ML20155K610
| ML20155K610 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/13/1988 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8806210301 | |
| Download: ML20155K610 (22) | |
Text
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DUKE POWER GOMPANY P.O. nox G3180 CIIARLOTTE, N.O. 28242 i
HALp. TUCKER rn'_crnowr, TM,H PRESIDENT (704) 073-4508 mm.
-m, j
i June 13, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
McGuire Nuclear Station Docket Numbers 50-369 and 50-370 l
Reply to Request for Additional Information Regarding Unresolved Item 50-369,-370/87-13-01 Gentlemen:
By letter dated April 28, 1988, NRC staff requested additional luformation to complete review of subject icem.
Attached find additional information that was requested, and a correction to information provided in Duke's April 25, j
1988 letter concerning the subject matter.
q Should there be any further questions regarding this subject, please contact S.E. LeRoy at (704) 373-6233.
Very truly yours.
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Hal B. T eker SEL/283/ bhp Attachment xc:
Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, Georgia 30323 Mr. Darl Hood U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C.
20555 Mr. W. T. Orders NRC Senior Resident Inspector gg(
McGuire Nuclear Station v
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8806210301 880613
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PDR ADOCK 05000369 Q
i Document Control Desk June 13, 1988 Page 2 bxc: R. G. Eble J. W. Foster R. O. Sharpe R. L. Gill, Jr.
N. A. Rutherford, Jr.
MC-815.01 (369, 370/87-13)
(6) i
.a RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RADI0 IODINE AND PARTICULATE SAMPLING AT THE McGUIRE NUCLEAR STATION, DOCKET NOS, 50-369 AND 50-370 By letter dated April 28, 1988, NRC Staff requested the following information:
1.
Describe the stock velocity profile study performed in 1981 and provide date or a summary of the data that demonstrates that representation sampling will be provided.
See Attachment I which provides the requested information.
2.
Provide a description of Nuclear Station Modification (NSM) MG-1-1623 and MG-2-0588.
The NSMs in question will provide additional tubing to allow remote particulate and iodine grab sampling, post LOCA.
Any sections of tubing exposed to a cold environment will be insulated and heat traced.
All inlet tubing will have a minimum of plate out locations such as 90 degree elbows, etc. provides a sketch of the grab sampling equipment.
3.
a.
Describe the equipment and procedures that will be used to continuously sample gaseous effluents post LOCA.
r To provide continuous sampling under post LOCA conditions a remote sampler is being installed per the previous discussed NSMs.
The remote sampler will sample from the unit vent stack sampling point currently in use. provides a sketch of the grab sampling equipment, b.
Provide an estimate of the doses that a worker would receive as a result of exposure during sampling handling, transport, and analysis, the basis for the estimated doses, and describe the provisions DPC has taken to limit exposure during the aforementioned process.
Refer to Attachment 3 for calculated dose rates from an unshielded iodine sample cartridge.
The dose rates are based on the following accident analysis assumption:
1.
Maximum instantaneous iodine concentrations in the unit vent from post accident effluent calculations are assumed to be sampled for 30 minutes; 2.
Maximum particulate filter activation is assumed based on conservative release assumptions; 3.
Sample time of 30 minutes;
J Page 2 4.
Sampler flowrate of 0.8 cfm and 100% efficient filter and cartridge; and 5.
Sampler construction 3/8" thick aluminum alloy.
Using six minutes handling time, the extremity dose is 350 rrem and the whole body dose is 5 mrem assuming 14 minutes exposure.
To maintain doses ALARA, handling times will be minimized and the sample handled with long handled tools when possible.
Shielding may be provided to lower dose rates if no interference with measurements can be assured.
The correlation of iodine and particulate concentration on the filter to dose rate assumes no scatter contribution as may be present with a shielded sample.
4.
Would the use of the "Procedure for Quantifying High Level Radioactivity i
Releases During Accident Conditions" 2imit DPC's ability to retrieve samples?
DRC believes that the ability to retrieve samples using the aforementioned procedure will not be limited due to occupational exposure for the following reasons:
a.
The remote sampler provides the ability to sample in an area of the plant that has lower general area dose rates; b.
The design of the remote sampler incorporates quick disconnects, etc., to allow shorter handling times during the sampling process; and c.
Based on DPC's post DBA-LOCA analysis the resultant dose rates (contact) of the sample will be 9.0 R/hr.
By letter dated April 25, 1988, DPC transmitted information regarding the basis for a valve of 0.033 microcuries per CC for unit vent particulate and iodine activity.
The valve diaagreed with the 100 microcuries per CC Design Basis Shielding Envelope Criteria mentioned in NUREG 0737. A recalculation of the dose assessment and correlation of activity built up on the remote cartridge filter has substantiated the criteria of NUREG-0737, Item II.F.1.
The valve of 100 microcuries per milliliter was initially misunderstood to represent the maximum iodine and particulate concentration in the unit vent.
This value can only reasonably represent the maximum concentration built up on the cartridge filter.
Comparing resultant dose rates for the h11 REG position verses DPC results snows the similarity of the conditions and basis for this position.
_ _ =.
Page 3 NUREG CRITERIA DPC ANALYSIS Maximum Concentration 100 Micro C1/CC 63 Micro Ci/CC on Filter I-131 equivalent (Thyroid dose) collected 1st 30 minute post DBA-LOCA Average Gamma Energy 0.5 Mev 0.83 Mev at T = 0 Resultant Dose Rate 10.4 R/Hr 9.0 R/Hr (contact)
This value actually represents a maximum concentration in the unit vent averaged over the first few minutes post DBA-LOCA.
)
The valve of 0.033 microcuries per CC concentration was incorrectly reported to represent the maximum concentration on the filter media in DPC's April 25, j
1988 letter to the NRC.
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ATTACHMENT 1
. Q CERTIFICATI0tl 0F ENGIllEERING CALCULATION FOR INFORMATION McGuire Unit 1 ONLY Station and Unit Number Verification of Unit Vent Sample Probe
. Title of Calculation Design and Installation Calculation Number MCC-1211.00-68 Originally consisting of Pages 1 of 14 through 14 of 14 These Engineering Calculations cover QA CONDITION 0
items.
In accordan.e with established procedures, the quality has been assured and I certify that the above calculation has been performed, checked or approved as noted below:
Performed by M h(
h Date 8-/O-8/
Checked by im Date d- // 8/
Approved by ldd s Date 6 - l2 -6/
O Issued to General Services Division Date
' {
Received by General Services Division Date Revision / Addenda Log:
Performed Chec d Approved 9 Issue Pages Pages Pages By By By Date tc'dil No.
Revised Deleted Added Date Date Date Date !
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- 2. FOR I!1STALLRY30rt or IScKIr(11C SA.d*LE n0!?LC, REFER TO asCD-t14.CS-129 2 M 3 I I*~ g g*s B. MIM NOT TO minIn prov w necws. LMC.C afCIUS OFW proul.tD.
(FIE1.D mouTED 10 WOST) 4 Shesatt Po!NT tocallon 15 to eE oETEmir(D sv Con 5TRUCT3cn (IEC2 prv.p.
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NOTE 6 NOTt 6 REre0TE FOR
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FOR ATTACHPENT 3 INFORMATION ONLY Maximum Doserate From lodine Sample Cortridge 1E+01; i
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