ML17037C164
| ML17037C164 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/09/1975 |
| From: | Bartlett J Niagara Mohawk Power Corp |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037C164 (6) | |
Text
NRC DISTRIBUTION FQR PART 50 DOCKET MATERIAL (TEMPQfkAAYFORM)
CONTROL NQ:
FILE'iagara Mohawk Power Corp Syracuse.
N Y J Partlet 7=9-75 7-l5-75
'DATE OF DOC DATE REC'D LTR XX 1WX RPT OTHER TO:
CLASS Mr. Lear Ui~ICLASS PROP If)IFO ORIG l signed INPUT CC OTHER NO CYS AEC'D SENT LOCAL PDA DOCKET NO:
50-220 Ltr concerns info transmitted DESCR IPTIQN:
by them on 6-27-75, Proposed Tech Spec change that. did not entirely conform to the guidline we presented in our 6-18-75 ltx', provide'd herewith is their schedule for responding to
, the required info described in attachment l of our ltr,..
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J PLANT NAML: Nine Mile Point ENCLOSURES:
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NIAGARAMOHAWKPOWER CORPORATION NIAGARA ~
MOHAWK 300 ERIE BOULEVARD, WEST SYRACUSE, N. Y. 13202
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~~egEO Mr. George Lear, Chief 7
Operating Reactors Branch ¹3 Division of Reactor Licensing
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U. S. Nuclear Regulatory Commission
<"<Is P~N I'lashington, D. C.
20555 j~o Re:
Nine Mile Point Unit 1 Docket No. 50-220 P~+p~ P 4~+
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Dear Mr. Lear:
On June 27, 1975 Niagara Mohawk Power Corporation submitted as scheduled proposed Technical Specification changes and supporting analysis in accordance with your December 27, 1974 Order.
The information transmitted did not entirely conform to the guidelines presented in your June 18, 1975 letter.
Provided herewith is our schedule for responding to the six items described in Attachment 1, "Required Information" of this June 18, 1975 letter.
1.
Break S ectrum and Partial Loo 0 eration Niagara Mohawk plans to submit by July 2S, 197S, information to supplement the June 27, 1975 submittal.
2.
Potential Boron Preci itation (Pl'IR's Onl )
This is not-applicable to Nine Mile Point Unit 1.
3.
Sin le Failure Anal sis The effects of a single failure or operator error that causes any manually controlled, electrically operated valve in the Emergency Core Cooling System to move to a position that could adversely affect the Emergency Core Cooling System has been included in our June 27, 1975 submittal.
/
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George Lear July 9, 1975 The potential for passive failure of fluid systems during long term cooling following a Loss of Coolant Accident as well as single failures of active components has been evaluated.
Single failures of passive components in electrical systems are assumed in designing against a single failure.
Emergency Core Cooling Systems are designed such that flow blockage of a single pipe cannot prevent a required safety output function.
During the long term cooling mode the Emergency Coze Cooling Systems are operating at pressures and temperatures considerably below their design basis, thus the propensity for failure is reduced below that during operation at design conditions.
4.
Submerged Valves Niagara Mohawk Power Corporation plans to submit by August 8, 1975 the results of our review of equipment arrangements to determine if any valve motors within the containment will become submerged followiag a Loss of Coolant Accident.
5.
Containment Pressure (PNR's Only)
This is not applicable to Nine Mile Point Unit 1.
6.
Low Emergency Core Coolin System Reload Rate g(estin house NSSS Onl )
This is not applicable to Nine Mile Point Unit 1.
Very truly yours, J. Bartlett Executive Vice President
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