IR 05000904/2010028: Difference between revisions

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#REDIRECT [[IR 05000245/1985024]]
{{Adams
| number = ML20138Q225
| issue date = 12/05/1985
| title = Notice of Violation from Insp on 850904-1028
| author name =
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| addressee name =
| addressee affiliation =
| docket = 05000245
| license number =
| contact person =
| document report number = 50-245-85-24, NUDOCS 8512270102
| package number = ML20138Q220
| document type = NOTICE OF VIOLATION OF A REGULATION, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 1
}}
 
{{IR-Nav| site = 05000904 | year = 2010 | report number = 028 }}
 
=Text=
{{#Wiki_filter:.
(c. . .
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APPENDIX A NOTICE OF VIOLATION Northeast Nuclear. Energy Company  Docket No. 50-245
' Millstone Nuclear Power Station, Unit 1  License No. OPR-27 During inspection from September 4 through October 28, 1985, and in accordance with the NRC Enforcement Policy (10 CFR 2, Appendix C), the following violation was identified:
The code of Federal Regulations Title 10, Part 40.72 (b)(1)(ii)(B) requires that the NRC Operations center be notified via the E...; aency Notification  i System (ENS) within one hour in the event that the plant is in a non-emergency condition outside its design basis. Similar notification is required by Part 50.72(b)(2)(ii) for any condition that results in manual or automatic actu-ation of any Engineered Safety Feature (ESF). Additionally, the Code of Federal Regulations Title 10, Part 50.73(a)(2)(ii)(B) and 50.73(a)(6)(iv)
require a written Licensee Event Report (LER) within 30 days for each such even Contrary to the above, a design deficiency in the Low Pressure Coolant Injec-tion pump start circuit caused the plant to be in a non-emergency condition outside its design basis, was discovered by the licensee on July 30, 1985 and was not reported to the NRC via the EN The LER for the event, dated Sep-tember 9, 1985, exceeded the.30 day requiremen In addition, an ESF actuation on July 18, 1985 at 1325 isolated the Reactor Building normal ventilation and an ESF actuation on August 7,1985 at 1115 isolated Reactor Building normal ventilation and the Water Cleanup System Containment Isolation Valves. These actuations were not reported via the ENS or in an LE This is a Severity Level IV Violation (Supplement I).
 
Licensee actions taken before the end of the inspection addressed: (1) the correc-tive steps taken and the results achieved; and (2) corrective steps to be taken to avoid further violations. Therefore, no reply to this Violation is require <
8512270102 851205 DR ADOCK 050 g 5
.
    ..._-__.._______________________m-eM
}}

Latest revision as of 11:59, 25 September 2020

Notice of Violation from Insp on 850904-1028
ML20138Q225
Person / Time
Site: Millstone, 05000904 Dominion icon.png
Issue date: 12/05/1985
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20138Q220 List:
References
50-245-85-24, NUDOCS 8512270102
Download: ML20138Q225 (1)


Text

.

(c. . .

.

APPENDIX A NOTICE OF VIOLATION Northeast Nuclear. Energy Company Docket No. 50-245

' Millstone Nuclear Power Station, Unit 1 License No. OPR-27 During inspection from September 4 through October 28, 1985, and in accordance with the NRC Enforcement Policy (10 CFR 2, Appendix C), the following violation was identified:

The code of Federal Regulations Title 10, Part 40.72 (b)(1)(ii)(B) requires that the NRC Operations center be notified via the E...; aency Notification i System (ENS) within one hour in the event that the plant is in a non-emergency condition outside its design basis. Similar notification is required by Part 50.72(b)(2)(ii) for any condition that results in manual or automatic actu-ation of any Engineered Safety Feature (ESF). Additionally, the Code of Federal Regulations Title 10, Part 50.73(a)(2)(ii)(B) and 50.73(a)(6)(iv)

require a written Licensee Event Report (LER) within 30 days for each such even Contrary to the above, a design deficiency in the Low Pressure Coolant Injec-tion pump start circuit caused the plant to be in a non-emergency condition outside its design basis, was discovered by the licensee on July 30, 1985 and was not reported to the NRC via the EN The LER for the event, dated Sep-tember 9, 1985, exceeded the.30 day requiremen In addition, an ESF actuation on July 18, 1985 at 1325 isolated the Reactor Building normal ventilation and an ESF actuation on August 7,1985 at 1115 isolated Reactor Building normal ventilation and the Water Cleanup System Containment Isolation Valves. These actuations were not reported via the ENS or in an LE This is a Severity Level IV Violation (Supplement I).

Licensee actions taken before the end of the inspection addressed: (1) the correc-tive steps taken and the results achieved; and (2) corrective steps to be taken to avoid further violations. Therefore, no reply to this Violation is require <

8512270102 851205 DR ADOCK 050 g 5

.

..._-__.._______________________m-eM