ML20147E644
| ML20147E644 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/11/1988 |
| From: | Bettenhausen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mroczka E NORTHEAST NUCLEAR ENERGY CO. |
| Shared Package | |
| ML20147E647 | List: |
| References | |
| NUDOCS 8801210188 | |
| Download: ML20147E644 (2) | |
See also: IR 05000245/1987030
Text
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JAN 11 BBB
Oocket No. 50-245; 50-336
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Northeast Nuclear Energy Company
ATTN: Mr. Edward J. Mroczka
Senior Vice President - Nuclear
Engineering and Operations Group
.
P. O. Box 270
Hartford, Connecticut 06141-0270
Gentlemen:
Subject:
Inspection 50-245/87-30; 50-336/87-25 (10/27/87 - 11/30/87)
This refers to the above subject resident inspection at Millstone 1 & 2.
Inspec-
tion results have been discussed with Messrs. J. Keenan and J. Stetz of your staff.
The enclosed Notice of Violation for Millstone 2 (Appendix A) addresses a prolonged
inoperability of the chilled water cooling system heat exchangers for both Vital
DC Switchgear Rooms due to maintenance problems. Af ter we expressed concerr, to
station management, a 24-hour per day, 7-day-a-week effort made the heat exchangers
operable by November 6, 1987.
That was responsive to our concern. We have also
noted the actions and comments on the chilled water system stated in your December
4, 1987 letter. Because of the alternate cooling assessed as acceptable by safety
evaluation and incorporated in procedures used bc the operating staff, we evaluated
this chiller inoperability as not being a serious safety matter. We are nonethe-
less concerned that operating and maintenance management controls allowed a re-
dundant safety-related subsystem described in the plant licensing basis to be in-
operable for about four years.
That inoperability appears to have been a de facto
and unreported facility change.
Also, as addressed in Report Detail 7, a Millstone 2 reactor scram occurred due
to malfunctioning of a feedwater regulating valve controller.
This scram was com-
plicated by failure of a motor-driven auxiliary feedwater pump to start due to a
switch malfunction and by an unanticipated plant cooldown due to moisture separator
reheater valve operability and alignment abnormalities.
Further, two of the four
reactor coolant pumps were de-energized by failure of the fast transfer function
for their power supply, with the cause attributed to a previous personnel error
while racking in a circuit breaker.
These conditions were acceptably responded
to by the operators.
Another Millstone 2 concern, addressed in Report Detail 10, is a Unit 2 sample sink
valve remaining open. A sneak ventilation path then resulted in introduction of
radioactivity into the Unit 2 control room. Worn ventilation plenum seals were
identified as a contributing factor.
O
Review of the above noted conditions found acceptable interim corrective actions.
Collectively, however, the above items indicate a need for reassessment of overall
management of Millstone 2 equipment configuration and performance.
Please give
this matter particular attention and address it in conjunction with your reply to
the apparent violation addressed in Appendix A.
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Your cooperation with us is appreciated.
Sincerely,
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Lee H. Bettenhausen, Chief
Projects Branch No. 1
Division of Reactor Projects
Enclosure: NRC Region I Report 50-245/87-30; 50-3?6/87-25
cc w/ encl:
W. D. Romberg, Vice President, Nuclear Operations
S. E. Scace, Station Superintendent
E. R. Foster, Director, Generation Construction
R. M. Kacich, Manager, Generation Facility Licensing
O. O. Nordquist, Manager of Quality Assurance
V. Papadopoli, Supervisor, Engineering Assurance
Public Document Room (PDR)
local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Senior Resident Inspector
State of Connecticut
bec w/ encl:
Region I Docket Room (with enclosures)
Management Assistant, DRMA (w/o enclosures)
DRP Section Chief
M. Boyle, LPM, NRR
Robert J. Bores, DRSS
D, Jaffe, LPM, NRR
R. Keimig, DRSS (See Detail 4)
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II
0FFICIAL RECORD COPY
DL50-245/87-30 - 0002.0.0
01/04/88