ML20235D923
| ML20235D923 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 09/18/1987 |
| From: | Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8709250409 | |
| Download: ML20235D923 (1) | |
See also: IR 05000344/1987024
Text
. - _ _ _ - _ - _ _
- c -
o
. - . . .
tJSNRC-DS
Docket No. 50-344
SEP 181987
M1 SEP 25 A 9 39
Purtland General Electric Company
121 S. W. Salmon Street
Portland, Oregon 97204
. Attention:
Mr. David W. Cockfield
Vice President, Nuclear
Gentlemen:
.Thank you for your letter dated September 11, 1987, in response to our Notice
of Violation and Inspection Report No. 50-344/87-24, dated August 10, 1987,
informing us of the steps you have taken to correct the items which we
brought to your attention.
Your corrective actions will be verified during a
future inspection.
Your cooperation with us is appreciated.
Sincerely,
.
.
.
.
R. P/ Zimmerma , Chief
Reactor Projects Branch
cc w/cy ltr dtd 9/11/87:
W. Dixon, DOE
bec w/cy ltr dtd 9/11/87:
RSB/ Document Control Desk (RIDS) (IE01)
Project Inspector
Resident Inspector
B. Faulkenberry
J. Martin
'J. Zo111 coffer
{
.l'
bcc w/o cy of ltr dtd 9/11/87:
M. Smith
Regiong
[\\Yp%6ST COPY ] AEQ)UI
[fffE
'ST COPY ] REQUEST COPY ] REQUEST gOPY ] REQUEST COPY ]
s
// NO
](YES
/ NO
] YES / (RT)
_] YES / rN0 1] YES / NO
~
"
"
y [$
TO PD
~
itf E
DPepeira/ norma
MMendonca
RPZimmerman
AJ
son
efWrsch yg
9/l1/87
9/K/87
9/1f/87
9/g 87
9/ /87
A/ E-
8709250409 870918
ADOCK 0 % 3 4
DR
/E01
L
i
_ - - -
- - _ - - _ _ _
_
_
.
- -
,
.
,
,;- . ..
.
REcgigED
-
b'WV
RE 10H V
David W. Cockfield Vice President, Nuclear
1981 SEP 1ti A O 23
September 11, 1987
Trojan Nucicar Plant
Docket 50-344
License NPF-1
U. S. Nucicar Regulatory Commission
Attention: Document Control Desk
Washington DC 20555
Dear Sir:
TROJIS NUCLEAR PLANT
Reply to a Notice of Violation
Your letter of August 10, 1987, transmitted a Notice of Violation based
upon NRC Inspection Report 50-344/87-24. Attached to this letter is our
response to that Notice of Violation. This letter and response is being
submitted two days late due to personnel error.
Sincerely,
/
r
Attachment
c:
Mr. John B. Martin
Regional Administrator, Region V
U. S. Nuc1 car Regulatory Commission
Mr. David Kish, Director
State of Oregon
Department of Energy
Mr. R. C. Barr
NRC Resident Inspector
Trojan Nuc1 car Plant
Subscribed and sworn to before mo this cloventh day of September 1987.
9
M dit
LLU
Nota 6y Public of Oregon
My Commission Expires:
(
n . . ~
-~
n
N
[
-.
-- _ _
.
.
.
.
. Trojan Nuclear Plant
Document Control Desk
~ ~
e
Docket 50-344
September 11, 1987
Licence NPF-1
Attachment
PCE REPLY TO NOTICE OF VIOLATION
Violation
10 CFR 50.72(b)(2)(ii) requires that the licensco shall notify the
NRC as soon as practical and in all cases, within four hours of he
occurrence of any event or condition that results in manual or auto-
matic actuation of any Enginecred Safety Feature, including the
Contrary to the above, an automatic actuation of the Reactor Protec-
tion System occurred at 9:02 p.m. on June 29, 1987, resulting in the
opening of reactor trip breakers RTA and RTB and bypass breaker BYB,
but this event was not reported to the NRC until 7:05 p.m. on June 30,
1987.
This is a severity Level V violation (Supplement I).
PGE Response
PGE acknowledges that the automatic actuation of the Reactor Protoc-
tion System (RPS) Which occurred at 9:02 p.m. on June 29, 1987, was
not reported to the NRC until 7:05 p.m. on June 30, 1987.
This is in
violation of 10 CFR 50.72(b)(2)(li) which requires this event to be
reported within four hours. The reason for the violation was person-
nel error.
At the time of the RPS actuation, the plant was in Mode 5 (cold shut-
down) with the Reactor Coolant System at about 110*F.
The control
rods were inserted and the control rod drive mechanisms (CRDM) were
deenergized with both CRDM generators shut down. The Plant operators
were conducting a simulated loss of offsite power test which involved
reactor trip breaker manipulations.
Under these conditions, the
operators failed to initially recognize roccipt of an unexpected re-
actor trip signal as immediately reportable and, therefore, did not
meet the four-hour reporting requirement.
In addition to discussing the event with operational staff, written
instructions worc issued to operators emphasizing the immediato re-
porting requirements for RPS actuations. Since that time, there have
been no similar occurrences. Since a telephone notification was made
on June 30, 1987, with a followup 30-day report submitted July 16,
1987 (LER 87-16), correctivo action addressing the operator error is
complete and full compliance has been determined to be achieved.
DLN/rc
1670P
9 % ^ W~ 1 l10 n*2~~) f,
f
0 /U
gvj g g.
l~
. _ _ _ . - . _____m