ML20235C657
| ML20235C657 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/08/1987 |
| From: | Tucker H DUKE POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8709240523 | |
| Download: ML20235C657 (3) | |
Text
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r' s-DUKE' POWER GOMPANY P.O. BOX 33180 011ARLOTTE, N.O. 28242 l-HALH. TUCKER reta: PHONE vsospan aonny (7o4) 373-4531 WUCLEAR PMODUUTION
' September 8, 1987 Dr. J. Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Commission-Region II 101 Marietta St. NW, Suite 2900 g
Atlanta, Georgia 30323 m
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Subject:
McGuire Nuclear Station Docket Nos. 50-369 and 50-370 Unresolved Item'50-369, 370/87-13-01 c.n
.c.
Dear.Dr. Grace:
During a telephone conversation on May 19, 1987, Duke agreed to submit a response to the subject Unresolved Item to the NRC Region II that would address the sampling requirements of Table II.F.1-2 in NUREG-0737 and how the sampling system meets those requirements. Please find attached the subject response.
Should there be any questions concerning this subj ect, please contact Duke Licensing.
Very truly yours,
/
A.-
Hal B. Tucker SEL/113/jgc Attachmeut xc:
U.S. Nuclear Regulatory Commission Mr. W.T. Orders Document Control Desk NRC Resident Inspector Washington, D.C.
20555 McGuire Nuclear Station 8709240523 87090r PDR ADOCK 05000369 P
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T RESPONSE TO URI 369, 370/87-13-01 The NRC requested a review of the radiciodine and particulate sampling re-quirements of NUREG 0737 Table II.F.1.-2 (attached) and a determination as to whether the four criteria for sampling considerations are met.
No documenta-tion could be found that specifically addresses the compliance to the NUREG Table; however, Duke believes that McGuire is complying with two of the four criteria and request an exception to one of the criteria.
Full compliance can be easily attained with the exception to one of the criteria.
Full compliance can be easily attained with the completion of Nuclear Station Modification (NSM) MG-1-1623 and MG-2-0588.
The NSM's are intended to satisfy the criteria of Regulatory Guide 1.97 and have an NRC commitment completion date before the end of the 1988 refueling outages.
Duke has performed a study of a design bases accident and determined that the maximum unit vent particulate and fodine activity is 0.033 microcurie per cc.
This value disagrees with the 100 microcurie per cc Design Basis Shielding Envelope criteria mentioned in the NUREG.
Duke believes representative sampling per ANSI N13.1-1969 is met based on a 1981 stack velocity profile study.
The stack sampler met the criteria of the ANSI standard. The NSM's include the installation of heat tracing; therefore, the sampling consideration for entrained moisture will be satisfied.
Duke believes the letter of the sampling consideration for continuous collec-tion is met with the present Technical Specification sampler.
Existing plans were to disrupt flow only to the radiation monitor providing remote readout when the unit vent noble gas high-high range monitor trip 1 alarm occurred.
The monitor setpoint is preferentially selected at three times background.
This would not affect the Technical Specification sampling equipment and a sample would continue to be obtained.
Our designed basis accident unit vent cctivity is 0.033 microcurie per cc and alone would not prevent sample collec-tion.
The proximity of the annulus ventilation filters could prevent retriev-ing a sample and an alternative sample location is being rursued. Duke plans under NSM MG-1-1623 and MG-2-0588 to route sampling lines to a lower radiation area away from the annulus ventilation filters.
Correlation charts for evaluating the particulate and fodine activity in the sample based upon dose rate are being developed.
Due to the expected maximum unit vent activity, Duke considers shielding is not necessary to meet the 5 Rem whole body and 75 Rem extremity dose criteria.
With the exception that the Design Basis Shielding Envelope criteria is not consistent with McGuire's design bases accident unit vent activity, Duke believes full compliance can be attained before the end of the 1988 refueling outages.
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i' Af SAMPLING ' AND ANALYSIS OR _ MFASUREMEN'I_OF HIGN RANGE RADIOI03INE PARTICULAT'E EFFLUENTS IN CASEOUS EFFLUENT STREAMS.
.t-Capability to collect and analyze or measure V
EQUIPMENT representative samples of radioactive iodines and particulate in plant gaseous effluents during and s
following)an' accident. The capability to sample and analyze for radioiodine and particulate effluents is not
.l required for.PWR secondary main steam safety valve and dump valve discharge lines.
To determine quantitative release of'radioiodines and PURPOSE particulate for dose. calculation and assessment.
4 102 pCi/cc of gaseous radioiodine and particulate, i
DESIGN BASIS SHIELDING deposited on sampling media; 30 minutes sampling time, ENVELOPE average gansna energy (E) of 0.5 MeV.
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Iodine > 90% effective adsorption for all forms of Baseous iodine.
Particulate > 90% effective retention for 0.3 micron (p) diameter particles.
sat 1PLING CONSIDERATIONS -
Representative sarcpling per ANSI N13.1-1969.
Entvained. moisture in effluent stream should not degrade adsorber.
Conkinuous collection required whenever exhaust flow occurs.
Provisions for limiting occupational dose to personnel incorporated in sampling systea, in sample handling and transport, and in analysis of samples.
ANALYSIS
. Design of analytical facilities and preparation of analytical procedures shall consider the design basis sample.
Highly radioactive samples may not be compatible with generally accepted L
analytical procedures; in such cases, measurement of emissive gamma radiations and the use of ~;hielding.and,djsgnce f actors should be
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considered in design.
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