05000000/LER-1983-034-03, /03L-0:on 830419,Fire Door S71-18,between Emergency Diesel Room 2H & Turbine Bldg,Would Not Latch. Caused by Latch Sticking.Latch Lubricated
| ML20083E839 | |
| Person / Time | |
|---|---|
| Site: | 05000000, North Anna |
| Issue date: | 05/11/1983 |
| From: | Cartwright W, Harrell E VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20083E834 | List:
|
| References | |
| FOIA-83-562 LER-83-034-03L-03, LER-83-34-3L-3, N-83-058, N-83-58, NUDOCS 8312300006 | |
| Download: ML20083E839 (2) | |
| Event date: | |
|---|---|
| Report date: | |
| 0001983034R03 - NRC Website | |
text
___
L..--
.~c o
U.S. NUCLEAR RECULATORT cot 9 FISSION LICWSEE EV DT REPORT CONTROL BLOCK / / / / / / / (1) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
/0/1/
/T/A/N/A/S/2/ (2)
/0/0/-/0/0/0/0/0/-/0/0/ (3)
/4/1/1/1/1/ (4)
/ / / (5)
LICENSEE CODE LICDf.E NLMBER LICENSE ITFE CAT 3/(6)
/0/5/0/0/0/3/3/9/ (7)
/0/4/1/9/8/3/ (8) D /5 /1/1/B /3 / (9)
DOCKET htHRER EV UT DATE REPORT CATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)
/0/2/
/ On April 19, 1953. w $ Unit 2 in the Refueling Mode, Tire Door $71-18, between /
/0/3/
/ the 7H ImorRency Diesel Room and the Turbine Building, would not latch. Since a /
/0/4/
/ fire watch was immediately posted the public health and safety were not affected./
/0/5/
/ The dearadation of fire doors between the Emergency Diesel Rooms and Turbine
/
/0/6/
/ Duildina due to dif ferential pressure between the areas during diesel operation _/
/0/7/
/ is a recurrina event. This event is contrarv to T.S. 3.7.15 and reportable pur- /
/0/8/
/ enant to T.S. 6.9.1.9.b.
/
SYSTEM
CAUSE
CACSE COMP.
VALVE CODE CODE SU3CCDE COMPONENT CODE SUBCODE SUBCCDE
/0/9/
/A/B/ (11) /E/ (12) /B/ (13) /I/I/I/I/I/I/ (14) /Z/ (15)
/Z/ (16)
SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT TEAR REPORT NO.
CODE TYPE NO.
(17) REPORT NCMBER
/8/3/
f-/ /0/3/4/
/N/
/0/3/
3/
J-/
/0/
ACTION FUTURE EFTICT SHUTIXNN ATTACIMENT NPRD-4 PRIME COMP. COMPONENT TAED ACTION ON PLANT METHOD HOURS SUEMITTED FORM SUS. SUPPLIER MANLTACTURER g/ (18) /I! (19) /Z/ (20) /Z/ (21) /0/0/0/0/ (22) /N/ (23) /N/ (24) /A/ (25) /C/1/7/5/ (26)
CAUSE DESCRIPTION AND CORRICTIVE ACTIONS (27)
/1/0/
/ Fire Door $71-18 would not latch because the latch was sticking. The latch was /
/1/1/
/ lubricated and operation of the fire door tested satisfactorily. Design modifi- /
/1/2/
/ cation to the fire doors between the Diesel Rooms and the Turbine Building are
/
/1/3/
/ being pursued.
/
/1/4/
/
/
FACILI!T METHOD OF STATUS 2 POWER OTHER STATUS (
DISCOVERY DISCOVERY DESCRIPTION (32)
/1/5/
/_H/ (28)
/0/0/0/ (29) /
NA
/
/A_/(31)
/ Operator Observation /
ACTIVITY COhTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY (35)
LOCATION OF RILEASE (36)
/1/6/
/Z/ (33)
/Z/ (34) /
NA
/
/
NA
/
PEb ONNEL EXPOSURES i
NLMBER TTPE DESCRIPTION (39) l
/1/7/ /0/0/0/ (37) /E/ (38) /
NA
/
PERSONNEL INJURIES NUMBER DESCRIPTION (41)
/1/8/ /0/0/0/ (40) /
NA 8312300006 831018
/
PDR FOIA LOSS OF Ott DAMAGE TO FACILITY (43 s
GRABER83-562 PDR TYPE
DESCRIPTION
/1/9/
/Z/ (42) /
NA
/
PUBLICITT ISSUED DESCRIPTION (45)
NRC USE ONLY
/2/0/
/N/ (44) /
NA
///// ////////
NAME OF FREPARER W. R. CARTWRIGHT PHONE (703) 894-5151
nn
-,n me.w,www-=
- =
y--
l-
,,~
..oc..
pt.,
I.,
- - g s 0,
l
.- 9
- / /
i
- Q Y i
.I December 20. 1982
~-
?=
$.EQ.
1
[.
J W n ' 36$la15 2
- r ouc JJHal
~-
U. S. Nucisar Regulatory Coonfssion
\\
a f
Office of Inspection and Enforcement
' i40 DATE MMd l
ion V I -I O Marta tane. Sutte t10 CD DATE _.
(
Walnut Creek C411fornia 94596-5368 2
y
.j I Attention:
Mr. R. H. Engelken. Regional Ad.inistrator
Dear Sir:
i n
tl
Subject:
Docket No. 50-361
(-
30-Day Report Licensee Event Repo-t No.82-152
)
{
San Onofre Nuclear Generating Station. Unit 2
{
i i
I This sutetttal is in accordance with the reporting requirerents of i
Section 6.9.1.13.b of Aopendix A to Facility Operating License NpF-10.
1 It describes a reportable occurrence involving Limiting Condition for I
Operation (LCO) 3.3.3.6 assocf.ated with Accident Honttoring Instrumentation.
.j A completed ccpy of LER 82-Ib2. is enclosed.
5 Uhile in 11 ode 3. at 2010 on Novoster 21. 1982, the daily surveillance testing in accordance with procedure 5023-3-3.21.1 was in pmgress. Due to loss of process flow, as indicated by radiation indictor 2RI-7872-1 the Condenser Evacuation Systen radiation monitor (wide range) was r
i declared inoperable. Action Stateraent 22 of Table 3.3-10 associated fi with tnis inoperable centter results in an undefined action requirement due to a typographical error in the Technical Specifications. Correction 4,
of this Action Statenent has been requested in License Amendnent Application l
44 15 and the action taken was as defined in that appitcation (i.e. either restore the inoperable nonttor to operable status within 7 days, or be
'i in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />).
S bsequent investigation revealed that the sonitor problem was ettributable
.j to a faulty velocity probe associated with the monitor. The faulty prce
.t was replaced and the senitor declared operable in accordance wtth 5023-f 3-3.21.1 at 1705 on Novenber 24, 1982. Ofscussions with the probe canufacturer indicate that this failure is infrequent and, therefore, t
this is considered an isolated event. No further corrective action is l
warranted at this time.
1 L
J 13
}.
mt - _..
2 u.,
n-y
.u
... mr
_. y q.
...7 +5 n
c,. :_.
oa T9 1 "s 1,
l 1
R. H. Engelken December 20,1962 thers was no tapact en plant 4perations or the health and safety of
.' i
.4 plar:t personnel or the public as a result of this event.
'k j
If there are any questions regarding the above, please contact me.
f,, s -
$1ncerely, I.* '
3 k
.'l -
6 y
nt>a/m H. B. RAY STATION MANAGER t
9 g
L!Mayweather:VM t
9 Enclosure: 1.ER 82-152 1;
4 cc:
A. E. Chaffee (UStiRC Res1' dent Inspector, San Onofre Unit 2)
~C U. S. Nuclear Regalatory Co::vntssion f[
Office of Inspection and Enforcenent U. S. Nuclear Regulatory 'Comission 1
Office of flanagecent Information and Program Control f.
Institute of fluclear Power Operations s
a
'i 1
.1 P
12 D
l 4
s y
e
- if f
e l
4
{,
Ifw, -
wg ;y..
, g.r.g m _
y _
'MA y
~
/