IR 05000344/1979009
| ML19241C129 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/21/1979 |
| From: | Andrea Johnson, Johnson P, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19241C128 | List: |
| References | |
| 50-344-79-09, 50-344-79-9, NUDOCS 7907270276 | |
| Download: ML19241C129 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTICd AND ENFORCEMEtE REGIJN V Report No.
50-344/79-09 Docket No.
50-344 License No.
flPF-1 Safeguards Group Licensee:
Portland General Electric Comoany 121 S. W. Salmon Street Portland, Oregon 97204 Facility Nare:
Trojan Irapection at:
Rainier. Orecon Inspection conducted:
March 27-30,1979 Ib/ 79 Inspectors:
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Approved By:
D. M. Sternb' erg,._Chkef, Reactor Project Section 1, Dhte S$gned Reactor Operations and Nuclear Support Branch Simr.a ry :
Inspection on March 27-30, 1979 (Report No. 50-344/79-09)
Areas Inspected:
Routine, unannounced inspection of licensee event reports, resoonse to IE Bulletins and Circulars, document control, management controls, ILRT preparations, and followup on previous inspection items; also included independent inspection effort.
The inspection involved 72 inspector hours onsite by three NRC inspectors.
Results:
No deviations or items of noncompliance were identified.
524 209 RV Forn 719 (7)
790737 0 L'7 6
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DETAILS 1.
Persons Contacted
- B. Withers, Plant Superintendent
- F. Lamoureaux, Assistant Plant Superintendent R. Barkhurst, Operations Supervisor
- W. Orser, Engineeriag Supervisor
- J. Perry, Administrative Engineer
- J. Reid, Quality Assurance Supervisor
- R. Schmitt, Chief Nuclear Plant Engineer
- T. Walt, Radiation Protectier Supervisor The inspectors also interviewed other licensee employees during the course of the inspection.
These included reactor operators, shift supervisors, maintenance personnel, and plant staff engineers.
- Denotes those attending the exit interview.
2.
Followup on Previous Inspection Findings (78-12-02, Open) Reactor Vessel Level Control During flaintenance Activities:
The licensee had initiated requests for design change (RDCs) fio.78-051 and flo.78-052 to provide improved indication of level in the reactor vessel during maintenance conditions.
These RDCs will provide a standpipe which is vented to the pressurizer, with a TV camera providing the control room operator the aoility to observe the level indication directly. This item remains oper pending completion of the modifications.
(78-19-02, Closed) Fire Brigade Training: The inspector verified by examination of lesson plans, training schedules, and training records that fire drills and fire brigade training had been implemented consis-tent with the licensee's commitment.
(78-19-01, Open) Documentation of Design Changes: A licensee task group was drafting recommendations to management regarding actions to expedite the completion of design change documentation. This study was initiated by the licensee as a result of a QA audit conducted in June 1978.
3.
Licensee Event Report During a previous inspection (Inspection Report fio. 50-344/76-26) the inspector reviewed the licensee's actions in response to LER 78-20, Grouting of Piping Penetrations.
Revision 3 to LER 78-20, dated 12/26/78, outlined the design changes being made by the licensee.
The changes involved either removal of grout or modification of nearby piping supports to avoid excessive stresses. Completion of in-plant work associated with 524 210
-2-the modifications was verified by the resident inspector prior to the resumption of power operation on January 2,1979.
During the current inspection, the inspector examined the licensee's documentation of the design charges related to LER 78-20. Two of the three as-built pack-ages (ABPs) related to this design change (RDC 78-063) were in the completed files with ABP No. 2 still undergoing engineering review.
Examination of ABPs !!o. 1 and No. 3 did not indicate any discrepancies with respect to the licensee's ~ocedures for the processing of design changes.
(Closed)
Cor:ments on the timeliness of drawing changes are presented separately in Paragraph 5.
No daviations or items of noncompliance were identified.
4.
Document Control The Document Ccntrol Program was rev'ewed for conformance with Technical Specifications, Regulatory Requiremeds and licensee commitments.
Appli-cable Quality Assuranca procedures were reviewed to verify that responsi-bilities are assigned for document control to assure conformance with the requirements.
A random selection from controlled copies of several Plant Operating Manual procedures and drawings (P& ids) was made and it was veri-fied that revision numbers for the selected controD ed copies were consis-tent with the master revision index file.
The timeliness of incorporating Design Changes into plant drawings is discussed in Paragraph 5.
No deviations or items of noncompliance were identified.
5.
Documentation of Design Changes During review of design changes the inspectors made certain observations related to the control of plant drawings.
During the processing of a request for design change (RDC), Plant Engineering issues an interim drawing change notice (IDCN) which (along with necessary procedures) gives direc-tions for accomplishing the work. Upon completion of work, the IDCN is marked up to show any changes approved during performance of the work.
This is then issued by Plant Engineering as a drawing change notice (DCN),
which serves as a basis for issuing revisions to plant drawings. The inspector noted that relevant DCUs were cross-referenced on the licensee's drawing index, as required by plant procedures to allow the user of a drawing to determine which DCNs apply to it (pending issuance of a revised drawing). The inspector noted, however, that several months can elapse after completion of in-plant work before necessary DCNs are issued, with 524 211
-3-system changas not reflected on the drawing index during the interim period.
The inspectors also observed that the status of pending RDCs cannot be found in any single location, making the design change program trore difficult to control and audit. The licensee stated during the exit interview that these matters would be evaluated during the ongoing re-view of design change package completion (see Paragraph 2, Item 78-19-01).
(79-09-01)
!!o deviations or items of ncncompliance were identified.
6.
Review of !!anagement hntrols This inspection included a review of the licensee's management control procedures against the requirements set forth in ANSI 18.7-1976.
The licensee is currently committed to the requirements of AtlSI 18.7-1972, and no deviations from the requirements of that standard were observed.
Although the licensee has not committed to the requirements of AflSI 18.7-1976, this review was conducted to determine whether significant differ-ences existed between the licensee's existing management controls and the more recent equirements. The inspector examined and discussed with licensee representatives pertinent documents related to facility organiza-tion; review and audit; and the programs, procedures, and policies used to control safety related activities at the plant.
The licensee stated that the areas discussed would be evaluated to determine whether or not changes to existing programs, policies and procedures would be advisable.
tio deviations or items of noncompliance were identified.
7.
IE Circular Followup The inspectors followed up on licensee actions related to two IE Circulars, with findings as follows:
IE Circular 78-08, Environmentai Qualification of Class IE Equipment (Closed): This matter is now the subject of IE Bulletin flo. 79-01, which requires a written response from the licensee by June 10, 1979.
Further review of the licensee's actions related to this subject will be documented as followup on IEB 79-01.
IE Circular 79-02, Failure of 120 Volt Vital AC Power Supplies (Closed):
The licensee had reviewed the circumstances cutlined in this circular and determined that similar conditions would not occur at Trojan.
In particular, the vital inverters at Trojan do not utilize an automatic transfer or time delay circuitry.
Optimum transformer tap settings were also verified.
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-4-8.
CILRT Preparations The inspector d1scussed licensee preparations for the containment integrated leak rate test (CILRT) to be performed during the spring maintenance outage.
The licensee stated that the peak pressure test will be performed using the guidelines of the Bechtel Topical Report, Bft-TOP-1, Rev.1.
9.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on 11 arch 30,1979.
During the exit interview, the inspectors sur:narized the scope and findings of the inspec-tion as discussed in Paragraphs 2 through 8.
The licensm' confirmed that the updating of plant drawings and the tracking of design change completion would be evaluated along with the ongoing review of the design change process (Paragraph 5).
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