ML19309A658
| ML19309A658 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/24/1973 |
| From: | Davis E SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003310566 | |
| Download: ML19309A658 (2) | |
Text
Y AEC "ISTRIBUTION FOR PART 50 DOCKET P**'ERIAL 7882 (TDIPORARY FORM)
CONTROL NO:
FILE:
FROM:
DATE OF DOC DATE REC'D LTR MEMO RPT OTHER S cramento !!unicipal Utility Dist.
Sacramento, Calif. 95813 Mr. E.K. Davis 10-24-73 10-29-73 X
TO:
ORIG CC OTHER SENT AEC PDR XXX SEUT LOCAL PDR XXX A. Giambasso 1 signed CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
XXX 1
50-312 DESCRIPTION:
ENCLOSURES:
Ltr submitting add'l info documenting ADD'L INF0; entitled " Accident Monitoring" conmitments made during recent discussions with AEC Staff....trans the following.....
(1 cy encl rec'd)
PLANT NAME:
Rancho Seco FOR ACTION /INFORMATION 10-30-73 JB BUTLER (L)
/ SCIMENCER(L)
ZIEMANN(L)
REGAN(E)
W/ Copies W/ACopies W/ Copies W/ Copies CLARK (L)
STOLZ(L)
DICKER (E)
W/ Copies W/ Copies W/ Copies W/ Copies GOLLER(L)
VASSALLO(L)
KNIGHTON(E)
W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L)
JOHalEL(L)
YOUNGBLOOD(E)
W/ Copies W/ Copies W/ Copies W/ Copies INTERNAL DISTRIBUTION f REG FILE ]
TECH REVIEW
/ DENTON A/T IND am,run HENDRIE
/ GRIMES LIC ASST BRAIDIAN OGC, ROOM P-506A SCHROEDER
/ GAMMILL DIGGS (L)
SALTZMAN MUNTZING/ STAFF
/ MACCARY KASTNER GEARIN (L)
B. HURT
/ CASE vKNIGHT BALLARD
/ GOULBOURNE (L) pggg
/
GIAMBUSSO v PAWLICKI SPANGLER LEE (L)
/ MCDONALD BOYD
- SHA0 MAIGRET (L)
DUBE MOORE (L)(BWR) /
STELLO ENVIRO SERVICE (L)
/
DEYOUNG(L)(PWR)
/ HOUSTON MULLER SHEPPARD (E)
INFO SKOVHOLT (L)
/ NOVAK
/ DICKER SMITH (L)
C. MILES P. COLLINS
/ROSS KNIGHTON TEETS (L)
/ IPPOLITO YOUNGBLOOD WADE (E)
/ REG OPR
/
TEDESCO REGAN WILLIAMS (E) 8 0 03 310R4 FILE & REGION (3)
/LONG
/ PROJECT LDR WILSON (L)
MORRIS
/ LAINAS Lasch STEELE
/ BENAROYA HARLESS l
/ VOLINER EXTERNAL DISTRIBUTION
\\\\ h
- 1 - LOCAL PDR.
Sacramento. Calif.
/1 - DTIE(ABERNATHY)
(1)(2)(10) NATIONAL LAB'S t/ -PDR-SAN /kkfdct 1
i
/1 - NSIC(BUCHANAN) 1-GERALD LELLOUCHE 1 - ASLB 7 ^Z,':lJ:Z '
,1-W. PENNINGTON, Rm E-201 GT BROOKHAVEN NAT. LAB WG9thheh&WM49. N[&a/
l-CONSULTANT' S 1-AGMED(Ruth Gusscan) 16 - CYS ACRS HOLDING NEWMARK/BLUME/AGBABIAN RM-B-12 7, GT.
1-GERALD ULRIKSON...ORNL l-RD.. MULLER..F-309 Gi
6 3
O Rs.~u!at:ry File Cyi
/
$ SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacramento, Califomia 95813; (916) 452-3211 i
I October 24, 1973
~, $' At., $
,..l* \\ : ' 'Wlc-e.h, y + / eg
-[
l Mr. Adgelo Giambusso I C g.
g Deputy Director for Reactor Projects t
4 Directorate of Licensing U
U. S. Atomic Energy Commi on g
Washington, D. C.
20545 p
Rancho Seco Nuclear Generating Station No. 1 AEC Docket No. 50-312 l
Dear Mr. Giambusso:
j The Sacramento Municipal Utility District hereby submits l
additional information documenting commitments made during recent discussions with your staff.
l l.- The District will add to its staff an engineer with metallurgical experience. With this addition, the Management Safety Review Committee will collectively I
have, or have access to, all areas of technical f
expertise defined in ANS 3.2, " Standard for Adminis-trative Controls for Nuclear Power Plants."
2.
The District has assured itself that instrumentation for determining the course of potentially serious accidents, on a time scale that will permit appropriate emergency action, is provided at the station and that appropriate calibration methods and calculated bases for interpreting instrument responses are available.
Enclosed is a summary of the capability of accident monitor-1 ing and evaluation.
Sincerely yours, g
S l
e 4
k 44 %
ocT sY@3
- E. K. Davis g
General Manager g
{
f.
h R stense 90GRET Attachment 8
g 7882 T H o fd MO@_00@
'N THE HEART OF CALIFORN!t
J
~
ACCIDENT MONITORING I.
Adequate instrumentation has been provided for determining the course of potentially serious accidents. The parameters to be monitored and the associated instrumentation provided are summarized below:
1.
Instrumentation inside the Reactor Building capable of withstanding the accident environment permit monitoring the following parameters:
Nuclear Instrumentation (as specified in FSAR Section 7.1.1.7) a.
b.
Reactor Building Pressure c.
Reactor Building Temperature d.
Reactor Building Emergency Sump Level Area Radiation Inside Reactor Building e.
f.
Reactor Coolant Pressure g.
Reactor Coolant Temperature 2.
Instrumentation outside the Reactor Building which would provide additional information for evaluation of a postulated accident include the following:
a.
Reactor Building Hydrogen Monitor b.
Area and Site Boundary Radiation Monitors c.
Recirculation Temperature from Sump d.
Recirculation Temperature -from Decay Heat Removal Coolers e.
High Pressure Injection Flow f.
Low Pressure Injection Flow g.
Reactor Building Spray Flow h.
Meteorological Instrumentation 1.
Indicating Lights for Equipment Operating Status (valve position, motor energized, etc.)
II.
Adequate calibration methods ani basis have been established and are specified in the plant standards and procedures. The minimum frequency for instrumentation check, calibration, and testing is provided in Technical Specification 4.1.
?SS2
,