Text

Forwards Util Response to 860718 Inquiry Into Operations & Mgt of Plant Liquid Effluent Program.Util Considers That Discharge of Radioactive Matl in Liquid Effluents Allowable by Tech Specs within Limits of 10CFR20,App B
	ML20245E067
Person / Time
Site:	Rancho Seco
Issue date:	12/02/1986
From:	Julie Ward; SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Marsh G; NRC OFFICE OF INVESTIGATIONS (OI)
Shared Package
ML20245E058	List: ML20245E054; ML20245E060; ML20245E063; ML20245E067; ML20248B416; ML20248B467;
References
	FOIA-89-2, FOIA-89-A-7 JEW-86-885, TAC-64735, NUDOCS 8811110173
	Download: ML20245E067 (76)
	v • d • e

- _ _ _ - _

kSMUD- SAC 8tAMENTo MUN10 PAL LFTUTY DtSTIOCT O P. o. Com 15830, secremento CA 95852 183o,(916)452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAUFORNIA

'J'EW 86-885 December 2, 1M6

G "MtSH DIRECTOR OrFICE OF INVESTIGATIONS. REGION V U S NUCLEAR REGUIATORY COMMISSION 14 50 MARIA . IANE SUITE 210 WALNUT CREEK CA 94596 DOCKET NO._50-312 l LICENSE NO. DPR-54.

OFFICE OF INVESTIGATION INQUIRY The Sacramento Municipal Utility District has thoroughly reviewed ]

the matters of your July 18, 1986 inquiry into the operations and. -l management of the Rancho Seco Nuclear Generating Station's liquid j effluent' program. Enclosure I provides the District's resIsonse to l your seven questions and is current to July 18, 1986. . l

)

The District has- summarized extensive volumes of data such that:

extraneous detail does not obfuscate the responses to your seven questions. References utilized in developing the District's '

responses are listed in Enclosure II and included as noted in l Enclosure III for your review. These references provide additional l detail as necessary to complete your review. l l

Planned radiological liquid ef fluent release information has been included. The District considers that the discharge of radioactive material in liquid af fluents is allowed by Technical Specifications to within the limits of 10 CFR 20, Appendix B.

The District wil'1 continue to be responsive to additional questions ;

that may arise during your review of this matter. !

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l WARD DEPUTY GENERAL MANAG

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I December 2, 19.-

G MARSH to the United Statss Nuclear,

Enclosures:

I - Response

Regulatory Commission Office of, Investigation Inquiry into the operation and Management of-the Liquid' Effluent System II - List of References III - Reference Materials cc: . INFO (Without Enclosure III)

J B Martin (Without Enclosure III)

I & E. (Without Enclosure III)

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ENCLOSURE I RESPONSE TO THE UNITED STATES NUCLEAR REGUIATORY COMMISSION OFFICE OF INVESTIGATION ,-

INQUIRY INTO THE OPERATION AND MANAGEMENT OF THE LIQUID EFFLUENT SYS NRC Question 1:

From the issuance of Rancho Seco's operating license to present, identify the water sources, from outside the Station's boundary, for all of Rancho Seco's water systems, including those systems . utilized or necessary for the generation of power as well as those systems utilized or necessary for other plant operations.

District Response:

From the issuance of Rancho Seco's operating license to present, water required for all phases of plant operation has been supplied by the Folsom South Canal, the Site Water ' Supply Reservoir, a site well, a Rancho Seco Park well, and a well located at a single f amily residence on site. Reference 1 (Figure 2.4-15 attached) and Reference 2 provide Rancho Secc site layouts with water sources highlighted.

The Folsom South Canal normally supplies the Site Water Supply System (SWSS) via a pumping station located four miles west of the plant site. The SWSS has physical connections with the following plant systems:

a. Circulating Water

b. Plant Cooling Water

c. Service Water

d. Fire Protection

e. Atulliary Feedwater

f. Waste Water Disposal

g. Domestic Water The SWSS contains an onsite reservoir which is used to supply the plant with water in the event of an outage of either the Folsom South Canal or the canal water supply systen. A branch line from the SWSS is used to supply water to the reservoir to make up for evaporative losses. If reservoir supply is required, water is fed to the SWSS via gravity flow to supply plant system water demands.

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l An onsite well (Well 1, Figure 2.4-15) was drilled just east of the protected area in May 1969 to supply the Plant Domestic Water system. This well is 410 feet deep and contains a deep well submersible pump.which provides the normal supply- of plant '

domestic water.

A well (Well 7, Figure 2.4-15) located approximately 2500 feet east of the area has also been used periodically to supply the Domestic Water System and potable. water. This well was connected to the plant via underground piping-which is no longer serviceable due to recent construction.

Another well (Well 2, Figure 2.4-15) located in the' Rancho Seco Park just south of the reservoir has been utilized infrequently for potable water when the Domestic Water System was not potable. The water is trucked to the plant in water cans and distributed to various locations for drinking purposes.

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NRC Question 2:

Identify what radioactive materials and other cont'aminants are present in Rancho Seco's water systems including those systems utilized or necessary for the generation of power as well' as those systems utilized or necessary for other plant operations.

District Response:

Tables 1and2prov[detheradionuclidespresentinplant systems. Table 3 provides a listing of the chemicals intentionally added to plant water systems and the major system in which the addition occurs. Reference 3 provides other contaminates found in plant waste water systems. Reference 17 provides specifications on contaminates in plant.vasta systems and Reference 22 provides a variety of graphic trend data showing the variation in selected chemical parameters over the 1984 operating year.

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Identified in " Peak Search" Routines.

- System water not analysed.for radioactivity-

- - - System water sampled and analysed, no radioactivity reported.

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7. Sulfuric Acid Circulating Water Regeneration-(Ion E:: change) System

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From the issuance of Rancho Seco's operating license to present, describe the pathways of the Station's water systems at their points of origin within the plant to their points of release outside the Station's boundary. Also describe the released effluents pathways from the Station's boundary to their ultimate destinations.

District Response:_

Figure 1 provides a simplified diagram of the pathways of the Station's water systems at their points of origin within the plant to their points of release outside the Station's boundary.

Water system pathways terminate at the final retention effluent basin before discharge to the Hadselville Creek via Clay Creek.

Waste waters from throughout the plant enter a mixing box in the restricted area upstream of two retention basins. Offsite sic canal water from the Folsom South Canal is automatically admitted to this mixing box. The canal water is used for dilution purposes and also helps to maintain a steady fl'ov to the clay creek. The mixture then flows to a mixing sump or is bypassed into a celected retention basin. 30 The numerous water pathways located throughout the plant, with a discharge to the retention basin area and eventmal release Additional inputs to sumps e

offsite, are detailed in Table 1.

are presented in Table 2. Modifications to these pathways from the issuance of Rancho Seco's operating license to present are y described in the response to Question 5.

The majority of the inputs listed in Table 1 include backwashes and area drains that are not expected to contain radioactive material. They are routed, however, through the retention 3 basin. The polishing domineralizar and the acid vaste sumps have contained small amounts of radioactive material as a result of steam generator tube leaks. As such, these sumps are routed to the regenerative holdup tanks for dilution, sampling and analysis, calculation of releases, and discharge to the ate retention basin. An additional periodic input to the regenerative holdup tanks is the anviliary boiler blowdown.

The stora drain system is the only othar water pathway within the plant that results in water being discharged off -site.

Rainwater collected in area stora drains is discharged by offsite to clay gravity drain to an area south of the plant, Creek.

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I Reference 1 (Figure 2.4-1, attached) shows the location of the Rancho Seco Nuclear Generating Station and surrounding streams and lakes. Effluent pathways. are - detailed in References 5 and 6. . Water utilized by the plant is discharged directly to Clay Creek. Clay Creek intersects -

Hadselville Creek - 3.0 km downstream.from the plant; Hadselville. Creek water drains into Laguna . Creek at a point some 6.5 km from the plant outfall. Water in Laguna Creek flows to the Cosunnes River'at a. point near Twin Cities Road.

between Interstate Highway 5 and State Highway 99.- The Cosunnes River empties into the Mokalumne River which' joins the Sacramento River about 20 miles- south of Sacramento.

Reference 4 provides the- survey of Laguna Creek' water users.

Other ultimate destinations and uses such. as irrigation, groundwater, . recreation, . wildlife, aquatic food, et cetera, are detailed in the following references:

Reference 7 UCID-20267_

This report discusses in detail the pathway of the liquid effluer*s in the environment downstream from Rancho Seco.

Reference 8_

- UCID-20295 Discusses the' observed radionuclides concentrations in fish downstream from Rancho Seco over a five-month period in 1984. .Also discusses the liquid pathway downstream from Rancho Seco.

Attachment B Discusses environmental parameters necessary to calculate a radiological dose to an individual via the liquid effluent pathway.

UCID-20298 Discusses the liquid effluent pathray downstre.am from Rancho Seco and the observed radionuclides in irrigated land and stream sediment samples in 1984.

Reference 9, Special Report No. 85-01 Discusses the environmental parameters necessary to calculate )

a uranium fuel cycle dose to an individual. I Reference 10, Rancho Seco Liquid Effluent Pathway Usage Survey Report This is a detailed report that discusses environmental pathways associated with the liquid effluents.

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Reference M UCID-20367 This report discusses the liquid affluent pathway in the environment downstream from Rancho Seco and reports observations of radionuclides in environmental samples collected during 1984.

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' Reference 12 Special Report No. 85-05 Discusses the environmental parameters necessary to calcula' a uranium fuel cycle dose to an individual.

Reference 13,UCID-20641 This report discusses the liquid effluent pathway'in the environment downstream from Rancho Seco and reports the observations of radionuclides in environmental samples collected during 1985.

Reference 14 1984 Annual Radiological Report Section III F discusses liquid effluent environmental parameters.

1985 Annual Radiological Environmental Operating Report Section IV discusses environmental parameters downstream frt Rancho Seco and calculates a radiological dose to a hypothetical family.

Appendir A presents the 1985 land use census for both the -

gaseous and liquid effluent pathways.

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A. yarious Orains/ Backwashes

1. Backwash from reservoir supply line filter.

2. Drain f rom cooling towers. .

3.- Circulating canal overflow.

4. Overflow from nuclear service spray ponds. -

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6. Area drain from chemical , storage tanks.

7. Drain from auxiliary boiler area.

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Crain f rom hydrochloride tank.

9. Backwash from service water filters;

50. Blowdown f rom cooling towers.

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13. Overflow and drain from condensate storage tank.

14. Sewa'ge treatment system.

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2. Condenser Pit Sump .

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3. Steam generitor drain booster pumps..

station battery room, west nuclear' service

4. Floor drains from:

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S. Training and Records Building floor drains. .

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NRC Question 4:_ 1 f

From the issuance of Rancho Seco's operating license to present, provide a detailed account of how and at, what intervals radioactive materials are identified and released !

I from the Station's water systems. For each testing process identified, provide the operational requirements for conducting such test. .

I District Response:

The following references provide an account of how and at what intervals materials are identified and released from the Station's water systems.

References:

(14) 7 Vols. Effluent Release Reports (15) 1 Vol. Procedure AP. 3 0 5-13 (Environment Releases of Radioactivity) (Comple*

Revision History up to July 18, 1986 (16) 1 Vol. Count Room Manual and other counti: '

equipmentprocedures (17) 1 Vol. Procedure AP.306-III (Sampling Point Analyses Required, Frequency and Specificatic Levels 1 Vol. Other Plant Procedures dealing with (18) sampling and Liquid Systems (19) 1 Vol. AP.310 Off-Site Dose Calculation Manual (ODCN)

(Liquid Effluent related sections) l Although the procedure purpose has not changed appreciably over time, the requirements within the procedure have changed considerably due to both operational constraints and evolving regulatory requirements. The only way to acquire a comprehensive understanding of the history of the liquid ef fluent release program at Rancho Seco Nuclear Generating Station (RSNGS) is to review the revision history of AP.305-13.

l AP.305-13 describes, in detail, the steps required to release liquids (both radiological and non-radiological in nature) to the environment. A complete revision history of AP.305-13 has been included as Reference 15 because these requirements have changed substantially since the issuance of the operating license. The original stated purpose of AP.305-13 dated April 1, 1974, is as follows:

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"Under normal operating conditions, every effort vill be made to prevent liquid radioactivity of plant origin from being released to the environment. However, under abnormal conditions it may be necessary to release limited amounts of low level radioactive liquid vaste. This procedure describes those actions to take to insure that the plant design objectives (less than 5 mren/yr to any one individual in the general public from planned releases of radioactive liquid vastes of plant origin) are met."

The stated purpose in Revision 21 (current revision) is as follows "Under normal operating conditions, every effort vill be made to prevent liquid radioactivity of plant origin from being released to the environment. Hovover, under abnormal conditions it may be necessary to release limited amounts of lov icvel radioactive liquid vaste. This procedure describes those actions to take to monitor and analyze liquid effluent releases to provide data that is used to determine if the plant design objectives (less than 3 mrem /yr whole body or 10 mren/yr to any organ and 1.5 mrem to the whole body and 5.0 mrem to any organ, during any calendar quarter to a member of the general public) are met. Additionally, the concentration of radioactive material released at any time beyond the site boundary shall be limited to the concentration specified in 10 CFR 20, Appendix B, Table II, column 2 for radionuclides other than dissolved or entrained noble gasses shall not exceed 2.OE-4 uCi/ml."

Procedure AP.306-III is a substantial document. A complete revision history would comprise a number of volumes. For this reason, only a copy of the current revision of t-hin procedure has been included as Reference 17. This procedure provides a complete description of which systems have regularly scheduled sampling and analysis (both radiological and non-radiological) performed. The stated purpose of the procedure is as follows:

"The program of chemistry and radiochemistry controls detailed in the chapter consists of measurements both required and desired; it is a composite of Technical Specifications which must be performed, Process Standards which have been designated as necessary for correct plant operation, and a larger body of measurements which enable diagnosis and correction of problem conditions in order that ' desired' methods of plant operation vill be achieved."

11 Xi BIT is

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AP 306-III outlines the Technical Specifications values that must be met for samples taken as well as when and what samples are required. The complete list of regularly scheddled sampling does not exclusively address Technical Specifications required samples. Samples which aid in the detection and early diagnosis of potential operational problems are also included in this procedure. This procedure and its requirements provides an account of all routinely scheduled sampling activities that take place at RSNGS.

When samples are obtained they are analyzed according to the Count Room Manual procedures and other counting equipment use procedures. These procedures also represent a large volume of !

paper and, therefore, only current revisions have been included here as Reference 16. As stated in the Count RMm Manual:

"This manual provides information concerning the laboratory equipment used for measurement of radioactivity in plant process samples, radiological swipes, effluent samples and environs 2ntal samples. Also described are methods of mounting solid samples for various counting systems,.

preparing plateaus, counting efficiencies and background measurements, statistical evaluation of count rates,

- reduction of counting data, spectrum stripping and data recording. Using .this manual, any sample containing radioactivity can be analyzed accurately for the desired active constituents."

These procedures provide instruction on how to prepare and analyze samples (using on-site equipment and procedures) in a reproducible way such that counting errors are kept to a minimum.

The operational parameters for the actual obtaining of samples are found in the Plant Operations Manual (POM). Tne procedures in this manual specify the exact operational sequence of steps required to obtain a sanple of a system (including valve -

lineups, etc.) . A copy of the POM Table of Contents has been included for reference at the beginning of Reference 18. The procedures are not included due to the large volume of paper.

Specific POM procedures will be made available upon request.

The Semiannual and Annual Radioactive Effluent Release Reports provide a synopsis of the disposition of radioactive material in gaseous and liqu3d effluents. A complete set of t.he current revisions to these reports for all years 1974 through 1985 have been included as Reference 14 as well as the January-June, 1986 report. At'the front of the first volume is a list of all reports and corrections thereof since the issuance of 12

X - B ie a G4 ., 4G n....

[

the operating license. Complete reports are sent to the NRC semiannually and annually.

Calculation of radiation exposure to the general population and the maximum hypothetical individual is performed in accordance with the Offsite Dose calculation Manual (ODCM).- This manual' explains the steps required and used to calculate a radiological exposure to a : maximum hypothetical individual and -

the general public based upon radioactive material discharged in gaseous and liquid affluents. A copy of the sections of the ODCM (AP.310) that pertain to liquid offluents has been included as Reference 19 for information purposes. The statement of purpose at the beginning of the manual is as follows:

"This Offsite Dose Calculation Manual (ODCM, September 1985) provides the information and methodologies to be used by the Rancho Seco Nuclear Generating Plant to ensure compliance with those portions of the Rancho Seco operating Technical Specifications which are related to liquid and gaseous radiological effluents. The ODCM is

' intended to show that Rancho Seco complies with 10 CFR 20, .

10 CPR 50.3 6A, 10 CFR 50, Appendix A (GDC 60 and 64), and Appendix I.

"This ODCM is based on " Radiological Effluent Technical Specifications for PWR's" - (NUREG-0472), October 1978),

" Preparation of Radiological Effluent Technical Specifications > ar Nuclear Power Plants" (NUREG-Ol33, October 1978), and other information provided by the U.S.

Nuclear Regulatory Commission (NRC). Specific plant procedures for implementation of the manual have been developed. These procedures are to be utilized by the operating staff of Rancho Seco to ensure compliance with Technical Specifications."

The ODCM also provides the definition of Lower Limit of Detection (LLD) as referenced by " Radiological Environmental Technical Specifications", sample point descriptions for the radiological environmental sarp? ing program,and a methodology for compliance with 40 CFR 390.

The decision to release radioactive liquid to the environment is not a routine process. Operations personnel will normally determine when liquid containing radioactive material must be released and schedule the release according to procedure AP.3 05-13. This decision is normally based on overall plant conditions, the current inventory in liquid holdup tanks as well as considerations for meeting the requirements of the various applicable environmental and radiation protection 13 E.B T m

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m s

n #..

I

'Il f

, s regulations.

[ All of the information . included ~ is on file at RSNGS. - Revision histories for all procedures are available at RSNGS. If specific revision histories / time period histories ~are reqttired, they can- be compiled at the request of the NRC.

i:

O i E 14 EXHIBT ts

l- !

i I

)

l NRC Question 5:

From the issuance of Rancho Seco's operating license to present, provide a detailed account of all planned and unplanned modifications to the approved Final Safety Analysis Report (FSAR) program to identify and release radioactive materials from the station's systems. Provide the reason why each modification occurred.

District Response From the issuance of Rancho Seco's operating license to present, there have been several planned and unplanned modifications to the approved FSAR program to identify and release radioactive materials. Table 1 provides the account of planned modifications to the approved FSAR program and the reason why each modification occurred. The original approved program is described in the PSAR (Reference 23). Planned modifications to the approved program are described further in the USAR and its amendments (Reference 1).

An unplanned modification is defined herein as those

modifications which did not result in the itsuance of an engineering change notice (ECN) and as such, may have not gone through the formal review process. The unplanned modifications were of a temporary nature until a planned modification was performed, or were a result of an abnormal system operation brought about by various plant transients. The following details unplanned modifications that resulted in a release of radioactive material in liquid effluent aaid provides the reason why each unpinnned modification occurred.

Only two unplanned modifications have occurred; the partial draining of the (1) Demineralized Reactor Coolant Storage Tank (DRCST) and (2) the Miscellaneous Water Holdup Tank (MWHUT) to the 'A' and 'B' Regenerant Hold-up Tanks (RHUTs) so that tritiated water could be processed and diccharged to the retention basins for eventual release offsite. Thase two unplanned modifications have been implemented several times since the issuance of Rancho Seco's operating license.

The unplanned modifications were performed when the tanks were near capacity as a result of additional water ganarated from the reprocessing of the 'A' and 'B' RHUT through the Radvaste System and the processing of other contaminated secondary liquids. These modifications were considered to Lave been operational enhancements to allow for future addition = to the DRCST and MWHUT.

25 EXF BT ts m___ _ _ _ _ _ _ _ _ _ -__... _ _ _ _ _ _ _ _ - _ _ . . - -

r: i I

L Both modifications installed a temporary line of PVC (Schedtde

80) piping to the RHUTs. Prior to use, the' temporary piping was hydrotested, barrier taped and radiation-area posted. The tanks were drained via the temporary piping pursuant to an abnormal' operating procedure with required walkdowns every one-half of an hour.

The concentration of tritium in the DRCST and the MWHUT was -5 MPC (1 MPC = 3E-3 uCi/ml). 10 CPR 20.106 and Appendix B to 10 CFR 20 limit releases off-site to 1 MPC. The water transferred to the RHUTs was suffielently diluted prior to release off-site to assure the 1 MPC limit would not be exceeded.

These temporary modifications were changes to the facility as described in the USAR (Reference 1). Because the changes were only temporary, the USAR was not updated to reflect the temporary system operation. The temporary modification of transferring DRCST water to the RHUTs is being incorporated to become a permanent modification to the plant.

L i

16 - .

. no ., e

H 1 ..

I ADDENDUM TO NRC QUESTION 5 In January 1980, a temporary modification was' implemented to bleed and feed the Component Cooling Water (CCW) systern to reduce a' slight contamination of CCW due to a small tube leak in the CCW heat exchanger. Makeup water was added to the CCW system and drained to the RHUT(s) via~a temporary line. ,

9 J

16a EXFIBIT = m

Table 1 CHANGES TO THE FSAR INVOLVING THE IDENTIFICATION OR RELEASE OF RAD:,QACTIVE MATERIALS ,

USAR SECTION DESCRIPTION OF CHANGE REASON FOR CHANGE 11.1.1.1 Paragraph added describing Liquid effluents are l the potential pathway being released.

for liquid releases from the site.

11.1.2.2.1 Sentence added stating Because of limited that the coolant vaste facilities for storing holdup tank T-610A is used concentrated liquid to hold concentrated radwaste, the coolant liquid radwaste prior to vaste holdup tank solidification. (T-610A) is now used to hold concentrated liquid radwaste prior to solidification.

11.1.2.2.1 Statement added to the These bottoms may effect that bottoms from become chemically the vacuum evaporator on contaminated. If this the boric acid happens, they are no concentrator may be sent longer usable and are to the spent regenerated disposed of.

tanks for processing as vaste.

11.1.2.2.2 Statement to the effect Decause it has not that the mise liquids proved to be cost radwaste collects and effective to processes vaste from the regenerate resins, deborating ion exchanger they as.e being disposed regeneration has been of and hence, the ion removed. regenerator is no longer in regeneration.

11.1.2.2.2 Description of disposal of The coolant vaste misc. Vastes concentrate holdup tank (T-610A) storage tank bottoms is now used to hold concentrated liquid cha:xJed from offsite radvaste prior to removal to storage in coolant vaste holdup tank solidification.

T-610A prior to solidification.

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USAR SECTION DESCRIPTION OF CHANGE REASON FOR CHANGE 11.1.2.2.2 ~ Description of Misc. water The' miscellaneous water evaporator added. evaporator,was added to the miscellaneous radwasta system to minimize the environmental impact- of liquid wasta processing.

Table 11.1-2 Notation added to the Because of a need for effect that coolant vaste greater. concentrated holdup tank T-610A may be liquid radwaste storage used to hold' concentrated capability, the coolant liquid radwaste prior to vaste holdup tank solidification. (T-610A) is now urod-to-hold concentrated liquid radvante prior to solidification.

11.1.4.1.B C1arification 'of The . ure.a-formaldehyde K concentrated liquid wasta solidification system disposal syetam ' originally employed by description. Radioactive SMUD was not accept-waste is now stated to be able. SMUD now uses a sent to a contractor wasta contractor supplied solidification cystem solidification rather than a tank truck system.

or 55 gallen drum. ,

- 11.1.4.1.C Spent resi.n disposal This is a clarification system description of the original expanded to state that program.

shipping containers include devatering and/or solidification capability.

11.1.4.2.1 Dry waste compactor A new dry waste description added. compactor was added to increase the volume reduction capability of the dry solid waste disposal system.

11.1.4.2.2 Concentrated liquid waste The coolant vaste disposal system description holdup tank is now used expanded to include to store concentrated 18 .P.:Ill!.I.

. uw 15

--___.-m_-__m.__ _ _ _ _ _ _ _ . . - - _ _ _ _ _ _

.c o

b

'USAR SECTION DESCRIPTION OF CHANGE REASON FOR CHANGE transport of. liquids from ' liquid radwaste prior the coolant vaste holdup to solidification.

tank T-610A to the solidification unit.

11.1.4.2.3 Inaccurate description of As originally designed, letdown' filter crud the shield assembly for disposal systen deleted. the letdown crud filter Actually disposed of as would be a certified any other crud filter. shipping container.

When the filter was to be. changed, the whole assembly would be removed and shipped.

The filter would be disposed of and the shield reused. This was never done as shipping container certification for the assembly was nevel received.

11.1.5.1.1 Evaluation of liquid Radioactive liquid-vastes changed to allow effluents are being for release of liquid released.

wastes.

11.1.5.6 Description of decay tank The District now uses discharge rate monitoring the guidelines of changed. NUREG-0133, rather than actual atmospheric dispersion factors, to establish radiation monitor setpoints for allowable discharge rates from the decay

i. tanks.

l l 11.1.7.1 Description of estimated Liquid effluents are

! liquid radvaste releases being released from the I wastes released from the regenerant holdup tank.

l regenerant holdup tank.

11.1.7.2 Paragraph added describing The miscellaneous water doses from gaseous evaporator was added to radioactive effluents the miscellaneous released as a result of liquid radwaste system 19 EXHBIT m l

'USAR SECTION DESCRIPTION OF CHANGE REASON FOR CHANGE-operating the - to minimize'the miscellaneous water environmental impact of evaporator. liquid waste processing.

11.2.1 . Paragraph added describing The District conducted compliance of Rancho Seco a review to ensure that Design Shielding with the Rancho Seco design NUREG-0737, Item II.B.2. shielding complies with-the guidelines of NUREG-0737, Item II.B.2.

Table 11.3-2 Addition of three channel Formerly, it was only 11.3-7 process radiation monitor possible to monitor atmosphere. the air in the: reactor building or the air downstream of the HEPA-and the purge duct.

The three additional channels monitor make it possible to mohitor the air in both

- locations.

Table 11.3-2 Range of vaste gas surge The range of the 11.3-10 tank monitor changed. monitor was formerly inadequate to measure the discharge from the l

waste gas surge tank (V-650).

l Table 11.3-2 Polisher domineralizer The polisher demin-11.3-10 area sump monitor R15020 eralizer sump is moved to waste water upstreau of the discharge. regenerator holdup tanks, which are the i release point for waste I water. Waste water may i reach the tanks ,

downstream of the i polisher demin sump. {

20

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. N _

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l USAR SECTION DESCRIPTION OF CHANGE REASON FOR CHANGE Table 11.3-3 Description of post The post accident 11.3-1cA accident radiation monitors were added monitors added. in compliance.with' NUREG-0737 Secs. ion

- II.F.1, subparts 1, . 2 and 3, and Reg. Guide 1.97 Table 2.

Table 11.3-3 Description of gaseous NUREG-0737 Section 11.3-10A,B effluent radiation II.F.1 and the.NRC's monitor system letter of December 4 added. .1984 both require that the reactor building purtje stack be monitored with a' wide range gas monitor before the reactor building equalizir.g valves can be used.

11.3.2.3 Paragraph added describing The post accident" the post accident monitors were added in

n. radiation monitoring compliance with NUREG system. 0737,Section II.F.1, subparts 1, 2 and 3, and Reg. Guide 1.97, Table 2.

11.3.2.6 Sentence stating that Liquid effluents are liquid effluents will not being released.

be released has been removed.

21 EX4 BIT e

r _.

f.

b NRC-Question 6:

Other than as described in ~ the FSAR, from the issuance of:

Rancho Seco's operating license to present, provide's description of each release pathway, the volume of. liquid for each release, the radioactive source and method of dotarmining the source ' for each release, . the amount' of radioactivity identified per release and if and how the NRC was notified of:

each response.

District Response:

- The information presented is. a' compilation of radiological data -

release from two separate sources. The first source is the file of Occurrence Description Reports (ODR) generated from the issuance of the plant operating license to present. - ODRs are a means by which plant personnel inform management of operational .

parameters which are believed to be deviating from the norm.

Copies of the release related ODRs has'been included as. ..

Reference 20.- This list includes all ODRs which indicate that a release of _ liquids, as defined above, has taken place. -In-many cases, these ODRs were submitted not to identify a release -

of liquids from a system, but to convey to Management operational parameters which deviated from normal.- .In most of these cases, the comprehensive' radiological analysis performed on releases of. liquids to the .off-site environment would not be

' warranted for the liquids released within the plant. Most releases within the plant are routed to drains and systems capable of treating the' liquid as radwaste. The Operating License does not require reporting of releases that do not leave the plant site (Reg. Guide 1.21). When data' for the nuclides containad in the released liquid was reported, the data was included in the' compiled list. The same is true for indication of volume released. This value is often a gross-estimate and this estimate is sometimes not even made because the liquid released would normally drain to plant drains and radwaste' treatment systems. When an estimate of volume released was documented on the ODR, the value was included in the list of release related ODRs. Copies of the release related ODRs have been included in this information package. l The second source is a compilation of the data included in evet,f planned' release since the issuance of the operating license. This list includes the date of the release, the release number, the volume released (in gallons), a column for the concentration of each gamma emitting isotope for which a I.ower Limit of Detection (LLD) value has been specified in the Technical Specifications, a column for the concentration of other gamma emitting isotopes for which LLD values are not specified in the Technical Specifications, a column for Tritium 22 :X JB

- I m e e o .,

1' t

concentratim (also a Technical Specification required value),

and a column for gross beta concentration values.. These concentration values are in uci/ml for the volume released. If an entry other than zero is made in the OTHER NUCLIDES column, the value is the sum of the concentrations of the isotopes identified in the OTHER NUCLIDES IDENTIFIED column. This compilation is provided as Reference 21.

Note: At this time, the first 71 Release P'ermit Records for 1975 and 5 Release Permit Records for 1980 have not been located. The data from these records will be transmitted if the records are located.

The release pathway for all of these releases is a route from one of two ' (A and B) regenerant holdup tanks (RBUT) to one of two (north or south) retention basins (an alternata pathway which allows the release of liquid from the RHUTs directly offsite exists but is not used in accordance with procedural restrictions) . As a rough estimate, it is possible to infer that if the Tritium concentration is 3 e 4ers of magnitude above the the total gamma emitter concentration, the liquid came from the Demineralized Reactor Coolant Storage Tank. In any other' cases, the sctual origin of the liquid in an RHUT would be very difficult to determine. However, the most likely origin of any radioactive material would be the secondary system (due to operation with a small primary to secondary leak). This data is compiled directly from the Release Permits.

Reference 14 provides the Annual and Semiannual Radioactive Effluent Release Reports for years 1974 through June, 1986.

Descriptions of events which led toabnormal' releases are included in these reports. A list of pages which supply a synopsis of the liquid releases during the year has been included in Reference 14.

In 1985 and 1986, samples sent to an outside contract vendor (Controls for Environmental Pollution) were evaluated for gamma I I

constituents in liquid effluent samples. A revised annual report was submitted to the NRC which incorporated the activity levels detected by CEP and ODCM calculatiords based on these releases were performed. The method used to determine the amount of radioactive materials released is outlined in the revised report for 1985 (which was included with the January- r June 1986 semiannual report, Reference 14).

Of the two sources above, the NRC notifications are made in differing ways. An ODR may require the generation of a Special Report or a Licensee Event Report (LER), (formally called Reportable Occurrence) which are generated and sent to the NRC. The list of release related ODRs contains a column for 23 -

- c . . . -

I the Reportable Occurrence number which generated an LER for the cited occurrence Description Report. If the District determined that an LER or Special Report was not re, quired for a particular ODR, no written notification to the NRC was made.

The data from the planned Release Permits and abnormal' releases is reported to the NRC in the Semiannual and Annual Radioactive Ef fluent Release Reports - (Reference 14). These are the methods of reporting releases to the NRC.

e e

O m

g

_----.______--__-_--..n.______---__ _ . _ _ - - - . . _ . _ - _ -

_NRC Question 7 For those planned and unplanned releases made other than as described in the FSAR, from the issuance of Rancho 'Seco's operating license to present, provide an analysis which shows all possible pathways to the environment and the radiological consequences of all possib1ra failure modes.

District Response All possible release pathways are provided in the response to Question 3.

The UL NRC Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974 defines " abnormal releases" as " unplanned or uncontrolled release of radioactive material from the site boundary."

The total amount of' all radioactive materials in liquid and gaseous effluents, both normal and abnormal is reported in the Semiannual Radioactive Effluent Release Report (Reference 14) with a section within the report specifically addressing abnormal releases.

The analysis of the radiological consequences of all normal and abnormal releases of radioactive materials in liquid and gaseous effluents has aircady been reported in the Semiannual Radioactive Effluent Release Reports (Reference 14). If the abnormal release event required it, a Licensee Event Report or Special Report was also prepared. The quantity of radioactive material released in an abnormal release is generally quite small in comparison with the total quantity released in the quarter. The radiological consequences of any single abnormal release is therefore bounded by consequences reported in the ef fluent reports.

The radiological consequences reported in the Semiannual Radioactive Effluent Release Reports are determined using the nethods and paraneters defined in the Offsite Dose Calculation Manual (ODCM) and uses the Maximum Hypothetical Individual concept The Maximum Hypothetical Individual as used in this response is consistent with its use in the U S NRC Regulatory, Guide 1.109 and 10CFR50 Appendix I. The Maximum Hypothetical Individual is characterized as ' maximum" with regard to food consumption, occupancy, and other usage or exposure pathway parameters in the vicinity of Rancho Seco that would represent an individual or composite of individuals with habits greater than usually 2S :X-IBIT . C.

A Cb OO s

expected for the average of the population in general. No single individual would be expected to be exposed to all the potential effluent exposure pathways. If the Annual Land Use Census or Radiological ' Environmental Monitoring proigram shows that a pathway does not exist, it may be deleted from the composition of the Maximum Hypothetical Individual. If the pathway is shown to exist, even if only one individual is known to be in the pathway (or parameter within the pathway) and that individual is not in the other pathways, the pathway or parameter is added to the Maximum Hypothetical Individual. If the pathway is observed but additional site specific environmental or usage data is unavailable, then the default values for the maximum individual in US NRC Regulatory Guide 1.109 are used.

The radiological consequences (in aren) reported in the Semiannual Radioactive Effluent Release Reports are used to compare the operation of the facility over the previous 6 months with the numerical guides for design objectives in 10CFR50 Appendix I. The values reported in the effluent reports cannot be equated to a real radiological exposure to a real individual or to test for compliance with 40CFR190.

To perform a 40CFR190 radiological consequence analysis of a real radiological exposure to a real individual, it is necessary to use information gathered from the Annual Iand Use Census and the Radiological Environmental Monitoring Program.

Reference 8 Attachment B, Reference 9, and Reference 12 are examples of a 40CFR190 radiological consequence analysis.

The Lawrence Livermore National Laboratory studies (references 7,8,11, and 13), the Usage Survey Report (reference 10), the 40CFR10 uranium fuel cycle dose evaluations (reference 9 and 12), and the Oak Ridge National Laboratory study (NUREG/CR-4286) were all used by NRC staff in their preparation of the "NRC Staff Assessment of the Environmental Radioactive Contamination in the Vicinity of the Rancho Seco Nuclear Power Plant transmitted to the District April 28, 1986.

The NRC Inspection Report No. 50-312/06-15, June 6, 1986, concluded that, "Accordingly, since it has not been reasonably f

established that a real member of the public received a dose in excess of the 40CFR190 standard, no violation of 10CFR20.106(g) has been identified. This matter is closed."

l

} The Annual Radiological Environmental Operating Report January-I December, 1985 (reference 14) includes an assessment of radiological impact on the environment resulting from liquid effluents. The assessment calculated a radiological doce in I the liquid ef fluent pathway of only 2 arem for 1985.

26 .

1 However, for purposes of responding to this question, the radiological consequence analysis will use the ODCM and the Marimum Hypothetical Individual approach.

'The Rancho Seco history of abnormal releases is as follows:

Liquid - None Gaseous:

.(1) 01/12/77 -> 02/16/77 Unplanned release Partial collapse of the reactor coolant drain tank. Reportable Occurrence 77-3 reported March 3, 1977.

i (2) 04/01/77 -> 04/04/77 -

Uncontrolled release Auxiliary Building ventilation system particulate activity monitor was taken out of service for repairs without performance of the required daily grab sampling in lieu.

Reportable Occurrence 77-4 reported April 25, 1977.

$r 1978 Liquid - None Gaseous - None 1979 Liquid - None Gaseous - None 1980 Liquid - None Gaseous - None 1981 Liquid - None Gaseous - Three (1) 01/24/81 Unmonitored release Leakage past two valves and inadvertent opening of 3rd valve primary system makeup tank leaked backward to the hydrogen gas ,

header.

~

(2) 02/11/81 Monitored i Reactor vessel head removed and unexpected 1 release of gas occurred. Reactor Building purge terminated within 10 minutes. Fuel -

transfer tubes open. Spent Fuel Building exhaust vent. !

1 2, EXH' BIT g -

7 ..

E

i: .

E iS.

t (3) 05/16/81

'B" Steam Generator Isak Activity ejected via the Condenser. Air-

! : Ejector. and Gland Steam. systems. Licensee

. Event Report LER 81-26 dated 05/29/81 1982- Liquid - None Gaseous - None i

1983 Liquid - One (1) 01/20/83 overflow of the Miscellaneous Wasta Boldup .

Tank with tritiated water entering the site affluent discharge. LER 83-04 reported 01/28/83.

Gaseous - None 1984 Liquid - None r

Gaseous - Three (1) 03/19/84 Hydrogen explosion and fire in the generator exciter. Steam dump valve opening near the-end of the plant shutdown. LER 84-15 reported 04/18/84, i

.(2) 07/03/84 .

Steam generator tube leak Release through the condenser hogger ejectors. LER 84-20 reported 08/03/84.

(3) 10/11/84 Steam generator tube leak LER 84-22 and Supplement 1 reported 11/07/84 and 11/29/84.

1985 Liquid - Three (1) 07/09/85 valve lineup to fill "A" steam generator.

Hose drained to the storm drain, no discharge offsite.

(2) 07/30/85 '

Isakage from high pressure throttle valve directed to stora drain.

I 28

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(3) 12/26/85 . .

DrainingofPASSbackup'watercoolin;gtank.

Gaseous - One (1) 12/26/85 Reactor trip'due to loss of ICS.

LER.85-25 1986 Liquid - None (1st and 2nd Quarter')

Gaseous - None The basis for the radiological analysis of radioactive' material ,

. in liquid effluents for purposes of comparison.with the numerical guide for design objectives of 10CFR50 Appendix I is the Rancho Seco Offsite Dose Calculation Manual (ODCM) . Revision 3, AP.310 (Reference 19). .

The simplest -method- cf analysis is to use a simplified equation l.

based upon the ODCM and an assumed mix of radionuclides. The-simplified equation is as follows: ,

Liquid Effluent Pathway-Simplified Radiological Dose Evaluation' Equation Dose = 1000/GPM (FAPIi j Cigapi + T ji_. Cit I where: Dose dose in aren resulting from radioactive liquid effluent using normalized source tara mix and Rancho Seco ODCM, Revision 3 (Reference 19).

GPM quarterly average plant liquid effluent discharge, gallons per minute (Table 3) .

FAPIi j Fission and Activation Products including Iodine dose factor for age group i. and organ j for the maximum hypothetical individual (area /CI) (Table 4).

T Tritium dose factor for age group i$ i and organ j for the ==vi=um hypothetical individual (ares /C1)

(Table 5).

EXHIBIT i s.'

29

o. 48 ., O -

_ _ _ _ _ _ _ _ _ _ _ __ . _ _ _ __- a

f ci gapi Fission and Activation Products including' Iodine source term.in-Curies. ,

Ci t. Tritium source term in curies.

CAUTION: This equation is not appropriate ' for the performance of a uranium fuel cycle dose analysis pursuant to 40CFR190.

The assumed mix of radionuclides is described in Table 1. This nix was derived from the Appendix I Evaluation Report, June 1976, and Rancho Seco historical liquid effluent data from 1981 through 1984 and normalized to a 1.0 curie total.

Table 2 provides a summary of the radioactive liquid effluent discharges from Rancho Seco broken down by the US NRC Regulatory Guide 1.21 categories.

Table 3 provides a summary of the t otal plant liquid discharge-volume from Rancho Seco.

Tables 4 through 9 provide a summary of the ODCM calculated radiological consequence's to the Maximum Hypothetical

- - Individual using the assumed mix of radionuclides normalized to 1.0 Curies of. fission and activation products including iodine and 1.0 Curie- of tritium and' normalized to a 1,000 gpa total plant discharge rate.

The radiological dose (mres) in Tables 4 through 9 and the dose factors (aren/Ci) in Tables 10 and 11 is more precisely defined as the 50 year committed dose resulting from a uniform and continuous discharge rate throughout one entire year, and a uniform and continuous usage by the Maximum Hypothetical Individual throughout one entire ycar. The calculation models within the ODCM also assume that the discharge rate is the same for each year the facility is licensed to operate and that the radionuclides have reached equilibrium in the environment.

Tables 10 and 11 provide the dose factors for the simplified dose evaluation equation.

Tables 12, 13, and 14 show that radiocesium contributes 99.2%

to the Maximum Hypothetical Adult total body exposure and 98.8%

to the Maximum Hypothetical t%ild liver exposure. Iodine-131 -

contributes 63.2% to the Maximum Hypothetical Child thyroid exposure.

Table 15 provides a summary of all the liquid effluent pathway site specific ODCM parameters.

30 EXHIBIT te

. . . oa .. u , . . . .

1 mi__._._.____.____________ _ _ _ _ _ _ _ _ _ _ __ _ _ _ ..]

1 1

l i

1 l

The supporting input and output listing from the INyrAP l computer runs are also provided as Reference 26 (NUREG/CR- l 1276). . j 1

One can then use the simplified equation to calculate the i radiological consequences for any event that releases radioactive material in liquid effluent very easily by the following step-by-step procedure: f I

1) Summarize the radioactive liquid affluent discharge in {

units of curies and divided into tritium and fission and activation products including iodine.

2) Determine the year and quarter of the discharge and obtain the quarterly average total plant discharge flow rate in gpm from Table 3.

3) Decide the age and organ you wish to determine and obtain the appropriate doce factor (arez/C1) from Tables 10 and 11.

4) Use the Simplified Radiological Dose Evaluation Equation to determined radiological consequence to the Maximum Hypothetical Individual.

The single largest failure mode to hypothesize vould be a failure of an outdoor tank not surrounded by liners, di.kes, or valls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radvaste treatment system.

NUREG-0472, Revision 2, July 1979 ' Radiological Effluent Technical Specification for PWRs" contains a Limiting Conditions for Operation for the quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in outdoor tanks (TS 3.11.1.4) . The Rancho Seco Technical Specifications Section 3.17.3 specifies a 10 Curie Limit to both the Regenerant Holdup Tanks (T-950A&B) and Outside Temporary Tanks.

The Bases in NUREG-0472 for Section 3.11.1.4 is to provide l assurance that in the event of an uncontrolled release of I the tank's contents, the resulting concentrations would be f less than the limits of 10CPR20, Appendix B, Table II, ]

Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

1 31 [r hlf 6 j

NUREG-0133, October 1978, " Preparation'of Radiological Effluent Technical Specification for Nuclear Power Plants -

r= A Guidance Manual for User's of Standard Technical Specifications" goes on' to clarify the statement in NUREG-0472 to include indoor tanks if the leaked fluid is capable of affecting the nearest existing or known future water.

supply in an unrestricted area. " Supply

is defined as well or surface water intake that is used as a water source for direct human consumption or indirectly through animals, crops, or food processing. "Known future" water supply is

. defined as potential wells or surface water intakes which are identified, or may be reasonably deduced from available information.

Our information indicates that the Clay, Hadselville, Laguna creek system transporting Rancho Seco liquid effluents is not used as a potable (drinking) water source. Our information also indicates that few,.if any, dairy cattle drink Lagunc Creek water, but beef cattle have accese to both Clay Creek and pasture irrigated by Clay Creek.

District management is now committed to maintaining the ,

total plant liquid effluent discharge rate of 5,000 gpm.

Reference (5) page II-8 provides annual average stream flow e rates for-Hadselville and Laguna Creeks from which dilution factors of 1.372 and 2.611 can be calculated for the respective streams. Because no potable water use has been identified out to Cosunnes River, . for purposes of this analysis, it will be assumed that potable water is obtained from the Cosunnes River. Reference 5 indicates that this water is diluted to 0.1% for 7 months and 1% for 5 months for an annual average dilution factor of 625.

Reasonable estimates indicate that no individuaa. consumes 35 Kg per year of fish so a value consistent with US Regulatory Guide 1.109 will be used, i.e., 21 Kg per year. This change will be made 1.n parallel with using the US Regulatory Guide 1.109 value of 2,000 for the cesium fresh water fish bioaccumulation factor of 2,000 pico-Ci/Kg per pico-Ci/litar.

The IADTAP computer code is used for the radiological consequence analysis. The inputs and outputs are provided as i Reference 27. The same liquid effluent source term mix in Table 1 was used for this analysis multiplied by 10 to obtain the 10 Curie quantity. -

l i

32 - XHl3 e I

h 1

t .

. The limits . of 10CFR20, Appendix B, Table II, Column 2 relate to a dose to the whole body not erceeding 500 arem per calendar year and averaged over a year.. The NRC can limit ~ the Licensee to one-third the values of 10CFR20, Appendix B, Table II if the resultant analysis exceeds the 500 aren value.

Table 16 provides a summary of the analysis. The analysis-indicates a dose of 221 aren,171 uren, and 158 aren to the vbole body of the Maximum Hypothetical Adult, Teenager, and Child respectively, all of which are below the 500 mren limit.

Because this analysis shows .that the limits of 10CFR20 are met,~'

the 10 Curie per tank limit is adequate for Rancho Seco and-provides the necessary protection to the general public.-

~

>> EXH; BIT is

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c L

1 'TA8LE 1 RADIOACTIVE LIQUID EFFLUENT-SOURCE TERM (1 Moraalized Annual' Estimated Annual Sourte Tern (Cl)

- Nucilde_ Source Ters (Cil 1.50E-05

.1.58E-47

Na-24 1.00E45 - 9.49C-44

Cy-51 4.41E-44

Hn-54 4.650 =9.490-44 1.00E-45 9.49E-04 Fe-55 1.00E-05

-59~ 6.540-46 6.89E-48

Co-57 1.20E44 1.14E-42 c

-58 9.49E-44 '

-40 1.00E-45 7.43E.06-7.83E-48

Sr-69.

0 0

-91

' 9.49E44 1.00E-45 Y-91 6.37E-45 6.71E-07 5.61E45

Zr-95' 5'.91 E-4)

' -97 3.84E-44 4.05C -2.52E-41:

Nb-95 2.65E-03 Mo-99 2.17E-01 2.29E-03 6.18E-44

.Tc-99m 6.51E-06

Ag-110m O O

Te-127m ' '0 0

-127 9.49C-44 .

-129m. 1.00E-05 9.49E -129 1.00E-05 1.00E45 9.49044

' ' -131m 0

-1 31 0

.1.33E-02

,-132 1.40E-04 9.49E-04

-1.00E-45 1-130 1.78E-01 ~

-131. 1.88E-03 1.80E-02

-132 1.90E44 1.77E41

-133 1.86E-03 0

-134 0 5.13E42

-135 5.40E-04 3.13C42 3.30E-44 Cs-134 -

1.52E-42

-136- 1.60E-04 2.37E42

-137 2.50E-04 0

Ba-137m (2) (2.30E-04) 3.41E-44

-140 3.59 E-46

3.33E-04

La-140 3.51E-06 9.49E-44 Np-239 1.00E-05 1.00 1.05E-42 Total ~

e a EXH 3 T is i

..n.-

TABLE 1 (Continued)-

RADIOACTIVE LIQUID EFFLUENT SOURCE TERM (1)

Appendi'x I Evaluation Report Table 3.4 June 1,1976 Radionuclides is not in the LADTAP data file so was. dropped froen (2) the analysis.

Radionuclides observed in Rancho Seco radioactive liquid effluent that were not included in reference (1) the 1981-1984 annual average value fission products -

normalized to the Cs-137 value in (1) I the 1981-1984 annual average value-activation products - nonnalized to the Co-60 value in (1) w 4

35 EXHlBlT is

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2 . :.~ e . . . . . .

TABLE 2

' RADIOACTIVE LIQUID EFFLUENT

SUMMARY

(Cur Fission & Tritium Dissolved Gross H-3 __ &ases __ Alpha Unidentified ye37 e Oua rter Activation _ _

0 0 ,- 0 3 0 0 2.00E-3 1974 7.57C-3 0 0 4 2.00E-3 0 0 0 0 0 0 1975 1 4.50E-2 0 0 2 0 0 0 9.31 E+1 0 3 2.87E-4 0 0 3.91E+1 0 4 0 0 0- 0 0 0 0 1976 1 0 0 0 2 0 0' O 0 0 3 0 0 0 0 0 4 0 0 0 0 0 0 0 1977 1 0 0 0 8.55E-2 0 2 0 0 0 0 0 3 0 0 4 0 0 0 0 0 0 0 O 1978 1 O O 0' O 2 0 0 0 0 0-3 0 0 0 4 0 0 0 0 0 0 1979- 1 0 0 0 0' 0 0 0 2

0 0 0 0 0 3 0 0 4 0 0 0 0 0 3.77E-3 1.47C-2 0

~

1980 1 0 0 0 0 0 2 0 0 3 0 0 0 0 0 4 0 0 0 0 0 0 0 0 1981 1 3.91C-4 0 4.16E-1 7.80E+1 0 2 8.11C-4 0 1.31E-1 7.26E-1 0 3 0 0 4 2.00E-2 1.44E-1 36 EXFBT is

w,-- _ - -

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i

'$ l TA8tE 2 '(Continued)

RADIOACTIVE LIQU10 EFFLUENT

SUMMARY

(Curies)(1)-

Fission &. Tritium 41ssolved Gross Gases - Alpha Unidentified Year Ocarter Activation H-3 ' __. _

0'.* 0 1 6.40E 4.64E ' 3.610-4 -0 1982 0 0 0

2. 1.05E-3 0 0 5.360-3 3.22E-2 1.41 E-4 3 0 0-4 1.99E-1 6.47E+1 2.27E-3 8.86E-5 0 0.

5.60E-2 6.47 E+1 1983- 1 0 0 0 1.04E-3 1.88E-1 2

4.910-2 1.19 6.68E-4 2.570-3 0 3 0 0 1.53E-1 7.97 4.45C-4 4

2.81E-3 0 0 2.07E-1 4.50 0 1984: 1~

1.78 2.77E-2 0 2 2.29E-1 1.94E-1 1.78E+2 5.19E-3 2.68E-5 0 3 0 0-3.05E-3 1.13E+2 2.6SE ' 4' 0 0 0 2.72C-3 5.60E+1 0

-1985 1 1.22E+1 0 0 2 l'. 55E-3

0 0 1.88E+1 0 3 2.79E-3 0 -

2.96 0 . Q.

4 3.?BE-4 5.27E+1 0 '3.77E-5 0 1986 1 6.29E-4 8.14E-6 0

' -* 2 4.67C-5 7.12E-3 .0 Rancho Seco Semiannual Radioactive Ef fluent Release Reports 'and (1) corrections thereof.

n EXH!BlT is

l l' .

TABLE 3 TOTAL RANCHO SECO t.IQUIO DISCHARGE VOLUME Quarterly Average Total Plant Discharge Flow Rate Gallons _ (callons per minute - com)

Year Quarter Ltters .

2.01E+3 1974 3 1.01E+9 1.12E+9 3.11E+3 4 1.56E+9 3.06E+3 1975 1 1.50E+9 2.97E+3 2 1.47E+9 2.60E+3 3 1.30E+S 1.55C+9 3.13E+3 4 1.57E+9 3.30E+3 1976 1 1.64E+9 1.53E+3 2 7.61E+8 1.44E+3 ,

3 7.23E+4 1.17E+9 2.60E+3 4 1.30E+9 .

1.61E+3 1977 1 7.91 E+8 1.20E+3-2 5.94E+8 1.37E+3 3 6.89E+8 7.89E+8 1.82E+3 4 9.12E+8 1.55E+3 1978 1 7.58E+6 1.11E+3 2 5.49E+4 1.19E+3 4- 5.98E+4 3 2.30E+3 4 1.15E+9 8.08E+8 2.35E+3 1979 1.15E+9 1 2.30E+3 2 1.14E+9

'2.20E+S 3 1.10E+9 1.11C+9 1.59E+3 4 7.96E*4 1.77E+3 1980 1 8.77E+8 2.10E+3 2 1.04E+9 3.03E+3 3 1.52E+9 2.66E+3 4 1.33E+9 1.26C+9 2.49E+3 l 1981 1 1.22E+9 4.77E+3 2.37E+9 l 2 5.43E+3 3 2.73E+9 2.24E+9 4.34E+3 4 2.18E*9 38 EXH B." m '

~ ~

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t TABLE 3 (Continued)

.l TOTAL RANCHO SECO LIQU10 013 CHARGE VOLUME

. Quarterly Avera9e Total Plant Olscharge Flow Rate -

(callons per minute -. com) :

Year Quarter Liters _ Gallons 3.24E+3 1982 1 1.59E+9 3.34E+3 2 1.66E+9 '

2.83E+3

.3 1.42C+9 -

3.24E+3 4 1.62E+9 1.66E+9 3.17E+3 1983 I 1.55E+9 2.43E+3-2 1.20E+9 3.50E+3 3 1.75E+9 4.21E+3 4 2.11E+9 1.75E+9 4.12E+3 1984 1 2.04E+9 6.89E+3 2 3.42E+9 8.29E+3 3 4.16E+9 8.74E+3 4 4.38C+9 1.38E+9 7.50E+3

.1985 1 3.68E+9 3.53E+3 2 1.75E+9 4.03E+3 3 2.02E+9 '5.28t+3 2.65E+9 2,. 67 E+9 4

4.57E+3 1986 1 2.24E+9 .6.85E+3 2 3.40E+9

References:

Rancho Seco Semiannual Radioactive Effluent Release Reports Monthly Central Valley Regional Water Quality Control Board Report F

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TABLE 10 FAP!gj (area /C1)

Fission and Activation Products including lodine Dose Factor k Total Liver Body Thyroid Kidnev lyurLq . gjl Skin _ Bone Adult 7.39E+00 1.36E+02 2.53E+02 1.92E+02 3.39E+02 9.6BE+01. 3.29E 3.

Teenager 7.39.C-41 1.36E+02 .2.49E+02 1.08E+02 4.51E+02 9.59E+01 -3.12E+01 Child 1.03E-01 3.59E+02 4.64E+02 9.61E+01 9.09E+02 1.74E+02 ' 5.17E TABLE 11 Tgj (arem/C1) o Tritium Dose Factor Total tiver Body Thyroid Kidnev {

Skin- Bone Adult 0.0 0.0 4.16E-02 4.16E-02 4.16E-02 4.16E-02 4.16E-02 e Teenager 0.0 0.0 4.69E-02 4.69E-0Z 4.69E-02 4.69E-02 4. 69 E-02 e Child 0.0 0.0 7.31E-02 7.31E-02 7.31E-02 7.31E-02 7.31E-02 '1 4

EXEBLT g =

l' l:;

1 '.

TA8LC 12 DISTRIBUTION OF CALCULATE 0 00$C TO

(-

THE- AOULT TOTAL 800Y (1)

T of Total % Cetius Contribution, Pathway 72.8 ' , 99.9

.i Fish 0.43 34.3 Invertebrate. 93.7 Shoreline 3.29 0.0085 51.7 Swinning 98.8 Vegetatton 16.0 6.76 98.4 Milt-0.82- 97.7-

-Heat

- 100.0- 99.2 TOTAL (1) .. Tritium not included in evaluation.

TABLE 13 DISTRIBUTION OF CALCULATED 00SE TO THE CHILD LIVER (1)

% of Total % Cesium Contribution Pathway 64.4 99.8 Fish 0.68 32.5 Invertebrate 93.7 Shoreline 0.019 0.0035 51.7 Swiming 98.5 Vegetation 23.7 10.8 97.4 Hilt 0.45 97.3 Heat 100.0 98.8 TOTAL (1) Tritium not included in evaluation.

47

? . . . .

6 -'

l TA8ti 14 l

DISTRIBUTION OF CALCUt.ATED 00SC TO THE CHILD THYROIO(1)

Pathway % of Total- % Iodine-131 Contribution

'12.8 . 98.5 Fish 0.485 41.1 Invertebrate 0.0097 0.482 Shoreline 0.0018 33.1 Swiming 100.0 Vegetation 49.2 37.1 99.9 Milk 99.6 Heat 0.514 100.0 63.2 TOTAL (1) Tritium not included in evaluation.

="..

te

,, EX-IBIT -

L- TA8LE 15

~

RANCHO SEC.0 SITE LIQUID EFFLUENT PATifWAY Usage Parameters Uap Maximum Exposed Individual Units Infant Child Teenager <

Pathway l

Kg/yr 0 21 - 21 Freshwater Fish .

Kg/yr 0 1 1

. Freshwater Invertebrate L/yr 0 0 0 Orinking Water 0 14 100 Shoreline Deposits br/yr hr/yr 0 100 100

' Swiming 0 0 0-hr/yr Boating.

Irrigated foods 0 520 630 Fruits, Vegetables, Grain Kg/yr Kg/yr 0 0 0 Leafy Yegetables 330 400 t/yr 0 Milk Kg/yr 0 41 65 Meat. Poultry Average Exposed Indlyidual.

General Public .

~ .

Kg/yr 0 2.2 5.2 Freshwater Fish Kg/yr. 0 0.33 0.75 Freshwater Invertebrate 260 260

%;- Drinking Water t/yr hr/yr 0

0 9.5 47 Shoreline Deposits 0 9.5 47 hr/yr Swiming 0 9.5 41 Boating br/yr Irrigated Foods 0 200 240 fruits, Vegetables, Grain Kg/yr Kg/yr 0 10 20 Leafy Vegetables 0 170 200

- t/yr Milk Kg/yr 0 37 59 Heat, Poultry e

O 49

XI 3"

'9 15 co . .

a

- . - '2- ,

' ' ' RANCHO SECO SITE LIQUID EFFLUENT PATHWAY Dilution Factors (reciprocal of Mp. )-

' ' Maximum Exposed Individual

~

Maximum Exposed Individual Quarter.1- Quarter 5 - Quarter 3 -Qua-4 1 1 1 Freshwater Fish . .

1 -1 1-1 Freshwater Invertebrate - - - -

' Crinking Water 1

-1 Shoreline. Deposits. 1 1- 1- 1 Swimming - --

Boating ..

Irrigated Foods _.

l' Fruits, Vegetables, Grain 1

.1 Leafy Vegetables 1 Milk .1- ~

1 1 1 Meat, Poultry 1

. Average' Exposed Individual General Public .

9 1000 100 100 1C-Freshwater Fish 1000 100 100 IC

" ' * ' ' Freshwater Invertebrate 100 100 if Drinking Water 1000 1000 100 100 1C Shoreline Deposits 100 - IC' 1000 100 Swi ming 100 .1C 1000 100 Boating Irrigated Foods 100 100 if Fruits, Vegetables, Grain 1000 1000 100 100 1 Leafy Vegetables 100 1 1000 100 Milk 100' 100 1 Meat. Poultry 1000 L

s0 EXHIBIT ts

l TABLE 15(Continued)

L RANCHO SECO SITE LIQUID EFFLUENT PATHWAY Tiime Parameters (hours)

Maximus Average Exposed Exposed - General l

Individual Individual Public Pathway 24 168 24 Freshwater Fish 24 24 240 Freshwater Invertebrate - 12 , 24 Orinking Water 0 0 Shoreline Deposits 0 0 0 0 Swi ming - 0 0 Boating Irrigated Foods 336 1440 1440 Fruits. .Yegetables. Grain - 48 48

t.eafy Vegetables ~ -96 96 48 Milk 480 480 480 Heat.. Poultry 96 __.- 96 Release Holdup and 72 ..

- Transit Time .

%*w e

b 15 51 XHl37- -

. L% ., <?> 2, r,.n

{' . e-l: .. ..

TABLE 15.(Continued)

RANCHO SECO SITE

LIQUID EFFLUENT PATHWAY l' Irrigated Foods Parameters Non- Nc Irrigation Crop Growing. Irrigated Ir:

Rate Yield Period Feed W (t/m2 /month) (Kg/m2) (days) Fraction . Fr

. Fruits, Vegetables, Grain ,263. 2.0 60 Leafy Vegetables 263 2.0 90 263 1.4 30 0 Milk 1.4 30 0 Meat, Poul+,ry 260 ,

TA8LE 2.3-5 RANCHO SECO SITE LIQUID EFFLUENT PATHWAY ,

- Anin&1 Consumption Rates Feed or Forage Water .

Qp (Kg/ day) QW A

(t/ day) .

50 60 Milk Cow 50 50

+ 8eef Cattle is EXHIBIT ,, ,,

.. . . . . .. ..... . . .. ......~...... . . .. .. ..... . . . . . .

4 TABLE ~16 TANK 10 CURIE LIMIT ANALYSIS (mres)

Maximum Hypothetical Individual.

Pathway Adu1_t. Teenacer Child Fish 1.75E42 1.34E402 1.28E+02 Invertebrate 1.22Edo 1.41E400 3'.19E40 Drinking 7.81E-03 4.62E-43 5.88E-43 Shoreline 4.98E+00 9.23E-01 1.29E-01 Swimr41n9 2.37E4 2 2.37E-02 2.37E-D2 Irrigation Vegetation 2.35E+01 2.16E+01 1.66C+01 Leafy Yegetables 3.11 E+00 1.58E+00 '9.66E-01

. Milk 9.99E400 9.86E+00 7.79E+00 Heat 3.15E+00 1.42E+00 8.68E-01 Total 2.21E+02 1.71E+02 1.58E42 b

4

" 15 EXHl3~

{

e l

ENCIDSURE II LIST OF REFERENCES ,

Note: The highlighted (*) references are included as Enclosure III.

(1) Rancho Seco Nuclear Generating Station, Updated Safety Analysis Report, Amendment 4 (not attached).

(2) Bechtel Drawing No. C-101, Revision 8, Sita Plan.

(3) California Regional Water Quality control Board, Central Valley Region Order No.85-210, Waste Discharge Requirements for SMUD Rancho Seco Nuclear Generating Station Unit 1.

(Board Transmittal August 30, 1985).

(4) United States Department of the Interior Geological Survey, Drawn January 1985, Galt Irrigation District Laguna Creek Water Users.

(5) Final Environmental Statement related to operations of Rancho Seco Nuclear Generating Station Unit 1, US AEC, March 1973.

(6) Appendix I Evaluation Report Rancho Seco Nuclear Generating Station, TERA Corporation, June 1, 1976. (District to NRC Transmittal , June 4, 1976.) (District to NRC Transmittal, November 29, 1976.)

(7) Rancho Seco Liquid Effluent Pathway, Aquatic and Terrestrial Dietary Survey Report, UCID-20267. Lawrence Livermore National Laboratory, November 30, 1984. (District to NRC transmittal November 30, 1984.)

(8) District to NRC transmittal December 31, 1984.

a) ConcentrationsofofRancho Radionuclides in Fresh Seco Nuclear Water Plant, Generating Fish UCID-Downstream 20295, Lawrence Livermore National Laboratory, December 27, 1984.

b) Radionuclides in Sediments Rancho Seco Nuclear Power Collected GeneratingDownstream from the Station, UCID-20298 (final draft), Lawrence Livermore National Laboratory.

(Final report transmitted to the NRC, February 13, 1985.)

c) Evaluation of Environmental Impact on Man. Best Estimates of the Radiological Dose via Fish Ingestion and Shoreline Erposure. (Attachment B).

EXFBT e -

/o 49 - .

1 h

(9) District to NRC transmittal, February 28, 1985. Special-Report .No. 85-01, Fuel Cycle Dose Evaluation on Family "Z 3".

(10) District to NRC transmittal ~ March 15, 1985,- Ranchk Seco .' Liquid'~

Effluent Pathway Usage Survey Report.

(11). Environmental Radiological Studies Downstream' from Rancho seco -

Nuclear Power -Generating Station. UCID 20367, Lawrence Livermore National Laboratory, March 22, 1985.- (District to NRC transmittal April 1, .1985).

(12) District to NRC transmittal, June 5, 1985. Special Report No.

85-05, Uranium Fuel Cycle Dose Evaluation on Family "Z 10".

t *(13) -Environmental Radiological Studies Downstream from the Rancho Seco Nuclear Power Generating Station,1985, UCID 20641 Parts 1 and 2, Lawrence Livermore National Laboratory, February 6,

-1986.

(District to NRC transmittal, February 28, 1986.)

(14) Effluent Release Reports (1974-1986).

(15) Procedure AP.305-13 (Environmental Releases of Liquid .

Radioactivity) (Complete Revision History).

w *(16) Count Room Manual and other counting equipment procedures.

(17) Procedure AP.306-III (Sampling Points, Analyses Required, Frequency and Specification Invels).

(18) Other Plant Procedures dealing with Sampling and Liquid Systems.

(19) AP.310 Off-Site Dose Calculation Manual (ODCN) (Liquid' Effluent related sections).

(20) Occurrence Description Reports.

(21) Computer compilation of Release Permit Data, October 14, 1974-through October 28, 1986.

(22) NWT Corporation, System chemistry Trends, 1984.

(23) Rancho Seco Nuclear Generating Station Unit No. 1 Final Safety Analysis Report, February 14, 1975 (through Amendment No. 29.)

(24) Rancho Seco Nuclear Generating Station Unit No. 1.

Environmental Report, Nay 18, 1975: Amendment 1, November 10, 1971; Amendment 2, June 30, 1972; Supplement 1, June 30, 1972; Additional Information, April 20,1972; Additional Information, September 28, 1972.

ss EXHl3 I /s

n. 49 .. 97 e--.

(25) Rancho Seco Nuclear Generating' Station, Systems Training Manual.

(26) NUREG/CR-1276, IADTAP Computer Run dated November'6,1986. .

(27) NUREG/CR-1276, IADTAP Computer Run dated November 13, 1986.

O O

O

'Ji e

9

+

56 gC X' L. .?

3 ,,I C . '

.__ 15. _ .._ -

e*

.________________m__.m. _ _ __.__ _ _ _ _ _ . _ . _ _ . _ . _ _ _ _

t ATTAODENT MEETING AGENDA OI INQUIRY ,-

December 3, 1986 TIME W PIC -DISCUSSION LEADER 1* gh M/ h-11:00 AM . Question 3 - Effluent Pathways Fl Bradley-Question 7 - Radiological Consequences 11:20 AM #

Question 2 - Effluent Contaminants'

- Fred Kellie Question'4 -. Program'for Identifying Radioactive-Mater 3als in Liquid Effluents Question 6 - Planned and Unplanned Radioactive Releases .

11:40 AM Question 1 - Water Sources Bob Wichert 11:50 AM Question 5 - Planned and Unplanned Modifications Bob Little 12:00 PM- Open Discussion

T & R Building, 5th Floor Conference Room, 11 - 12.

y # Q& 3 % W A% O Snb l

i I

L ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _

TX- B T

.it

.y...... .....- - -- .....- wa. - ~-l (Cl/ month) 0.C 4 0.035

{

O.03 i f O.025 2

E

'! D.C2 *

) 0.01 5 0

0.01

- 4) 0 --p ; 5 w * * * * * * '

g 75 Wof-77 Wof-81 C~b 142 nth 0 Cs-134 (CJ/rnenth) + Co-137 (Ci/ month)

Cesium Release Amounts (Ci/ quarter)

(Achd W. MM ,

1.3 pgmu t.;mit (M1 owed pe Q&) -

1.2 -

1.1 -

^

] 1-B 0.9 -

h I O.8 - '

o ,

I. D.7 -

2 e 0. 6 - ,

b

,3 0. 5 - '

l l

d 0.4 -

f e-0.3 -

l. c.2 -

! o.1 - .

x- E '

g 7 9 Y O -Q Q Y Y

~

Dec-81 sep-75 W */~

642 nth

+ Cs-137 (Ci d'3.. ._ 5 D Cs-134 (Ci/ month) ,

L__________________..______________._

L- . D.06 0.05 7.

l l' ]. C.04 1 1

$ D.03 y ,

I +

0 .

b li

$ O.02 +

l m 0.01 0 D $g7N~ viiieivi~T, iaiiieiieiii T#W99HHHNMtiM@fHlHP94HHtil An-83 Jan -84 An-85 kn-86 kn-82 Month C Co-134 (Ci/ month)

+ Co-137 (Ci/ month)

Cesium Release Amounts (Ci/ quarter)

(Actual w. Me-ed) 1.3 .

1.2 - Rol*3*e Umt (AJbwed per Qisarter) -

1.1 -

9 1-o j 0.9 -

I o.s -

9 I 0.7 -

I O.6 -

{

! o.5 -

$ O. 4 -

2

% 0.3 -

r O.2 -

0.1 -

0 0;QQ WQQSQ77Q;@Qs;;g I fTiQGi777@77777777GPQsiiGPQO Jon-83 Jor4-64 An-85 Jon-86 son-E2 Month

+ Cs-137 (C tO O Cs-134 (Ci/ month)

(

. The equipment installed in the liquid radioactive waste system shall be l maintained and shall be operated to process radioactive liquid wastes prior i to their discharEe when the projected cumulative release rate will exceed i

1.25 Ci/ reactor / calendar quarter, excluding tritium and dissolved gases.

The annual total quantity of radioactive materials in' liquid waste, excluding tritium and dissolved gases, discharged from cach reactor should not exceed 5 Ci.

The release-rate of radioactive materials in liquid wastes, excluding tritium and dissolved gases, shall not exceed 10 C1/ reactor / calendar quarter.

The. release rate of radioactive materials in liquid vastes, excluding tritium and' dissolved gases, shall not exceed 20 C1/ reactor in any 12 consecutive months.

During release of radioactive wastes, the. effluent control monitor shall be set to alarm and to initiate the automatic closure of the waste discharge valve prior to exceeding the limits specified in 2.6.1.a above. .

t EX48T e m,, ,. ,

Tritium Release l Amo'unts- (Ci/ month)'

90-80 70 0 D

'j 60 I ' -

j so n ..

2 f 40 i

30 (I o R

20- u in g

I G O O mi37..d -

kn-82 kn-83

\~

,imiirw-c,aiiisenii An-84 kn-E Wu isniinvariiwi1.ar;+,,..

An-86 75 5/81 Wordh D H-3 (Ci Resow) 9 e

g

u Pro,iected Dose Frcm Liquids

@dJt Y. hob Body}

'130-120 - -

1DCTF2D .!500 mP/y}

11D -

1DD -

90 -

' r. .CD - g .,-

h E y' 70 -

v i,0 '

g BD - y b' SD -

4D _ 9-3D - 'E 2D -

l- 2. l 10 - P k ,j l

D- , r , w ww v w w r v9N9999N Y E Q h , . 7 . . i,,

1E74- 1975 '1978 1977. 1972 197B 1EBD 1GD1 1852 1983 1924 1985 1928

%or and hair EXHIBIT .m'S .. _

_ _ _ _ - _ _ - - _

v t e Letter Sequence Other
TAC:64735, (Approved, Closed)
Initiation Request, Request, Request Acceptance... Supplement, Supplement Administration Meeting, Meeting, Meeting, Meeting, Meeting Questions Answers Results Approval Other: ML20147C490, ML20149E859, ML20151B320, ML20155D675, ML20197B030, ML20199B161, ML20204F596, ML20210R060, ML20211B406, ML20211B442, ML20212H574, ML20212H582, ML20214E205, ML20214L960, ML20215H383, ML20215H397, ML20234F422, ML20235R405, ML20235R426, ML20236D305, ML20236D319, ML20236P920, ML20245E060, ML20245E067
MONTHYEAR1987-10-20 [Table View]

ML20245E067

Text

Enclosures:

References:

SUMMARY

SUMMARY

References:

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