ML20151V766
| ML20151V766 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/08/1998 |
| From: | Gordon Peterson DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9809150071 | |
| Download: ML20151V766 (3) | |
Text
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- O) g Duke Energy Corporation
'd Catawba Nudear Station 4800 Concord Road York, SC 29745 Gary R. Peter' son (803) 831-425I onx:t We 1%iden, (803) 831-3426nx September 8, 1998 U.S.
Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Corporation Catawba Nuclear Station, Unit 2 Docket Number 50-414 Clarification of Statement in the Notice of Enforcement Discretion (NOED) Request Ice Condenser Technical Specification Surveillance Requirement 4.6.5.lb.2
Reference:
Letter dated August 12, 1998, Duke Energy Corporation to U.S. Nuclear Regulatory Commission Notice of Enforcement Discretion (NOED) Request Ice Condenser Technical Specification Surveillance Requirement 4.6.5.lb.2 TAC Number MA32'19 The purpose of this letter is to correct one sentence in Reference 1 concerning at power expected dose rates in lower containment that was used in part as a justificatio.. for Enforcement Discretion for Catawba Unit 2.
As a result of a
'miscommunication the information provided did not accurately reflect expected plant conditions.
Reference 1 provided the written documentation of the background and technical information supporting the Catawba Unit 2 Notice of Enforcement Discretion (NOED) request.
In Attachment 1 of Reference l'under Item 2 " Circumstances surrounding the situation", the following statement was made,
" Dose rates in the lower ice condenser at power exceed 3.6 R/hr."
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Nuclear Regulatory Commission Page 2 September 8, 1998 hhile it is true that the lower containment is not usually accessible during power operation because of high personnel radiological dose considerations, survey data for lower containment, extrapolated to 100% power, indicate a highest contact dose of approximately 2.3 R/hr and a highest general area dose of approximately 1.0 R/hr.
The collective exposure to an individual performing Surveillance 4.6.5.lb.2 on the lower inlet plenum support structures and the turning vanes is estimated to be 3.6 Rem.
Duke regrets any confusion that may have been caused by the incorrect dose information.
Should you have any questions concerning this information, please call M.S.
Kitlan, Jr. (803) 831-3205.
Very truly yours, J-G.R.
Peterson
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U.S.
Nuclear Regulatory Commission Page 3 September 8, 1998 xc:
1 L.A. Reyes
-U.S. Nuclear. Regulatory Commission Regional Administrator, Region II Atlanta' Federal Center 61 Forsyth St.,
SW, Suite 23T85 Atlanta, GA 30303 D.J.
Roberts Senior. Resident Inspector (CNS)
U.S. Nuclear Regulatory Commission Catawba Nuclear Station P.S.
Tam NRC Senior Project Manager (CNS)
U.S.
Nuclear Regulatory Commission Mail Stop O-14H25 Washington, D.C. 20555-0001 V.R. Autry.
Division of Radioactive Waste Management Bureau of Solid and Hazardous Waste Department of Health & Environmental Control 2600 Bull St.
Columbia, SC 29201
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