IR 05000267/1986001
| ML20153C244 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/06/1986 |
| From: | Jaudon J, Skow M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20153C242 | List: |
| References | |
| TASK-1.C.6, TASK-TM 50-267-86-01, 50-267-86-1, NUDOCS 8602190085 | |
| Download: ML20153C244 (4) | |
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APPENDIX.
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-267/86-01 License:
DPR-34 Docket:
50-267 Licensee:
Public Service Company of Colorado (PSC)
P. O. Box 840 Denver, Colorado 80201
Facility Name:
Fort St. Vrain Nuclear Generating Station Inspection At:
Fort St. Vrain Nuclear Generating Station, Platteville, Colorado Inspection Conducted:
January 6 - 10, 1986 Inspector:
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R ctor Erojec Branch Inspection Summary Inspection Conducted January 6 - 10, 1986 (Report 50-267/86-01)
Areas Inspected:
Routine, unannounced inspection of nonlicensed operator training, fire prevention / protection program implementation, follow-up to
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NRC Inspection Report 50-267/85-26, and follow-up to NRC review of Revision 3 to the FSAR.
The inspection involved 34 inspector-hours onsite and 4 inspector-hours offsite by one NRC inspector.
Results: Within the areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted Principal Licensee Employees
- T. Borst, Support Services Manager / Radiation Protection Manager
- W. Craine, Superintendent of Maintenance
- M. Ferris, QA Operations Manager
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- C. Fuller, Station Manager
- J. Gahm, Manager Nuclear Production
- M. Novachek, Technical / Administrative Services Manager T. Prenger, QA Services Manager G. Redmond, MQC Supervisor
- T. Schleiger, Health Physics Supervisor
- L. Singleton, Manager QA R. Webb, Maintenance Supervisor
- J. Gramling, Supervisor, Site Licensing
- D. Evans, Superintendent of Operations
- R. Craun, Nuclear Site Engineering Manager
- M. Holmes, Nuclear Licensing Manager J. Johns, Supervisor, Nuclear Ergineering R. Schenderlein, Engineer J. Selan, Sr. Licensing Engineer 0. Lewis, Maintenance R. Rivera, Operator Training Supervisor
- Denotes those attending the exit Sterview.
2.
Follow-up to NRC Inspection Report 50-267/85-26 The NRC inspector performed a follow-up inspection to verify the findings of NRC Inspection Report 50-267/85-26, hereafter referred to as the PAT report. The NRC inspector also determined what, if any, corrective actions had been taken by the censee.
The paragraph number of the PAT report is used below to discuss the specific concarn of that report.
The specific item number is also identified.
PAT Report Paragraph 2.a.(li, Open Item 8526-01 The licensee's equipment control procedures did not comply with the requirements of TMI Item I.C.6.
Procedure P-2, " Equipment clearances and Operation Deviation," Issue 13, did not require a second qualified person to verify the correct implementation of tagging activities.
On May 22, 1985, NRC Region IV had requested a response within 120 days to a similar finding that had been discussed at a Management Conference on November 14, 1984.
Clearance control form revisions were noted to be in progress during this inspectio.
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Inspection Followup The NRC Inspector reviewed licensee procedures relating to Independent Verification.
Station Manager's Administrative Procedure SMAP-19, Issue 1 dated September 10, 1985, Paragraph 3.5.7, addresses independent verification for clearances.
It applies for all plant operations, maintenance and modification activities requiring isolation and/or operation deviation of equipment, annunciators and instruments.
Procedure RP-A-01, Issue 2, dated November 13, 1985, establishes independent verification for procedures used for the calibration and maintenance of plant instrumentation.
Surveillance SR-RE-86-X, Issue 2, dated July 19, 1985, provided an example of independent verification which is used in surveillance procedures.
Open Item 8526-01 is CLOSED.
3.
Followup to NRC review of Revision 3 to the Updated FSAR Section 1G.2.5.3, Page 10.2-15, Revision 3, to the updated FSAR, indicates that the actuation signals for the hot reheat steam line power operated relief valves were revised to sense signals from loss of or degraded voltage sensors rather than a turbine trip signal.
Changes made in the FSAR, not requiring prior Commission approval pursuant to 10 CFR 50.59(a),
were to have either been reported to the Commission in an attachment to the FSAR revision submittal to the NRC, or in previous 10 CFR 50.59 annual reports.
It did not appear to NRC reviewers that reports had been made for the change to Section 10.2.5.3.
Discussions with the licensee revealed that the changes to the facility were accomplished in accordance with Change Notice CN 1622.
The licensee did report CN 1622 pursuant to 10 CFR 50.59 by their letter P-84091, which covered the period January 1-22, 1984.
However, their report did not appear to address the relief valve actuation aspect of the change notice.
The Safety Evaluation performed on CN 1622 noted that
... sections 7,8,10.3, Appendix C..." of the FSAR were reviewed.
It
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appears that changes to FSAR Section 10.2 was not included in the Safety Evaluation. A copy of the original Safety Evaluation was placed in reissues A, B, and C of CN 1622.
In the discussions, the licensee was able to establish that they had performed the appropriate evaluations.
However, to clarify the Safety Evaluation included in the CN package, the licensee stated that they will reissue the Safety Evaluation to include any missed applicable FSAR sections and improve the basis statement.
4.
Nonlicensed Staff Training This inspection was to evaluate the effectiveness of the training programs for the nonlicensed staff, and is a continuation from NRC Inspection Report 50-267/85-33.
The NRC inspector reviewed approximately 30 training records to verify conformance with regulatory requirements and licensee
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commitments.
In addition, the inspector interviewed approximately 12 individuals to ascertain whether they had received training for specific tasks and operations.
No violations or deviations were noted.
5.
Fire Protection / Prevention Implementation This inspection was to ascertain whether the licensee was implementing a program for fire protection and prevention that is in conformance with regulatory requirements and commitments.
The NRC inspector reviewed the following surveillance procedures.
Title Issue Date SR 5.10.2ab-Q
11-22-85 SR 5.10.2c-A
11-30-85 SR 5.10.8-R
12-07-84 SR 5.10.8-M
09-20-85 SR 5.10.8-3Y
12-07-84 SR 5.10.9b-SA
11-30-84 SR 5.10.9a-M
11-21-84 SR 5.10.9c-A
11-30-84 SR-MA-1-SA
12-06-85 SR-MA-10-M
10-18-85 The NRC inspector performed a facility tour and observed work activities.
Special attention was paid to control of combustible materials, flammable liquids, welding and cutting operations, housekeeping, fire brigade equip-ment, and fire protection equipment.
Fire watch and maintenance personnel were interviewed to determine the level of training received relating to fire protection duties.
Recently completed surveillances from the above list were also reviewed.
The surveillence SR-MA-10-M, which was accomp-lished in May 1985, could not be retrieved. The computerized list which showed when surveillances were last performed did not recognize its completion in May.
There was a Nonconformance Report NCR 85-710 issued on May 22, 1985, concerning the calibration of the scale used in the surveil-lance.
Disposition of the NCR states that the extinguishers checked in the surveillance shall be used as-is.
The NRC inspector recognized this as indication that the surveillance had indeed been performed as scheduled.
Since the surveillance appeared to have been performed, and the surveil-lance was not required by the Technical Specifications, failure to maintain record of its completion was considered an error, but not a violation.
6.
Exit Interview An exit interview was held on January 10, 1985, with those personnel denoted in paragraph 1_of this report.
The NRC senior resident inspector and Mr. R. E. Baer, NRC Region IV Radiation Specialist, also attended this meeting.
At the meeting, the scope of the inspection and findings were summarized.
The licensee also confirmed thos? commitments identified in paragraph 3.