Information Notice 1996-57, Incident-Reporting Requirements Involving Intakes, During a 24-Hour Period That May Cause a Total Effective Dose Equivalent in Excess of 0.05. Sv (5 Rem)

Incident-Reporting Requirements Involving Intakes, During a 24-Hour Period That May Cause a Total Effective Dose Equivalent in Excess of 0.05. Sv (5 Rem)

ML031050565
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant
Issue date:	10/30/1996
From:	Cool D, Martin T NRC/NMSS/IMNS, Office of Nuclear Reactor Regulation
To:
References
IN-96-057, NUDOCS 9610230239
Download: ML031050565 (7)

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS

WASHINGTON, DC 20555 October 30, 1996 NRC INFORMATION NOTICE 96-57: INCIDENT-REPORTING REQUIREMENTS

INVOLVING INTAKES, DURING A 24-HOUR

PERIOD THAT MAY CAUSE A TOTAL EFFECTIVE

DOSE EQUIVALENT IN EXCESS OF 0.05 Sv

(5 rem)

Addressees

All U.S. Nuclear Regulatory Commission licensees.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to remind

recipients of certain incident notification requirements found in 10 CFR 20.2202(b)(1)(i)

relating to intakes received during a 24-hour period that may cause a Total Effective Dose

Equivalent (TEDE) in excess of 0.05 Sv (5 rem). It is expected that recipients will review the

information for applicability to their facilities, to ensure that this information is considered

when making a decision about the reporting of a radiation exposure incident. However, this

information notice does not contain NRC requirements; therefore, no specific action nor

written response is required.

DescriDtion of Circumstances

Recently, NRC was informed of, and responded to, two incidents involving phosphorus-32 (P-32) and the resulting internal contamination of individuals at biomedical research facilities.

P-32 is a radioisotope widely used in research institutions, as are many other radionuclides.

Although only one of these events raised a question associated with reporting requirements

and is discussed below, our concerns regarding reporting of incidents involving internal

exposure extend to all facilities using licensed material.

On October 16, 1995, a licensee informed the NRC that an incident involving internal

contamination of a researcher had occurred at its facility almost two months earlier. The

licensee's final evaluation of the TEDE received by the individual was 0.048 Sv (4.8 rem)

which was within 5 percent of the annual limit of 0.05 Sv (5 rem). An NRC Incident

Investigation Team analysis (NUREG-1535, "Ingestion of Phosphorus-32 at Massachusetts

Institute of Technology, Cambridge, Massachusetts, Identified on August 19, 1996")

concluded that the licensee's final dose assessment was appropriate, but further concluded

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IN 96-57 October 30, 1996 that data available within the first week was sufficient to indicate that the event threatened to

cause an individual to receive a TEDE in excess of 0.05 Sv (5 rem). Licensee officials told

NRC staff that they had not reported the incident earlier because their analysis indicated that

the researchers TEDE received during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> did not require reporting, pursuant

to 10 CFR 20.2202(b)(1)(i).

The pertinent rule, 10 CFR 20.2202(b)(1)(i), states "...each licensee shall, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of

discovery of the event, report any event involving loss of control of licensed material

possessed by the licensee that may have caused, or threatens to cause, any of the following

conditions:

(1) An individual to receive, in a period of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s- (i) A total effective dose equivalent exceeding 5 rem (0.05 Sv);or..."

The licensee had interpreted this to mean that the dose actually received by the individual

during the particular 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the event had to exceed 0.05 Sv (5 rem) before the

24-hour notification was required. This interpretation is not consistent with the definitions of

TEDE, committed effective dose equivalent (CEDE), and committed dose equivalent (CDE) in

10 CFR 20.1003.

Discussion

As noted above 10 CFR 20.2202(b)(1)(i) requires 24-hour notification if a loss of control of

licensed material may have caused, or threatens to cause, an individual to receive, in a

period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a TEDE exceeding 0.05 Sv (5 rems). NRC's interpretation of the rule is

derived from the definitions in 10 CFR 20.1003 as follows: TEDE is defined as the sum of

the deep-dose equivalent (for external exposures) and the CEDE (for internal exposures),

CEDE is the sum of the products of the weighing factors applicable to each of the body

organs or tissues that are irradiated and the CDE to these organs or tissues, and CDE

means the dose equivalent to organs or tissues of reference that will be received from an

intake of radioactive material by an individual during the 50-year period following the intake.

Licensees are required by 10 CFR 20.2202(b)(1)Qi) to report the TEDE received by an

individual that is based on all doses received during the 24-hour period, including committed

doses (i.e., the CEDE) and not just the doses delivered during the 24-hour period. For

internal doses, the 24-hour period specified in 10 CFR 20.2202(b)(1) refers to the period of

intake and not the period of dose delivery. In the case described above, the CEDE from the

intake received during the event (in a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) threatened to exceed 0.05 Sv

(5 rem). Because this case does not involve external exposure (rather, only ingestion),

CEDE is equal to TEDE. In such a case, a licensee would be required by 10 CFR

20.2202(b)(1)(i) to notify NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery of the event.

IN 96-57 October 30, 1996 This information notice requires no specific action nor written response. If you have any

questions about the information in this notice, please contact the technical contacts listed

below or the appropriate regional office.

-' AtJa 1/f4r L-

Thomas T. Martin, Director Donald A. Cool, Director

Division of Reactor Program Management Division of Industrial and

Office of Nuclear Reactor Regulation Medical Nuclear Safety

Office of Nuclear Material Safety

and Safeguards

Technical contacts: Cynthia G. Jones, NMSS

(301) 415-7853 Email: cgj~nrc.gov

James E. Wigginton, NRR

(301) 415-1059 Email: jew2@nrc.gov

Attachments:

1. List of Recently Issued NMSS Information Notices

2. List of Recently Issued NRR Information Notices

Are'4"' f (11; I d4-1 -7TAgkc-

- IN 96-57 October 30, 1996 This information notice requires no specific action nor written response. If you have any

questions about the information in this notice, please contact the technical contacts listed

below or the appropriate regional office.

original signed by original signed by

Thomas T. Martin, Director Donald A. Cool, Director

Division of Reactor Program Management Division of Industrial and

Office of Nuclear Reactor Regulation Medical Nuclear Safety

Office of Nuclear Material Safety

and Safeguards

Technical contacts: Cynthia G. Jones, NMSS

(301) 415-7853 Email: cgj@nrc.gov

James E. Wigginton, NRR

(301) 415-1059 Email: jew2@nrc.gov

Attachments:

1. List of Recently Issued NMSS Information Notices

2. List of Recently Issued NRR Information Notices

• SEE PREVIOUS CONCURRENCES

DOCUMENT NAME: 96-57.IN

To receive a cony of this document. hIlicate hI the box: C' - Copy without attachment/enclosure _-E - Copy with attachment/enclosure 'N- - No copy

lOFFICEITECH CONTS L  :/PECB I D:DlR l D:IMNS,/

NAME CJones K kV, AChaffee* TMtin' Do

JWigginton* __

DATE 10/24/96 10/28/96 100Y96 104o/ 9 6 OFFICIAL RECORD COPY

IN 96-57 October 29, 1996 This information notice requires no specific action nor written response. If you have any

questions about the information in this notice, please contact the technical contacts listed

below or the appropriate regional office.

Thomas T. Martin, Director Donald A. Cool, Director

Division of Reactor Program Management Division of Industrial and

Office of Nuclear Reactor Regulation Medical Nuclear Safety

Office of Nuclear Material Safety

and Safeguards

Technical contacts: Cynthia G. Jones, NMSS

(301) 415-7853 Email: cgj@nrc.gov

James E. Wigginton, NRR

(301) 415-1059 Email: jew2@nrc.gov

Attachments:

1. List of Recently Issued NMSS Information Notices

2. List of Recently Issued NRR Information Notices

DOCUMENT NAME: 96-57.INa. 'N' - No copy

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DATE 1 0t46 aV- 10/,;l6 101 /96 101 196 OFFICIAL RECORD COPY

Attachment 1 IN 96-57 October 30, 1996 Page 1 of I

LIST OF RECENTLY ISSUED

NMSS INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

96-54 Vulnerability of Stainless 10/17/96 All material licensees

Steel to Corrosion When

Sensitized

96-53 Retrofit to Amersham 660 10/15/96 All industrial radiography

Posilock Radiography licensees

Camera to Correct Incon- sistency in 10 CFR Part 34 Compatibility

96-52 Cracked Insertion Rods 09/26/96 All U.S. Nuclear Regulatory

on Troxier Model 3400 Commission portable gauge

Series Portable Moisture licensees and vendors

Density Gauges

96-51 Residual Contamination 09111/96 All material licensees

Remaining in Krypton-85 Handling System After \

Venting

96-47 Recordkeeping, Decommis- 08/19/96 All U.S. Nuclear Regulatory

sioning Notifications for Commission licensees

Disposals of Radioactive

Waste by Land Burial

Authorized Under Former

10 CFR 20.304, 20.302, and Current 20.2002

96-35 Failure of Safety Systems 06/11/96 All U.S. Nuclear Regulatory

on Self-Shielded Irradia- Commission irradiator

tors Because of Inadequate licensees and vendors

Maintenance and Training

K) K)

Attachment 2 IN 96-57 October 3CL,1996 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

96-56 Problems Associated with 01/22/96 All holders of OLs or

Testing, Tuning, or Reset- CPs for nuclear power

ting of Digital Control reactors

Systems While at Power

96-55 Inadequate Net Positive 10/22/96 All holders of OLs or

Suction Head of Emergency CPs for nuclear power

Core Cooling and Contain- reactors

ment Heat Removal Pumps

Under Design Basis Accident

Conditions

96-54 Vulnerability of Stainless 10/17/96 All materials licensees

Steel to Corrosion When

Sensitized

96-53 Retrofit to Amersham 660 10/15/96 All industrial radio- Posilock Radiography graphy licensees

Camera to Correct Incon- sistency in 10 CFR Part 34 Compatibility

95-04, Excessive Cooldown 10/11/96 All holders of OLs or CPs

Supp. I and Depressurization and vendors for nuclear

of the Reactor Coolant power reactors

System Following Loss

of Offsite Power

OL = Operating License

CP = Construction Permit