ML19220C140
| ML19220C140 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/22/1977 |
| From: | Skovholt D Office of Nuclear Reactor Regulation |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904280288 | |
| Download: ML19220C140 (2) | |
Text
~
6 NUG23197
~
DISTRIBU110ft cDgket FiTes.
R. C. DeYoung flRR Reading D. J. Skovholt GA Reading R. J. McDermott QA Project Docket No.: 50-320 HEMORANDU:i FOR:
D. B. Vassallo, Assistant Directo.- for Light Water Reactors, Division of Project Management FROM:
Donald J. Skovholt, Assistant Director for Quality Assurance and Operations, Division of Project Management
SUBJECT:
METROPOLITAN EDISCN COMPANY, THREE MILE ISLAllD UNIT NO. 2, SUPPLEMENT TO SAFETY EVALUATION REPORT FOR INITIAL TESTS AND OPERATION t
The Quality Assurance Branch has completed review of Section 14 of the FSAR, Initial Tests and Operation, through Amendment 58. A supplement l
to our original Safety Evaluation Report, dated May 14, 1976 is enclosed.
j We conclude that the initial test progra:n is acceptable.
L Original Signed by.
Dona!d J. Skovholt Donald J. Skovholt, Assistant Director for Quality Assurance & Operations Division of Project Managecent Enclosure Section 14.0 Initial Tests and Operation s
cc: w/ enclosures S. Varga, LWR 14 s
H. Silver, PM R. DeYoung, PM cc: w/o enc 1osure W. Mcdonald, MIPC
'b f
8]
J C
E 0___
________,___j _________
2 A _!kDhoh d_L _lf len:e s_!jk.sivftolt_i _ _ _ __ _ _ _ __ _ _ !__ _
--i[-l ~ __ _
8/g7__f___8f[i/_77___[___8/_7J7_7___f___
I
. 676) NRCM 02040 c u.s'. sov raN*4cN r p aiN riN o o w n c t: ins u
_,u 7 909'2 s 07fg
14.0 INITIAL TESTS AND OPERATION The staff's original Safety Evaluation Report concluded that the initial test program proposed by the applicant was acceptable with the exception of the following two outstanding items:
1.
The proposed acceptance criteria for scram tinie testing of control rods.
2.
Tests that would demonstrate the response times o' tection system primary sensors and interfacing hardware bt the measured variables and the input to the sensors for
.e Reactor Protection System and Engineered Safety Features Actuation System.
The applicant has amended his FSAR, through Amendment 58, to resolve Item 1 above.
Item 2 was resolved satisfactorily by both Amendment to the FSAR and by tne Babcock & Wilcox letter to NRR dated June 15, 1977. The staff, therefore, concludes that the applicant has proposed to conduct an acceptable initial test program for the facility, s
B/
3u0
~
-7
/