ML20237H707
| ML20237H707 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/10/1987 |
| From: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mroczka E NORTHEAST NUCLEAR ENERGY CO. |
| Shared Package | |
| ML20237H709 | List: |
| References | |
| NUDOCS 8708170319 | |
| Download: ML20237H707 (2) | |
See also: IR 05000423/1987012
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AUG 101987
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Docket / License: 50-423/NPF-49
Northeast Nuclear Energy Company
ATTN:
Mr. Edward J. Mroczka
Senior Vice President, Nuclear
Engineering and Operations
P.O. Box 270
Hartford, Connecticut
06101-0270
Gentlemen:
Subject:
Millstone 3 Routine Inspection 50-423/'.7-12 (5/12/87 - 7/10/87)
This transmits the report of the above subject inspection by Mr. J. T. Shedlosky.
The inspection findings have been discussed with Mr. C. H. Clement of your staff.
No violations were identified during this inspection and no reply to this letter
is required.
However, we are concerned about the discharge of the Carbon Dioxide
fire protection system into the East MCC Rod Control Switchgear area on July 6.
This incident is addressed in the enclosed inspection report and your corrective
actions will ba inspected relative to the associated Unresolved Item.
During our onsite inspection of the May 14 reactor trip, we noted that prompt
action was taken by the Computer Services Group in response to discovery of a
possible tie between the process computer and reactor safeguards equipment.
Our
inspector found this issue to have been handled very professionally.
We have reviewed your May 1, 1987 letter responding to a Violation identified in
our Inspection Report Number 50-423/86-39.
Your letter addressed the root cause,
corrective actions, and generic implications for an incident which caused a safety
injection pump to be degraded.
We have examined your actions during onsite in-
spections and have no additional questions.
We have also reviewed your letter dated May 12, 1987 responding to a Violation
identified in our combined Inspection Report Number 50-245/87-02; 50-336/87-02;
50-423/87-03.
Your letter addressed the root cause and corrective actions for a
Violation in which a Safeguards information container was unlocked and unattended.
We have examined your actions during onsite inspections and have no additional
questions.
Thank you for your cooperation.
Sincerely
N181aal Signed Byi
Eb
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dward C. Wenzinger, Chief
rojects Branch No. 3
Division of Reactor Projects
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' Northeast Nuclear Energy Company
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AUG 101987
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' Enclosure: 'NRC Region I Inspection Report 50-423/87-12
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cc w/ encl:
W. D. Romberg, Vice President, Nuclear Operations
D. O. Nordquist, Manager of Quality Assurance
R. M. Kacich, Manager, Generation Facilities Licensing
S. E. Scace, Station Superintendent
Public Document Room (PDR)
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Local'Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Senior. Resident. Inspector
State of Connecticut
'bec w/ encl:
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Region I Docket Rnom (with' concurrences)
Management Assistant, DRMA (w/o encl)
DRP Section Chief
J. Beall, SRI, BV-2
T. Rebelowski, SRI, Millstone'l&2
R. Ferguson, LPM, NRR
R. Bores, DRSS
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