 0 0 3 SSW 0 1 1 0 0 0 2 SW 0 1 0 0 0 0 1 WSW 1 . 0 0 0 0 3 W 1 0 0 0 0 0 1 M 2 1 0 0 0 0 3 NW 0 2 1 0 0 0 3 NNW 0 2 2 0 0 0 4 TOTAL 5 32 15 0 0 0 52 PERIODS OF CALM (HOURS): 0 I VARIABLE DIRECTION HOURS OF MISSING DATA:
O 28 I
I _
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION .
BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 3 STABILITY CLASS: ALL DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL.
WIND I
DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 8 3 0 0 0 15 l
- NNE 2 5 3 0 0 0 10 NE 2 10 0 0 0 0 12 ENE- 2 3 0 0 0 0 5 E 4 4 0 0 0 0 8 l.
ESE 1 4 2 0 0 0 7 SE 3 13 6 0 0 0 22 SSE 5 13 7 0 0 0 25 I
) S 4 18 8 2 0 0 32 SSW 8 24 5 2 0 0 39 SW 11 28 22 7 0 0 68
! WSW 8 55 76 14 0 0 153-f W 7 45 58 8 0 0 118 WNW 7 20 13 2 0 0 42 NW 2 12 13 9 5 0 41 NNW 6 11 10 5 0 0 32 TOTAL 76 273 226 49 5 0 629 PERIODS OF CALM (HOURS): 0 i VARIABLE DIRECTION O 28 HOURS OF MISSING DATA:
1
l '.
l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
! JULY - DECEMBER 1988 l RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY-HOURS AT EACH WIND SPEED AND DIRECTION
PERIOD OF RECORD = 1988 QUARTER 4 STABILITY CLASS: A DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O' O O O O O O l- NNE O O O O O O O NE O O O O O O O l ENE O O O O O O O i
E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 1 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 TOTAL 0 0 1 0 0 0 1 PERIODS OF CALM (HOURS): 76 VARIABLE DIRECTION O HOURS OF MISSING DATA: 205
I SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT I JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 4 STABILITY CLASS: B DT/DZ ELEVATION: GROUND LEVEL RELEASE l ...... _-____ _____
WIND WIND SPEED (MPH) AT 10 METER LEVEL DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL I _________
N O
O O O O O O NNE O O O O O O O NE O O O O O O O O O O O O O O ENE E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 2 0 0 0 2 W O O 1 1 0 0 2 WNW 0 0 0 0 0 0 0 NW O O O O O O O
, NNW 0 0 0 0 0 0 0 PERIODS OF CALM (HOURS): 76 I VARIABLE DIRECTION HOURS OF MISSING DATA:
O 205 I
I
I SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION I CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 4 STABILITY CLASS: C DT/DZ ELEVATION: GROUND LEVEL RELEASE I _______________________________________________.________________
WIND WIND SPEED (MPH) AT 10 METER LEVEL DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL I _________
N O
O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S O O O O O O O SSW 0 0 0 0 0 0 0 I SW 0 0 0 0 0 0 0 WSW 0 1 4 0 0 0 5 W 0 0 5 0 0 0 5 WNW 0 0 0 0 0 0 0 NW 0 0 0 2 0 0 2 NNW 0 0 0 0 0 0 0 PERIODS OF CALM (HOURS): 76 VARIABLE DIRECTION O HOURS OF MISSING DATA: 205 I
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY I HOURS AT EACH WIND SPEED AND DIRECTION l
]
PERIOD OF RECORD = 1988 QUARTER 4 STABILITY CLASS: D DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL I -_---____
N O
3 3 0 0 0 6 NNE O O O O O O O NE O O 1 0 0 0 1 ENE O 1 0 0 0 0 1 E O O O O O O O ESE O O 1 0 0 0 1 SE O 1 2 2 3 0 8 SSE O 11 4 8 3 0 26 S 1 15 12 1 0 0 29 SSW 0 8 4 0 0 0 12 SW 2 20 6 2 0 0 30 WSW 1 53 32 2 0 0 88 W 1 40 19 1 0 0 61 WNW 0 16 8 0 0 0 24 NW 0 17 24 9 0 0 50 NNW 0 2 6 2 3 0 13 PERIODS OF CALM (HOURS): 76 I VARIABLE DIRECTION HOURS OF MISSING DATA:
O 205 I
I - ___
I SEMIANNUAL RADIOACTIVE. EFFLUENT RELEASE REPORT JULY -. DECEMBER'1988 RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY
-HOURS AT EACH WIND SPEED AND DIRECTION )
PERIOD OF RECORD = -1988 QUARTER 4 STABILITY CLASS: . E. DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH)-AT 10 METER LEVEL I WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL
-N 7 10 2 0 1 0 22 NNE 4 2 0 1 1 1 12 NE 5 4 0 0 0 0 12 ENE 5 6 0 0 0 0 11 E 3 5 1 0 0 0 10
~ESE 5 22 16 2 0 0 47
'SE- 14 36 45 33 16 17 162 SSE 12 41 30 26 15 16 142 S 11 30 12 1 3 0 58 SSW' 10 19 6 2 1 0 38 SW 4 32 5 9 1 0 52 WSW 9 37 13 1 1 0 61 W 13 41 5 0 0 0 59 WNW 3 27 5 0 0 0 39 NW 7 21 12 2 1 1 45 ll TOTAL 115 347 161 79 43 40 806 L ______________________________________________________________
PERIODS OF CALM (HOURS): 76 l- VARIABLE DIRECTION O
[ HOURS OF MISSING DATA: 205 I
i
F
) SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l JULY _ DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION
! CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = _1988 QUARTER 4 STABILITY CLASS: F- DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 7 3 0 4 2 20 NNE 7 7 2 0 2 1 21 NE 7 9 0 0 0 0 20 l- ,
j ENE 5 12 0 0 0 0 17 l E 6 9 4 0 0 0 21 l'
ESE 3 33 16 '3 0 0 56 SE 2 38 22 3' O O 65 i
SSE 4 13 13 2 0 0 33 l
J S 2 15 7 0 0 0 24 SSW 6 17 1 0 0 0 24 l
I- SW 5 18 4 1 0 0 29 WSW 4 31 5 0 0 0 40 W 5 7 1 0 0 0 15 WNW 4 10 2 0 0 0 16 NW 1 18 7 2 1 0 29
). NNW 4 7 5 2 0 0 20 f .. TOTAL 66 251 92 13 7 3 450 PERIODS OF CALM (HOURS): 76 VARIABLE DIRECTION O HOURS OF MISSING DATA: 205
SEMIANNUAL RADIOACTIVE. EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH. WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 4 STABILITY CLASS: G. DT/DZ ELEVATION: GROUND LEVEL RELEASE
___._-__.________..__.__.____....___. ----_-________.________.__ f WIND SPEED (MFH) AT 10 METER LEVEL' WIND DIRECTION 1-3 4-7 8-12 13-18.19-24 >24 TOTAL N. 2 8 4 1 0- 0 16 !
l NNE 2 17 0 0 0 0 20 .!
1 NE 11 32 0 0 0 0- 46
^ENE 8 36 0 0' 0 0 50 E 2 23 7 0 0 0 35 l '
ESE 3 24 28 0 0 0 58 i
SE. 4 22 14 0 0 0 43-SSE. 1 15 5 0 0 0 26 S 3 5 1 0 0 0 13 SSW 2 9 1 0 0 0 14 i
SW 2 5 0 0 0 0 9 WSW 1 5 0 0 0 0 6 1
W 2 3 1 0 0 0 7
-WNW 2 3 1 0 0 0 6 NW 1 7 3 0 0 0 13 NNW 2 10 4 1 0 0 18 k -TOTAL 48 224 69 2 0 0 380 t ..____.......... ................--.................__........
PERIODS OF CALM (HOURS) : 76 l- : VARIABLE DIRECTION O
}. HOURS OF MISSING DATA: 205 u
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION CONTINUOUS RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 4 STABILITY CLASS: ALL DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND-DIRECTION 1-3 47 8-12 13-18 19-24 >24 TOTAL N 10 28 12 l' 5 2 64 NNE 13 26 2 1 3 2 53 r
NE 23 45 1 0 0 0 79 ENE 18 55 0 0 0 0 79 E 11 '7
)
S 17 65 32 2 3 0 124 i
SSW 18 53 12 2 1 0 88 l
i SW 13- 75 16' 12 1 0 121 WSW 15 -127 56 3 1 0 202 I
W 21 91 32 2 0 0 149 WNW 9 56 16 0 0 0 85 NW 9 63 46 15 2 1 139 l NNW 9 33 24 7 6 5 87 TOTAL 234 1010 457 124 59 43 2003 l
l PERIODS OF CALM (HOURS): 76 VARIABLE DIRECTION O HOURS OF MISSING DATA: 205 1
i
i SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l JULY - DECEMBER 1988 l RANCHO SECO NUCLEAR GENERATING STATION i l
a BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 4 STABILITY CLASS: A DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O -0 0 0 0 0 0 ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S O O O O O O O
)
SSW 0 0 0 0 0 0 0 SW 0 0 1 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WA 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 i-l NNW 0 0 0 0 0 0 0 TOTAL 0 0 1 0 0 0 1 PERIODS OF CALM (HOURS): 23 VARIABLE DIRECTION O HOURS OF MISSING DATA: 60
)
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l JULY - DECEMBER 1988
) RANCHO SECO NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY l
l HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD = 1988 QUARTER 4 l STABILITY CLASS: B DT/DZ ELEVATION: GROUND LEVEL RELEASE l
WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL I N O O O O O O O l NNE O O O O O O O NE O O O O O O O I ENE O O O O O O' O i
E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O I S 0 0 0 0 0 0 0 I-SSW 0 0 0 0 0 0 0 I 0 0 0 0 0 0 0 SW WSW 0 0 1 0 0 0 1 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 TOTAL 0 0 1 0 0 0 1 y ---_ -_----------_---__-----------_-----_--------_---_-----_--
PERIODS OF CALM (HOURS): 23 VARIABLE DIRECTION O HOURS OF MISSING DATA: 60
l 1
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION i l
.. BATCH RELEASE METEOROLOGY-
. HOURS AT EACH WIND SPEED AND' DIRECTION PERIOD OF RECORD = 1988 QUARTER 4 j STABILITY CLASS: C DT/DZ ELEVATION: GROUND LEVEL RELEASEL WIND SPEED (MPH)'AT 10 METER LEVEL -l WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL
'N O O O O O O O NNE O O O O O O O t
NE O O O O O O O ENE O O O .0 0 0 O E O O O O O O O ESE O O O O O O O SE O O .0- 0 0 0 0 SSE O O O O O O O p S 0 .0 0 0' O O 0 SSW' O O O O O O O l
I SW O O O O O O O WSW 0 1 4 0 0 0 5
[
)
W 0 0 4 0 0 0 4 l- WNW O O O O O O O I
NW 0 0 0 2 0 0 2 NNW O O O O O O O
- t. TOTAL 0 1 8 2 0 0 11 PERIODS OF CALM (HOURS) : 23 VARIABLE DIRECTION O HOURS OF MISSING DATA: 60
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 RANCHO SECO NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 4
-STABILITY CLASS: D DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MP f AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL' N O 1 0 0- 0 0 1 NNE O O O O O O O NE O O 1 0 0 0 l' ENE- 0 0 0 0 0 0 0 E O O O O O O O E 1 0 0 0 ESE 0' O l' SE- 0 1 0 2 2 0 5~
SSE O 7 1 3 1 0 12' i
)
i, ,S 0 8 10 0 0 0 18 SSW 0 5 1 0 0 0 6 I
L SW .2 15 1 0 0 0 18 f WSW 1 34 20 0 0 0 55 W 0 23 13 0 0 0 36 WNW 0 13 5 0 0 0 18
)
NW 0 13 18 6 0 0 39 l NNW O 2 0 1 0 0 3 TOTAL 3 122 71 14 -3 0 213 L ---___-----__--_--_-_-_-----_-_-----------__-----_-_---_----__
PERIODS ~OF CALM (HOURS): 23 VARIABLE DIRECTION O
. HOURS OF MISSING DATA: 60
/..
l
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT I JULY - DECEMBER 1988 'I RANCHO SECO NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY !
1 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 4 STABILITY CLASS: E DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 7 0 0 1 0 13 I
NNE 2 2 0 1 1 1 9 NE' 3 3 0 0 0 0 7 ENE. 4 4 0 0 0 0 8 E 3 4 1 0 0 0 8 ESE 5 15 8 1 0 0 30 SE 11 27 31 25 10 6 110 SSE 9 25 8 9 8 5 66
)
S 4 14 9 1 2 0 30 i
SSW 6 12 4 2 1 0 25 i
SW 4 22 1 3 0 0 30 l
WSW 3 26 9 0 0 0 38 I W 7 25 3 0 0 0 35 WNW 2 18 3 0 0 0 24
)
NW 7 13 2 1 1 0 25 NMW 2 10 1 1 2 5 21 TOTAL 76 227 80 44 26 17 479 i
1 --------------------------------------------------------------
PERIODS OF CALM (HOURS): 23 VARIABLE DIRECTION O j HOURS OF MISSING DATA: 60 I
r l
I SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT f JULY - DECEMBER 1988 L RANCHO SECO NUCLEAR GENERATING STATION l
BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION 1-PERIOD OF RECORD = 1988 QUARTER 4 STABILITY CLASS: F DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND
, DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL i --------- --- --- ---- ----- ----- --- -----
N 1 4 1 0 4 2 13 NNE 4 5 1 0 2 1 14 L
NE 2 6 0 0 0 0 9 I~
ENE 2 9 0 0 0 0 11
}
E 5 5 1 0 0 0 12 s
> ESE 2. 20 13 3 0 0 38 SE 2 25 11 3 0 0 41 SSE 3 8 9 1 0 0 21 S 2 11 4 0- 0 0 17 SSW 4 12 0 0 0 0 16 SW 5 14 1 0 0 0 20 WSW 4 21 3 0 0 0 28 W 5 4 1 0 0 0 10
.WNW 3 6 1 0 0 0 10 NW 1 13 4 1 0 0 19 NNW 4 2 0 1 0 0 7 TOTAL 49 165 50 9 6 3 286 PERIODS OF CALM (HOURS): 23 ,
VARIABLE DIRECTION O i HOURS OF MISSING DATA: 60
l l
h j- SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER-1988 RANCHO SECO NUCLEAR GENERATING STATION l BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION
?
PERIOD OF RECORD = 1988 QUARTER 4 STABILITY CLASS: G . DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND
- DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 5 0 0 0 0 7 NNE 2 12 0 0 0 0 14 f-NE 9 21 0 0 0 0 32 ENE 7 22 0 0 0 0 30 E O 13 4 0 0 0 17 ESE 2 15 12 0 0 0 30 SE 4 15 7 0 0 0 28 SSE O 9 2 0 0 0 12
?
S 2 2 0 0 0 0 5 SSW 1 7 1 0 0 0 9 0 0 0 0 5 SW 2 2 s WSW 1 3 0 0 0 0 4 W 2 1 1 0 0 0 4 WNW 2 2 1 0 0 0 5
'NW 1 2 2 0 0 0 6 NNW 1 1 1 0 0 0 3 TOTAL 38 132 31 0 0 0 211 PERIODS OF CALM (HOURS): 23 VARIABLE DIRECTION O HOURS OF MISSING DATA: 60
-I i
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 j RANCHO SECO NUCLEAR GENERATING STATION BATCH RELEASE METEOROLOGY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 1988 QUARTER 4 STABILITY CLASS: ALL DT/DZ ELEVATION: GROUND LEVEL RELEASE WIND SPEED (MPH) AT 10 METER LEVEL WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 7 17 1 'O 5 2 34 NNE 8 19 1 1 3 2 37 NE 14 30 1 0 0 0 49 ENE 13 35 0 0 0 0 49 E 8 22 6 0 0 0 37 ESE 9 50 34 4 0 0 99 SE 17 68 49 30 12 6 184 SSE 12 49 20 13 9 5 111
- S 8 35 23 1 2 0 70 SSW 11 36 6 2 1 0 56 L SW 13 53 4 3 0 0 74 y WSW 9 85 37 0 0 0 131 i
W 14 53 22 0 0 0 89
, WNW 7 39 10 0 0 0 57 L
NW 9 41 26 12 1 0 91 NNW 7 15 2 3 2 5 34 TOTAL 166 647 242 69 35 20 1202 V ..............................................................
PERIODS OF CALM (HOURS): 23
-VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 60
I-RSNGS SEMIANNUAL RADIOACTIVE' EFFLUENT RELEASE REPORT t
- JULY . DECEMBER 1988 o
,' .l p 3: ,
b.
i ADDENDUM'A
.. ~ CORRECTED DOSES FOR SEMIANNUAL REPORTS FROM JANUARY 1980 THROUGH-JUNE 1988 f[
I e
I.
1 k
L s
)
J:
RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 i ADDENDUM A
SUMMARY
- l Doses and dose commitments are calculated per the ODCM using the guidance from 10 CFR 50, Appendix I and associated Regulatory Guides. These doses are based on the activity released in liquid effluents, total volume of liquid released, and various parameters which reflect the way the liquid discharge may affect the surrounding population.
Calibration of the plant effluent flow recorder (FR 95108) was performed by the United States Geological Survey (USGS) on November 10,1988. This new calibration resulted in minor changes in the dose values which have been reported in various submittals to the NRC. This addendum includes a graph provided by the USGS which displays the relationship between actual flow versus indicated flow (in gpm).
f A summary of the recalculated doses from January 1980
) through June 1988 is presented in this addendum. The h maximum Total Body dose and the maximum Organ dose in each quarter and year during this time period are underlined in the following pages. Some doses have been decreased by as
)
much as about 30 percent while others have increased by a similar amount. All doses are within the established regulatory limits for the time period during which they occurred. These calculated doses are based on theoretical estimates to a maximum exposed individual, not on actual doses to a real person. The theoretical estimates are l
calculated in a conservative manner, and are designed to
} ensure that the actual dose to a real person is not underestimated.
The dose values presented in this addendum supersede the f corresponding dose values submitted in previous SRERRs.
h
! NOTE: In the January - June 1988 SRERR, the maximum l Total Body dose from liquid effluents in Quarter 2 was incorrectly reported on page 28. The value 6.62E-01 mrem should have been reported on that page, as it was in other sections.
1 1
)
l
INDICATED vs ACTUAL PLANT EFFLUENT FLOW '-
12000 11500 11000 10500 7 10000 9500 ,
9000 ,
w 2500
,j' 8000 ,#
A 7500 ,'
C -
3 7000 l U 6303 f A ,
L 6000 ,'
5500 ,.'
7 L l 5000 ,
0 '
/
w 4500 l 4000 _
l N 3500
> 1
( g 3000 ,
P 2500 '
V '
2000
> f 1500 1000 ;
500 0 ,, ,,,, ,,,
,,,,,,,,,,,,,,,,,,,,,,,,,,,j,,,,j ...,....,j,,,,,,,,,,,,,,,,,,,,
C 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 IND:CATED FL0n IN GPV 2
}
) R$0GS SEQlANNUAL RADIOACTIVE EFFLUEN7 RELEASE REPORT ,
DECEAgER 1988 i oULV l .,
l i
1978 8 1979 No activity retessed.
1980 Totst gody Skin gone Liver Thyroid Kidney Lung GI LLI M er 1 Adult 2.94E+00 1.04E 01 2.45E+00 4.03E*00 8.90E-02 1.40E*00 5.25E 01 1.$2E 01 feen 1.62E*00 1.39E 02 2.50E*00 4.07E*00 1.20E 02 1.35E+00 5.29E 01 6.67E-02 l
Child 6.19E*01 2.91E 03 3.10E*00 3.57E*00 2.53E 03 1.14E+00 4.12E 01 2.36E-02
! Infant No doses calculated.
Plant effluent everage flow rate during the quarter was 2493 spm.
Volume of dilution water used during the quarter was 3.27E+08 sets.
Guarter 2 Adult No activity retessed.
Teen Child
} Infant
)
Plant effluent everage flow rate during the quarter was 2692 spo.
Volume of dilution water used during the quarter was.3.53E+08 sets.
f Guarter 3 Adult No activity released.
Teen
) Child Infant I
f Plant effluent everage flow rate during the quarter was 3258 spm.
Volume of dilution water used during the quarter was 4.32E*08 sets.
I Guerter 4
'- Adult No activity retessed.
Teen Child Infant Plant effluent everage flow rate during the quarter was 3023 spm.
Volume of dilution water used during the quarter was 4.00E+08 gets.
Annuel Adult 2.94E+00 1.04E-01 2.45E+00 4.03E+00 8.90E-02 1.40E+00 5.25E 01 1.62E 01 feen 1.62E+00 1.39E 02 2.50E+00 4.07E*00 1.20E 02 1.35E*00 5.29E 01 6.67E 02 Child 6.19E 01 2.91E 03 3.10E+00 3.57E+00 2.53E 03 1.14E+00 4.12E 01 2.36E 02 Infant No doses calculated.
Plant effluent everage flow rate during the year was 2867 spm.
Volume of dilution water used during the year was 1.51E*09 sets.
3
E R$NGS SEMIANNUAL PA0losCTIVE EFFLUENT RELEASE REPORT JULY DECEMBER 1988 1
1981 1 Total gody Skin gone Liver Thyroid Kidney Lung GI LLI I Guerter i Adult No activity released.
feen I. Child Infant Plant effluent everage flow rete during the quarter was 2929 spa.
I Volume of dilution water used during the quarter was 3.80E*08 sets.
euertee 2 1.01E*01 2.03E+01 I Adult feen 4.8?E+01 3.16E+01 2.85E+00 3.90E+01 3.81E 01 4.53E+01 6.48E+01 7.51E+01 2.62E+01 3.23E*01 2.38E+01 2.57E*01 1.07E+01 1.62E+0i Child 1.92E*01 7.96E-02 7.60E+01 8.95E+01 5.91E+01 2.98E+01 1.16E+01 9.80E+00 Infant No doses calculated.
Plant effluent everage flow rate during the quarter was 4297 ppm.
Volume of dilution water used during the quarter was 5.63E+08 gols.
Querter 3 3.48E+01 1.37E+00 4.75E+01 1.76E+00 1.66t+01 6.282+00 5.78E+00 I
Adult 2.88E+01 feen 2.24E+01 1.84E 01 3.40E+01 5.55E+01 9.47E-01 1.84E*01 7.21E+00 4.08E+00 child 1.20E+01 3.85E 02 5.71E+01 6.57E+01 1.50E*00 2.10E+01 7.5dE+00 2.11E+00 Infant No doses calculated.
Plant effluent average flow rate during the quarter was 4722 spm.
Volume of dilution water used during the quarter was 6.26E*08 gols.
Guerter_4 Adult 5.06t+00 3.91E 01 4.33E+00 C.92E+00 3.35E 01 2.52E+00 1.06E*00 5.06E 01 feen 2.71E+00 5.24E 02 4.28E+00 6.83E+00 4.53E-02 2.29E*00 9.14E 01 1.71E 01 Child 1.04E+00 1.09E 02 5.29E+00 5.98E+00 9.52E-03 1.92E+00 6.96E 01 5.64E-02 Infant No doses calcuteted.
Plant effluent swerese flow rate during the quarter was 4056 ppm.
I Volume of dilution water used during the quarter was 5.37E*08 gals.
ennuet 4.61E+00 7.21E+01 1.19E+02 2.83E+01 4.29E+01 1.75E+01 2.65E+01 I Adult feen R.80E*09 5.66E+01 6.18E 01 p.36E+01 1.37E*02 3.33E*01 4.64E+01 1.88E+01 2.04E+01 Child 3.22E+01 1.29E 01 1.38E+02 1.61E+02 6.06E*01 5.27E+01 1.99E*01 1.20E+01 Infant No doses calcuteted.
Plant effluent everage flow rate during the year was 4001 ppm.
Volume of dilution water used during the year was 2.11E*09 gets.
I '
I
R$hCS SEMIACNUAL RADIOACTIVE EFFLUECT RELEASE REPot?
JULT - DECEMgER 1988 l
1 1
1982 j Total ;
gody Skin gone Liver Thyroid Kidney Lung Cl LLI Guarter i Adult 2.87t+01 1.57E 01 2.42E+00 3.92E*00 1.34E 01 1.40E+00 5.53E 01 2.38E 01 Teen 1.56E+00 2.11E 02 2.44E*00 3.92E+00 1.81E 02 1.31E+00 5.17E 01 9.39E 02 Child 5.97E 01 4.40E 03 3.02E+00 3.44E+00 3.79E 03 1.09E*00 3.98E-01 3.22E 02 Infant No doses calculated.
Plant effluent everage flow rate during the quarter was 3375 spa.
Volume of dilution water used during the quarter was 4.37E+08 sets.
Quarter 2 Adult 4.73E 01 3.11E 02 4.25E 01 6.55E 01 2.65E 02 2.37E 01 9.62E 02 7.59E 02 feen 2.98E 01 4.16E 03 4.95E 01 7,58E 01 3.57E 03 2.54E 01 1.00E 01 5.01E-02 Child 1.62E-01 8.691 04 8.32E 01 9.07E 01 7.47E 04 2.90E 01 1.05E 01 2.88E 02 Infant No doses calculated.
Plant effluent everage flow rate during the quarter was 3443 gpm.
Volume of dilution water used during the quarter was 4.51E+08 gols.
Guarter 3 Adult 3.25E+00 1.58E 01 2.96E+00 4.55E+00 1.36E 01 1.61E+00 6.26E 01 3.63E-01 l Teen 2.05E+00 2.12E 02 3.51E*00 5.32E+00 1.88E 02 1.78E*00 7.03E 01 2.32E 01 Child 1.09E+00 4.42E 03 5.91E+00 6.38t+00 4.76E 03 2.04E+00 7.40E 01 1.30E 01 Infant No doses calculated.
t Plant effluent everage flow rate during the quarter was 3144 gpm.
Votume of dilutten water used during the quarter was 4.17E+C8 gals.
Guarter 4 Adult 1.13E+05 1.45E+00 9.21E+00 1.50E+01 2.78t+00 5.86E*00 2.81E*00 5.72E+00 l Teen 5.BBE+00 1.94E 01 8.57E+00 1.42E+01 1.58E+00 4.85E+00 1.99E+00 3.31E+00
! Child 2.32E+00 4.06E 02 1.05E+01 1.24E+01 1.50E*00 4.01E*00 1.49E+00 1.20E+00 Infant to doses calculated.
Plant effluent ave age flow rate during the quarter was 3375 gpe.
Volume of dilution water used during the quarter was 4.47E+08 Annual Adult _1. 79 E
- 01 1.79E+00 1.50E*01 2.41E*01 3.08E*00 9.11E*00 4.09E*00 6.39E*00 Teen 9.79E+00 2.40E 01 1.50E*01 2.42E*01 1.62E+00 8.20E+00 3.31E*00 3.68t+00 Child 4.17E*00 5.03E 02 2.02E+01 2.31E+01 1.51E+00 7.44E+00 2.73E*00 1.39E+00
) Infant No doses calculated.
Plant effluent everage flow rate during the year was 3334 gpm.
Volume of dilution water used during the year was 1.75E*09 gols.
l 5
l l
)
25hC5 SEQlACWUAL RAD 10AC71VE EFFLUEk? RELEASE REPOR7 I JULY - DECEn3ER 1988 I
1983 Total Body skin Bone Liver Thyroid Kidney Lung GI LLI tuerter i Adult 9.98t+00 6.85E 01 8.13E+00 1.35t*01 6.79E 01 4.92E+00 2.08E+00 1.24E*00
[
Teen 5.41E+00. 9.18E 02 8.05E+00 1.33E*01 1.43E 01 4.48E+00 1.81E*00 5.40E 01 Child 2.10E+00 1.92E 02 9.88E*00 1.17E+01 8.55E 02 3.75E*00 1.39E+00 2.19E 01 Infant No doses calculated.
I Plant effluent everage flow rate during the quarter wee 3337 8ps.
! Volume of dilution water used during the quarter was 4.32E*08 gols.
Quarter 2 i Adult 8.59E-01 2.57E 02 7.67E 01 1.2CE+00 2.55E 02 4.20E-01 1.57E 01 5.44E 02 feen 5.52E 01 3.44E 03 9.18E 01 1.42E+00 6.90E-03 4.78E 01 1.89E 01 3.27E 02 Child ~ 2.09E-01 7.19E 04 1.56E+00 1.70f+00 6.65E-03 5.52E 01 2.02E 01 2.07E 02 Infant ko doses calculated.
Plant effluent everage flow rate during the quarter was 2893 spm.
Volume of dilution water used during the quarter wee 3.79E+08 sets.
f
)
cuarte* 3-Adult 1.48t+01 5.95E 01 1.23E+0i 1.03E+01 1.79E*01 7.20E+00 2.69E+00 1.47E+00 i Teen 9.56E+00 7.98E 02 1.45E+01 2.37E+01 2.36E*01 8.04E*00 3.08t+00 9.56E 01 Chltd 5.17E+00 1.66E 02 2.44E*01 2.81E*01 4.36E+0i 9.20E+00 3.24E+00 5.48E 01 Infant No doses calculated.
Plan; ffluent everage flow rate dur'ng the quarter was 3535 spm.
Volume of dltution water used during the quarter was 4.68E+08 sets.
Quarter 4 Adult ga49E+0i 2.41E+00 5.36E*01 8.86E+01 3.16t*00 3.09E+01 1.17E+01 3.72E+00 feen 3.58E*01 3.23E-01 5.46E+01 8.92t+01 1.28E+00 2.98E*01 1.17E+01 1.51E+00 Child 1.17E*01 6.75E 02 6.77E+01 7.82E*01 1.10E+00 2.50E+01 .9.03E+00 5.34E 01 Infant ko doses calculated.
Plant effluent everage flow rate during the quarter was 3972 ppe.
Volume of dilution water used during the quarter was 5.26E+08 pels.
Annuel Adult 9.06t+0i 3.71E+00 7.47E*01 1.24E+02 2.18E+01 4.34E+01 1.66E*01 6.50E*00 feen 5.13E*01 4.98E 01 7.82E+01 1.28E*02 2.50E*01 4.28E*01 1.67E+01 3.04E+00 Child 2.12E+01 1.04E 01 1.04E+02 1.20E+02 4.48E+01 3.85E+01 1.39E+01 1.32E*00 Infant No doses calculated.
Plant effluent everage flow rete during the year was 3434 spm.
Volume of dilution water used during the year was 1.81E*09 gols.
6
RENGS SEQlANDUAL RADIOACTIVE EFFLUEO? RELEASE REPOR7 JULT - DECEMBER 1988 1984 Totel Body Skin Bone Liver Thyroid Kidney Lung GI LLI Guerter i Adult 7.99f*01 2.83E+00 6.59E+01 1.08E+02 5.49E+00 3.79E+01 1.42E+01 4.42E+00 feen 4.41E+01 3.79E 01 6.75E+01 1.09E+02 3.18E+00 3.66E*01 1.43E+01 1.81E*00 child 1.68E*01 7.93E 02 8.36E+01 9.65E+01 3.03E+00 3.10E+01 1.12E+01 6.44E 01 Infant No doses calculated.
Plant effluent everage flow rate during the quarter was 3924 spp.
Volume of dilution water used during the quarter was 5.14E+08 gel 2.
Quertee 2 Adult 9.74E+0i 2.99E+00 8.26E+01 1.34E+02 6.20E+00 4.64E*01 1.71E+01 6.54E*00 feen 6.24E+01 4.00E 01 9.86E+01 1.58E+02 5.24E+00 5.26E*01 2.06E+01 3.91E*00 child 3.25E+01 8.36E 02 1.66E+02 1.88t+0? 9.20E+00 6.02E*01 2.17E*01 2.08E+00 Infant No doses calculated.
Plant effluent everage flow rate during the quarter was $602 spm.
. Volum* of dilution water used during the quarter was 7.34E+0B gets.
Quarter 3 Acult 3.95t+0i 1.02E*00 3.28E+01 5.44E+01 3.59E*01 1.99E*01 8.07E+00 3.55E+00 feen 2.62E+01 1.36E 01 3.95E*01 6.40E+01 4.71E*01 2.28E*01 9.73E+00 2.85E+00 Child 1.54E+01 2.85E 02 6.65E+01 7.70E+01 8.67t+01 2.69E*01 1.11E+01 3.16t+00 lefant No doses calculated.
Plant effluent everage flow rate during the quarter was 6426 spm.
Volume of dilution water used during the quarter was 8.51E+08 sets.
)
Quarter 4 Adult 3.86t 01 1.83E 02 2.90E 01 5.12E-01 1.18E 01 2.25E 01 1.28E 01 9.02E 02 l Teen 2.16E 01 2.46E-03 2.94E 01 4.90E 01 7.83E 02 1.94E 01 1.01E 01 5.08E 02 l Child 1.12E-01 5.14E 04 3.64E 01 4.42E 01 8.17E 02 1.73E 01 9.13E 02 4.84E 02 Infant No doses calculated.
i Plant effluent everage flow rate during the quarter was 6723 ppm.
Volume of dilution wete ' used during the quarter was 8.91F+08 sets.
A nnue l Adult 2.17t+02 6.86E+00 1.82E+02 2.98E*02 4.77E+01 1.04E*02 3.95E+01 1.46E*01 Teen 1.33E+02 9.18E-01 2.06E+02 3.32E+02 5.56E*01 1.12E+02 4.47E+01 8.63E+00 l Child 6.49E+01 1.92E-01 3.17E+02 3.62t+02 9.90E+01 1.18E+02 4.40E+01 5.94E+00
) Infant ho doses c:l:ulated.
Plan; effluent everage flow rate during the year was 5669 spm.
Volume of dilution water used during the year was 2.99E+09 sets.
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R$WGS SEQIAWNUAL AA910AC71VE EFFLUENV RELEASE REPORT JULY.* DECEMBER 1988 1985 Total Sody Skin Bone Liver Thyroid Kidney Lung GI LLI Guerter i Adult 1.29t+00 4.61E-02 8.03E 01 1.63E+00 4.60E 01 8.35E 01 5.64E 01 4.88E 01 feen 9.21L 01 4.61E 03 8.07E 01 1.68E+00 4.85E 01 8.57E-01 6.03E-01 5.00E 01-Child 1.08E+00 6.45E 04 2.15E*00 3.05E*00 7.70E 01 1.45E*00 9.61E*01 7.28E 01 Infant No doses calcuteted.
Plant effluent everage flow rete during the quarter was 5952 spa.
Volume of dilution water used during .h4 quarter was 7.71E+08 gets.
Guerter 2 Adult 1.21t+00 6.16E 02 9.05E 01 1.60E*00 1.95E 01 6.62E 01 3.51E 01 2.37E 01 feen 7.32E 01 6.16E*03 8.99E 01 1.60E+00 1.65E 01 6.40E 01 3.49E 01 2.02E 01 Child 7.20E 01 8.61E 04 2.39E+00 2.97t+00 2.49E 01 1.12E+00 5.63E-01 2.78E 01 Infant ko doses calculated.
) Plant effluent everage flow rate during the quarter was 3566 spa.
Volume of dilution water used during the quarter was 4.67E+08 sets.
Guerter 3 Adult 2.48t+00 9.67E 02 1.82E*00 3.26E+00 2.86E 01 1.27E+00 6.14E-01 3.42E 01 feen 1.46E+00 9.67E 03 1.82E*00 3.26E+00 2.37E 01 1.23E+00 6.22E 01 2.79E 01 Child 1.37E*00 1.36E-03 4.81E*00 6.06t+00 3.59E 01 2.17E*00 1.01E+00 3.92E 01 l Infant No doses calculated.
1 Plant effluent everage flow rete during the guerter was 3875 spm.
l Volume of dilution water used during the quarter wee 5.13E+08 gets.
Quarter 4 Adult 2.05f 01 1.10E 02 1.98E 01 2.94E 01 2.40E-01 1.23E 01 6.51E 02 4.10E-02
! Teen 1.23E 01 1.10E-03 2.01E 01 2.96E-01 3.10E 02 1.21E 01 6.61E 02 3.48E C2 Child 1.23E 01 1.54E 04 5.41E-01 5.65t-01 4.70E 02 2.16E 01 1.08E 01 5.02E 02 Infant No doses calculated.
Plent. effluent everage flow rate during the quarter was 4632 gpm.
Volume of dilution water used durlies the quarter was 6.14E*08 sets.
- f. Annuel Adult 5.19t+00 2.15E 01 3.72E+00 6.79E+00 1.18E+00 2.89E+00 1.59E+00 1.11E+00 feen 3.24E+00 2.15E 02 3.72E+00 6.84E+00 9.18E 01 2.85E+00 1.64E+00 1.02E+00
, Child 3.29E*00 3.02E-03 9.90E*00 1.26t+01 1.43E+00 4.96E+00 2.64E+00 1.45E+00 Infant No doses calculated.
Plant effluent everage flow rate during the year was 4506 ppm.
[ Volume of dilution meter used during the year was 2.37E+09 gols, f
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R$2GB $EMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMgER 1988 1986 Total Body Skin Bone Liver Thyroid Kidney Lung Cl LLI Guerter i Adult 9.01E ci 2.34E 02 4.17E 01 1.09E*00 5.44E 01 7.29E 01 6.05E 01 5.55E 01 feen 7.88E 01 -2.34E 03 4.25E 01 1.16t+00 5.92E 01 7.82; 01 6.66E-01 6.00E-01 Child 1.0er+00 3.26E 04 1.15E+00 2.02E*00 9.20E 01 1.28E+00 1.05E+00 9.28E 01 Infant to doses calculated.
Plant effluent everage flow rete during the Quarter was 4193 gpm.
Volume of dilution water used during the quarter was 5.43E+08 sets, guarter 2 Adult 2.16E 02 1.34E 03 2.41E 03 3.25E 02 1.21E 03 1.18E 02 4.73E 03' 1.81E 03 feen 1.15E 02 1.34E 04 2.45E 02 3.25E 02 1.77E 04 1.12E 02 4.46E 03 6.37E 04 Child 9.42E 03 1.88E 05 6.59E 02 6.31E 02 1.13E 04 2.05E 02 7.51E 03 5.08E 04 Infant to doses calculated.
Plant effluent everage flow rate during the quarter was 5569 spm.
Volume of dilution water used during the cuarter was 7.30E*08 sets.
Gusrter 3 Adult 2.74E 02 1.21E 02 4.36E 02 4.95E 02 6.47E 03 1.66E 02 -6.56E-03 2.67E 03 Teen 1.13E 02 1.69E 02 4.64E 02 3.98E 02 7.75E 03 1.39E 02 4.72E 03 6.47E 04 Ctlld 9.92E 03 4.01E 02 1.08E-01 7.26E 02 1.25E 02 2.64E-02 8.13E 03 4.48E-04 Infant .No doses calculated.
j Ptset effluent everage flow rate during the quarter was 4696 spm.
j Votume of dilution water Lsed'during the quarter was 6.22E+08 gals.
Cuerter 4 I_ Acult 2.39E 01 2.56E 02 1.33E 01 2.90E 01 1.19E 01 1.75E 01 1.38E 01 1.57E 01 Teen 1.80E 01 2.56E 03 1.19E 01 2.86E 01 1.11E-01 1.69E 01 1.34E 01 1.50E 01 Child 2.31E*01 3.59E-04 3.44E 01 5.05E-01 1.70E 01 2.78E 01 2.09E 01 1.96E-01 i Infant No doses calculated.
Plant effluent everage flow rate during the quarter was 5289 som.
Volume of dilution water used during the quarter was 7.01E+08 sels.
Annuel Adult 1.19E+00 6.24E 02 5.96E 01 1.46t+00 6.70E 01 9.33E 01 7.54E 01 7.16E 01 I' feen 9.91E 01 2.20E 02 6.14E 01 1.52E*00 7.11E 01 9.76E 01 8.09E-01 7.51E 01
'Chilt 1.33E+00 4.08E 02 1.63E+00 2.66E*00 1.10E+00 1.60E+00 1.27E+00 1.12E+00 Infant No doses calculated.
Plant effluent everage flow rete during the year was 4937 spm.
Volume of dilution water used during the year was 2.60E*09.
g
E R$NGS SEQIANWUAL RA010 ACTIVE EFFLUEdf RELEASE REPORT JULY - DECEMBER 1988 I
l 1987 l
i Total body Skin gone Liver Thyroid Kidney Lung GI-LLI Quarter 1 g Adult 4.51E 02 2.36E 03 4.30E 02 6.43E 02 2.03E 03 2.29E 02 8.98E 03 3.20E 03 feen 2.40E 02 2.36E 04 4.35E 02 6.40E 02 2.04E 04 2.16E 02 8.50E 03 1.09E 03 Child 1.96E 02 3.30E-05 1.17E 01 1.23E 01 2.95E 05 3.95E-02 1.43E-02 7.73E 04 I Infant No doses calculated.
Plant effluent everage flow rate during the quarter was 5871 spm. -
Volume of dilution water used during the quarter was 7.61E*08 sets.
cuarter ?
I Adult 1.50E 01 1.37E 03 2.06E 02 1.60E 01 1.33E 01 1.43E-01 1.37E 01 1.34E 01 feen 1.59E 01 1.37E 04 2.09E-02 1.76E-01 1.49E 01 1.58E 01 1.53E 01 1.49E 01 Child 2.41E-01 1.91E 05 5.62E 02 2.87E 01 2.32E 01 2.50E 01 2.39E 01 2.32E 01 Infant No doses calculated. 4 Plant effluent everage flow rate during the quarter was 5772 spm. ,
Volume of dilution water used during the quarter was 7.56E+08 gels.
Everter 3 Adult 3.37E-02 2.46E-03 3.72E 02 4.94E 02 2.11E 03 1.83E 02 7.55E 03 2.99E 03 feen 1.86E 02 2.4eE-04 3.76E 02 5.02E 02 2.13E 04 1.72E 02 6.81E 03 1.28E 03 Child 1.45E 02 3.45E 04 1.01E 01 9.71E 02 3.06E 05 3.17E 02 1.14E 02 8.81E 04 I Infant No doses calculated.
I Plant effiuent .everage flow rete during the guerter was 5218 spm.
Volume of dilution water used during the quarter was 6.91E+08 gols.
I Guertee 4 Adult Teen 1.30E 01 9.46E-02 1.20E-02 1.33E 01 1.88E 01 1.20E 03 1.83E 01 2.57E-01 1.02E 02 6.99E-02 3.01E 02 1.72E 02 1.03E 03 8.73E 02 3.45E-03 8.14E 03 Child 2.35E 02
- 67E-04 4.97E 01 5.n2E-01
. 1.49E 04 1.62E 01 5.85E-02 5.64E 03 I
Infant to doses calculated.
Plant effluent everage flow rate during the quarter was 5427 spm.
Volume of dilution water used during the quarter was 7.19E*08 gols.
Annuel 1.47E 01 2.54E 01 1.83E 01 1.58E 01 I 3.60E Ei Adult 1.42E 02 2.34E 01 4.62E 01 feen 2.96E 01 1.82E-03 2.85E 01 5.48E 01 1.51E 01 2.84E 01 1.72E 01 1.60E 01 Child 2.99E 01 5.64E 04 7.71E 01 1.01E+00 2.33E-01 4.83E 01 3.23E 01 2.40E-01 Infant ho doses calculated.
- Plant effluent everage flow rate during the year was 5572 som.
~
Volume of dilution water used during year was 2.93E*09 gols. ,,
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R$ HGS SEQ!ANOUAL RAD 10AC71VE'EFFLUENV RELEASE REPOR7 JULY - DECEMBER 1988 1988 l
Total Body Skin tone Liver Thyroid Kidney Lung GI LLI Guerter 1 l Adult 5.83E-02 2.33E 03 6.39E 02 8.70E 02 2.03E 03 3.08E 02 1.16E 02 1.05E 02
{ Teen 3.66E*02 1.17E 03 7.53E 02 1.00E 01 1.04E 03' 3.46E 02 1.42E 02 8.91E 03 Child 1.92E 02 1.64E 04 1.20E 01 1.15E 01 2.03E 04 3.75E 02 1.36E 02 4.82E 03 Infant 2.05E 03 No date 2.33E 02 2.74E 02 1.94E 05 7.35E 03 2.99E 03 1.96E-04 l
Plant effluent everage flow rate during the quarter was 6471 gps.
Volume of dilution water used during the quarter was 8.48E*06 sets.
l Guerter 2 Adult 8.74E 01 1.87E 02 8.82E 01 1.26E+00 1.66E 02 4.33E 01 1.54E 01 1.09E 01 feen 5.53E 01 9.37E 03 1.04E+00 1.45E+00 8.71E 03 4.91E 01 1.94E 01 8.63E 02 i
Ch(Ld 2.93E 01 1. 31 E
- 0 3 1,68t+00 1.64E+00 2.22E 03 5.29E 01 1.91E 01 4.45E 02 Infant 3.01E 02 No date 3.11E-01 3.84E 01 1.57E 03 1.03E 01 4.16E 02 1.83E 03 f Flent effluent everage flow rete during the quarter was 7117 ppm.
) Volume of dilution water used during the quarter was 9.33E*08 sets.
I f
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IRSNGS SEMIANNUAL RADIOACTIVE' EFFLUENT ' RELEASE 4 REPORT DECEMBER 1988
. JULY ADDENDUM B COMMISSIONING OF ABGLV-GASEOUS EFFLUENT MONITOR ~R-15546A
-AS A TECH SPEC MONITOR DURING THE SEMIANNUAL REPORT PERIOD FROM JANUARY - JUNE 1988 I
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I RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
I JULY - DECEMBER 1988 ADDENDUM B
'.?he Auxiliary Building Grade Level Vent (ABGLV) officially became I e Technical Specification gaseous effluent pathway on 3/19/88 per Amendment 98 to RSNGS Technical Specifications.
9/28/87 is the date that ABGLV monitor R-15546A was put into Although l service (ECN R-1227), 3/19/88 is the date it was considered to be I the official Technical Specification monitor. Presently, the ABGLV is a continuous release pathway for gaseous effluents per Technical Specification Table 3.16-1. This information was inadvertently omitted in the SRERR for January to June 1988.
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RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT I JULY - DECEMBER 1988 L.
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ADDENDUM C MAJOR CHANGES ' TO THE LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM DURING'THE FOLLOWING SEMIANNUAL REPORT PERIODS:
JULY DECEMBER 1987 JANUARY - JUNE 1988 l
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I RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 ADDENDUM C Major changes to the Liquid Effluent Radwaste Treatment System were completed in Quarter 3 of 1987, and the testing of this equipment was completed in Quarter 1 of 1988. These changes were implemented to further reduce offsite doses resulting from radioactive liquid effluents, in order to ensure that Rancho seco Nuclear Generating Station is operated within the numerical I guidelines of 10 CFR 50, Appendix I. The following changes have been implemented, but were not reported in previous SRERRs:
- 1. Disposal of condensate polishing demineralized resins to reduce the radiological effluent source term.
I 2. Installation of demineralization processing secondary waste water to reduce effluent activity.
for Installation of effluent strainer processing for I 3.
secondary waste water to (i.e., to remove resin).
reduce effluent activity I 4. Installation of a 100,000 gallon Regenerant Holdup Tank (RHUT) to improve segregation of radioactive and non-radioactive effluents and thereby improve and I radioactivity detectability, waste water capacity.
increase the total Installation of permanent piping from the RHUTs back to I
5.
the primary side radioactive liquid treatment system to provide additional processing capability.
- 6. Installation of control devices to assure RHUTs A and B cannot be discharged directly offsite, thus providing improved control over radioacti.ve effluent releases.
- 7. Increase in plant ef fluent dilution flow to a minimum 5000 gpm to reduce final effluent concentrations.
Note: Minimum flow of 5000 gpm has since been changed l
to an average flow of 8500 gpm to more accurately reflect plant conditions.
- 8. Installation of additional radiation monitoring capability to provide increased monitoring and control over liquid effluent releases.
References:
SMUD letter GCA 87-763 to NRC, dated 11/12/87 SMUD letter GCA 87-916 to NRC, dated 1/7/88 1
I- RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 I
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ATTACHMENT A OFFSITE DOSE CALCULATION MANUAL I (Procedure AP.310, Rev. 6)
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APPROYAL fo . 0 F I N A L APPROVAL (FOR PROCEDURES DEVELOPED UNDER AP.2.91 ONLY F OR PROCEDURES DEVELOPED UNDER RS AP-e502 SHALL BE 1(IE COVER SHEC1 Of THE PROCEDURE) ,e jd AP Pft ov E D : Y E c c /<'QCON} NT T E D ONfg)
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i ZFTECTIVE DATE 10-29-65 Rev .' 6' HP5389A D-5054A AP.310 0FFSITE DOSE CALCULATION MANUAL I/
Syl/Sppg N Ng Ol TABLE OF CONTENTS i eg.j9 SECTI 8 jg[.Sgg USgg jLAE
! 1.0 PURPOSE h#U.9 3 O' E 2.0 SCOPE y 3 3
044
3.0 REFERENCES
ND 4 l 4.0 DEFINITIONS I
5.0 PROCEDURE 5 0.1 Calculations Involving Liquid Effluents - General Considerations 5 5.2 Calculations for Compliance with 10CFR20 (Technical Specifications 3.17.1 and 3.15) 6 5.3 Calculations for Compliance with 10CFR50, Appendix I i
(Technical Specification 3.17.2) 9 12 5.4 Gaseous Effluent l 5.5 Atmospheric Dispersion of Gaseous Effluent 15 5.6 Radionuclides in Effluent Air 15 5.7 Calculations for Assessing Compliance with 10CFR20.106 (Technical Specifications 3.16 and 3.18.1) 16 5.8 Calculations for Determining Compliance with 10CFR ,
Part 50, Appendix I: Air Dose From Noble Gas 21 5.9 Compliance with 10CFR Part 50, Appendix I: Dose From Tritium, Iodine, and Particulate in Effluent Air 23 5.10 Evaluating Compliance with 40CFR Part 190.10: Fuel Cycle Dose 26 29 5.11 Administration of Offsite Dose Calculations j Rev. 6 AP.310-1
TABLE OF CONTENTS (Continued)
SECTION. PKtE 6.0 RECORDS 30 7.0 ATTACHMENTS 30 7.1 ODCM Site Specific Data Base 30-LIST OF TABLES TABLE NUMBER IIJ1E PAGl Gaseous Effluent Release Points 13 5.4.1 .
Liquid Source Terms 37 A-1 Gaseous Source Terms 38 A-2 A-3 Deleted i A-4 1986 Annual Average X/Q and D/0 -
Special Locations .39 A-5 . Distances for Gaseous Effluent Pathway Evaluation 41 A-6 Dose Factors for Noble Gases and Daughters 42 7
A-7 Values Used to Derive Dose Factors for the Maximum Exposed Individual 43 LIST OF FIGURES FIGURE NUMBER lilLE PKI
) 4.8-1 Exclusion Area 4.8-2 Site Boundary for Liquid Effluents 4.8-3 Site Boundary for Gaseous and Liquid Effluents Liquid Effluent Flow Diagram 33 l- 5.1 l 5.4 Gaseous Effluent Flow Path 34 i
Rev. 6 AP.310-2 1 _
1.0 PURPOSE The Offsite Dose Calculation Manual (ODCH) describes the methods .
used to calculate doses from ionizing radiation to the general 'l public due to operations at the Rancho Seco Nuclear Generating.
Station (RSNGS). Methods are described for assessing compliance with the Rancho Seco Technical Specifications as they apply to-10 CFR Part 20.106, 10 CFR Part 50 Appendix I, and 40 CFR 190.10a for liquid and gaseous effluents.
t 2.0 SCOPE The ODCM describes the methods used to calculate doses to the most exposed members of the general public and effluent monitor I setpoints for radioactive gaseous and. liquid effluents The ODCM also contains important site specific parameters used in the calculations (Attachment 7.1). Detailed instructions for performing the calculations described in the ODCM are contained in separate implementing procedures for the ODCM.
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3.0 REFERENCES
3.1 Code of Federal Regulations. Title 10, Chapter 1, Parts 20,
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50.36a and Part 50 Appendix I 3.2 Rancho Seco Unit 1 Technical Specifications, Sections 1.0, 3.15 through 3.26, 4.19 through 4.29, 5.1, 6.8, 6.9, 6.15, and 6.16 3.3 USNRC Regulatory Guide 1.109, Rev. 1. 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, October f
1977 8
3.4 H.C. Burke, et.al., Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133, USNRC:NRR, October 1978 l
l 3.5 ORNL, User's Manual for LADTAP II, NUREG/CR-1276, May 1980 3.6 D.L. Strange, et.a1., LADTAP-II, Technical Reference and User Guide, NUREG/CR-4013, Pacific Northwest Laboratory, April 1986 3.7 Eckerman, K.F., et.al., User's Guide to GASPAR Code, NUREG-0597, USNRC:NRR, June 1980, in RSIC CCC-463
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b Rev. 6 f' AP.310-3 l
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i I 4.0 DEFINITIONS r
4.1 REAL INDIVIDUAL The Real Individual is defined as any member of the public who
(- participates in activities that result in that person being in the actual pathways for offsite dose. A Real Individual who is expected, based on Land Use Census, to receive the maximum offsite dose to a real person may be used to calculate-doses to assess compliance with 40 CFR 190.
l- 4.2 BATCH RELEASE 4.2.1 The discharge of 11guld radioactive wastes of discrete volume.
Batch releases are n3rmally from one of the retention basins to the Waste Water discharge canal (Environmental Release Point).
"C" Regenerative Hold-Up Tank (RHUT) is a non-radioactive source of water and can be used as a source of dilution water when it is
! being discharged.
4.2.2 The discharge of gaseous wastes of discrete volume. Batch releases for the gaseous pathway include, but are not limited to, l Reactor Building Purges and Haste Gas Decay Tank releases.
4.3 CONTINUOUS RELEASE
)
4.3.1 Contir,>.,ous liquid releases are not planned to be made from RSNGS.
) 4.3.2 A continuous gaseous release is the discharge of gaseous wastes of a nondiscrete volume from a system that may have an input flow during the release.
y 4.4 DEFAULT RADIONUCLIDES HIX f A mixture of radionuclides that can be used to determine monitor setpoints when no detectable activity is available. (Table A-1, Liquid Source Terms, and Table A-2 Gaseous Source Terms) 4.5 DILUTION FLOW The volume or volume rate of fluid (liquid or gas) which is added
) to a radiological release stream for the purpose of decreasing-the instantaneous concentration of the stream.
4.6 MAXIMUM EXPOSED INDIVIDUAL i
The Maximum Exposed Individual is that member of the public (real l individual) who is expected, based on the Land Use Census, to !
receive iLe maximum exposure to radioactive effluent being evaluated, via applicable pathways. Alternatively, exposure to more conservative conditions (i.e., location and/or pathways, yielding greater exposure) may be assumed. Values of parameters in RG 1.109 Table E-5 are assumed to represent the maximum exposed individual unless Land Use Census data justify a different value.
Rev. 6 AP.310-4
47 RSNGS Rancho Seco Nuclear Generating Station 4.8 UNRESTRICTED AREA Any area at or beyond the site boundary access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation anti radioactive materials, and any area within the site boundary used for residential quarters or industrial, commercial, institutional and .
recreational facilities. For environmental protection / effluent control purposes, the Rancho Seco Unrestricted Area is the area outside the Exclusion Area and Liquid Effluent Discharge boundaries, as shown in Figures 4.8-1 and 4.8-2.
NQlE: Figure 4-8-3 is the site boundary for gaseous and liquid effluents. -
4.9 Safety Factor (SF)
A number greater than Unity used in calculations to introduce greater conservatism (larger margin of safety) to offset various uncertainties in instrumentation and methods. Safety factors are~
set by Chemistry Supervison based on either analysis or professional judgement. Unless otherwise specified, the default value is two (2).
5.0 PROCEDURE J
5.1 CALCULATIONS INVOLVING LIQUID EFFLUENTS--GENERAL CONSIDERATIONS 5.1.1 A simple diagram of the main flow paths of radioactive liquid effluent produced by the RSNGS appears as Figure 5.1. The liquid
) effluent discharge of RSNGS forms the headwaters of Clay Creek.
The dilution factor of a typical nuclear power plant is not applicable.
5.1.2 Dilution of the liquid effluent occurs offsite:
5.1.2.1 At the confluence of Clay and Hadselville Creeks and of f Hadceiville and Laguna Creeks, and j 5.1.2.2 At the confluence of Laguna Creek and the Cosumnes River.
I 5.1.3 For calculation of offsite doses to determine compliance with 40 CFR 190 (Technical Specification 3.25), dilution which occurs offsite may be used. When dilution offsite is used, the ,
following general equation applits:
Cd - Ca Fa l
( Fd
) i Rev. 6 AP.310-5
Where:
Cd - the concentration downstream from a confluence C= the concentration upstream from a confluence Fa - the average yearly upstream flow rate Fd the average yearly downstream flow rate 5.1.4 When calculations are done to assess compliance with.10 CFR 50, Appendix I (Technical Specifications 3.17.2), no dilution which occurs outside the site boundary for liquid effluent is assur'd.
5.2 CALCULATIONS FOR COMPLIANCE WITH 10 CFR 20 (Technical Specifications 3.17.1 and 3.15) .
5.2.1 Pre-release Calculations 5.2.1.1 Radioactive liquid effluent discharges normally originate in one of the RHUT tanks (A or B) and are then discharged into one of the retention basins (North or South). Samples are collected and analyzed from each RHUT prior to discharge to ensure that compliance with Technical Specifications 3.17.1 and 3.17.2 can be achieved when discharging from the retention basins. The retention basin discharge is the actual liquid effluent release point (Environmental Release Point).
5.2.1.2 The following equation is used to determine if a radioactive 11guld effluent discharge will meet the conditions of Technical p Specification 3.17.1:
F MPCF - I C'- X I
L
! .MPC.j F +F r l
Where:
1 MPCF - the calculated fraction of Maximum Permissible Concentration in the radioactive liquid effluent discharged into f the unrestricted area Ct
- the total concentration of radionuclides 1 in the batch, prior to dilution, of liquid effluent in pCi/ml MPCj - the MPC of radionuclides i from Appendix B, Table II, L
tolumn 2 of 10 CFR 20 in pCi/ml i i
Fr - discharge flow rate; the flow rate of the radioactive liquid batch release from the retention basin to the Waste Water Discharge Canal in gpm (See Figure 5.1) ,
)
Rev. 6 AP.310-6 I
]
fc - the total available flow rate of the dilution water at
.the time of discharge of the liquid effluent in gpm (See figure 5.1)
Compliance with Technical Specification 3.17.1 is anticipated when MPCF is less than or equal to 1.0.
- 5. 2. l '. 3 When it is desired to determine the dilution flow or maximum discharge flow so as to meet Technical Specification 3.17.1. the following equations may be used. Any combination of maximum discharge flow and minimum flow which satisfy 5.2.1.2 is
. acceptable.
5.2.1.3.1 Minimum Dilution Flow (Femin) r C, .
-1 Icmin - F r
- SF[(i MPC g Where: i Fr - a fixed discharge. flow rate (gpm) (as required by specific release restrictions) e SF - a factor which may be applied to incorporate a margin of conservatism (SF 2 I).
5.2.1.3.2 Maximum Discharge Flow (Frmax)
F rmax " C SF ~I MPC
( Where:
Fc - a fixed dilution flow rate (gpm) (as required by specific j release restrictions) 5.2.2 Monitor Setpoint Calculation I fiQlE: When no batch release is occurring or the liquid effluent streams which make up the batch have no detectable activity then the mixture in Table A-1 of the ODCM data base may be used as a
" default" value to make the liquid effluent monitor setpoint I
calculation. The values in Table A-1 are used for Ct .
i 5.2.2.1 The following equations are given for the general situations
! described.
Rev. 6 AP.310-7 r
I f .i
5.2.2.1.1 When the monitor is measuring the radioactivity of a process liquid prior to that liquid being diluted by either dilution flow 3
J or volumetric dilution:
LSPundiluted
- Sf*1 C MPC o
F r
g 5.2.2.1.2 When the monitor is measuring the radioactivity of the liquid effluent as it is discharged or no further dilution will occur prior to discharge offsite, the following formula is used:
+ Bkg LSPdiluted " gf * .
I o MPC g
Where:
ICg - the total concentration of gamma emmitting radionuclides g in the batch, prior to dilution, in pC1/ml LC the calculated fraction of Maximum Permissible MPbaconcentrationofgammaemmitingnuclidesintheliquid effTuent LSP - the monitor setpoint level in pCi/ml for either the diluted or undiluted case Bkg = the background reading of the monitor in pC1/ml Fe - the dilution flow rate (total available dilution flow) prior to the addition of process liquids from the retention 8 basins and/or RHUTs in gpm (See figure 5.1)
I Fr - the discharge flow rate of the retention basin (See figure 5.1) 5.2.2.2 LSP is the highest value that may be used as the alarm setpoint for the liquid effluent monitor occurring when SF = 1. A lower 8 value may be used for the liquid effluent monitor alarm setpoint.
5.2.3 Post-release Assessment of Compliance with 10 CFR Part 20.106 After the results of all measurements reautred by Technical Specifications Table 4.21-1 are available, an evaluation of I compliance with 10 CFR Part 20.106 is performed using the equation:
MPCF = I (Cg /MPC g ) x (Fr /(F g
+F)r i
Where:
Fr flow from retention basin during trNase (gpm)
Rev. 6 AP.310-8 8
I t
5.2.3 (Continued)
Fc - flow of dilution water in discharge canal during release (gpm)
Compliance with Specification 3.17.1 has been demonstrated when HPCF 1 1.0.
i 5.3 CALCULATIONS FOR COMPLIANCE WITH 10 CFR 50, APPENDIX I (Technical l Specification 3.17.2) 5.3.1 Prior to the initiation of a batch release, a calculation of the l projected dose from the 11guld pathway is made. This projected dose is added to any cumulative dose for the calendar year and I quarter.
Pre-release Calculations are performed to estimate whether the 5.3.1.1 limits of Technical Specification 3.17.2 will be observed for the total amount of radioactive material expected to be released in the liquid effluent.
5.3.1.2 The dose resulting from the release of radioactivity through the liquid pathway:
Daj = I I Qi Ai jap i p I
Where:
Dahan(Annualcalculateddose(50yeardosecommitment)totheor or tot group a (mrem /yr)
I Qt - Activity of isotope i released during the year (C1/yr)
Ai jap - Site specific dose factor for organ (or total body) j for a person of age group a via pathway p due to isotope 1 I (mrem-CF/Ci-sec)
F - Annual average discharge volumetric flow rate (waste water plus dilution) in CF/sec i
Because the dose rate varies linearly with activity release rate, I the dose for a shorter period of time (mrem) may be calculated by using the activity released (C1) during that period for Og in the above equation. However, volume flow rates should not be averaged over a period less than a calendar quarter. More I conservative flow rates are, of course, acceptable.
Rev. 6 AP.310-9 I
I
-l d
~
5.3.1.3 Dose factors, A ijap.for'the RSNGS are derived using equations and methods in Regulatory Guide 1 109, Rev. 1. (LADTAP and EMS may be used to perform the calculations.) Values of parameters
-in RG 1.109, Rev. 1, Table E-5 are assumed to represent the Maximum Exposed Individual unless the Land Use Census data justify a different value. Representative valut:; of other parameters recommended in RG 1.109, Rev. 1, including those recommended in the absence of site specific data, are used in the equations to derive the dose factors.
, Appropriate salues of Aliap representing applicable exposure pathways and age group f5r the Maximum Exposed Individual are-selected and used to compute this dose. Unless determined by a Land Use Census to be inappropriate during a given season, the exposure pathways evaluated will include at least the following:
- fresh water fish,
- fresh water invertebrate,
- river. shoreline deposits.
- milk from cows that eat fresh or stored forage irrigated with Clay Creek water.
- meat from cows that eat fresh or stored forage irrigated with Clay Creek water, and
- vegetation.
Alternatively, the expected dose from a release may be' calculated by using the LADTAP and EMS computer code, provided the same exposure pathways, age group (s) and values of parameters in RG 1.109, Rev. 1, stipulated above in this section are used, t
i i
I
, 1 Rev. 6 AP.310-10 1
5.3.2 -Post-release Assessment of Compliance At least once every 31. days, an assessment of compliance'with Technical Specification 3.17.2 is performed. The same equation, exposure. pathways, and values of Ai jap appearing in Section 5.3.1.2 are used in the assessment, except that the calculated dose is accumulated over all batches of water discharged during the time period of interest.
i
)
I-I-
[
Rev. 6 ,
AP.310-11
l 5.4 ' GASEOUS EFFLUENT v
5.4.1 Overview L
Airborne radioactive material in the various rooms and systems at.'
the RSNGS is routed and discharged as airborne effluent as illustrated schematically in Figure 5.4. Figure 5.4 shows the functional arrangements of these streams, treatment and controls, radioactivity monitoring points, and effluent release points, j 5.4.2- Effluent Release Points The gaseous effluent release points at RSNGS are summarized in
)
Table 5.4-1.
T l
I L
i h
l
)
r
/
l Rev. 6 AP.310-12 L
_ _ - - . _ _ _ _ - - . _ . - _ _ _ - _ _ _ _ _ _ _ _ _ ]
Table 5.4-1 Gasecus Effluent Release Points Release Point Data Reactor Building System: Reactor Building Stacks Ventilation Maximum Flow rate: 74,000 CFM Height of Top of Stacks: 146 feet above grade Location: WSW face of the Reactor
. Building Height of Top of Nearest Structure: 162 feet above grade (Reactor Building)
Aufiliary Building System: Auxiliary Building Stacks Ventilation Maximum Flow rate: 47,740 CFM (with one Fan motor)
Height of Top of Stacks: 146 feet above grade Location: WSW face of the Reactor Building Height of Top of Nearest Structure: 162 feet above grade I- (Reactor Building)
B B
I B
Rev. 6 AP.310 13 8
Table 5.4-1 Gaseous' Effluent Release Points (Continued)
Release Point Data Auxiliary Building System: Auxiliary Butiding Grade Level Vent Ventilation Maximum Flew rate: 21,450 CFM Height of Top of Stacks: 66 feet above grade Location: , NE Corner of the Auxiliary Building Height of Top of Nearest Structure: 162 feet above grade.
(Reactor Building)
Interim Onsite System: Interim Onsite Storage Storage Building Building (IOSB) Ventilation Ventilation
- r Maximum Flow rate: Building Ventilation 8.050 CFM Height of Top of Vent: 24 feet above grade Location: Southwest Corner of IOSB Height of Top of i Nearest Structure: 425 feet above grade (West Cooling Tower)
I '* The' Interim Onsite Storage Building is not a Technical Specification release pathway and is not subject to continuous discharges of radioactivity.
Because of the infrequency of releases, assessment will be done on each release using RSNGS procedures.
i
{
\
Rev. 6 f- AP.310-14 1
5.4.3- BOUNDARIES F The two boundaries for-compliance with gaseous effluent Technical.
Specifications are the Exclusion Area Boundary and the Site Boundary for Gaseous Effluent. The Exclusion Area Boundary is for calculations involving Technical Specification 3.18.1'. The Site Boundary for Gaseous Effluent (Figure 4.8-3) is used for-calculations involving Technical Specification 3.18.2 and l 3.18.3. In general, the Exclusion Area Boundary is used for calculations to demonstrate compliance with'10 CFR 20, while the Site Boundary for Gaseous Effluent is used for calculations to assess compliance with.10 CFR 50, Appendix I, 5.5 ATMOSPHERIC DISPERSION OF GASEOUS, EFFLUENT Atmospheric dispersion (i.e., X/O or X d/Q) and deposition (i.e., D/Q) factors used in performing calculations involving
' airborne effluent are derived via the MIDAS program from meteorological measurements made at the RSNGS meteorological tower. The measurements are reduced to atmospheric stability classes and joint frequency tables. Using them, relative atmospheric dispersion and deposition factors for a ground-level, L building wake discharge are computed with a straight line, 22.5 degree, cardinal sector-width-averaged, Gaussian plume diffusion model.
l A reference year or several years of meteorological data collected at RSNGS has been reduced to the relative atmospheric dispersion and deposition factors in Table A-4. These factors
! are normally used to establish radioactive noble gas effluent monitor setpoints and to assess compliance with Specifications 3.18.1, 3.18.2 and 3.18.3.
5.6 RADIONUCLIDES IN EFFLUENT AIR Radionuclides concentrations and quantities in effluent air are-needed to establish effluent noble gas nonitor setpoints, to estimate offsite radioactivity concentration, and to estimate radiation dose offsite.
5.6.1 PRE-RELEASE MEASUREMENT Before discharge, noble gas radionuclides concentrations in the 1 waste gas decay tanks or in the reactor containment building are measured by gas sampling and analysis. These measured concentrations are used to establish maximum effluent gas flow and the maximum setpoint for reactor containment building effluent and auxiliary building stack effluent noble gas monitors.
For batch releases, the quantity of each radionucitde expected is projected as the product of the measured concentration times the total expected release volume, or the product of the measured concentration times the expected flow-rate times the expected time interval.
Rev. 6 AP.310-15 2
. 6 . 2 EFFLUENT MEASUREMENT Measured radioactivity concentrations in effluent air are relied upon.for estimating offsite radionuclides concentration or radiation dose. The radioactive waste gases sampling and .
analyses performed to measure these concentrations are identified I in Technical Specifications Table 4.22-1.
The quantity of each radionuclides released in effluent released in batches or in continuous effluent air streams is estimated as the product of each measured radionuclides concentration, the measured average effluent air flow, and the discharge time increment. Exhaust fan capacity, e.g., number of operable fans, etc., may be used to estimate effluent air' flow in lieu of air flow measurement. Alternatively,'the gross beta and gamma radioactivity concentration in effluent air may be measured by the effluent noble gas monitor and integrated over time to derive the quantity of gross radioactive effluent gas. The product of the gross radioactive effluent gas quantity and the fraction attributable to a specific noble gas radionuclides would estimate the amount of the radionuclides in the effluent air during that time:
Ovnt " O vn
- I vni I Where:
Qvni - the quantity of each noble gas radionuclides't in a batch in time increment n released via effluent stream v I (pCi) l Qvn - the quantity of gross noble gas radioactivity in f batch n or time increment n released via effluent stream v (UC1) l fvni = the fraction of radioactive gas in effluent stream v during time increment n or in batch n that is radionuclides 1
) 5.7 CALCULATIONS FOR ASSESSING COMPLIANCE WITH 10 CFR 20.106 (Technical Specifications 3.16 and 3.18.1) i Specifications 3.16 and 4.20 require radioactive noble gas monitors named in Table 3.16-1 therein to have alarm and/or trip (as specified) setpoints determined by a method described in this ODCH. Specification 3.18.la sets maximum dose rate limits that l effluent noble gas must meet outside the Exclusion Area, l
)
Rev. 6 AP.310-16 L
5.7.1 NOBLE GAS EFFLUENT MONITOR SETPOINTS Technical specification 3.16 requires that effluent noble gas monitors named in Table 3.16-1 have their alarm and/or trip setpoints determined as described here. The gamma dose rate to a person's whole body is expected to be a larger fraction of the limit (500 mrem /yr) than is the beta plus gamma dose rate to skin is to its limit (3,000 mrem /yr). Each noble gas effluent monitor setpoint is derived on the basis of the gamma dose rate to a person's whole body alone, such that an alarm is set to occur at or before the total body dose rate outside the Exclusion Area exceeds 500 mrem /yr.
The setpoint of a noble gas effluent monitor is calculated with the equation:
500
- Py *ICj i + Bkg My -
SF * (X/Q)
- I (Cj
- Kj) i i
Where:
f Hv - Monitor setpoint for vent v (i.e.; RBS, ABS, or ABGLV) in pCi/sec 500 - Technical Specification limit for total body dose rate (mrem /yr)
Partition factor, dimensionless, which distributes the Py tota l site release rate among the three vents (see discussion below)
Concentration of isotope i in gaseous effluent Cj (pCi/ml). The isotope mix should be vent specific (see Table i
A-2)
)
SF - Safety Factor, dimensionless (SF 1 1)
I X/0 - Maximum atmospheric dispersion factor for a ground level release to a sector beyond the Exclusion Area Boundary (sec/m3). Either an annual average or multiple-year average is acceptable.
Kj - Factor converting ground-level concentration of noble gas isotope i to total body dose [(mrem-m3) / (pCi-yr))
j Bkg - Instrument background reading (pCi/sec)
Rev. 6 AP.310-17 l
i
I 5.7.1 (Continued)
Technical Specification 3.18.1 applies to the entire site, not to just one vent or monitor. Consequently, the total release rate must be partitioned among the three vents. For routine I operations, the parition factor may be calculated by assuming i that the effluent concentration is the same for all pathways and using a ratio of flow rates. The total volume flow rate for all I three vents is 143,190 CF/ min. Therefore, Prbs = 74000 CF/ min - .52 143,190 CF/ min i
I Pabs
- 47740 CF/ min = .33-143,190 CF/ min Pabgiv " 21450 CF/ min . .15 143,190 CF/ min Chemistry Supervision may elect to use a different set of partition factors based on plant conditions and specific isotope mixes in the vents. However, the sum of all the partition I factors for the site must be less than unity.
Monitor setpoints based on effluent concentration may be I calculated with the following equation:
HCy = MRy _ + Bkg 472 F y I
. Where:
MCy - Monitor setpoint for vent v based on concentration (pCi/mi) mrv - Monitor setpcint for vent v based on release rate (pC1/sec) excluding the background term, that is, My - Bkg Fv - Maximum design volumetric flow rate (CF/ min) from Table 5.4-1
- 1 min /60 sec 472 - 28317 ml/CF Bkg - Monitor background (pC1/ml)
Monitor setpoints are determined to ensure compliance with Technical Specification 3.18.la at the Exclusion Area Boundary in I the sector where the maximum atmospheric dispersion (maximum X/0) occurs. This value is obtained from Table A-4.
Rev. 6 AP.310-18 I
I
1 ;
5.7.1 (Continued)
For the purpose of deriving a setpoint, the distribution of noble gas radionuclides is estimated
- 1. By sampling and analyses according to Technical' Specification. Table 4.22-1, or
- 2. By assuming an historical mix from Table A-2 that applies to the effluent point of interest.
l A safety facter, (SF 2 1) in value may be. included in a setpoint to compensate for-statistical fluctuations, measurement. errors, l and for other radioactive gaseous effluent.
5.7.2 Dose Rate from Noble Gates Each of the effluent noble gas monitors named in Technical Specification Table 3.16-1 includes an alarm that can be set to activate when the dose rate due to radioactive noble gases beyond l the Exclusion Area Boundary is expected, by calculation, to exceed a preset level. Compliance with the dose rate limits for noble gases in Specification 3.18.1.a is demonstrated by setting each gaseous effluent monitor alarm setpoint so that an alarm
}
will occur at or before either dose rate limit in Specification 3.18.1.a is reached. The dose rate due to noble gas is evaluated as follows:
The maximum total body dose rate from noble gases beyond the.
Exclusion Area Boundary is calculated with the equation
)
btb - (X/0) I I hvj
- Kg f vi and the maximum skin dose rate from noble gases beyond the l Exclusion Area Boundary is calculated with the equation i.
b - (X/Q) IIhvt(Lj+1.1Mj) 5 vi Where:
btb - the total body dose rate from noble gases (mrem /yr) b5- the skin dose rate from noble gases-(mrem /yr)
X/Q - the Maximum atmospheric dispersion factor for a ground level release to a sector beyond the Exclusion Area Boundary (sec/m3). Either an annual average or multi-year average is acceptable.
Rev. 6 AP.310-19
a I
l I
5.7.2 (Continued) hvi-thereleaserateofnoblegasradionuclideifrom effluent vent v during the time of the release (pC1/sec) r Kj - a factor converting time integrated, ground-level l concentration of noble gas radionuclides i to total body dose from its gama radiation (mrem-m3/pCi-yr)
Lt - a factor converting gamma radigtton from noble gas radionuclides i to skin dose (mrem-m3/pC1-yr)
M3 - a factor converting gamma redir. tion from noble gas radionuclides 1 to air dose (mrad-m3/pci-yr) 1.1 - a factor converting air dose from gamma radiation to skin dose equivalent (mrem / mrad)
To assess complianct with Specification 3.18.1.4, the atmospheric l
dispersion factor, X/Q, to any sector (width-averaged) beyond the
) Exclusion Area _ Boundary.from a ground-level release at the R5NGS is used. The value used is taken from Table A-4.
l Values of Kg, Lg, and Mg are in Table A-5.
5.7.3 Dose Rate from Radioactive Particulate, Iodine, and Tritium Specification 3.18.1.b provides a maximum limit on organ dose rate equivalent beyond the Exclusion Area E,oundary from todine-131, lodine-133, tritium, and for all radioactive
- materials in particulate form with half-lives greater than 8 days. Compliance is evaluated subsequently by calculating the dose rate to the most exposed org;n of a Maximum Exposed Individual located outside the. Exclusion Area and who.is exposed L by inhaling the airborne radionuclides.
The organ dose commitment rate resulting from inhalation is'
) calculated with the equation:
D0aj-(X/Q)IIhyj Raji vi Where:
the dose commitment rate to organ j of a person in 00aj oup a (mrem /yr) age gr l Radi = the factor racic,nuclide to convert i to organ j doseair concentration commitment of a person rate of in age group a exposed by inhalation (mrem-m3/pCi-yr)
Rev. 6 AP.310-20
I:
5.7.3 (Continued) l .
3 Qvj - the release rate of radionuclides i via effluent vent v during the time of the release (pCi/sec) 3 Exposure to dose rate factors, Ra by using equation 13 in RGrev. 1.109,ji, forE-5, 1, Tables inhalation E-7, E-8,are derived
'I E-9, and E-10 are assumed to represent the Maximum Exposed Individual in the equation to derive Raji-To assess compliance with Technical Specification 3.18.1.b, radionuclides other than noble gases in gaseous effluent that are
,g measured in the gaseous sampling and_ analysis program in Technical Specification Table 4.22-1 are used to describe the g release rate Qvg for each vent. .
The variable X/Q refers to the maximum value at or beyond the Exclusion Area Boundary in Table A-4.
5.8 CALCULATIONS FOR DETERMINING COMPLIANCE HITH 10 CFR PART 50.
iI APPENDIX I: AIR DOSE FROM NOBLE GAS 5.8.1 Method Technical Specification 4.22.2 requires cumulative dose to air from radioactive effluent noble gases to be determined in order to astess compliance with Specification 3.18.2. The air dose is
'E evaluated in the sector of maximum exposure at or beyond the Site 5
Boundary for Gaseous Effluent.
Air dose from noble gas gamma radiation is calculated cumulatively with the equation
.l Dr-3.17x10-8I(X/Q)II(Qvnt*M) v in 1
m I .
I I
I Rev. 6 AP.310-21 I
I
5.8.1 (Continued)
Air dose from noble gas beta radiation is calculated cumulatively
~
with the equation DB-3.17x10-8I(X/Q)II(Qvnt*Nj) v in Where:
Dr - the noble gas gamma dose to air (arad)
DB - the noble gas beta dose to air (arad)
X/Q = the atmospheric' dispersion factor for noble gas effluent from a ground-level release to a lector beyond the Site Boundary for Gaseous Effluents (sec/m3). Either an-annual average or multi-year average is acceptable.
Hj - a factor converting. ground-level concentration to gamma radiation from noble gas radionuclides i to air dose (mrad-m3/pCi-yr)
Ni - a factor converting ground-level concentration to beta radiation from noble gas radionuclides i to air dose (mrad-m3/pCi-yr)
Qvn) - the quantity of each noble gas radionuclides i in batch n released via effluent stream v (pC1) 3.17 x 10 1 yr/3.156 x 107 sec-Factors Hj and Ng are 106 pCi/pC1 times the values in RG 1.109, Rev. 1, Table B-1, columns 4 and 2, respectively. The i
computer codes GASPAR and EMS may be used to perform these
! calculations.
5.8.2 Pre-release Dose Projection for Batches I Before the gas in the reactor containment building (for a batch release) or in a waste gas decay tank is released, noble gas radionuclides concentrations are measured and the quantity of each i expected to be released is estimated as described in Section 5.6.1. The expected air dose from the noble gases to be released is calculated and is added to any air dose accumulated from earlier noble gas effluent during the quarter-to-date and the year-to-date. j The air dose from noble gases is evaluated with the maximum X/Q beyond site Boundary for Gaseous Effluents recorded in Table A-4.
4 Rev. 6 !
AP.310-22
5.8.3 Post-release Dose Assessment' Specification 4.22.2 requires air dose accumulated during the calendar quarter and year from effluent noble gases to be calculated. The quantity of noble gas radionuclides in effluent air is determined by measurements as described in Section 5.6.2.
The noble gas gamma and beta doses to air are calculated beyond the Site Boundary for Gaseous Effluents in the sector experiencing the maximum atmospheric dispersion factor used to compute air dose is in Table A-4.
Alternatively, the average atmospheric dispersion factor for the same calendar quarter or year as the effluent may be used to perform the quarterly and/or annual air dose assessment.
5.9 COMPLIANCE WITH 10 CFR PART 50, APPENDIX I: DOSE FROM TRITIUM, IODINE, AND PARTICULATE IN EFFLUENT AIR 5.9.1 Method Technical Specification 4.22.3 requires the radiation dose or dose commitment to the Maximum Exposed Individual accumulated from exposure to tritium, todine-131, iodine-133, and radioactive materials in particulate form having half-lives greater than 8.0 days, that originate in effluent air, be determined at least every month. The radiation dose or dose commitment accumulated during a calendar quarter and a year may not exceed values stated in Technical Specification 3.18.3.
A person may be exposed to effluent radioactive material of this i
t type in air by inhalation or indirectly via environmental pathways that involve deposition onto vegetation and the ground.
The exposure pathways evaluated will include, the following:
P Exoosure Pathway 1 Air-inhalation Deposition onto ground--irradiation
)- 2 3 Deposition onto vegetation--ingested 4 Deposition onto forage--cow--milk--ingestion 5 Deposition onto forage--meat animal--meat--ingestion The equation used to calculate the dose commitment to the Maximum Exposed Individual from radionuclides other than tritium is Daj - 3.17 x 10-8 [(Xd /0)p=1 I I Qvi
- Rajip-l +
vi 5
I (D/Q)p I I Qvt
- Rajip3 p2 vi Rev. 6 4 AP.310-23
)
5.9.l' (Continued)
Where:
p - 1, i.e., air-inhalation, in the first term, and p - 2, 3, 4, and 5 in the second term of the equation-i excludes H-3 Dai - the dose commitment to organ j of a person in age gr5up-a (mrem)
Ovt = the quantity of tritium, radionuclides, or radionuclides in particulate form having half-lives greater than 8.0 days in air discharged via effluent stream v (pC1)
Xd /O - atmospheric dispersion fa'ctor for a ground-level.or building wake discharge, adjusted for depletion by 8. days of radioactive decay and by deposition of particulate (sec/m3)
D/Q - relative c'eposition factor, l'.e., factor converting a ground-level or building wake discharge in air to a real
' deposition on land (m-2)
Rajip - a factor converting time integrated concentration I
of radionuclides i in air (pC1 yr/m3) or deposited on vegetation and/or ground (pCi yr/m2) to radiation dose commitment to organ j, including total body, of a person in age group a who is exposed via pathway p.
f.
When p 1, representing air-inhalation, Rajip has units (mrem j m3/pCi/yr). When p 2.3,4 or 5 in the second term of the
! equation above, representing pathways involving deposition, Raiip has units (mrem-m2)/((pCi/sec)yr). When the ra5ionuclide is H-3, Rajip has units (mrem-m3)/pCi-yr).
Tritium is assumed not to deposit onto vegetation or the ground, unlike particulate. Hence, the concentration in vegetation is assumed to be related to the local atmospheric concentration as described in RG 1.109, rev. 1, Appendix C. The dose commitment to the Maximum Exposed Individual from tritium in gaseous effluent is calculated with the equation Da3 - 3.17x10-8 [I X/Qp I (Qvi Rajip)1=H-33 Where:
f p - 1, 3, 4, and 5 i includes H-3 only X/O - atmospheric dispersion factor for gaseous effluent discharged at ground level or in a building wake (sec/m3) f Rev. 6 I AP.310-24 I
L
5.9.1 (Continued)
Dose factors Rajio for the RSNGS are derived using the equations and mtthods in RG 1.109, rev. 1, Appendix C. Values of parameters in RG 1.109, rev. 1, Table E-5 are assumed to represent the Maximum Exposed Individual unless Land _Use Census data justify a different value. Any different values from default values will be justified and added as a table to the ODCH. The revised sections of the ODCM, including these values, will'be provided with the next Semi-Annual Effluent Report.
Values of other parameters recommended in RG 1.109, rev. 1.-
including those recommended in the absence of site-specific data, are used in the equations to derive the dose factors. (GASPAR and EMS may be used to perform the calculation.s.)
5.9.2 . Pre-release Dose Projection .
Projection of dose commitment attributable to tritium, radioiodine, and radioactive particulate in the reactor containment building atmosphere or in a waste gas decay' tank is not normally done before release in effluent air.
5.9.3 Post-release Dose Assessment The quantity of tritium, iodine-131, iodine-133, and radionuclides having greater than 8.0 dey half-lives and that are in particulate form in effluent air are measured by the radioactive gaseous waste sampling and analysis specified in Technical Specification 4.22-1. A post-release calculation of dose commitment accumulated during the quarter or year to date is performed by summing the successive measurements for each quantity of radionuclides made during that period, that is, Ovi - I Qvnt n
where Qvni = the quantity of radionuclides i in effluent air stream v during the time represented by sample n (pC1)
The cumulative dose commitment via each pathway is evaluated with respect to the offsite location where inhalation, gardening, grazing, or harvesting forage occurs together with maximum X/0, or D/0 (from Table A-4) to represent the pathway and to be used to evaluate the dose commitment via that pathway. As a result, l
differing locations for inhalation, gardening, grazing, and-l forage harvesting may be evaluated. An exposure pathway may be excluded from evaluation if it is inappropriate for the season.
l Appropriate values from Table A-4 through A-5 representing I applicable exposure pathways for the Maximum Exposed Individual are selected and used to compute this dose.
Rev. 6 l' AP.310-25
)
1
- 4
l 5.9.3 (Continued) y As an alternative, the average atmospheric dispersion or l~ deposition factors for the same quarter er year as the effluent may be used to evaluate quarterly and/or annual dose commitment to the Maximum Exposed Individual from tritium, radioiodine, and radioactive particulate.
5.9.4 Alternative Nethod i
i Alternatively, the dose comitment from tritium, radiciodine, and radioactive particulate in effluent air may be calculated'by using the GASPAR computer code, provided the same exposure l pathways, age group (s) and values of parameters in RG 1.109, Rev. 1, stipulated in sections 5.9.1 and 5.9.3, are used to estimate the dose to the Maximum Exposed Individual.
5.10 EVALUATING COMPLIANCE HITH 40 CFR PAR.T 190.10: FUEL CYCLE DOSE 7.
5.10.1 Method As long as the RSNGS operates at a level below the limits of Technical Specifications 3.17.2, 3.18.2, and 3.18.3, no extra analysis is required to demonstrate compliance with Specification 3.25.b In the event a dose calculated in accordance with Specification 4.21.2, 4.22.2, and 4.22.3 exceeds twice the limit of Specification 3.17.2.1, 3.17.2.b, 3.18.2.a. 3.18.2.b 3.18.3.a, or 3.18.3.b. or exceeds a reporting level in Table 3.22-2, an assessment of compliance with Specification 3.25 must be made.
Specification 3.25 requires the dose or dose commitment to any real member of the public from radioactive material in effluent air and water and from direct radiation, combine, during a year to be kept to no more than 25 mrem to the total body, 75 mrem to the thyroid, and 25 mrem to any other organ.
There is no other fuel cycle facility within 50 miles of the RSNGS. Thus, only radiation and radioactivity in the environment attributable to the RSNGS are considered in the evaluation of compliance with Specification 3.25.
For the purpose of evaluating compliance with the Specification, the most exposed member of the public is described such that the dose commitment to any resident near the RSNGS will not knowingly be underestimated. The most exposed member of the public, i.e.,
the Real Individual,is selected on the basis of the applicable combination of existing pathways of exposure identified in the annual Land Use Census and the exposure pathways evaluated in the quarterly assessments required by Specifications 4.21.2, 4.22.2, and 4.22.3.
bCongel. F.J., Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), NUREG-0543, USNRC:NRR, February 1980.
Rev. 6 AP.310-26
}~- ' h' s
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v i r 5.10.1 (Continued)- o Receptor location,' pathways, or. conditions more conservative,
.i~.e., yielding a higher dose estimate. than' appropriate'for.the. j
.Real Individual may be assumed.in the dose assessment. LThe,
' pathways considered for evaluation;will, at least, include the-following: a m
water--fish--ingestion . ,
water--mollusk (shellfish)--ingestion i water--irrigation--stored forage--meat .j 7 animal--meat--ingestion 1 air--inhalation 3
. air--deposition onto vegetation--ingestion-air--deposition onto ground--trradiationc .
. air--deposition onto forage--cow.--milk--ingestion. .
. air--deposition onto forage--meat animal--meat.-ingestion )
p . irradiation directly from the'RSNGS j u
-Total body and maximally. exposed organ-dose commitmentseto.the' Real Individual from waterborne effluent.are calculated by the '
l- method. described in Section 5.3.-
Total body ~and maximally exposed organ dose commitments to the-1 Real' Individual from airborne' effluent other than noble gases are.
l calculated by the method described in Section 5.9.1.
Total body'and skin dose to the Real. Individual from radioactive L noble gases in effluent air are calculated'by the method described-in Sections 5.10.2 and 5.10.3. Organ doses other than l
skin dose from immersion.in a noble gas are assumed:to be equal:
l.'
to.the total body dose.
-Irradiation, i'.e., exposure to an external source of. radiation, directly from the RSNGS will beLevaluated with the aid of environmental dostmetry such as thermoluminescent dosimetry (TLD).
or portable ion chamber (PIC) measurements. The' dosimetry data will be' tested statistically for difference (i.e. : increase).in radiation exposure near the station relative to more distant L
measurements.
5.10.2 Total Sody Dose from Airborne Noble Gases The gamma radiation dose.to the total body of_a Real-Individual from radioactive noble gas discharged from the RSNGS is.
calculated with the equation DT = 0.7 x 3.17 x 10-8 (X/Q) I I Qvt
- Kg vi -i Rev. 6 i AP.310-27 1
i 5.10.2< '(Continued) where:
DT - the total body dose from irradiation by noble gases 3
(mrem) .j 3.17 x 10 1 yr/3.156 x 107 see i
0.7 - adjustment to account for residential shielding i (dimensionless)
X/0 the atmospheric dispersion from a ground-level discharge to the receptor loc.ation (sec/m3)
Qvi.- the quantity of noble gas radionuclides i released via effluent stream v during the time period being evaluated (pC1)
Ki = factor converting immersion in semi-infinite cloud of noble radionuclides i to total body dose (mrem-m3/pC1-sec)
The dose factors, Kj, are derived with the equation-Kg - (106 pCi/pC1) DFBj l
where:
DFBq = total body dose factor for radionuclides i in RG 1.109, Rev. 1, Table B-1, column 5 (mrem-m3/pCi-yr)
The dose to body organs other than skin is assumed to be equal to the total body dose.
5.10.3 Skin Dose from Airborne Noble Gases The beta plus gamma dose to the skin of a Real Individual from radioactive noble gas discharged from the R5NGS is calculated with the equation DS - 3.17 x 10-8 (X/Q) I I Qvj
- 0.7 (Lj + 1.1Hj) vi where:
DS - dose to skin from irradiation by noble gases (mrem)
X/Q - atmospheric dispersion of a ground-level discharge to the receptor location (sec/m3)
Qyj - the quantity of noble gas radionuclides released via effluent stream v during the time period being evaluated (pC1) !
Rev. 6 AP.310-28
L l
[: 5.10.3 (Continued)
Li - a factor converting beta; radiation from radionuclides i to skin dose in RG 1.109, Rev. 1, Table B-1, Column 3 (mrem-m3/pci-yr)
Hg - a factor converting semi-infinite cloud gamma radiation from radionuclidt i to air dose, in RG 1.109 Rev. 1, Table B-1, Column 4 (mrad-m3/pC1-yr) 1.1 - conversion factor (mrem /arad) /
l 0.7 - a factor to account for shielding by a house (30% reduction) 5.10.4 Alternative Method Alternatively, the dose to a Real Individual from exposure to'a
) . radioactive material. originating in'RSNGS liquid effluent may be computed using the LADTAP or EMS computer program, provided the data entered. comply with the conditions specified in Section 5.9.1 and otherwise with values recommended in RG 1.109 Rev. 1 for use in the absence of site-specific data. Alternatively, the dose to a Real Individual from exposure to radioactive material originating in RSNGS effluent air may be calculated using the GASPAR and EMS computer program, provided the data entered comply with the conditions specified in Section 5.9.1 and otherwise with values recommended in RG 1.109, Rev. I for use in the absence of site-specific data.
).
5.11 ADMINISTRATION OF OFFSITE DOSE CALCULATIONS 5.11.1 Implementing procedures which provide instructions for the calculation of offsite doses and dose rate or concentration, effluent monitor setpoints, for which formulae are provided in i the ODCM, shall be written and used, f 5.11.2 An offsite dose calculation data base is maintained and controlled by procedure. Data base values, that are in addition to those presented in the ODCM, reside in LADTAP, GASPAR, and XOQD0Q computer programs and are controlled by Chemistry Administrative Procedures (CAPS). ;
5.11.3 The ODCM shall be reviewed annually. Licensee-initiated changes i to the ODCM and/or its data base are made pursuant to Technical Specification 6.16.2.
Rev. 6 AP.310-29
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.I j 6.0: RECORDS-As. required by Technical Specifications and ODCM Implementing Procedures.
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u FIGURE 5.1 LIQUID EFFLUENT FLON DIAGRAM i FIGURE 5.1 LIQUID EFFLUENT FLOW DI AGR AM s SEC. PUMP SEALS D 3 TURBINE BulLDING FLOOR DRAINS y =
CONDENSER e CONDENSER WATER PIT SUMP BOX DRAINS e CONDENSER PIT j e S ATTERY RM. DRAINS e CHEM INJECTION -
CONDENSATE PUMP DRAINS '
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I s RX COOLANT DEMIN e COOUNG TOWER STORAGE TANK SLOWDOWN e SOME TANK FARM = a TANK FARM STORM DRAINS N.R. STORM OR AINS e AUXIUARY BOILER BLOWDOWN e MAKE-UP DEMIN I
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TABLE OF CONTENTS Table A-1. Liquid Source Terms Table A-2 Gaseous Source Terms
-Table A-4 1985 Annual' Average X/Q and 0/Q,-Special Locations Table'A-5 Distances for Gaseous Effluent Pathway Evaluation Dose Factors For Noble Gases and Daughters
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Table A-6 Table A-7 Values used to Derive Dose Factors for the Maximum Exposed Individual f-
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4 o Rev. 6
)
AP.310-36
- _ - = _ . _ _ - - . _ . - _ _ _ _.
L 1
! TABLE A-1 LIQUID SOURCE TERMS f
. Relative j Nuclide MPCg (pC1/m1) (a) Radioactivity (b) Percent (c)
(C1/yr) (except H3 )
Ho 99 4.00E-05 (Insol) 0.0 0 I 131 3.00E-07 (Soluble) 1.23E-01 19.55 1 132- 8.00E-06 (Soluble) 0.0- 0 1 133 1.00E-06 (Soluble) 1.70E-02 2.70 f I 135 4.00E-06 (Soluble) 1.87E-03 0.30 Cs 134 9.00E-06 (Soluble) 1.53E-01 24.32 Cs 137 2.00E-05 (Soluble) 3.01E-01 47.85 Cr 51 2.00E-03 (Both) 0.0 0 I Mn 54 1.00E-04 (Both) 2.45E-03 . 0.39 Fe 59 5.00E-05 (Insoluble) 0.0 0 Co 58 9.00E-05 (Insoluble) 1.13E-02 1.80 i Co 60 3.00E-05 (Insoluble) 1.94E-02 3.08 H .3 3.00E-03 (Both) 2.97E+02
{ Total 2.9BE+02 100%
Notes (a) Based on 10 CFR 20, Appendix B, Table II, Column 2 l (b) Liould source terms are representative of the " radionuclides mix" of the
. liquid effluents, based on the 1984 Annual Report.
(c) The concentration of the mix in pCi/ml can be multiplied by the relative percent (divided by 100) to obtain the concentration of each isotope in pC1/ml.
Rev. 6 AP.310-37
TABLE A-2 GASEOUS SOURCE TERMS Aux Bldg Reactor (a,b) Cont Relative (a,c) Batch Relative I Nuclide. (C1/Yr) Percent (d) (Ci/yr) Percent (d)
Kr 85m 8.27E+00 .33 3.65E-01 0.0 Kr 85 0.0 . 0.0 - 9.86E+00 0.71 Kr 87 4.18E+00 .17 5.93E-02 0.0 Kr 88 6.53E+00 . 26 2.32E-01 0.0 Xe 131m 1.5BE+00 .06 5.51E-01 0.0 Xe 133m 2.39E+00 .10 5.31E+00- 0.38 i Xe 133 2.29E+03 91.6 1.36E+03 98.5
- Xe 135 1.74E+02 7.0 4.52E+00 0.0 Xe 135m 6.54E+00 0.27 3.52E-06 0.0 Xe 138 3.83E+00 .15 0.0 0.0 Ar 41 2.39E+00 _ dQ 3.52E-02 0.0 TOTAL 2.50E+03 100% 1.38E+03 100%
l holts (a) Based on operational history of Rancho Seco (1984 annual report) l (b) This source term is also applicable for the Auxiliary Bldg. Grade Level vent.
(c) This is also applicable for the Reactory Bldg, Maste Gas Decay Tank, Hoggers, and Air Ejectors.
(d) The concentration of the mix in pCi/tt. can be multiplied by the relative percent (divided by 100) to obtain the concentration of each isotope in pCi/cc.
)
Rev. 6 AP.310-38
TABLE A-4 1986 ANNUAL AVERAGE X/Q AND D/Q SPECIAL LOCATIONS X/Q (SEC/M3 ) D/0 LOCATION DISTANCE NO 2.26 DAY 8.00 DAY 6(r.g)
(METERS) DECAY DECAY DECAY (1/m')
! UNDEPLETED UNDEPLETED DEPLETED TRITIUM NOBLE IODINE &
GAS PARTICULATE NEAREST HOUSE NE 1432.00 4.157E-06 4.144E-06 3.663E-06 2.34BE-08:
NEAREST HOUSE ENE 1128.00 9.092E-06 9.071E-06 8.127E-06 6.559E-08 i NEAREST HOUSE SE 2560.00 9.085E-07 9.032E-07 7.665E-07 3.868E-09 NEAREST HOUSE SSE 7803.00 8.593E-08 8.424E-08 6.397E-08 1.786E-10 NEAREST HOUSE S 6492.00 1.580E-07 1.553E-07 1.206E-07 2.245E-10 NEAREST HOUSE SSH 3718.00 5.269E-07 5.213E-06 4.290E-07 7.59BE-10
}
NEAREST HOUSE SH 1219.00 7.613E-06 7.587E-06 6.774E-06 1.477E-08 NEAREST HOUSE HSH 2103.00 1.455E-06 1.4474-06 1.248E-06 2.905E-09 l NEAREST HOUSE H 3414.00 5.814E-07 5.763E-07 4.775E-07 1.060E-09 NEAREST HOUSE HNH 4389.00 3.737E-07 3.702E-07 2.991E-07 8.669E-10 NEAREST HOUSE NH 5334.00 3.250E-07 3.215E-07 2.545E-07 8.826E-10.
NEAREST HOUSE NNH 7254.00 1.852E-07 1.822E-07 1.394E-07 5.441E-10
[ SITE BOUNDARY N' 640 1.7 E-05 1.7 E-05 1.5 E-05 7.5 E-08 SITE BOUNDARY NNE 670 1.1 E-05 1.7 E-05 1.0 E-05 5.8 E-08 SITE BOUNDARY NE 790 1.2 E-05 1.2 E-05 1.1 E-05 7.3 E-03 SITE BOUNDARY ENE 680 2.1 E-05 2.1 E-05 1.9 E-05 1.5 E-07
}' SITE BOUNDARY E 670 1.4 E-05 1.4 E-05 1.3 E-05 7.9 E-08 SITE BOUNDARY ESE 680 1.1 E-05 1.1 E-05 1.0 E-05 5.5 E-08 l SITE BOUNDARY SE 800 9.7 E-06 9.7 E-06 8.9 E-06 5.1 E-08
) SITE BOUNDARY SSE 950 6.0 E-06 6.0 E-06 5.4 E-06 2.4 E-08 SITE BOUNDARY S 930 7.8 E-06 7.8 E-06 7.1 E-06 2.1 E SITE BOUNDARY SSH 950 8.9 E-06 8.9 E-06 8.0 E-06 1.9 E-0B SITE BOUNDARY SH 1125 8.7 E-06 8.6 E-06 7.7 E-06 1.7 E-08 SITE BOUNDARY HSH 980 7.6 E-06 7.5 E-06 6.8 E-06 1.7 E-08 SITE BOUNDARY H 960 8.2 E-06 8.2 E-06 7.4 E-06 2.1 E-08 i
SITE BOUNDARY HNW 980 8.2 E-06 8.2 E-06 7.4 E-06 3.0 E-08 SITE BOUNDARY NH 780 1.5 E-05 1.5 E-05 1.4 E-05 7.0 E-08 SITE BOUNDARY NNH 670 2.0 E-05 2.0 E-05 1.8 E-05 1.1 E-07 MILK CON ENE 1128.00 9.092 E-06 9.071E-06 8.127E-06 6.559En08 MILK CON SH 3187.00 9.254 F'97 9.170E-07 7.651E-07 1.305E-09 MILK CON HSH 3621.00 4.936 E-07 4.889E-07 4.030E-07 7.714E-10 MILK COH H 7741.00 1.329 E-07 1.303E-07 9.903E-08 1.634E-10 MEAT ANIMAL N 640 1.7 E-05 1.7 E-05 1.5 E-05 7.5 E-08 MEAT ANIMAL NNE 670 1.1 E-05 1.1 E-05 1.0 E-05 5.8 E-08 HEAT ANIMAL NZ 460 2.8 E-05 2.8 E-05 2.6 E-05 1.7 E-07 HEAT ANIMAL ENE 460 3.9 E-05 3.9 E-05 3.6 E-05 2.7 E-07 i HEAT ANIMAL E 670 1.4 E-05 1.4 E-05 1.3 E-05 7.9 E-0B Rev. 6 AP.310-39
TABLE A-4 (Continued) i 1986 ANNUAL AVERAGE X/Q AND D/Q
' SPECIAL LOCATIONS X/Q X/Q (SEC/M3 ) D/0 I LOCATION DISTANCE NO 2.26 DAY 8.00 DAY 6(r.0)
(HETER 5) DECAY DECAY DECAY (1/m2)
UNDEPLETED UNDEPLETED DEPLETED TRITIUM NOBLE IODINE &
GAS PARTICULATE MEAT ANIMAL ESE 680 1.1 E-05 1.1 E-05 1.0 E-05 5.5 E-08 MEAT ANIMAL SE 700 1.2 E-05 1,2 E-05 1.1 E-05 6.4 E-08 MEAT ANIMAL SSE 210 7.7 E-05 7.7 E-05 7.4 E-05 2.4 E-07
) MEAT ANIMAL 5 220 9.4 E-05 9.4 E-05 9.1 E-05 1.9 E-07 MEAT ANIMAL SSW 210 1.2 E-04 1.2 E-04 1.2 E-04 1.9 E-07 MEAT ANIMAL SW 290 9.6 E-05 9.6 E-05 9.2 E-05 1.4 E-07 MEAT ANIMAL W5W 420 3.3 E-05 3.2 E-05 3.1 E-05 6.5 E-08 MEAT ANIMAL W 515 2.4 E-05 2.4 E-05 2.2 E-05 5.7 E-08 MEAT ANIMAL WNW 450 3.0 E-05 3.0 E-05 2.8 E-05 1.0 E-07 MEAT ANIMAL NW 515 2.9 E-05 2.9 E-05 2.8 E-05 1.3 E-07 MEAT ANIMAL NNW 500 3.1 E-05 3.1 E-05 2.9 E-05 1.7 E-07 MILK GOAT SW 5633.00 3.247 E-07 3.196E-07 2.522E-07 3.456E-10 NEAREST GARDEN ENE 1128.00 9.092 E-06 9.071E-06 8.127E-06 6.559E-08 NEARIST GARDEN SE 6550.00 1.405 E-07 1.384E-07 1.072E-07 4.289E-10 NEAREST GARDEN SSW 5327.00 2.705 E-07 2.664E-07 2.115E-07 3.299E-10 NEAREST GARDEN SW 5633.00 3.247 E-07 3.196E-07 2.522E-07 3.456E-10 8.046 E-07 7.986E-07 6.730E-07 1.412C-09 NEAREST GARDEN H5W 2816.00
)
NEAREST GARDEN W 7714.00 1.337 E-07 1.311E-07 9.965E-08 1.647E-10 NEAREST GARDEN NW 7242.00 1.866 E-07 1.838E-07 1.405E-07 4.455E-10 225.00 9.004 E-05 8.999E-05 8.695E-05 4.045E-07 VISITOR CENTER E PARK KIOSK E 525.00 2.076 E-05 2.073E-05 1.940E-05 1.150E-07 WAREHOUSE ENE 225.00 1.350 E-05 1.349E-05 1.304E-05 7.892E-07 DESIGN CITY ENE 250.00 '1,118 E-05 1.117E-05 1.076E-05 6.791E-07 EXCLUSION AREA N 640.00 1.676 E-05 1.673E-9425 1.550E-O(WNT 7.549E-07 EXCLUSION AREA NNE 640.00 1.206 E-05 1.204E-94-os 1.115E-D(-os 6.232E-07 640.00 1.648 E-05 1.646E-05 1.525E-05 1.025E-08 EXCLUSION AREA NE 640.00 2.246 E-05 2.243E-05 2.078E-05 1.644E-08 EXCLUSION AREA ENE 640.00 1.508 E-05 1.505E-05 1.395E-05 8.428E-07 EXCLUSION AREA E 640.00 1.204 E-05 1.202E-05 1.114E-05 6.012E-07 EXCLUSION AREA iSE 640.00 1.384 E-05 1.382E-05 1.280E-05 7.357E-08 EXCLUSION AREA SE 640.00 1.125 E-05 1.123E-05 1.040E-05 4.502E-06 EXCLUSION AREA SSE 640.00 1.460 E-05 1.457E-05 1.350E-05 3.775E-08 EXCLUSION AREA S 640.00 1.741 E-05 1.738E-05 1.610E-05 3.555E-08 EXCLUSION AREA SSW 640.00 2.298 E-05 2.294E-05 2.126E-05 4.22BE-08 EXCLUSION AREA SW 640.00 1.558 E-05 1.556E-05 1.441E-05 3.390E-08 EXCLUSION AREA WSW W 640.00 1.629 E-05 1.626E-05 1.506E-05 4.049E-08 EXCLUSION AREA 640.00 1.652 E-05 1.649E-05 1.528E-05 5.985E-08 EXCLUSION AREA WN4 640.00 2.074 E-05 2.072E-05 1.919E-05 1.540E-08 EXCLUSION AREA Nd 640.00 2.127 E-05 2.124E-05 1.967E-05 1.169E-07 EXCLUSION AREA NN4 Rev. 6 AP.310-40
I TABLE A-5 DISTANCES FOR GASEOUS EFFLUENT PATHWAY EVALUATION (METERS) i
{
(2)
HEAREST NEAREST NEAREST NEAREST NEAREST
- RECEPTOR SITE I DIRECTION BOUNDARY RESIDENCE GARDEN MEAT ANIMAL MILK COW MILK Got.T N 640 (3) (1) (1) 640 (3) (1) (1)
NNE 670 (1) (1) 670 (1) (1)
NE 790 1430 4830 460 (1) (1)'
ENE 680 1140 1140 460 1140 (1)
E 670 (1) (1) 670 (1) (1)
ESE 680 (1) (1) 680 . (1) (1)
SE 800 2560 2560 700. (1) (1)
SSE 950 7800 (1) 210 (1) (1)
I S 930 6490 (1) 220 (1) (1)
SSH 950 2900 5300 210 (1) (1) 1125 1220 3190 -290 3190 5630 SW WSW 980 1830 2380 420 3620 (1)
W 960 3230- 3230 510 7740 3230 WNW 980 4390 4390 450 (1) (1)
NW 780 5330 6750 510 (1) (1)
' NNW 670 7250 (1) 500 (1) (1)
I (1) Locations, if they exist, are greater than 8.047 meters (5 miles) from the Rancho Seco site.
Additional Locations:
Visitor Center E 225 meters 17.9% occupancy factor Park, Kiosk E 525 meters 41.7% occupancy factor Warehouse ENE 225 meters 23.8% occupancy factor Design City ENE 250 meters 23.8% occupancy factor (2) Site Boundary for Gaseous Effluent (3) Exclusion Area Boundary - 640 meters Rev. 6 !
AP.310-41 j
TABLE A-6 DOSE FACTORS FOR NOBLE GASES AND DAUGHTER 5*
1 Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Ng Radionuclides Kg Lg Mt (mrem /yr (mrem /yr (mradlyr (mrad /yr per pC1/m3) per pC1/m3) per pC1/m3) per pC1/m3) i Kr-83m 7.56E-02 ---- 1.93E+01 '2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 .1.72E+03 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03-Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-136 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 I
- The listed dose factors are for radionuclides that may be detected in gaseous effluents.
1 I-Rev. 6 AP.310-42
b ll TABLE A-7 Values Used to Derive Dose Factors for the Maximum Exposed Individual i Values of personal and environmental parameters used to derive dose factors for the maximum exposed individual that differ from values i
recommended in Regulatory Guide 1.109, Rev. 1 in the absente of site 1 specific data or that are not in Regulatory Guide 1.109, Rev. 1 are identified by an asterisk (*).
TABLE A-7a l
Usaae Values Aeolicable to the Maximum Exnosed Individual Ace Grouc Pathway Units Infant Child Teen Adult t
Fruits, vegetables & kg/yr- - 520 630 520 i grain l
Leafy vegetables kg/yr - 26 42 64' Miik li/yr 330 330 400 310 Meat kg/yr - 41 65 110 l Fish kg/yr - 6.9 16 21 Crayfish kg/yr - 2.2 5.2 6.9 l
Drinking water li/yr 330 510 510 730 Shoreline usage hr/yr - 14 100* 200*
(w-0.20 Inhalation m3/yr 1400 3700 8000 8000 Swimming hr/yr - 14* 100* 100*
TABLE A-7b Irrication Related Values Parameter Food Agric. Leafy Produce (a) Veaetables Milk Meat Irrigation rate (11/m2 mo)
/ 263* 263* 263* 263*
Fraction of year field is irrigated 1* 1* l' 1*
Time field has been irrigated prior 15* 15* 15* 15*
to crop of interest (yrs)
Rev. 6 AP.310-43
f b
' TABLE A-7b (continued)
Irriaation Related Values i
. Parameter Food l
Agric. Leafy Produce (a) Venetables Milk Meat
)
Fraction of crop that is not 0* 0* 0* 0*
contaminated l
Fraction of cow's drinking water that 1* 0*
u is not contaminated (a) Fruit, vegetables, and grain .
1 END Rev. 6 AP.310-44
I ,.
RSNGS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 I
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.I a^o o wo c^t v no"xtur^t "o"zron "o enoon^" x^"u^t REVISION 2 I
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RADIOLOG1 CAL ENV1RONMENTAL HON 1 TOR 1NG PROGRAM MANUAL REVISION: 2 PAGE 1 OF 29 -
' LEAD DEPARTHENT Effective date:
!.- Environmental Protection 07_2 _89
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} d e _ w. j . i s ..
Manager,Env)tonmentalIProtection Date h(r'nnnne?->At 4 -x 66 Director, Qualitj Assurance Date OuA'&f & #30d$
haiQerson PRC / ,
Date
/ )/.
' / j '/I ' , , . .
Chairperson, MSRC- ,
Date-
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l F. .ts PROCEDURE -
/M.ANUAL
'ND REFLECTS Tr.,
, i3 !*" in
! [ENT CONTROL PROCEDURi f
! ATEST REVISION.
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' SSiGNED
-C, _,,, ~ ~~ . .
- -10 MANU Al P
. _ - - _ _ - - - _ _ . - - - _ - - - - - - - - - . - - - _ . _ - - - - .- _ .A
RADIOLOGICAL ENVIRONMENTAL K)NITORING PROGRAM MANUAL REVISION: 2 l PAGE 2 0F 29 .
(-
l TABLE OF CONTENTS -
l-SECTION TITLE PAGE 0.0 Rancho Seco REMP Policy 3 1 -. 0 Radiological Environmental Monitoring Program Bases 4 l
2.0 Radiological Environmental. Monitoring Program Description 5 2 .1. Radiological Environmental Monitoring 7
Program Parameters Analysis of Expplure Pathways 9 2.2 2.3 Identification bf Sampling and Monitoring Sites and Samples 10 2.4 Reporting Results of Radiological 11 Environmentti Data i
'2.5 Selection of Radiological Environmental 11 l( Monitoring Locations l
PAGE-TABLE TITLE 1 Two Letter Designation to Identify the ;
13 Type of Sample 2 Sector Letter Designations Used in Sample 14 Identification 1 3 Radiological Environmental Sampling Locations 15 - 27 4 Environmental Thermoluminescent 28 - 29 Oosimeter Locations i
. ___-____.____.___._.m_______..__._2- _ _ . _ . _ _ _ _ - _ . - - -
I RAD 10L(X;1 CAL ENVIRONMENT AL HONITORING PROGRAM MANUAL.
REVISION: 2 I .
PAGE 3 0F 29 0.0 POLICY The Sacramento Municipal Utility District (SHUD) and the Rancho Seco Nuclear Generating Station recognize their responsibility to comply with the Technical Specifications and the (p)licable regulations, codes, standards and industry-wide criteria for establishing end maintaining a viable Radiological Environmental Honitoring Program. He are committed to operating the Rancho Seco Nuclear Generating Station in such a manner that will assure proper radiation protection to all employees, contractors and I the general public. To this end, we have committed to performing an environmental sampling program which meets the intent of the applicable regulations while providing an accurate assessment of the radiological environment in and around the environs of the Rancho Seco site.
I' jrQaN1e JdphF.Firlit Chief Executive Officer, Nuclear I
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RADIOLOGICAL ENVIRONMENTAL H3NITORlNG PROGRAH MANUAL REVISION: 2 3 PAGE 4 0F 29 El-1.0 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM BASES The Rancho Seco Unit One Technical Specifications, Section 4.26, i
)
state in part that:
"The Radiological Environmental Honitoring Program required by this specification provides measurements of radiation and radioactive materials in those exposure pathways and for those s 3 radionuclides which lead to the highest potential radiation 3 exposures of individuals resulting from station operation. This monitoring program thereby implementsSection IV.B.2 of 10CFR50, Appendix 1, and supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected." -
The Sacramento kunicipal Utility District and the Rancho Seco Nuclear Generating Station, to ensure that this requirement is met, have I instituted a Radiological Environmental Honitoring Program (REHP) which this manual serves to implement. The REMP is based upon the information contained in Title 10 of the Code of Federal Regulations, Part 20, Section 106 (10 CFR 20.106). That Regulatory basis and associated guidelines have been the foundation of the REHP and its programmatic elements which:
- 1. Provide the technological basis of, and the instruction for, monitoring the site and environs for radioactivity of all sources, including;
- a. naturally occurring background
- b. releases during normal operations I c.
d.
operational occurences and postulated accidents weapons testing and major nuclear accidents which contribute to detectable radioactivity in the environs.
- 2. Provide the means to verify the effluent control program of the Rancho Seco Nuclear Generating Station.
- 3. Heet minimum limits for detecting radioactive elements in samples collected from the environs, or direct measurements in the field.
- 4. Provide measurements of radiation and radioactive materials in those exposure pathways, i.e., liquid, gaseous, and direct radiation, and for those radionuclides, i.e., iodine, cesium, I and cobalt, which lead to the highest potential radiation exposure of individuals resulting from station operation.
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RAD 10 LOGICAL ENVIRONMENTAL K)N!TORING PROGRAM MANUAL L REVISION: 2 1 PAGE 5 0F 29 2.0 RADIOLOGICAL ENVIRONMENTAL H3NITORING PROGRAM DESCRIPTION.
The Radiological Environmental Monitoring Program is under the cognizance of the Chief Executive Officer, Nuclear, with the responsibility for the administration and oversight of the program assigned to the Manager Environmental Protection.
The' design of the program is consistent with the intent of: Title 10 Code of federal Regulations Part 20, " Standards for Protection Against Radiation" Section 106. To implement these requirements, the Technical Specifications, Offsite Dose Calculation Manual and Health Physics Implementation Procedures have been developed. The implementing procedures address specific areas in the program that require direct attention for completion. The following is a list of those documents used for th,e implementation of the REMP:
Radiological Effluent, Technical Specification Sections:
3.22 Radiological Environmental Monitoring 3.22-1 Radiological Environmental Monitoring Program 3.22-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3.23 Land Use Census 3.25 fuel Cycle Dose 3.26 Interlaboratory Comparison Program 4.26 Radiological Environmental Monitoring 4.26-1 Haximum Values for the Lower Limit of Detection (LLD) 4.27 Land Use Census 4.29 Fuel Cycle Oose 6.9.2 Radiological Reports 6.9.5 Special Reports Offsite Dose Calculation Manual.
Health Physics Implementing Procedures:
HPIP 2010 Training and Qualification of Radiological Environmental Personnel,
.I RADIOLOGICAL ENVIRONMENTAL H3N110 RING PROGRAM MANUAL
' REVISION: 2 I PAGE Interlaboratory Comparison of Radiological,
.__29 HPIP.202)
Environmental Honitoring Analysis.
I- Radiological Environmental Trend Analysis.
HPIP.2040 I l HPIP.2050 Radiological Environmental Reports, HPIP.2051 Annual Radiological Environmental Operating Report, HPIP.2060 Radiological Environmental Records and Documentation, I HPIP.2130 Preparations Prior to Performing Environmental Sampling, HPIP.2131 Handling gnd Preparations of Radiological Environmental Samples for Shipment, HPIP.2140 Land Use Census.
HPIP.2201 Sampling of Hater for Radiological Environmental Honitoring.
l HPIP.2260 Operation of the ISCO Hodel 2700 Sampler HPIP.2261 Inspection and Maintenance of the ISCO Composite Hater Sampler, HPIP.2310 Algae Sampling for Radiological Environmental Monitoring, HPIP.2401 Airborne Radiological Environmental Honitoring.
HPIP.2501 Terrestrial Sampling for Radiological Environmental Monitoring, HPIP.2610 Posting and Retrieval of Environmental Thermoluminescent Dosimeters, HPIP.2710 Sampling of Hilk for Radiological Environmental Monitoring,
.I HH P.2720 Sampling of Aquatic Life for Radiological Environmental Monitoring, HPIP.2730 Sampilng of Botanical Specimens for Radiological Environmental Monitoring.
HPIP.2740 Sampling of Animal Tissues for Radiological Environmental Honitoring, Sampling of Honey for Radiological Environmental I HPIP.2750 Monitoring.
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RADIOLOGICAL ENV!RONMENTAL M')N1TORING PROGRAM MANUAL I- REVISION: . 2 l PAGE 7 0F 29 Several documents that were used as guidance during the developmental-
[_
i phases of the program: .
American National Standards Institute Standard ANSI H545-1975, Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry (Environmental Appilcations),
ANI/MAELU Information Bulletin 86-1, Regulatory Guide 4.1 Programs for Honitoring Radioactivity in the Environs of Nuclear Power Plants, Regutatory Guide 4.15. Rev. 1, 1979, Quality Assurance for Radiological Honitoring Programs (Normal Operations) - Effluent Streams and the Environment.
NUREG-0472', Rev. 2 Radiological Effluent Technical l Specifications for PHR's, July 1979, NUREG 0543, Methods for Demonstrating LHR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190),
Branch Technical Position, Rev. 1. November 1979,
- f. NRCP Report No. 50 - Environmental Radiation Measurements.
2.1 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM PARAMETERS The monitoring and sampling aspects of the program are:
l Identification of the effluent release pathways, Identification of the human exposure pathways.
Identification of the land usage parameters by the population within a ten mile radius of the site.
Three principal release pathways at Rancho Seco Nuclear Generating Station, are:
Gaseous Effluents discharges from the waste gas system for the reactor building stack, auxiliary building stack, miscellaneous water evaporator stack and the auxiliary grade level vent.
Licuid Effluents discharges which are released from the retention basins via the waste water disposal system (regenerant hold up tanks (RHUT) A and B).
I
RADIOLOGICAL ENVIRONMENTAL K)NITORING PROGRAM MANUAL REVISION: 2 PAGE 8 0F 29 Direct -
Radiation radiation that emanates from radioactive material i contained within tanks or other containers which are within the site boundary to humans outside of the site boundary.
The pathways to human exposure to radioactive materials' in the effluent release pathways from Rancho Seco are:
Gaseous Inhalation of airborne radioactive material by humans, or by animals that inhale and retain the material in animal products eaten by the public, 1.e. meat or milk.
- Consumption of radioactive particulate material which, although carried by air currents, is. deposited onto or is taken u.f by water sources or plants consumed by humans, or by animals that provide products'that are
. consumed by humans, i.e. milk or meat.
- Exposure from being imersed in air containing radioactive materials as a gas and/or particulate.
- Exposure to the direct radiation from radioactive materials that have been deposited onto surfaces from airborne releases.
{
Licuid Drinking of water from the release pathway by humans, or by animals that are a food source for humans.
- The consumption of fish, shellfish or other animals that have eaten fish or shellfish taken from water within thE liquid release pathway.
- The consumption of animal meats or products of animals that have eaten vegetation that have been irrigated with water from the release pathway.
- The consumption by humans of fruit or vegetation grown
(-
)
in soil irrigated with water from the release pathway.
Direct l Radiation The exposure to radiation emitted from radioactive I materials within the Rancho Seco site boundary.
Sources include, but are not limited to, the Borated Hater Storage Tank, Reactor Coolant Storage Tank, and the Radioactive Haste Storage Area.
I
- The exposure from being immersed in the release pathway water, to radiation emanating from material
} contained in the water.
RADIOLOGICAL ENVIRONMENTAL KWITORING PROGRAM MANUAL
' REVISION: 2 PAGE 9 0F 29 2.2 ANALYSIS OF EXPOSURE PATHRAYS Exposure pathways are analyred through a systematic process which identifies a sample medium or organism that is found in the effluent pathways. Usage factors are determined that will suitably represent biological concentration, retention or uptake which may ultimately represent a contribution to human exposure. The pathways to human
'- exposure are evaluated through the analysis of data obtained from the performance of a land use census. The performance of the land use The census is required by the Technical Specifications Section 4.27. ,
analysis of the effluent and exposure pathways enables the selection l of sampling and monitoring locations that fall into one of two l classes, those which are, and those which are not.. influenced by
[
effluent pathways. Those in the pathways are referred to as J
indicator locations. Several of the unaffected locations are i selected to represent basgIine or control locations.
j k
Indicator locations provide data from the surrounding environment j that may be influenced by the operation of the plant because they are l nearby, downwind or downstream in the release pathway. Such data can I be used to calculate doses to humans to verify compliance with
) 40CFR190, using method 61ogy contained in the OOCH. (This is referred i to as the Real Individual Exposure. The Real Individual is defined as any person who participates in activities that result in that
- f. person being in the actual pathways for offsite. dose. A Real .;
Individual who, based upon the land use census, is expected to receive the maximum offsite dose to real individuals, may be used to calculate doses to demonstrate compliance with 40 CFR 190).
Control sample locations are to provide data that should not be influenced by the operations of Rancho Seco. These locations are selected based upon the distance from the plant, being upwind, or upstream of the release pathways. Data from these locations help l
discriminate between Rancho Seco releases and other natural or manmade events that may impact human exposure.
}
At Rancho Seco, potentially radioactive liquid effluent is discharged into Clay Creek. Continuously, an average flow of 8500 gallons per minute of non-radioactive water is released above the discharge point. The continuous minimum flow and the liquid effluent release are the major effluent release pathway, and thus the exposure pathway l-for the station during normal operations. Prior to the minimum release rate being established, Clay Creek wt.s a seasonal stream, formed as the confluence of three and one half square miles of drainage runoff upstream of the site. The now continuous flow of Clay Creek intersects Hadselville Creek North and West of California State Highway 104 Hadselville Creek intersects Laguna Creek just East of the Folsom Canal. Laguna Creek flows intoHadselv111e the Consumnes and f' River approximately 20 miles from Rancho Seco.
Laguna Creeks are also seasonal streams and also receive irrigation runoff during periods when irrigation is used. Because these streams f are the major release pathway for liquid effluents from the site, the l
majority of recent program enhancements have focused on this effluent I
pathway.
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RADIOLOGICAL ENVIRONMENTAL H3N170 RING PROGRAM MANUAL REVISION: 2 PAGE 10 0F 29 I The gaseous pathway analysis is also related to the land use census.
This pathway is not confined by creek banks, but is subject to the meteorological conditions during the time of the release. This presents the requirement for having indicator and control sampling stations more evenly distributed with particular attention to those areas of greater population density. While not the major release nor exposure pathway, recent improvements in monitoring this pathway have been instituted.
The direct radiation exposure pathway is the least likely pathway for l the exposure to plant radiation by humans. It is the most easily measured with the use of thermoluminescence dosimeters, which monitor i continuously and passively. The dose is integrated over three months to accumulate a statistical,1y significant exposure. The vast
[ majority of the , dose integrated by these detectors is delivered from geological surface of the Earth, which I
primordial elements in contain naturally radioact the;ive elements. A smaller fraction of the i dose is delivered by cosmic radiation which has penetrated the Earth's atmosphere.
) 2.3 IDENTIFICATION OF SAMPL'ING AND MONITORING SITES AND SAMPLES Sampling and monitoring sites and the samples collected from them, 1 must be identified with a concise designation. This has been accomplished using the following methodology:
To estabi'.h the Utility identification, the letter *R" has been chosen. Therefore all samples from the Rancho Seco begin with the letter "R".
Hext, that portion of the identification related to the type of f sample is made with a two letter designation, i.e., AS - Air Sample. A complete list is contained in Table 1.
A group of digits follows the sample type. These indicate the straight-line distance from the center of containment. For distances less than ten miles, the figure is to the nearest tenth of one mile. For distances ten or more miles the figure is to the nearest mile. Distances are measured with the use of U.S. Geodetic Survey maps.
Following that is a letter designation which specifies one of the 16 wind sectors as identified in the Emergency Response Plan, i.e., "H". Emergency Response Plan Wind Settors are defined in Table 2.
The final character is the letter "0" which designates the i
sample as being one collected after the plant was declared operational, f
RADIOLOGICAL ENVIRONMENTAL H3NITORING PROGRAM MANUAL REVISION: 2 PAGE 11 OF 29 Thus, a Rancho Seco Air Sample, collected at ten miles from the plant in Emergency Plan Hind Sector "H" after operational status was established would be identified as:
RAS 10HO.
The present system of identification has been incorporated in preference to the system originally used to identify samples and sites. There is a necessity to retain the ability to identify, and continue to use data from, previously collected samples. The former identification designation is shown in parenthesis under the currently used one.
2.4 REPORTING RESULTS OF RADIOLOGICAL ENVIRONMENTAL DATA The requirements for reporting radiological environmental data are specified in the Technical Specifications Section 6.9.2, i
Environmental Reports. Those subsections which require supporting data from the Radiological Environmental Monitoring Program address the Annual Radiological Environmental Operating Report and the 7
Semi-annual Radioactive Effluent Release Report. Technical j Specification Section 6.9.5, Special Reports, is made specific in HPIP 2050, Radiological Environmental Reports. Specified therein are 1
conditions requiring special reports, and reporting requirements in days for submittal. This includes those calculations to provide rapid assurance of the degree of compliance with 10CFR50 Appendix I, i
and 40CFR190 calculations after releases of any origin.
f 2.5 SELECTION OF RADIOLOGICAL ENVIRONMENTAL H3NITORING LOCATIONS In conjunction with the data base established from the land use census, the requirements of the Technical Specifications, and the guidance described in Section 2.0 of this Manual, the selection of
[ sampling and monitoring sites was performed. These selected s
locations provide at least the minimum number of locations specified in Technical Specifications, Section 3.22 Table 3.22-1.
Data was gathered from the land use census Lawrence Livermore National Laboratory Rar.cho Seco Study Reports, Oak Ridge National Laboratory Study Reports, and from additional sampling sites from
! which materials have been collected. The information gathered was used to determine indicator si'tes. Presently, a sufficient number of j
control sites have been selected and are not anticipated to be t increased in number.
h
RADIOLOGICAL ENVIRONMENTAL H3N110 RING PROGRAM MANUAL REVISION: 2 PAGE 12 Or 29 Environmental thermoluminescence dosimeters are placed in the l
environs around the site. These devices passi.vely monitor radiation in the immediate environs. Data from TLDs is trended to establish variations which are influenced by seasonal, meteorological, local and global sources. TLDs will also respond to radiation in the ef fluents of the plant if they pass in near proximity. The data is included in each quarterly environmental report.
Sample locations for the collection of the flora and fauna are concentrated in the liquid effluent pathway to the West.
Representative samples of all the pathways and suitable locations are established in all directions. Air samplers are distributed to achieve a sampling of air from major wind directions across the site.
The Radiological Environmental Monitoring Program maintains at least l those minimum sampling loc,&tions and type of samples to meet the requirements listed in Tech Specs, Table 3.22-1. Many sample types and locations have been added to enhance characterizing the radiological environmental impact of plant operations. The increased l
i sample locations and types in this manual, will be maintained unless it is determined that they are no longer useful or necessary data
[
) sites. The number and type will not be reduced below those stated in T.S. 3.22-1.
Two special sites that have been established are vegetable gardens T
' maintained by site personnel. One is established at the site boundary alongside the Clay Creek, and irrigated with water from the
[ effluent stream. These data are considered essential for comparisons t
to vegetation not irrigated with effluent stream water for determination of bioaccumulation for soll types common to the environs. The second garden is at the North of the site, and is irrigated with domestic water. Washed vegetables from this site will be compared to the site boundary washed vegetables for the comparison. Unwashed samples will be taken from this garden to I evaluate possible airborne materials to the North of the site via the l gaseous effluent exposure pathway.
Three other site vegetable gar nt.i have been established to the
[
/
south, east, and west, to ful!j represent the four principal meteorological directions. U washed samples from these gardens will be evaluated as indicator samples.
All of the current environment 3' sample locations selected for the Radiological Environmental Montioring Program are designated in Tables 3 and 4 Detailed maps c 1 which the sampling and monitoring I
i locations are marked are maintained by the Environmental Programs Group.
l l
f
RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM MANUAL REVISION: 2 PAGE 13 OF 29 i
TABLE 1 t TWO LETTER DESIGNATION TO IDENTIFY THE TYPE OF SAMPLE LETTER DESIGNATION TYPE OF SAMPLE REPRESENTED AS Air Sample RW Runoff Water
- l-SH Surface Water OH Orinking Water
?
WW Well Water L ,
HS Hud and Silt Milk Sample (Cow)
Soil HS Honey Sample BF Beef Tissue BT Beef Thyroid FS Fish Sample LV Garden Vegetation AG Algae Sample PV Pasturage TL Thermoluminescence Dosimetry SG Small Game FG frog CF Crawfish
)
) PH Pheasant DU Duck RI Rice l
Additional letter designation may be added as sample designators if f additional sample types are collected for analysis.
- Runoff water, the portion of precipitation on the land that ultimately reaches streams, is considered to be surface water.
L
RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM P.ANUAL REVISION: 2 PAGE 14 OF 29 TABLE 2 -
SECTORLETTERDESIGNATIONSUSEDINSAMPLEIbENTIFICAITON SECTOR LETTER SECTOR DEGREES AND TRUE NORTH COMPASS SECTOR A 348.65 TO 11.25 N 8 11.25.70 33.75 NNE C 33.75 TO 56.25 NE D 56.25 TO 78.75 ENE E .' 78.75 TO 101.25 E F 101.25 TO 123.75 ESE G 123.75 TO 146.25 SE H 146.25 TO 168.75 SSE J 168.75 TO 191.25 S K 191.25 TO 215.75 SSH L 213.75 TO 236.25 SH H 236.25 TO 258.75 HSH 258.75 TO 281.25 W H
281.25 TO 303.75 HNH P
I 303.75 TO 236.25 NH Q
326.25 TO 348.75 NNH R
)
The letters "I" and "0" are not utilized. This reduces the chances for mistaking them as numbers one and zero respectively.
l
)
)
[ .
RADIOLOGICAL ENVIRONMENTAL K)N1TORING PROGRAM MANUAL
-1 REVISION: 2
[ PAGE 15 0F 29 t
TABLE 3 -
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS L
SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY Location Name/ Degrees /Hi-I (OLD 10#)
AIR SAMPLES RASO.1CO IND Heekly On Site. / 54 /0.1 (RAHO) ,
I RASO.6KO IND Weekly Tokay Substation /192 /0.6 (RADO)
RAS 6.200 IND Heekly Hiller Residence /310 /6.2 (RAAO)
RAS 7.8CO IND Weekly Carbondale / 53 /7.8 (RAFO) l RAS 9.0E0 IND Weekly Ione / 88 /9.0 (RAEO)
RAS 10.HO CON Weekly Fish Hatchery /149 /10.
(RAGO)
RAS 18.K0 CON Weekly Lodi Substation /212 /18.
(RACO)
RAS 23.00 CON Weekly SMUD Headquarters /315 /23.
(RABO) i
i RADIOLO~ICAL ENVIRONMENTAL ONITORING PROGRAM MANUAL REVISION: 2 PAGE 16 0F 29 TABLE 3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY Location Name/ Degrees /Hi (OLD ID*)
HILK SAMPLES RHFO.BDO IND Heekly Marciel Ranch / 75 /0.8 (RHFDO) ,
RMF5.8PO IND Aeekly Hederlos Dairy /298 /5.8 (RHFAO)
RMF8.2X0 IND Heekly Angelo Dairy /204 /8.2 (RHFBO)
RMF10.ND IND Heekly Harmerdam Dairy /260 /10.
i RUNOFF WATER l
l RRHO.3HO IND Biweekly Effluent Discharge /250 /0.3 (RRHCO)
L RRHO.6HO IND B1 weekly Site Boundary /255 /0.6 f (NEH)
SURFACE HATER l RSHO.7NO IND Honthly Hater Sump /265 /0.7 (NEH) 1 RSH1.3F0 IND Honthly Rancho Seco Reserv. /104 /1.3
- (RSHCO) f R5W3.7NO CON Honthly Folsom South Canal /262 /3.7
-(R5HBO)-
RADIOLO";ICAL ENV!RONMENTAL K)N!TORING PROGRAM MANUAL REVISION: 2 PAGE 17 0F 29 TABLE 3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLL TYPE SAMPLE COLLECTION DESCRIPTION Of LOCATION IDENTIFICATION CLASS FREQUENCY Location Name/ Degrees /Mi
__IOLO ID*)
RSW12.G0 CON Monthly Camanche Reservoir- /130 /12.
(RSHA0)
RSHO.3MO IND Monthly ISCO Composite (NEH) Composite Sampler at Effluent Discharge /250 /0.3 DRINKING HATER RDHO.1G0 IND Honthly Rancho Seco Site /NA /0.1 (RHHCO)
RAIN HATER RRNO.8DO IND Seasonal Het Station / 75 /0.8 L (NEH)
L-RRN23.K0 CON Seasonal SHUD Headquarters /315 /23 (NEH) h.
PASTURAGE RPVO.6HO IND Honthly Site Boundary /255 /0.6 (NLH)
RPVO.8N0 IND Honthly Silva Property /260 /0.8 (NEH)
RPv0.800 iNo sonthiy sarciei Ranch / 75 /0.e
}
(RLVHD)
RADIOLOGICAL ENVIRONMENTAL H3 nil 0 RING PROGRAM MANUAL
~ REVISION: 2 PAGE IB Or 29 TABLE 3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY location Name/ Degrees /Hi (OLO 10#)
RPV1.5N0 IND Honthly Silva Property /264 /1.5 (NEW)
RPVI.8N0 IND Ho,nthly Silva Property /268 /1.8 (NEW) i RPV5.8P0 IND Honthly Hederlos Dairy /298 /5.8 (RLVFO) ,
RPV8.2K0 IND Honthly Angelo Dairy /204 /8.2 (RLVGO)
RPV10.N0 IND Honthly Harmerdam Dairy /250 /10.
(RLVEO)
HELL HATER RWWO.1GO IND Quarterly Site Well /138 /0.1
, (RWHAO) l RWWO.8DO CON Quarterly Marciel Ranch / 75 /0.8 (NEW)
RWWO.8LO IND Quarterly Clay Cattle feedlot /215 /0.8 (RWWEO) l
i RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM MANUAL REVISION: 2 I PAGE 19 0F 2f TABLE 3 -
RADIOLOGICALENVIRONMENTALSAMPLINGLkATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY location Name/ Degrees /Hi (OLD 100 RHH3.7HO IND Quarterly Silva Feed Lotwell /262 /3.7-l (NEH)
RHH2.1NO IND Quarterly Silva Rancho (NEH)
- Vaquero Hell /260 /2.1 i
RHW1.8F0 IND Quarterly Rancho Seco Reserv. /114 /1.8 (RHWEO)
) *
)
RHW2.1HO IND Quarterly Clay Area Hell /254 /2.1 (RHWBO)
HUD AND SILT RMSO.3HO IND Quarterly Effluent Discharge /250 /0.3 (NEH)
)
RMSO.6HO IND Quarterly Site Boundary /255 /0.6 (RMSEO)
RMSO.7NO IND Quarterly Water Sump /265 /0.7 (NEW)
RHS1.3F0 IND Quarterly Rancho Seto Reserv. /104 /1.3 (RMSCO)
RMSI.BND IND Quarterly Confluence of Clay (NEH) and Hadselville Creeks /272 /1.6
(
RADIOLOGICAL ENV!RONMENTAL HONITORING PROGRAM KANUAL REVISION: 2 j
PAGE 20 0F 29 TABLE 3 -
! RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS l
- l. SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY Location Name/ Degrees /H1 (OLD 10#)
RH514.H0 IND Quarterly Laguna Creek at /265 /14 Twin Cities Rd.
l RMSO.2HO IND Quarterly Storm Drain 1 /150 /0.2 y
RMSO.2HO IND Quarterly Storm Drain 2 /168 /0.2 l
RMS3.7NO IND Quarterly Laguna Creek at (NEW) Folsom South Canal /260 /3.7 l
f RHSS.4HO IND Quarterly Laguna Creek at (NEW) Laguna Road /256 /5.4 i
RMS10.NO IND Quarterly Laguna Creek at (NEW) McKenzie Road /259 /10.
1 RMS12.G0 CON Quarterly Camanche Reservoir /130 /12.
(NEH)
RHS14.H0 IND Quarterly Laguna Creek at (NEW) Twin Cities Road /265 /14.
FISH SAMPLES Include species identified as Bass, Sunfish, Perch, Catfish, Carp or Suckers.
RF50.3HO IND Quarterly Effluent Discharge /250 /0.3 (RFBO)
RFSO 6HO IND Quarterly Site Boundary /255 /0.6 (RFDO)
RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM MANUAL 2 REVISION:
21 0F 29 I PAGE TABLE 3 -
RADIOLCGICALENVIRONMENTALSAMPLINGLh'TIONSJ I SAMPLE TYPE IDENTIFICATION SAMPLE CLASS COLLECTION FREQUENCY DESCRIPTION OF LOCATION location Name/ Degrees /Hi (OLD 10#)
IND Quarterly Hater Sump /265 /0.7 RFSO.7NO (NEH) i CON Quarterly Rancho Seco Reserv. /104 /1.5 I RFS).5F0 ,
(NEH)
~
I RFS1.8ND IND Quarterly Confluence of Clay and Hadselv111e I (NER) ,
Creek /272 /1.8 li-RFS2.2NO (NEH)
IND Quarterly Hadselville Creek above Clay Station Road /260 /2.2 IND Quarterly Laguna Creek Hear RFS3.7NO Folsom South Canal /260 /3.7 IND Quarterly Laguna Creek at RFSS.4HO Laguna Road /256 /5.4 (NEH)
IND Laguna Creek at RFS10.H3 McKenzie Road /259 /10 (NEH)
ALGAE SAMPLES Quarterly Effluent Discharge /250 /0.3 IND I
RAGO.3HD (RBAO)
Quarterly Site Boundary /255 /0.6 RAGO.6H3 IND (N m
L l !
RADIOLOGICAL ENV!RONMENTAL H3NITORING PROGRAM MANUAL REVISION: 2 L PAGE 22 0F 29 TABLE 3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENT!f! CATION CLASS FREQUENCY Location Name/ Degrees /H1 (OLD ID#)
I RAGO.7NO IND Quarterly- Water Sump /265 /0.7 (NEH)
RAGl.3f0 . CON Quarterly Rancho Seco Reserv. /104 /1.3 (NEH).
RAG 1.8NO IND ' Quarterly Confluence of Clay (NEH) and Hadselville f Creek /272 /1.8 5 RAG 2.2NO IND Quarterly Hadselville Creek (NEH) near Clay Station Road /260 /2.2 l
RAG 3.7NO IND Quarterly Hadselville Creek (RBBO) at Folsom South Canal /260 /3.7 RAG 5.4HO IND Quarterly Laguna Creek at (NEH) Laguna Road /256 /5.4 RAG 10.NO IND Quarterly Laguna Creek at (NEH) McKenzie Road /259 /10.
RAG 14.H3 IND Quarterly Laguna Creek at Twin Cities Road /265 /14
~
RADIOLOGICAL ENVIRONMENTAL HON 110 RING PROGRAM HANUAL REVISION: 2 I TABLE 3 PAGE 23 OF 29 I
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION Of LOCATION CLASS FREQUENCY location Name/ Degrees /Hi IDENTIFICATION (OLD 100 RABBIT RRBX.XNO IND Quarterly Hest of the Site Boundary / /X.X (NEH) g =
IND Quarterly Storm Orain 3 /187 /0.2 RSLO.230 IND Quarterly Storm Drain 4 /210 /0.2 RSLO.2KO I
l l
IND Quarterly Storm Drain 5 /235 /0.3 l RSLO.3LO I RSLO.2HO IND Quarterly Storm Drain 6 /162 /0.2 I RSLO.3HO IND Quarterly Storm Drain 7 /241 /0.3 I RSLO.3HO IND Quarterly Storm Drain 8 /244 /0.3 IND Quarterly Storm Drain 9 /250 /0.3 RSLO.3HO l
IND Quarterly North Site Garden /005 /0.5 RSLO.5A0 Site Boundary /255 /0.6 l RSLO.6HO (NEH)
IND Quarterly I
I -
E k/> . RADIOLOGICAL ENVIRONMENTAL H3NITORING PROGRAM MANUAL REVISION: 2 PAGE 24 0F 29
]M , ..
. TABLE'3
['y b '
SAD 10 LOGICAL ENVIRONMENTAL SAMPLING LOCATIONS
. o.
(y ,
( gay.PLE DESCRIPTION OF: LOCATION-
' SAMPLE. TYPE. ' COLLECT 10N' CLASS FREQUENCY; Location Name/ Degrees /Hii IDENTIFICATION 1QLD IDW _ -_.,
l i 3 .
/250'/0.7 Silva Propertys
. 811 RSLO.7hD , .IN0 ' Quas;terly
-(NEH) .-
RSLl~.3F0 CON Quarterly . Rancho Seco Reserv. /104'/1.3' (HEN) "
(
RSLI.5NO IND Quarterly . Silva Property -/264 /1.5.
I, (NEW)
RSLI.8N0 INO Quarterly; .
Silva Property /268 /1.8:
1*
(HEH)
. ~
CMWFISH
, . J RCf0.6HO 'IND Quarterly Site Boundary. /245 /0.6 g
-(NCH)
RCFO.7NO IND Quarterly hater Sump. < /265 /0.7 (NEH)
RCF3.7NO IND Quarterly Hadselville Creek i
" at Folsom South 'l (NEH) l Canal /260 /3.7 '
RCF10HO IND Quarter 1,y Laguna Creet at McKenzte Road /259 /10 (NEH) t fi ,
i
/
RADIOLOGICAL ENVIRONMENTAL HDNITORING PROGRAM MANUAL
^ REVISION: 2 PAGE 25 0F 29 TABLE 3 -
l R_AD10 LOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION CLASS FRE0VENCY Location Name/ Degrees /H1 IDENTIFICATION (OLD ID#)
I CARDEN VEGETABLES HARVESTED AT LEAST SEMI-ANNUALLY (.SA).
HONTHLY THROUGHOUT THE GR0HING SEASON (-HTGS)
IND SA-HTGS Site Garden North / 5 /0.5 RLVO.5A0 (NEH)
RLVO.5E0 IND SA-HTGS Site Carden East / 92 /0.5 (NEH 1988)
RLVO.530 IND SA-HTGS Site Garden South /182 /0.5
( (NEH 1988)
RLVO.5NO IND SA-HTGS Site Garden West /275 /0.5 (NEW 1988)
RLVO.6HD IND SA-HTGS Site Garden at Site /245 /0.6 (NEH) Boundary, irrigated with Clay Creek Water RLV2.2HO IND SA Clay Station Area /250 /2.1 (RLVAO)
RLV9.5E0 IND SA lone Area / 90 /9.5 (RLVCVO)
ClemEnts Area /171 /I)
RLVll.JO IND SA (RLVCO)
INO SA Sloughbovse Area /341 til RLV11.R0 (RLVDO)
RADIOLOGICAL ENVIRONMENTAL MON 1TORING PROGRAM MANUAL REVISION: 2 PAGE 26 0F 29
~
TABLE 3 .
L RADIOLOGICALENVIRONMENTALSAMPLINGLdCATIONS
' SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY location Name/ Degrees /Mi (OLD 10#)
l RLV18.K0 CON SA Lodi Area /212-/18 l (RLVF0) l Y
I HONEY RSHX.XNO IND SA NEAREST HIVES TO THE HEST (NEH)
I I BEEF TISSUE l
RBFX.XHO IND SA BEEF TISSUES FROH CATTLE (NEH) RAISED HEST OF THE SITE BEEF THYROID RBTX.XNO IND SA THYROIO GLAND FROM CATTLE THAT (NEH) HERE RAISED HEST OF THE SITE Pffd5_9ff.I RPHK.XNO IND ANNUALLY PHEASANT TAKEN HEST OF THE (NEH) SITE
I RADIOLOGICAL ENVIRONMENTAL HONI10 RING PROGRAM MANUAL REVISION: 2 PAGE 27 Or 29 TABLE 3 RADIOLOGICAL _.[ ENVIRONMENTAL SAMPLING LCDTIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY location Name/ Degrees /Hi (OLO 10#)
I SOUIRREL RS0X.XN0 IND AS NEEDED COLLECT FROM HEST OF THE PLANT (NEW 1988) NEAR SITE BOUNDARY CARDEN g
To be collected if squirrel 15 meat enters food chain
- I =
RFG0.6HO IND Quarterly Site Boundary /255 /0.6 RFG2.2ND IND Quarterly Hadselville Creek /260 /2.2 at Clay Station Road RFG3.7NO IND Quarterly Hadselville Creek /260 /3.7 at Folsom South Canal I RFG10.H0 IND Quarterly Laguna Creek at /259 /10 McKenzie Road I
I I
I _
RAD 10 LOGICAL ENVIRONMENTAL HONITORING PROGRAM MANUAL REVISION: -2
-PAGE 28 0F 29 TABLE 4 ,-
ENVIRONMENTAL THERMOLUMINESCENT DOSIMETER LOCATIONS CLASS TLD MAP # IDENT/DESIG CLASS TLD MAP #
I IDENT/DESIG NUMBER IND/ CON NUMBER IND/ CON IND 1 RTLI.7LO IND 21 RTLO.3R0 l
IND 2 RTL1.6JO IND 22 l
RTLO.3E0 RTLO.3NO IND 3 RTL).8KO IND 23 l
IND 4 RTLI.7HO IND 24 RTLO.3LO IND 5, RTL3.6LO IND 25 RTLO.3HO RTL3.9KO IND 26 RTLO.4E0 IND 6, IND 7 RTL3.6JO IND 27 RTLO.5CO RTL3.7H0 IND 28 RTL6.200 IND ,B f RTL23.00 CON 9 RTL4.2JO IND 29 10 RTL7.4HO IND 3D i RTL18.K0 CON IND 11 RTL3.7NO IND 31 RTLO.6KO 12 RTL4.8PO IND 32 RTL9.0E0 CON RTL10.NO IND 13 RTL3.8HO IND 33 14 RTL3.800 IND 34 RTL11.H3 CON RTL10.HO CON 15 RTL).9NO IND 35 l
I 36 RTL2.7LO IND 16 RTL).6PO IND IND 17 RTLt.900 IND 37 RTLB.2K0 IND 18 RTLt.6RO IND 38 RTL7.8C0 19 RTLI.580 IND 39 RTLO.7G0 IND IND 20 RTL1.5A0 IND 40 RTL1.5HO
RADIOLOGICAL ENVIRONMENTAL H3NITORING PROGRAM MANUAL-REVISION: 2 PAGE 29 0F 29 TABLE 4 (Continued) -
I .
I- ENVIRONMENTAL THERHOLUH1NESCENT 0051 HETER LOCATIONS IDENT/DESIG CLASS TLD MAP # IDENT/DESIG CLASS TLD MAP #
NUMBER IND/ CON NUMBER IND/ CON RTLI.8CO IND 41 RTL14.P0 CON 61 i
RTL4.4GO IND 42 'RTL11.HO CON 62 RTLI.8F0 IND 43 RTLO.8DO IND 63 l
RTL1.6EO IND 44 RTL9.5EO IND 64 RTL1.8F0 IND 45 65 RTL1.4DO IND 46 f
I RTL3.0C0 IND 47 RTL3.7DO IND 48 RTL3.2E0 IND 49 RTL3.5F0 IND 50
)
RTL10.E0 CON 51 l
RTL19.E0 CON 52 RTll2.G0 CON 53 RTL11.30 IND 54 RTL8.0PO IND 55 RTL4.600 IND 56 RTL7.6A0 IND 57 RTL6.6B0 IND 58 RTL11 R0 CON 59 RTL11.A0 CON 60
g- . ~ ,
.- ... _.- s
$SMUDSACKAMENTo MUNICIPAL UTIUTY DtSTRICT O 6201 S Street, P.o. Box 15830, Sacramento CA 95852 1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA AGM/NPP 89-085 March 1, 1989 U. S. Nuclear Regulatory Commission Attn: J. B. Martin, Regional Administrator y Region V 1450 Maria Lane, Suite 210 Halnut Creek, CA 94596 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1988 1 s
y x
Dear Mr. Martin:
The Sacramento Municipal Utility District hereby transmits two copies of the Semiannual Radioactive Effluent Release Report for the period July 1 through December 31, 1988, in compliance with Technical Specification 6.9.2.3. ;
i Members of your staff with questions requiring additional information or )
clarification may contact Mr. Peter Murphy at (209) 333-2935, extension 4144. ;
1 Sincerely, Dan R. Keuter Assistant General Manager Nuclear Plant Manager Attachment cc w/atch: A. D'Angelo, NRC, Rancho Seco C. Hooker, NRC, Halnut Creek C. Hillis, NRC, Rockville Document Control Desk, Washington DC
[6$
I \ l RANCHO SECO nlUCLEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95638-9799: (2091 333-2935 l