ML20091P665
| ML20091P665 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/05/1984 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM TAC-44421, NUDOCS 8406130133 | |
| Download: ML20091P665 (2) | |
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Telephone (412) 393-6000 Nuclear Onrision P.O. Box 4 Shippingport, PA 15077-0004 June 5, 1984 Director of Nuclear Reactor Pegulation United States Nuclear Regulatory Conmission Attn: Mr. Steven A. Varga, Chief Operating Peactors Branch No. 1 Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Powr Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 NUREG-0737, item II.B.3, Pequest for Additional Information Gentlemen:
Your letter dated April 20, 1984 requested additional information on our Post-Accident Sampling System (PASS). Specifically, your request was fo.:
our procedure to estimate the extent of core damage (II.B.3, criterion 2) the accuracy of the chloride analysis (II.B.3, criterion 2) information demonstrating applicability of procedures and instrumentation in the post-accident water chemistry and radiation environment (II.B.3, criterion 10)
On May 31, 1984, a conference call between Mr. P. Tam and Mr. P. Wil of the NBC and Mr. S. Sovick and Mr. V. Linnenbom was held in order to obtain clarification on the third of these three items. Mr. Wu explained that our response should address the accuracy of the PASS instruments when tested with the standard text matrix as to whether the instruments had met those accuracies to which we had cmmitted.
He waF also questioning whether these instrument accuracies were dmonstrated in the presence of a
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radiathn field. As to this second concern, it was stated that the tests were not performed-in the presence of this radiation field and that this was not a test criteria which had been made known at the time of equipment procurement or acceptance testing. However, the instruments were purchased with certification that they would function in a radiation field exceeding.
'10 E4 rads per gram of reactor coolant and were satisfactorily tested using the standard test matrix.
Subsequent ~ to this conference call we were advised that the reviewers in the NBC Chemical Engineering Branch'had found our approach acceptable.
8406130133 840605 q Q; PDR ADOCK 05000334-1
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J' Beaver Valley Power Station, Unit Po. 1 Docket No. 50-334, License No. DPR-66 NUREG-0737, item II.B.3, Pequest for Additional Information Page 2
'Ihe procedure to estimate core damage is currently being developed using the NOG core damage assessment methodology which was recently found acceptable by the NBC.
In order to permit close-out of this 1UREG-0737 item, Mr. Wu requested one subnittal be made containing all the information requested by your letter. Agreenent was reached during the conference call that all requested information would be provided upon ccupletion of the core damage assessment procedure.
Therefore, we will provide all the requested information by July 15, 1984.
If you have any questions concerning this subnittal, please contact me or mmbers of my staff.
Very trul yours, J. J. Carey Vice President, Nuclear cc: Mr. W. M. Troskoski, Pesident Inspector
,U. S. Nuclear Regulatory Ccmnissicn Beaver Valley Power Station Shippingport, PA.15077 U. S. Nuclear Regulatory Ccmnission c/o Document Managenent Branch Washington, DC 20555 Mr. Peter Tam, Project Manager U. S. Nuclear Regulatory Ccmnission Phillips Building Washington, DC 20555
- Mail Stop 438 -
4 T-
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