ML19309A759
| ML19309A759 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/24/1980 |
| From: | Lewis S NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Bowers E, Cole R, Shon F Atomic Safety and Licensing Board Panel |
| References | |
| NUDOCS 8004010292 | |
| Download: ML19309A759 (2) | |
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March 24, 1980 Elizabeth S. Bowers, Esq., Chairman Dr. Richard F. Cole Atomi, Safety and Licensing Board Panel Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Washington, D.C.
20555 Mr. Frederick J. Shon Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.
20555 In the Matter of Sacramento Municipal Utility District (RanchoSecoNuclearGeneratingStation)
Docket No. 50-312 (SP)
Dear Members of the Board:
Mrs. Bowers and Dr. Cole have called to my attention that there may be some confusion as to what NRC Staff testimony was admitted at Tr. 1163.
The fact that the Reporter failed to insert the testimony in the record undoubtedly added to the confusion. To clarify the record I have prepared the attached list of NRC Staff testimony which should now be found following Tr. 1163.
I will ask that this list be inserted in the record at the outset of the session of April 8, 1980.
Sincerely, A k, bN Steph n H. Lewis Counsel for NRC Staff
Enclosure:
List of NRC Staff Testimony Which Was Admitted and Should Be Bound Following Transcript 1163 cc w/ enclosure: David S. Kaplan, Esq.
Mr. Michael R. Eaton Thomas A. Baxter, Esq.
Atomic Safety and Licensing Senator Allen R. Carter Board Panel Christopher Ellison, Esq.
Atomic Safety and Licensing Dian Grueneich, Esq.
Appeal Board Panel Herbert H. Brown, Esq.
Docketing and Service Section Lawrence Coe Lanpher, Esq.
8 0 0<1010 2 0 2
r RANCHO SECO LIST OF NRC STAFF TESTIMONY WHICH WAS ADMITTED AND SHOULD BE B0UND FOLLOWING TRANSCRIPT 1163 1.
Testimony of Robert A. Capra on Implementation of Long-Term Modifications Established in the Commission Order of May 7, 1979 (F0E Ccntention III(c)).
2.
NRC Staff Testimony of Philip R. Matthews, Adequacy of the Pressurizer and Pressurizer Relief Tank Size (Board Question 21).
3.
NRC Staff Testimony of Philip R. Matthews On Reliability and Timeliness of the Emergency Feedwater System (Board Question - CEC 1-6).
4.
NRC Staff Testimony of Thomas M. Novak Regarding Reconsideration of the Requirements for Automatic and Manual Safety Actions (CEC Issue 5-3a).
5.
NRC Staff Testimony of Mark P. Rubin and Thomas M. Novak Regarding the Sensitivity of the Once-Through Steam Generator Design (Additional Board Question 3).
6.
NRC Staff Testimony of Mark P. Rubin and Thomas M. Novak Regarding the Acceptability of Feedwater fransients Referenced in NUREG-0560 (F0E Con-tention III(a)).
7.
NRC Staff Testimony of Mark P. Rubin and Thomas M. Novak Regarding the Design Basis for Rancho Seco Safety Systems (CEC Issues 1-1 and 1-12).
8.
NRC Staff Testimony of Dale F. Thatcher Relative to Direct Initiation of Reactor Trip Upon the Occurrence of Off-Normal Condition in the Feedwater System (Board Question 9 and Additional Board Question 1).
9.
NRC Staff System of Dale F. Thatcher Relative to the Integrated Control System (Board Question 16). (The ORNL review of B&W's Integretated Control System Reliability Analysis is attached to Mr. Thatcher's testimony.
That document has been marked for identification as CEC Exhibit 4.)