ML17179A858
| ML17179A858 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 02/25/1993 |
| From: | Kelly G Office of Nuclear Reactor Regulation |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17179A859 | List: |
| References | |
| NUDOCS 9303220074 | |
| Download: ML17179A858 (2) | |
Text
Common.Ith Edison 1400 Opus ce Downers Grove, Illinois 60515 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Attn: Document Control Desk September 10, 1993
SUBJECT:
Transmittal of Revision to Relief Request RV-23H from the 3rd Ten Year Interval Inservice Testing (IST) Plan
REFERENCES:
(a)
R. Barrett to T. Kovach letter dated September 11, 1992 (TAC Nos. M82986 and M82987).
Dr. Murley:
(b)
- P. Piet letter dated to T. Murley, dated June 30, 1993.
This letter provides transmittal of the response requested by the Reference (a) Safety Evaluation Report (SER) regarding relief request RV-23H from the 3rd Ten Year Interval Inservice Testing (IST) Plan. The remainder of items from this SER have been previously submitted under Reference (b). Relief Request RV-23H has been modified to include the p:r;eventive maintenance performed on the HPCI Exhaust Drain Pot Solenoid valves. In addition to stroking the valves without timing on an operational basis and functionally testing on a refuel outage basis, these valve assemblies will be replaced every third refuel outage.
Two other methods of testing were considered for the HPCI Exhaust Drain Pot Solenoid valves. These methods were acoustic testing and measurement of the coil impedance or resistance. Acoustic testing was eliminated because the valve has a DC electrical power source. The Dresden Station acoustic monitoring equipment is not effective on DC power sources. The measurement of coil impedance would require breaking the circuit; thus, the system would be degraded. Dresden Station does not believe that either of these methods would significantly add to the reliability of these valves.
k:\\nla\\dresden\\piet3. wpf\\ 1
Dr. Murley September 10, 1993 The following is a listing of the attached pages affected by this revision. Please make the following replacements to Revision 1 of the IST Plan.
SECTION REPLACEMENT 2
Page 2-1 Rev. 1 with page 2-1 Rev. 2 13 Pages 13-1to13-4 Rev. 1 with pages 13-1 to 13-4 Rev. 2 14 Page 14-40 Rev. 1 with page 14-40 Rev. 2 Dresden Station requests NRC Staff review and approval of the subject Inservice
- (
Testing Relief Request (RV-23H) Revision.
If there are any questions concerning this submittal, please contact this office.
Sincerely,
\\fl;:SiP-1 Peter L. Piet Attachment cc:
J. B. Martin, Regional Administrator - Riii J. F. Stang, Project Manager - NRR Nuclear Licensing Administrator M. N. Leach, Senior Resident Inspector - Dresden k:\\nla\\dresden\\piet3. wpf\\2