ML20195H683
| ML20195H683 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/05/1988 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20195H689 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, NUDOCS 8801200309 | |
| Download: ML20195H683 (2) | |
Text
_ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _
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wonon. om maoo W$l". PA 4077@04 Shengport U.
S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station Unit No. 1 BV-1 Docket No. 50-334, License No. DPR-66 Generic Letter No. 82-33; Supplement 1 to NUREG-0737 Detailed Control Room Design
- Review, Supplemental Report Gentlemen:
In accordance with your letter of April 10, 1987, Beaver Valley Unit-1 Request for Response To Interim Technical Evaluation Report on Control Room Design Review (TAC 56102),
we are providing the Supplemental Report for the Detailed Control Room Design Review (DCRDR) of the Beaver Valley Power Station Unit-1 (BVPS-1) Nuclear Power Plant.
The submittal date for this Supplemental Report is in agreement with the schedule which was discussed with Mr. Peter Tam.
The DCRDR Supplemental Report was prepared as a self sufficient report to facilitate the NRC Staff's review.
Consequently, the need to refer to previous documentation is minimized in the Report.
We provide responses to all of the NRC Staff's concerns that are contained in the Technical Evaluation Report (TER).
The responses are arranged to correspond to the items in the TER and one accompanied by discussions of the HEDs in the appendices.
In
- addition, a
computerized list of all HEDs is provided in Appendix 0 of the Report.
References to HED discussions in the appendices are provided in the comment field of the list.
The current status of the HEDs is indicated on the computerized list.
The status of corrective actions that were implemented prior to the NRC's letter of April 4, 1987 is indicated as closed.
The implementation date for these HEDs, and the HEDs for which no action was recommended in tbc DCRDR Summary Report, is designated as the date of the NRC's
- letter, if the NRC Staff found the resolutions acceptable.
Other corrective actions are scheduled for implementation during the currently in-progress sixth refueling outage.
They are assigned a hold status pending our final review of their implementation.
We also reviewed all HED resolutions and our evaluation of the HEDs requiring further study.
These are identified D
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Betvar VallGy Powmr Stetion, Unit No. 1 Dockst No. 50-334, Licsnzo No. DPR-66 Generic Letter No. 82-33; Supplement 1 to NUREG-0737 Detailed Control Room Design Review, Supplemental Report Page 2 in the Report and are also. assigned a hold status.
It is noted that-the hold status for these HEDs generally signifies the need for further NRC review.
However, where indicated, we are proceeding with implementation of corrective actions.
Finally, the computerized list will be used to track all HED resolutions to completion.
Following our meeting with the NRC Staff subsequent to the submittal of the Summary Report, a considerable effort was begun to process the DCRDR findings.
The effort required review and evaluation by departments within Duquesne Light Company (DLC) to ensure that corrective actions would be properly implemented.
In addition to control room design factors there were other factors such as training, implementation of the new EOPs, the SPDS, and Regulatory Guide 1.97 which needed to be considered.
Also, as was the case for l
DCRDR team assessments, a primary consideration was the impact of the corrective actions on plant operations.
As a
result, _a6Me resolutions were revised to reflect these considerations.
We believe that these revisions are appropriate and have provided discussions of them in the Report.
As discussed in the telecon of September 3, 1987 with the NRC
- Staff, we will complete certain surveys in conjunction with our BVPS-2 DCRDR Program.
These surveys are identified in Section 2.4 of the Report and will be performed for the combined Unit 1 & 2 control rooms.
We plan to begin the surveys shortly after the completion of the Unit-1 sixth refueling outage.
Upon completion of the surveys and the assessment of discrepancies, a report of our findings will be submitted to the NRC.
In
- summary, we believe that the DCRDR Supplemental Report provides a
comprehensive and up-to-date response to the NRC's request.
The arrangement of items in the Report should facilitate the NRC Staff's review.
We have also provided a computerized list in a
manageable format to assist in tracking HED resolutions.
DLC will continue to actively pursue the timely processing of new HEDs to be identified in the upcoming surveys and to seek the closure of all DCRDR issues.
If you have any questions regarding this submittal, please contact myself or members of my staff.
Very truly yours, 4
i bW D.
Sieber ice President, Nuclear Attachment cci Mr. J.
Beall, Sr. Resident Inspector i
Mr.
W. T. Russell, NRC Region I Administrator Mr.
P. Tam, Project Manager t.