ML19339B830

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Std Order for DOE Work, Source Term Measurements, Issued to Inel
ML19339B830
Person / Time
Issue date: 10/16/1980
From: Arsenault F
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
Shared Package
ML19339B827 List:
References
CON-FIN-A-6075-1 NUDOCS 8011100232
Download: ML19339B830 (3)


Text

L NRC Fonu 173 u s Nucts an at GutaTom v couusssioN osotnNuwata 2 7si 60-81-018 G

STANDARD ORDER FOR DOE WORK DCT1C(03; ISSUED TO (DOE Office)

ISSUE D BY; (NRC Of fice)

ACCOUNTING CITATION Idaho Operations Office Division of Safeguards, Fuel

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3 Cycle & Environmental Research

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60190230 PERFORMING ORGANIZATION AND LOCATION FIN NUMBE R Idaho National Engineering Laboratory A6075-1 WOR K PERIOD. THIS ORDER FIN TITLE FIXED 0

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FROM.

TO.

Source Tenn Measurements 10/01/80 09/30/81 OBLIGATION AVAILABILITY FROVIDED BY:

A. THIS ORDER S

317,000 8.

TOTAL OF ORDERS PL ACED PRIOR TO THIS DATE WITH THE PERFORMING ORG ANIZ ATION

"'A 1 N M

L" AND THE FIRST FOUR DIGITS OF THE S

'EN"N 70,483,000 E

Cl E

C. TOTAL ORDERS TO DATE (TOTAL A & B) 5 70,800,000 D. AMOUNT INCLUDED IN "C" APPLICABLE TO THE " FIN NUMBE R" CITED IN THIS OR DE R.

S 317,000 FINANCIAL FLEXtBILITY:

C FUNDS WILL NOT BE REPROGR AMMED BETWEEN FINS. LINE D CONSTITUTES A LIMITATION ON OBLIGATIONS

' AUTHORIZED.

@ FUNDS MAY BE REPROGRAMMED NOT TO EXCEED 210% OF FIN LEVEL UP TO S50K. LINE C CONSTITUTES A LIMITATION ON OBLIGATIONS AUTHORIZED.

STANDARD TERMS AND CONDITIONS PRoVIDED DOE ARE CONSIDERED PART OF THIS ORDER UNLESS OTHERWISE NOTED.

. ATTACHMENTS:

THE FOLLOWING ATTACHMENTS ARE HEREBY SECURITY; MADE A PART OF THIS ORDER:

O WORK ON THIS ORDER IS NOT CLASSIFIED.

@ STATEMENT OF WOR K O WORK ON THIS ORDER INVOLVES CLASSIFIED D ADDITIONALTERMS AND CONDITIONS INFORMATION. NRC FORM 187 IS ATTACHED.

O OTHER

"'"*"*S; Final work packages (189a's) reflecting approved FY 1981 resources and scope should be furnished within 60 days. Five copies should be sent to the Office of Nuclear Regulatory Research and one copy to the NRC Controller.

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l$sUINf AUTHORfTY ACCEPTING ORGANIZATION h%. -[ dg SIG N AT U R E SIGNATURE Frank J. APsWaultED1 rector Division!Of Safegu6rds, Fuel Cycle TITLE TITLE r and Entronmenta'l Research i DAM NRCFORM1 78) 80,3799 lY

SAFiR PROJECT BRIEF TITLE: Source Term Measurements FIN NO.: A6075 CONTRACTOR:

INEL RES LEAD BRANCH:

Systems Performance Research Branch SITE:

INEL STATE:

Idaho RES PROJECT MANAGER:

D. E. Solberg PRINCIPAL INVESTIGATOR:

PERIOD OF WORK:

9/1/80 - 9/30/81 J. W. Mandler FY 1981 OBLIG: $317K BUDGET ACTIVITY:

60190230 The princinal objective of the project is to obtain radionuclide source term data at operating PWRs. Specific objectives are:

(1) Obtain radionuclide source term data for improvement of gaseous and liquid effluent models for LWRs.

(2) Evaluate the source term data on the basis of known plant design and operational information.

(3) Provide a data base for evaluating system design improvements for new plants.

(4) Develop and test improved source term measurementstechniques.

(5) Provide technical support to NRC.

SCOPE:

Perform radionuclide measurements in liquid, gaseous and solid systems in six operating commercial PWRs to be selected by the NRC. Evaluate the data obtained using information about plant design and operation and knowledge of the sampling and measurement uncertainties.

GUIDANCE FOR FY 1981:

Conduct research described in 189a dated May,1980 and as sumarized below:

Prepare a measurement plan for the Prairie Island Plant based on plant design, available measurement locations, conclusions of the interim report of measure-ments at the four prior plants and the expressed needs of NRC. Move the mobile laboratory to the Prairie Island Plant, complete measurements agreeable to NRC, INEL and Northern States Power and perform data evaluation.

Initiate prperation of a draft report on measurement results from Prairie Island.

Measurement data should generally be in the following areas, (1) Radioisotope t sncentration in all plant systems from the primary coolant systems to release points to the environment.

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. A6075 (2) Performance of the radwaste, process gas and containment systems.

(3) Characterization of waste solidification system input.

(4) Characterization of primary to secondary system leakage and transport of the fission products through the system.

(5) As available, measurement and characterization of crud in primary coolant samples, particularly associated with transient

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reactor operation.

Complete the interim report, the Rancho Seco measurements report and a topical report on radionuclide buildup and transport in LWRs.

Submit monthly progress letters summarizing (1) the significant project-activities and accomplishments, (2) providing the spending level for this current month, cumulative spending level for the fiscal year and funds

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remaining and (3) identifying and expected changes in future milestones.

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