ML14192A607

Forwards Revised Initial Draft Guidance Re Scaling Factors for Irradiated Components,Incorporating Comments from Nmss. Original Needs Expressed in Satisfied & Review Terminated.W/O Encl

ML14192A607
Person / Time
Site:	Brunswick, Robinson, 05000000
Issue date:	03/05/1985
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Utley E CAROLINA POWER & LIGHT CO.
References
NUDOCS 8503220297
Download: ML14192A607 (8)

Text

March 5, 1985 Docket Nos. 50-261, DISTRIBUTION:

50-325 Docket File SNorris and 50-324 NRC PDR MGrotenhuis Local PDR ORB#2 Gray File ORB#2 Reading GRequa Mr. E. E. Utley HThompson, Jr.

SVarga Executive Vice President EJordan CParrish Carolina Power & Light Company BGrimes ORB#1 Reading Post Office Box 1551 JPartlow ORB#1 Gray File Raleigh, North Carolina 27062 ACRS-10 OELD CNichols

SUBJECT:

10 CFR PART 61 SCALING FACTORS FOR IRRADIATED COMPONENTS Re:

H. B. Robinson Steam Electric.Plant, Unit 2 Brunswick Steam Electric Plant, Units 1 and 2 By letter dated February 2, 1984, CP&L presented the methods intended for use in obtaining scaling factors for waste streams. By letter dated April 20, 1984 we sent you an evaluation for the waste oil solidified and in storage at the H. B. Robinson Plant. At that time we understood that your staff would use the NRC Low-Level Waste Licensing Branch Technical Positions for obtaining scaling factors.

By letter dated May 22, 1984, we enclosed initial draft guidance which we believed would help CP&L in considering possible amendments to their proposed methods for obtaining scaling factors for irradiated components.

We have recently revised this guidance to incorporate comments from the Office of Nuclear Material Safety and Safeguards and to provide more clarity. We enclose that revised guidance for your future use.

We understand from your staff that the original needs expressed in your letter dated February 2, 1984 have been satisfied and we are terminating our review of that request.

Sincerely, Original, signed by/

Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Enclosure:

As stated cc w/enclosure:

See next page

• Please see previous c rrence page.

ORB#2:DL ORB#2:DL ORB#1:DL ORB#1:DL

1. 2:DL SN ffis MGrotenhuis/pn*

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DBVa allo 03/01/85 03/01/85 03/01/85 03/01/85 03/

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Mr. E. E. Utley Carolina Power & Light Company Brunswick Steam Electric Plant, Units 1 and 2 cc:

Richard E. Jones, Esquire James P. O'Reilly Carolina Power & Light Company Regional Administrator 336 Fayetteville Street Region 11 Office Raleigh, North Carolina 27602 U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 George F. Trowbridge, Esquire Atlanta, Georgia 30303 Shaw, Pittman, Potts and Trowbridge 1800 M Street, N. W.

Dayne H. Brown, Chief Washington, D. C. 20036 Radiation Protection Branch Division of Facility Services Mr. Charles R. Dietz Department of Human Resources Plant Manager Post Office Box 12200 Post Office Box 458 Raleigh, North Carolina 27605 Southport, North Carolina 28461 Mr. Franky Thomas, Chairman Board of Commissioners Post Office Box 249 Bolivia, North Carolina 28422 Mrs. Chrys Baggett State Clearinghouse Budget and Management 116 West Jones Street Raleigh, North Carolina 27603 Resident Inspector U. S. Nuclear Regulatory Commission Star Route 1 Post Office Box 208 Southport, North Carolina 284613

Mr. E. E. Utley H. B. Robinson Steam Electric Carolina Power and Light Company Plant 2 cc: G. F. Trowbridge, Esquire Mr. Dayne H. Brown, Chief Shaw, Pittman, Potts and Trowbridge Radiation Protection Branch 1800 M Street, N.W.

Division of Facility Services Washington, DC 20036 Department of Human Resources P.O. Box 12200 Reqional Radiation Representative Raliegh, North Carolina 27605 EPA Regiona IV 345 Courtland Street, N.E.

Atlanta, GA 30308 Mr. McCuen Morrell, Chairman Darlington County Board of Supervisors County Courthouse Darlington, South Carolina 29535 State Clearinghouse Division of Policy Development 116 West Jones Street Raleigh, North Carolina 27603 Attorney General Department of Justice Justice Building Raleigh, North Carolina 27602 U.S. Nuclear Regulatory Commission Resident Inspector's Office

.H. B. Robinson Steam Electric Plant Route 5, Box 413 Hartsville, South Carolina 29550 James P. O'Reilly Regional Administrator - 'Region7II U.S. Nuclear Regulatory Commission Sutie 2900 101 Marietta Street Atlanta, GA 30303 Mr. R. Morgan General Manager H. B. Robinson Steam Electric Plant Post Office Box 790 Hartsville, South Carolina 29550

January 30, 1985 SCALING FACTORS FOR IRRADIATED REACTOR COMPONENTS

1. Introduction The following guidelines may be used in determining the activity concentrations in irradiated reactor components of radionuclides specifically required to be reported and radionuclides potentially important to waste classification, in accordance with the Waste Classification Branch Technical Position (Ref. 1).

The guidelines are based on the methodology provided in NUREG/CR-3474 (Ref. 2).

II. Composition of Components The initial step should be the determination of the composition of the irradiated component in regard to the dominant target isotopes corresponding to the important radionuclides. Table 1 identifies the dominant target isotopes for radionuclides specifically required to be reported. Table 2 identifies the dominant target isotopes in, for example, steel reactor components for radionuclides potentially important to waste classification'. It should be confirmed that additional radionuclides, outside those listed in Tables 1 and 2, need not be considered (see 10 CFR 61.55 and the Waste Classification Branch Technical Position, Ref. 1).

Vendor-supplied certifications for component compositions should be used if possible. If certifications are not available, sampling and chemical

2 analyses should be used, to the extent practicable, to determine component compositions. Otherwise, conservative values of component-compositions should be used. The degree of conservation employed should reflect the range of compositions known to exist for the materials as used in the fabrication of the particular type of component. For example, NUREG/CR-3474 provides in Table 4.7 the chemical analysis results for thirteen samples of nuclear grade Type 304L stainless steel.

These results for the target isotopes listed in Tables 1 and 2 are ranked in Table 3 and statistics provided in the form of approximate percentiles assuming norma.1 distributions.

III. Activity Concentrations of Radionuclides The activity concentrations of radionuclides specifically required to be reported and radionuclides potentially important to waste classification should be determined using activation analysis. The method described in NUREG/CR-3474 is an acceptable approach which can be used to take into account the neutron fluxes, in-core geometry, and in-core residence time of the irradiated components being assessed. Dose measurements, coupled with a standard dose-to-curie conversion, should then be used as a check on the reliability of the calculated activity concentrations.

REFERENCES

1. "Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification," May 1983. Attachment to letter to Commission Licensees from Leo B. Higginbotham, Chief, Low-Level Waste Licensing Branch, Division of Waste Management, U.S. Nuclear Regulatory Commission, May 11, 1983.

2. Evans, J. C., et al. 1984, "Long-Lived Activation Products in Reactor Materials," NUREG/CR-3474.

Table 1 Target Isotopes for Radionuclides Specifically Required to be Reported Radionuclide Specifically Required Dominant

% Abundance to be Reported Target Isotope Target Isotope H-3 Li-6 7.4 C-14 N-14 99.6 Tc-99 Mo-98 24.6 1-129 Te-128 31.8 Table 2 Target Isotopes in Steel Reactor Components for Radionuclides Potentially Important to Waste Classification Radionuclide Potentially Important Dominant

% Abundance to Waste Classification Target Isotope Target Isotope C-14 N-14 99.6 Ni-59 Ni-58 67.8 Nb-95 Nb-93 100.

Tc-99 Mo-98 24.6 Fe-55*

Fe-54 5.9 Co-60*

Co-59 100.

Ni-63*

Ni-62 3.7 Cs-137 Ba-137 11.3

• Note:

These radionuclides will most likely determine waste classification for nuclear grade Type 304L stainless steel.

Table 3 Chemical Analysis Results for Thirteen Samples of Nuclear Grade Type 304L Stainless Steel (from NUREG/CR-3474, Table 4.7), ppm after adjusting for percent isotope abundance Statistics given assume normal distributions.

Isotope Li-6 N-14 Mo-98 Te-128*

Ni-58 Nb-93 Fe-54 Co-59 Ni-62 Ba-137 Ranked 0.0096 400 19 60,000 5

40,000 229 3,300 60 Results 428 130 62,000 6

40,000 750 3,400 60 523 470 64,000 10 41,000 820 3,500 60 540 64,000 16 41,000 1,240 3,500 60 540 65,000 30 41,000 1,720 3,600 80 570 68,000 63 41,000 1,720 3,700 100 570 70,000 70 41,000 2,265 3,800 100 570 71,000 71 42,000 2,570 3,800 100 590 71,000 110 42,000 3,800 790 72,000 120 42,000 3,900 960 73,000 190 43,000 4,000 1,100 73,000 200 44,000 4,000 1406 75,000 300 45,000 4,100 Approximate Percentiles 50 0.0096 450 630 68,000 92 42,000 1,410 3,700 80 90 560 1,100 76,000 220 44,000 2,850 4,100 120 99 660 1,500 83,000 330 46,000 4,050 4,500 150 99.9 720 1,800 88,000 410 47,000 4,850 4,700 170

• Note:

No results reported in NUREG/CR-3474.