ML20215M768
| ML20215M768 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/28/1986 |
| From: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Opeka J NORTHEAST NUCLEAR ENERGY CO. |
| Shared Package | |
| ML20215M769 | List: |
| References | |
| NUDOCS 8611030274 | |
| Download: ML20215M768 (3) | |
See also: IR 05000423/1986028
Text
_ _ _ - _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ -
'
.
,
,
.
OCT 2 81986
.
Docket / License: 50-423/NPF-49
Northeast Nuclear Energy Company
ATTN: Mr. John F. Opeka
Senior Vice President-Nuclear
Engineering and Operations Group
P.O. Box 270
Hartford, Connecticut
06101-0270
Gentlemen:
,
Subject: Millstone 3 Routine Inspection 50-423/86-28 (8/12/86-10/6/86)
This transmits the report of the above subject inspection by Messrs. J. Shediosky
and F. Casella of this office. The inspection findings have been discussed with
Messrs. W. Romberg and J. Crockett of your staff.
While observing Control Room operations our inspectors witnessed the prompt and
effective actions taken by plant operators on September 15 in response to valve
failures in the feed and condensate system. Their timely response prevented a
challenge to the reactor trip system. Overall, however, despite excellent operator
performance and improvements in the steam generator (SG) level control equipment,
{
SG 1evel transients are still resulting in plant trips.
Thank you for your June 19, 1986 letter in response to concerns stated in Inspec-
tion Report 50-423/86-12. These included the high number of illuminated control
room annunciators and also the deterioration of the rubber lining of service water
pump discharge valves. Your progress toward resolution of both of these items will
be. addressed in our routine resident inspections. Additionally, the Attachment
to the enclosed Inspection Report addresses the current status of control room an-
nunciators. A focus of our future inspections will be on whether, in light of your
commitment to the total " blackboard" concept, you have placed high enough priority
on annunciators to effect a significant reduction in the annunciators in an alarm
status.
Thank you, also, for your June 20, 1986 response to a Violation identified in In-
spection Report 50-423/85-74. This Violation concerned the failure to report a
deficiency in reactor coolant pump snubber support design to the NRC. Although
you decided not to contest this violation, we noted your comments upon it.
Prompt
notification of deficiencies of this type provides information for evaluation of
potential safety consequences at facilities other than the one where the deficiency
is found. We consider this violation to be a valid safety consideration in prin-
ciple as well as a literal noncompliance with requirements.
Therefore, the viola-
tion stands as cited. The ongoing effectiveness of your actions to assure timely
and valid reporting will be assessed incident to our routine inspection program.
Your August 13, 1986 letter addressed the impact on the plant's accident analysis
caused by a Reactor Coolant System (RCS) Loop No. 2 hot leg transit time in excess
of the previously established acceptance criteria for RCS resistance temperature
detector (RTD) response times. This issue was addressed in our Inspection Report
No. 50-423/86-21. You state in your letter that the increase in RTD response time
does not impact the acceptability of continued plant operation and that a follow-up
8611030274 861028
ADOCK 0500
3
_ ._
.
-.
.,
.
.
.00T 2 81986
~
Northeast Nuclear Energy Company
2
.
report will be submitted if any changes are necessary to the Technical Specifica-
tion or Final Safety Analyses reports. We wish to emphasize that the need for any
such changes should be promptly identified to us.
No violations were identified during this inspection and no reply to this letter
is required.
Thank you for your cooperation.
Sincerely,
p, ngm
.
E ward C. Wenzinger, Chief
Projects Branch No. 3
Division of Reactor Projects
Enclosure: NRC Region I Inspectf n Report 50-423/86-28
cc w/ enc 1:
V. Papadopoli, Construction Quality Assurance Supervisor
E. R. Foster, Director of Generation Construction
W. J. Mroczka, Vice President, Nuclear Operations
D. O. Nordquist, Manager of Quality Assurance
R. T. Laudenat, Manager, Generation Facilities Licensing
W. D. Romberg, Station Superintendent
Public Document Room (PDR)
Local Public Document Room (LPDR)
'
Nuclear Safety Information Center (NSIC)
NRC Senior Resident Inspector
State of Connecticut
T
4
!
I
-
. -
-. -_.- _. .
- . . - . . _..-. _ . - - - - - _ . . - . - -
.- - . -
. _ .
^
': o , * * ,
.
Northeast Nuclear Energy Company
3
MT 2 8150
bec w/ encl:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
DRP Section Chief
L. Prividy, RI, BV-2
T. Rebelowski, SRI, Millstone 1&2
B. Doolittle, LPM, NRR
Robert J. Bores, DRSS
J. Durr, DRS
M. Shanbaky, DRSS
W. Pasciak, DRSS
R gP
RI:DRP
RI:DRP
She
A /meo
M abe
en in er
10/ /86
p(f,
/ gy'f
0FFICIAL RECORD COPY