ML17037B955
| ML17037B955 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/30/1976 |
| From: | Rhode G Niagara Mohawk Power Corp |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037B955 (4) | |
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NRQ FORM 195 I
(276 I DOCKET NUMBER V.S. NUCLEAR BEGULATORVCot SION FILE NUMOEB Mr Stolr.
Niagara Mohawk Pwr Corp G K Rhode Syracuse, NY'ATE OF DOCUMENT 6"30-76 DATE BECE VED 7-6-76 QNOTOBIZED lj(UNCLASSIFIED NUMBER OF COPIES RECEIVED PROP INPUT FORM ETTER lgORIGINAL QCOPV one signed ENCLOSU BE
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.'<Plant Design, Assessment for Safety Relief Valve tandI Eoss of~Coolant Accident Loads"
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NIAGARA MOHAWK POWER CORPORATION NIAGARA~
MOHAWK 3DD ERIE BOULEVARDWEST SYRACUSCd N.Y. I3202 June 30, 1976 Director of Nuclear Reactor Regulation Attn:
Mr. J'. F. Stolz, Chief Branch 2-1 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Re:
Nine Mile Point Unit 2 Docket No. 50-410
Dear Mr. Stolz:
Your letters of'pril 18 and 21, l975 requested information on containment hydrodynamic loads and safety relief valve blowdovn phenomena for Nine Mile Point Unit 2.
Enclosed are three copies of a report entitled, "Plant Design Assessment for Safety Relief Valve and Loss of Coolant Accident Loads."
This report substantiates that the Unit 2 containment can vithstand simultaneous loss of coolant accident and safety relief'alve loads.
Sections 1.5, 4.3, 7.0 and 10.2 describe additional analyses which are continuing.
The results of these analyses vill be reported in supplements to this report.
I l / /
Very truly yours, NIAGARA MOM@K POVER CORPORATION d
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=Todd GERALD K. R ODE Vice President E ineeri ng
('sz Enclosures (3) 86SS
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