ML20055H569
| ML20055H569 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/11/1990 |
| From: | Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20055H568 | List: |
| References | |
| 50-344-90-19, NUDOCS 9007270008 | |
| Download: ML20055H569 (3) | |
Text
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APPENDIX A NOTICE OF VIOLATION-Report No:
50-344/90-19 Portland General Electric Company Docket No. 50-344 TrojanPlant License No. NPF-1 During an inspection conducted on June 11-15,-1990, three violations of NRC' requirements were identified.- In-accordance with the " General Statement of l
Policy and Procedure for NRC Enforcement Actions,'! 10 CFR Part 2, Appendix C-
.i (1990), the violations are listed below:-
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A.
Technica1' Specification 3.3.2, " Engineered Safety Feature Actuation System Instrumentation," states in part:
The Engineered Safety Feature Actuation System (ESFAS)
-instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE...
ACTION:
b.
With an ESFAS instrumentation channel inoperable, take the i
action shown-in Table 3.3-3."
Table 3.3-3, Section 3.b, " Containment Ventilation Isolation," requires a minimum of one operable channel in PRM-1A during Modes 1, 2, 3,_and 4, and refers to Action 17, which' states:
With less than the Minimum Channels OPERABLE,-operation may. continue provided the containment ventilation valves are maintained closed.
Technical-Specification 3.4.6.1, " Reactor Coolant System Leakage-Detection Systems," states-in-part:-
.The following Reactor Coolant System'1eakage detection systems shall be OPERABLE:
The containment atmosphere particulate radioactivity monitoring a.
system...
ACTION:
With one of-the above required radioactivity monitoring leakage a.
i
' detection systems inoperable, operations may continue up to 30 l
days ^provided:
1.
The other two above required leakage detection systems are OPERABLE, and 2.
Appropriate grab samples are obtained and analyzed at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
otherwise, be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
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radioactivitymonitorIngecontainment' atmosphere _ particulate-Contrary to ne above th system (PRM-1A) was inoperable for greater than-thirty days prior-to January 30, 1990, during which containment i
ventilation isolation. valves were not maintained closed and appropriate grab samples were not obtained.
PRM-1A was inoperable due to depletion ofthefilterpgper,whichwasnotreplenishedbecausethe"lowpaper"
'j and " tear paper alarms were nonfunctional.
This is a Severity Level IV violation (Supplement-1)
B.
Technical specification 6.8.1: states in part:
Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, November, 1972.
Regulatory Guide 1.33, Appendix A, Part C,' states in part:,
Instructions for... startup, shutdown, and changing: modes of a
operation should be prepared, as appropriate, for the following systems:
22.
Process Radiation-Monitoring System Part H of Appeno8x A_ states in part:
l-1.
Procedures of a. type appropriate to the circumstances should be provided to. assure that tools' gauges, instruments controls,andothermeasurIngandtesting-devicesare,properlycontrolled, calibrated,andadjusted l.
at specified periods to maintain accuracy.- Specific-l examples of such equipment to be calibrated and tested-are:- readout instruments... alarm devices...:
E Contrary to the above, procedures were not provided to assure PRM-1A paper advance and paper-alarms were properly tested at-specified periods-to maintain accuracy and operability, resulting in PRM-1A being rendered inoperable for an extended period.
L This'is a Severity Level IV violation (Supplement IV) u C.
10 CFR 50.73, " Licensee event' report system," states in part:
3 (a)(1)
The holder.of an operating license for a nuclear power, lant (licensee)-shall submit.a Licensee Event Report p(LER) for any event of the type described in this-n r
paragraph within 30 days after.the discovery of the. event' (2) The licensee shall report:
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~3 (i)(B)
Any operation or condition prohibited b
-the plant's Technical Specifications..y Contrary to the'above,-prior to January 30, 1990, PRM-1A was-inoperable for an extended period-in violation of Technical Specifications 3.3.2 and 3.4.6.1, and a Licensee Event Report was not submitted within 30 days-l after the discovery of.the condition;-
This is;a Severity Level IV' violation (Supplement I)
Based on the submittal of Licensee Event Report 50-344/9 0, no response to
. this Notice is required A
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. j' l Dated at Walnut Creek, California 7 i L i
This l[diday of July,- 1990.
Gregory P. Yuhas Chief ReactorRadiologIcalgrotection Branch 1
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