ML20151X056

Forwards Request for Addl Info Re Util 870908 Response to Unresolved Item Re Radioiodine & Particulate Sampling Noted in Insp Repts 50-369/87-13 & 50-370/87-13.Response Requested within 45 Days of Ltr Receipt

ML20151X056
Person / Time
Site:	McGuire, Mcguire
Issue date:	04/28/1988
From:	Hood D Office of Nuclear Reactor Regulation
To:	Tucker H DUKE POWER CO.
References
RTR-NUREG-0737, RTR-NUREG-737 TAC-66897, TAC-66898, NUDOCS 8805040042
Download: ML20151X056 (4)

See also: IR 05000369/1987013

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April 28, 1988

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Docket Nos. 50-369

50-370

Nr. H. B. Tucker, Vice President

Nuclear Production Department

Duke Power Company

422 South Church Street

Charlotte, North Carolina 28242

Dear Mr. Tucker:

SUBJECT: SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION REGARDING

RAD 1010 DINE AND PARTICULATE SAMPLING, NCGUIRE STATION

STATION, UNITS I and 2 (TACS 66897/66898)

The NRC staff is reviewing your le+ ter dated September 8,1987 responding to

an unresolved item identified in 1..spection Report 50-369, 370/87-13-01.

This item regards criteria for radioiodine and particulate sampl 6g listed in

NUREG-0737 Table II.F.1-2. These criteria address: (1) representative

sampling;f2)considerationofentrainedmoistureinsamplinglines;(3)

continuous sampling; and (4) shielding.

NRR is assisting Region II in the review of this unresolved item. We find

that additional information, identified by the enclosure, is needed to complete

the review. The enclosure is supplemental to our request of March 7,1988.

Your response to this enclosure is requested within 45 days of receipt of

this letter. Contact me at (301) 492-1442 if you have any questions.

The reporting and/or recordkeeping requirements contained in this letter

affect fewer than ten respondents; therefore, OMB clearance is not required

under P.L.96-515

Sincerely,

Darl S. Hood, Project Manager ,

Project Directorate II-3 1

Division of Reactor Projects I/II

Enclosure:

As stated '

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cc W/ encl: 8805040042 880428

PDR

See next page P ADOCK 05000369

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DISTRICUTION

Dicket!FT W NRC PDR Local PDR PDII-3 Reading File

S. Varga G. Lainas D. Matthews D. Hood H. Rood

OGC-WF E. Jordan J. Partlow ACRS(10) D. Collins, Ri!

J. B. Kahle, RII E. Branagan L. Cunningham

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0j/MI/88 01/A/88 0& /M/88

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Mr. H. B. Tucker

Duke Power Company McGuire Nuclear Station

cc:

Mr. A.V. Carr, Esq. Dr. John M. Barry

Duke Power Company Department of Environmental Health

P. O. Box 33189 Mecklenburg County

422 South Church Street 1200 Blythe Boulevard

Charlotte, North Carolina 28242 Charlotte, North Carolina 28203

County Manager of Mecklenburg County Mr. Dayne H. Brown, Chief

720 East Fourth Street Radiation Protection Branch

Charlotte, North Carolina 28202 Division of Facility Services

Department of Human Resources

701 Barbour Drive

Mr. Robert Gill Raleigh, North Carolina 27603-2008

Ouke Power Company

Nuclear Production Department

P. O. Box 33189

Charlotte, North Carolina 28242

J. Michael McGarry, III, Esq.

Bishop, Liberman, Cook, Purcell

and Reynolds

1200 Seventeenth Street, N.W.

Washington, D. C. 20036

Senior Resident inspector

c/o U.S. Nuclear Regulatory Connission

Route 4, Box 529 * -

Hunterville, North Carolina 28078

Regional Administrator, Region II

U.S. Nuclear Regulatory Commission,

101 Marietta Street, N.W., Suite 2900

Atlanta, Georgia 30323

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S. S. Kilborn

Area Manager, Mid-South Area

ESSO Projects

Westinghouse Electric Corporation

MNC West Tower - Bay 239

P. O. Box 355

Pittsburgh, Pennsylvania 15230

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ENCLOSURE

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SUPPLEMENTAL

REQUEST FOR ADDITIONAL INFORMATION

REGARDING RADI0 IODINE AND PARTICULATE SAMPLING AT THE MCGUIRE NUCLEAR STATION

DOCKET N0s. 50-369 AND 50-370

By letter dated September 8,1987, Duke Power Company (DPC) submitted infonna-

tion regarding sampling of gaseous effluents that may be released from the

McGuire Nuclear

radioiodines and Station during(an

particulates accident,

Ref. 1). DPC's and analysis

letter of these in

was submitted samples for

response

to an Unresolved Item identified during an inspection (Ref. 2). The inspection

report ouestioned whether the McGuire Nuclear Station met all of the criteria

for radiciodine and particulate sampling listed in NUREG-0737, Table II.F.1-2.

These criteria concern: (1) collecting representative samples of gaseous

effluents; (2) considering entrained moisture in sampling lines; (3) continuous

sampling of gaseous effluents; and (4) shielding to limit occupational exposure

during semple handling, transport and analysis.

1. In Ref.1 DPC stated that a stack velocity profile study was performed in

1981, and that the sampling system at the McGuire Nuclear Station met the

criteria stated in ANSI N13.1-1969 (Ref. 3). Describe the study that was

performed, and provide the data (or a sumary of the data) that demon-

strates that representative sampling will be provided for under accident

conditions.

2. DPC stated that Criteria 2 regarding entrained moisture will be met after

Nuclear Station Modifications (NSM) MG-1-1623 and MG-2-0588 are completed.

Provide a description of the subject modifications. In particular, the

description should include: (1) a list of the various effluent streams

that are subject to entrained water under accident conditions and that

will need to be sampled; (2) a brief description of the equipment that

will be used to prevent entrained moisture in each of the lines identified

in item #1 from degrading the adsorbers; and (3) confirmation that the

capacity of the heat tracing equipment will be adequate to ensure that air

centaining entrained water will not degrade the adsorbers.

3. DPC stated that they believe the criteria regarding continuous sampling is

met; however, little infonnation was provided (or referenced) to document

this claim.

a. Describe the equipment and procedures that DPC will use to continu-

ously sample gaseous effluents under post-accident conditions. In

particular, identify "the present Technical Specification sampler"

that meets Criteria 3.

b. Provide an estimate of the doses that a worker would receive as a

result of exposure during sample handling, transport and analysis.

Provide the basis for the estimated doses. Describe the provisions

that DPC has taken to limit occupational exposure during sample

handling, transport and analysis.

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4. OPC uses Procedure HP/0/B/1009/06, "Procedure for Quantifying High Level

Radioactivity Releases During Accident Conditions." It appears that use

of this procedure could result in excessive occupational exposure (Ref. 2, I

page 8). Would this occupational exposure limit OPC's ability to retrieve j

samples? Provide the basis for DPC's response.

REFERENCES

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1. Letter from Hal B. Tucker, Duke Power Company, to J. Nelson Grace. l

U. S. Nuclear Regulatory Commission, dated September 8,1987.

2. Gloersen, W. B. and S. S. Adamovitz, U. S. Nuclear Regulatory Commission,

Inspection Report Nos. 50-369/87-13 and 50-370/87-13, dated June 1, 1987. l

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3. American National Standards Institute, Inc., "American National Standard l

Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities,"  !

ANSI N13.1-1969, February 1969.

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