ML17037B566
| ML17037B566 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/05/1976 |
| From: | Rhode G Niagara Mohawk Power Corp |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037B566 (6) | |
Text
NRI FORM 195 (2-76)
FROM: NIAGARA MOHAWK POWER CORP
- SYRACUSE, NY U.S. NUCLEAR REGULATORY COMMIS N
NRC DISTRIBuTION FDR PART 50 DOCKET MATERIAL DOCKET NUMBER 50-220 FILE NUMBER DATE OF DOCUMENT MR B C RUSCHE LETTE R
@ORIGINAL OCOPY ONOTORIZED gUNC LASSIFI ED PROP R
I)F INPUT FORM DATE RECEIVED 3-8-76 NUMBER OF COPIES RECEIVED k Siga~b DESCRIPTION ENCLOSU RE LTR RE OUR 2-27-76 LTR......FURN CLARIFACATION ON CERTAIN ITEMS CONTAINED IN REFERENCE....:
FURTHER ADVISING TAAT THE CALCULATED LOAD RATIONS.
ON THE TORUS SUPPORT COMPONENTS WERE BELOW 1.0...........
PLANT ME: g)gq SAFETY ASSXGNED AD:
BiUUiCH CHIEF:
PROJECT MANAGER:
- LXC, SST ENVIRO
- II-ASSIGNED AD:
BF IINCP CPTEF PROJECT MANAGER:
LIC, ASST, FOR ACTION/INFORMATION REG FI
'NRC PDR I&E GOSSICK & STAFF PROJECT MANAGEMENT BOYD P
COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LP.DR-4)c 0
TIC NS ASLB INTERNALD IST EN NEE N
KNIGHT SIHWEIL PAVLXCKI REACTOR SAFETY ROSS NOVAK ROSZTOCZY CHECK AT & I SALTZMAN RUTBERG EXTERNAL DISTRIBUTION NATL LAB REG~ V-IE LA PDR CONSULTANTS RI BUTION BENAROYA IPPOLITO OPERATING REACTORS STELLO OPERATING TECH EISENHUT SHAO BAER SCHWENCER GRIMES SITE SAFETY & ENVIR ANALYSIS DENTON & MULLER BROOK VEN NATL LAB ULRIKSON(ORNL)
ERNST AL RD SPANGLER SXTE TECH GAMMILL STEPP HULMAN SITE ANALYSIS VOLLlIER BUNCH J,
COLLINS KREGER CONTROL NUMBER NRC FORM 195 {2-76)
I sn
NIAGARAMOHAWKPOWER CORPORATION
.iIWh; NIAGARA '~
MOHAWK ii j i 300 ERIE BOULEVARD. WEST SYRACUSE. N. Y. 13202
~ w(i ji March 5, 1976
, IiIjllo Office of Nuclear Reactor Regulation Attn:
Mr. Benard C. Rusche, Director U. S. Nuclear Regulatory Comu'.ssion Washington, D. C.
20555 Re:
Nine Mile Point Unit 1 Docket No. 50-220 DPR-63
Dear Mr. Rusche:
This letter is to acknowledge receipt of your February 27, 1976 communication and t'o provide clarification on certain items con-tai ned therein.
My February 27, 1976 letter to Mr. George Lear confirmed our commitment to implement a drywell pressure increase of one pound per square inch over the suppression chamber pressure at Nine Mile Point Unit 1 and we subsequently advised your staff on March 1 t'hat this operating mode had indeed been achieved.
It should be not'ed that'he calculated load ratios on the torus support components for Nine Mile Point Unit 1 were considerably below t'e 1.0 referenced in your letter, even before the drywell pressure increase.
This new pressure adjustment should improve the safety margin at Nine Mile Point Unit 1 to at least a factor of two for the welds at the top of the torus support columns.
Therefore, there are no plans for structural modifications to the containment system at this facility.
V i('
Mr. Benard C. Rusche U. S. Nuclear Regulatory Commission Page Two March 5, l976 Xt is our understanding that your directive of February 27, l976 was intended to be complementary to-the current Technical Specifi-cations for Nine Mile Point Unit l.
Specifically, Specifications 3.3.l.b and 4.3.6.a provide for short operational periods during containment inerting after a shutdown and for monthly vacuum relief valve operability tests, respectively, when maintenance of the differential pressure would not be possible."
The Technical Specifications will continue to be followed in these cases.
Very truly yours, NIAGARA MONAhK POWER CORPORATION LD ODE Vice President -
ngineeri ng
/sz
0 vN I >
g%
~
h