ML18019A274

Provides Addl Info Re Offsite Dose Calculation Manual Submitted on 850831,per 850404 Request.Setpoint Calculation for Normal Svc Water Monitor,Basis for External Radiation Value & Direct Radiation Dose Estimates Provided

ML18019A274
Person / Time
Site:	Harris
Issue date:	07/01/1985
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NLS-85-226, NUDOCS 8507160410
Download: ML18019A274 (12)

Text

REGULA

'f INFORMATION DISTRIBUTIOI

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ACCESSION NBR 850716041 0

DOC ~ DATE o 85/07/0]

NOTARIZED NO'OCKET'ACIL:50-400 Shearon Harris Nuclear Power Plantr Unit 1< Carolina 05000400 AUTH ~NAME, AUTHOR AFFILIATION ZIMMERMANES.R, Carolina Power 8 Light Co ~

REC IP ~ NAME RECIPIENT AFF IL'IATION DENTONEH ~ RE Office of Nuclear Reactor Regulationi Director

SUBJECT:

Provides addi info re offsite dose calcualtion manual submitted on 850831<per 850404 request+Setpoint calculation for normal svc water monitorEbasis for external radiation value 5 direct radiation dose estimates pl ovided, DISTRIBUTION CODE:

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TITLE: OR/Licensing Submittal:

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Carolina Power 8 Light Company JUL 01 1985 SERIAL: NLS-85-226 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.

1 DOCKET NO.50-000 OFFSITE DOSE CALCULATIONMODEL

REFERENCE:

Letter from George W. Knighton (NRC) to Mr. E. E. Utley (CPRL) dated April0, 1985.

Dear Mr. Denton:

The referenced letter transmitted a request for additional information in regard to the Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual that was submitted to you on August 31, 1980. Carolina Power R Light provides responses to your request for additional information in Enclosure 1.

If you have any questions, please contact Mr. Gregg A. Sinders at (919) 836-8168.

Yours very truly, GAS/crs (1609GAS)

Enclosure S. R.

im erman ager Nuclear Licensing Section cct Mr. B. C. Buckley (NRC)

Mr. G. F. Maxwell (NRC-SHNPP)

Mr. Tin Mo (NRC-RAB)

Dr. J. Nelson Grace (NRC-RII)

Mr. Travis Payne (KUDZU)

Mr. Daniel F. Read (CHANGE/ELP)

Wake County, Public Library Mr. Wells Eddleman Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)

Dr. J. H. Carpenter (ASLB)

Mr. J. L. Kelley (ASLB) 85071S0O>0 S5070>

PDR ADOCK 05000400 A

PDR 411 Fayettevilte Street o P. O. Box 1551 o Raleigh, N. C. 27602

ENCLOSURE 1

RESPONSES TO U. S. NUCLEAR REGULATORY COMMISSION REQUEST FOR ADDITIONALINFORMATIONIN REGARD TO THE SHEARON HARRIS NUCLEAR POWER PLANT (SHNPP) OFF-SITE DOSE CALCULATIONMANUAL(ODCM)

Comment 1:

Although the Applicant indicated that the normal service water (NSW) is monitored and covered by T/S 3.3.3.0, the Applicant has not provided a setpoint calculation of such a monitor. Also, the Applicant's Figure 2.1-2 does not show such a flow path in the flow stream diagram.

Provide the setpoint calculation for the NSW monitor, and revise Figure 2.1-2 as appropriate.

~Ree once:

The setpoint for the normal service water (NSW) monitors willbe determined by either of the two methods listed below:

Method 1 - This method determines the alarm setpoint using the following formula:

2~~Rbk MDC 2T sensitivity where:

MDC cpm Sensitivity Minimum detectable concentration for a given isotope (11Ci/ml).

Ambient cpm + (mR/hrbkg ~ cpm/mR/hr).

Time constant of signal processor in minutes (a function of cpmbkg).

For selected isotope (cpm/pCi/ml).

Method 2 This method determines the alarm setpoint as 2 x background.

This latter technique is acceptable from an effluent release standpoint because NSW is not discharged directly to the environment and it undergoes significant dilution in the cooling tower basin.

Downstream monitoring for ODCM effluent accountability purposes is provided by the continuous grab sampler in the cooling tower blowdown.

The methods listed above willbe incorporated into the ODCM. To show the NSW flow paths, Figure 2.1-3 entitled "Normal Service Water Flow Diagram" willbe added to the ODCM. The diagram is included here as Attachment l.

(1649GAS/cr s )

ATTACHMENT1 Fl, E 2.1-3 NORMALSERVICE WAT

. FLOW DIAGRAM NSW REACTOR AUXILIARYBUILDING

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For detsiled flowdrawing of Service Water System refer to FSAR Figure 9.2.1-1 HARRIS LAKE COOLING TOWER BLOWDOWN

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Comment 2:

Under Assumption (0), the Applicant stated, "To sum numbers represented as less than

(<), use the value of the largest number in the group (i.e., <5+<1+<1+<3+ = <5) [sic]."

Provide the basis for this assumption.

~Res nse:

Should the technical specifications as stated in Section 6.1 of the ODCM be exceeded, it is the purpose of Chapter 6.0 to evaluate compliance with 00 CFR 190 on as realistic a basis as possible.

Since a total dose estimate must be obtained, the process willrequire the summation of dose from several dose pathways; and for each pathway, a series of numbers may also require summation.

In each of these processes, measurements may provide values that are less than the lower limitof detection (LLD)for the analytical system.

- From the theory of analytical sensitivity (see NCRP-58 1978), it is conceivable that the < LLDvalues actually range from negative numbers to the LLD itself. Clearly, if zero or negative numbers are used in the dose estimate processes, it would bias the results in a nonconservative manner.

Similarly, if the LLDvalue is used, an overly conservative bias may result. Assumption (0) provides a reasonable "middle course" that seeks to eliminate unnecessary bias in either nonconservative or overly conservative directions.

(1649GAS/crs )

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Comment 3:

Under Applicant's Step (I), the Applicant stated that the direct radiation dose at the plant boundary in each sector willbe determined.

The Applicant, however, has not indicated by what method this direct radiation dose willbe obtained.

Provide the method for estimating doses from direct radiation.

~Res nse:

It is the Applicant's intention to evaluate the direct radiation dose at the site boundary in both the preoperational and operational phases of the plant. Measurements willbe performed with pressurized ionization chambers or equivalent devices.

Measurements willbe performed at the same locations in each phase to discern the direct radiation contribution from plant operation. After these baseline values are obtained, the in-place thermoluminescent detector (TLD) network willbe relied upon to indicate any upward trends in direct radiation. If a significant increase is observed in the direct radiation intensity, it willbe reevaluated utilizing the method described above.

(1649GAS/crs)

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Comment 0:

The Applicant stated that dose from other fuel cycle sources willbe treated as

< 1 mrem/yr. Provide the basis for this statement.

~Res nse:

There are no other uranium fuel cycle sources within a 50-mile radius of SHNPP as defined in 00 CFR l90. Thus, the <

1 mrem figure would be reasonable.

(1649GAS/crs

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