ML20151U345

Advises That Util Should Continue to Perform Releases from Reactor Bldg Sump by Batch Method to Comply w/10CFR20

ML20151U345
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/11/1988
From:	Heitner K Office of Nuclear Reactor Regulation
To:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
References
TAC-61580, NUDOCS 8808190045
Download: ML20151U345 (4)

Text

- . August 11, 1938 -

Docket No. 50-267 Mr. ' R. O. Williams, Jr.

Vice President, Nuclear Operations Public Service Company of Colorado ,

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Post Office Box 840 Denver, Colorado 80201-0840

SUBJECT:

REACTOR BUILDING SUPP IN-LINE BETA MONITORING SYSTE.

(TACNO.61580)

On July 20, 1984, a liquid release from the Reactor Building Sump exceeded the Maximum Permissible Concentration for unknown beta emitters. As a result of this event, Public Service cemitted to the following two actions. Firs t ,

Public Service was to perfonn all liquid releases from the Reactor Building Sump in the batch mode and sarple and analyze the surp contents prior to and during each release. Second, Public Service was to investigate the feasibility of installing an in-line beta-sensitive effluent monitor on the Reactor Building effluent discharge line to permit continuous monitored effluent discharges. A beta monitoring system was developed and was tested and evaluated for o 12-month period. During that time a number of prcblems with the equirnnt and quality of the water in the Reactor Building Sump were encountered. Attempts to resolve these problems have been unsuccessful.

After a review of Public Service's efforts to design and install an in-line beta monitoring system for the Reactor Building Sump, it appears such a sy: tem is not feasible for implementation at Fort St. Vrain. In light of this, Public Service is to continue to perform releases from the Reactor Building Sump by the batch method and sample and analyze surp contents prior to a release and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the release. The NRC considers this to be an acceptable approach for demonstrating :0mpliance with 10 CFR Part 20 limits.

Sincerely,

/s/

Kenneth L. Heitner, Project Manager Project Directorate - IV Division of Reactor Projects - III.

IV, Y and Special Projects cc: See next page DISTRIBUTION

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. . August 11, 1988 e s .

Docket No. 50-267 Mr. R. O. Williams, Jr.

Vice President, Nuclear Operations l Public Service Company of Colorado Post Office Box 840 l Denver, Colorado 80201-0340 I

SUBJECT:

REACTOR BUILDING SUMP IN-LINE BETA MONITORING SYSTEM (TACNO.61580)

On July 20, 1984, a liquid release from the Reactor Building Sump exceeded the i Maximum Permissible Corcentration for unknown beta emittcrs. As a result of l this event, Public Service comitted to the following two actions. First,  !

Public Service was to perfonn all liquid releases from the Reactor Building Sump in the batch mode and sarple and analyze the sump contents prior to and l during aach release. Second, Public Service was to investigate the feasibility 1 of installing an in-line beta-sensitive effluent monitor on the Reactor Building  !

effluent discharge Ifne to pennit continuous monitored effluent discharges. A j beta monitoring system was developed and was tested and evaluated for a 12-month l

period. Du-ing that time a number of problems with the ecuipment and quality of the water in the Reactor Building Sump were encountered. Attempts to resolve these problems have been unsuccessful.

After a review of Public Service's efforts to design and install an in-line beta monitoring system for the Reac'.or Building Sump, it appears such a system is not feasible for implementation at Fort St. Vrain. 'n light of this, Public Service is to continue to perform releases from the Reactor Building Sump by the batch method and sample and analyze surp contents prior to a release and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the release. The NRC considers this to be an acceptable approach for demonstrating cor.pliance with 10 CFR Part 20 limits.

Sincerely,

/s/

Kenneth L. Heitner, Project Manager 1 Project Directorate - IV l Division of Reactor Projects - III, l IV, Y and Special % jects  !

cc: See next page l DISTRIBUTION ~

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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 August 11, 1988

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Docket No. 50-267 Mr. R. O. Williams, Jr.

Vice President, Nuclear Operations Public Service Company of Colorado i Post Office Box 840

' Denver, Co1orado 80201-0840

SUBJECT:

REACTOR Bull'"% SUMP IN-LINE BETA MONITORING SYSTEM (TACNO.(>

Ca July 20, 1984, a liquid release from the Reactor Building Sump exceeded the Maximum Permissible Concentration for unknown beta emitters. As a result of this event Public Service connitted to the following two actions. First, l Public Eervice was to perfonn all liquid releases from the Reactor Building  :

Sump in the batch mode and sample and analyze the susp contents prior to and  !

during each release. Second, Public Service was to investigate the feasibility l of installing an in-line beta-sensitive effluent ronitor on the Reactor Building effluent discharge line to pemit continuous monitored effluent discharges. A beta monitoring system was developed and was tested and evaluated for a 12-month period. During that time a number of problems with the equipment and quality of the water in the Reactor Building Sump were encountered. Attempts to resolve these problems have been unsuccessful.

After a review of Public Service's efforts to design and install an in-line beta monitoring system for the Reactor Building Sump, it appears such a system is not feasible for implementation at Fort St. Vrain. In light of this, Public Service is to continue to perfonn releases from the Reactor Building Sump by i the batch method and sample and analyze sump contents prior to a release and i every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the rtlease. The NRC considers this to be an acceptable i spproach for demonstrating compliance with 10 CFR Part 20 limits. 1 Sincerely, i

ws.h '

, Kenneth L. Heitner, Project Manager Project Directorate - IV Division of Resctor Projects - III,

! IV, Y and Special Projects i

cc: See next page 1

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2 Mr. R. O Williams, Jr. I Public Service Company of Colorado Fort St. Vrain cc:

Mr. D. W. Warembourg. Manager Albert J. Hazle Director Nuclear Engineering Division Radiation Control Division Public Service Company Departnant of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201-0840 Mr. Daviri Alberstein, 14/159A Mr. R. O. Williams, Jr., Acting Manager GA Technologies Inc. Nuclear Production Division Post Office Box 85608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr. P. F. Tomlinson, Manager Public Service Comrany of Colorado Quality Assurance Division P. O. Box 840 Public Service Company of Colorado Denver, Colorado 80201-0840 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Connission Mr. R. F. Walker P. O. Box 640 Public Service Company of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 80201-0840 Kelley, Stansfield & 0'Donnell Public Service Company Building Commitment Co9 trol Program Room 900 Coordinator 550 15th Street Pubite Service "ompany of Colorado Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-D Denver, Colorado 80211 Regional Administrator, Region IV.,

U.S. Nuclear Regulatory Comission i n xa El l Chairman, Board of County Comissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiatien Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colorado 80202-2413

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