ML20082P249
| ML20082P249 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/29/1991 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-17, NUDOCS 9109100249 | |
| Download: ML20082P249 (3) | |
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o.h. l l 1,' s ?\\il DUKE PCWER August 29,1991 U. S. Nuclear Regulatory Commission ATI'N: Document Control Desk Washington, DC 20555
Subject:
Catawba Nuclear Station, Units I and 2 Docket Nos. 50-il3 and 50-414 Generic Letter 88-17, " Loss of Decay Heat Removal" Status of Programmed Enhancements In a letter dated April 29, 1991, the NRC transmitted it's comments on Duke Power's iesponse to Generic Letter (GL) 88-17 with respect to the programmed enhancements either planned or implemented at Catawba Nuclear Station. This letter also requested that Duke Power inform the NRC if any of these programmed enhancements were not completed in the time frame stated in the GL.
Find attached the status of the programmed enhancements that were not coinpleted in the time frame of the GL. These open items are referenced to Duke Power's response to the NRC on programmed enhancements dated February 2,1989.
Very truly yours, M hw h i
M. S. Tuckman CRIJGLS817.791 Attachment xc: S. D. Ebneter Regional Administrator, Region 11 W. T. Orders Senior Resident inspector R. E. Martin, ONRR 9109100240 910929 DR r4 DOCK 0500 3
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CATAWBA NUCLEAR STATION Status of Generic Letter 88-17 Programmed Enhancements (2) Procedures Duke stated that the " Loss of DHR" procedure would be integrated with the emergency procedure logic taMng into consideration a loss of reactor coolant during non power operations.
The recovery from a loss of RHR is currently proceduralized in an abnormai procedure. The integration of this abnormal procedure with the emergency procedures is currently pending the issuance of the WOG Emergency Response Guideline (ERG) for a shutdown LOCA. This procedure guideline has been delayed in publication, but is pending issuance in the Fall of 1991, he abnormal procedure for loss of RHR will be integrated into the emergency procedure framework within a reasonable time period after receipt of the ERG.
(5) Technical Specifications The following is a list of the planned Technical Specific.ition changes that will not be pursued along with the reasons why these changes are not needed:
- Incceased availability of ECCS subsystems during non-power operations.
The use of a safety injection pump as an alternate high head injection flowpath was added to the abnormal procedure for loss of RHR. This action was taken based on one of the recommendations from a Duke Power design study. Since this administrative control serves the same purpose as the planned Technical Specification changes related to ECCS availability, these Technical Specification changes are no longer considered necessary and will not be pursued.
- Deletion of the autoclosure interlock from the DHR system The physical deletion of the autoclosure interlock hardware has not been implemented at the plant, although it has been internally approved for implementation Procedural requirements currently disable the interlock function during RHR operations by removing power from the isolation valves during
- periods of reduced inventory.
Since this meets the intent of the planned Technical Specification change as it relates to GL 88-17, this Technical a
SpeciGeation change will no longer be pursued in connection with the programmed enhancements for Generic Letter 88-17.
- Possible Technical Speci0 cation requirements for containment closure during periods of reduced inventory operations.
Current procedural requirements for containment closure during reduced inventory operations are being placed into a Selected Licensee Commitment which covers reduced inventory operations.
As a result of this SLC, no Technical Speci6 cation change will be necessary in this area.
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