ML20003D682
| ML20003D682 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 03/25/1981 |
| From: | Parker W DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM NUDOCS 8103300336 | |
| Download: ML20003D682 (2) | |
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Dt:r:s Powru COMPANY Powra Dettomo 422 Soce Cucacu StazzT, Cruaz.orTz. N. C. as242 WI LLI Aho C. PAR E C R J R.
su. a.oo-c..'o-March 25, 1981
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Mr. Harold R. Denton, Director 2
Office of Nuclear Reactor Regulation j
Q'v Vg U.S. Nuclear Regulatory Cot: mission
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i-2 Attention: Mr. B. J. Youngblood, Chief
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Licensing Projects 3 ranch No.1 7
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Re: McGuire Nuclear Station Docket Nos. 50-369 t.,,,/
Dear Mr. Denten:
This letter is to confirm our telephone discussion of March 24, 1981 regarding Item II.F.2 as well as to provide Duke Power Company's position on'several other outstanding review items on McGuire.
II.F.2 Prior to June 1, 1981, Duke Power will replace the existing analog meter on the core exit thermocouple monitoring panel with an installed display capable of reading to at least 2300 F.
A loss of power to the reference junction thermocouple enclosure will not pre-ciudrj utilization of the installed readout capability.
Duke Power is evaluating the core exit thermocouple system in light of the NRC Staff's review guidance, R.G. 1.97 and Attachment 1 to II.F.2 and will provide its assessment of the system by April 23, 1981.
With regard to the Reactor Vessel Level Indicating System (RVLIS) testing pro-gram, it is our understanding that the " developmental" testing is being con-ducted jointly by Westinghouse, NRC and EG&G personnel. Upon completion of this testing, a report documenting the results would presumably be written.
If necessary Duke Power will submit this report on the McGuire docket to.sup-port use of the RVLIS. Additionally, the results of the plant calibration and testing will be provided upon completion of these activities.
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81033008 36
e Mr. Harold R. Denton, Director March 25, 1981 Page 2 I.D.2 This item requires each applicant to install a Safety Parameter Display System in accordance with NUREG 0696. NUREG 0696 was recently transmitted to Duke Power Company by letter of March 5, 1981. This letter stated that "The Com-mission has approved NUREG 0696 and noted that this doct'ent provides general guidance only,... and that compliance with NUREG 0696 is not a requirement."
Auditionally, NURIG 0700 is scheduled to be issued in the near future as guidance for conducting control room reviews. Duke will address the SPDS concept as part of its control room review. This is considered an appropriate couse of action since any decision relating to safety displays must consider the integration of these displays with overall operating objectives.
II.D.1 Duke Power will provide verification cf block valve functionability under all
- fluid conditions expected during operating and accident conditions by July 1, 1982. The basis for this verification will be functional testing with appro-priate supporting analysis. A program outline describing the methods will be submitted by July _1,1981.
Please advise if you have additional questions regarding any of these matters.
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'truly yours t.LLi LA 1f.<.A.
~ William O. Parker, GAC:pw cc:
T.:J. Donat J. P. O'Reilly, Director Senior Resident Inspector U.S. Nuclear. Regulatory Commission McGuire Nuclear. Station Region II 101 Marietta Street, Suite 3100 Atlanta,_ Georgia 30303