ML20247G210
| ML20247G210 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/15/1989 |
| From: | Chaffee A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20247G201 | List: |
| References | |
| 50-344-89-01, 50-344-89-1, NUDOCS 8904040157 | |
| Download: ML20247G210 (3) | |
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APPENDIX A NOTICE OF VIOLATION i
Portland General Electric Company Docket No. 50-344 Trojan Nuclear Plant License No. NPF-1 During an NRC inspection conducted from January 1 through February 11, 1989, violations of NRC requirements were identified.
In accordance with the
" General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the violationr. are listed below:
A.
10 CFR 50.9 states, in part:
"Information provided to the Commission by
... a licensee... shall be complete and accurate in all material respects."
Contrary to the above, on February 2,1989, the inspectors found that Plant Operations Test (P0T) Procedure 26-2, Revision 24,
" Process Radiation Monitor Calibration," had not been changea as stated in Licensee Event Report 88-49, Revision 0, " Partial Containment Isolations Result from Signal Spike and Operator Error", dated January 26, 1989.
This.is a Severity Level IV violation (Supplement 1).
B.
10 CFR Pert 50, Appendix B, Criterion V, states, in part:
" Activities affecting quality shall be prercribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings."
1.
Periodic Instrument and Control
,e PICT-5-2, " Steam Generator Level, Protection Set II," Revision 12, approved August 26, 1988, requires, in part, the use of multiple photocells associated with the comparator logic tester and the use of a simulated test signal initially set at five volts, decreased to one volt while recording applicable bistable actions, and then' increased while recording applicable bistable actions.
Contrary to the above, on February 2,1989,. test personnel performed the test in a n.anner inconsistent with the procedure, in that only one photocell associated with the comparator logic tester was used and the simulated test signal was ramped down and up in a staggered fashion to obtain data for each bistable action until the signal was decreased to one vcit.
This is a Severity Level V violation (Supplement I).
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2.
Licensee Quality Inspection Procedure QIP.15, "QI Observations of
'I&C : Calibration Activities," Revision.0, approved January 4, 1989, specifies, in part, that the quality control inspector shall note.
whether work was' performed.in accordance with' approved instructions, procedures', and/or technical manuals to assure that-plant procedures, work package instructions, and installation standards are followed.
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Contra'ry to the above,' on February 2, = 1989, a. quality control Kinspector failed to note and document failures to' follow approved procedures during the performance of channel functional testing of steam generator water level instrumentation per-licensee procedure PICT-5-2.
This is a ' Severity Level' IV violation (Supplement. I).
3.
Licensee Plant Safety Procedure (PS) 3-30, Revision 17, section IV item E. states:
"It is the responsibility of the person accepting the equipment clearance to check the equipment clearance and assure himself that the equipment is' satisfactorily: tagged and the equipment is deenergized and cleared for work before. starting work."
Further,' licensee procedure Administrative Order (AO) 3-9, Revision 26, section I,. item 4. states:
"the assigned craftsman / technician performs the maintenance prescribed by the MR work instructions-and-documents its completion in the work performed section.of the MR."
Contrary to the above, on February 12, 1989, a maintenance craftsman rtplaced the charcoal adsorber in the
'B' train of.the Containment Hydrogen Vent System that was not tagged out or cleared for work, and failed to replace the charcoal.adsorber of the 'A' Containment Hydrogen Vent System specified in MR work instructions.
This is a Severity Level IV violation (Supplement I).
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! Pursuant to the provisions of 10 CFR 2.201, Portland General Electric Company is hereby required to submit a written statement of explanation to the U.S.
Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, Region V, and a copy to the NRC Senior Resident Insoector, Trojan, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a
" Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation if admitted, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
Consideration may be given to extending the response time for good cause shown.
FOR THE NUCLEAR REGULATORY COMMISSION
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A. E. Chaffee, Acting Director Division of Reactor Safety and Projects Dated at Walnut Creek, California thisj[f /lday of /) f)( U [] 1989 i
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