IR 05000267/1978014
| ML19256A073 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/19/1978 |
| From: | Dickerson M, Verdizco G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19256A068 | List: |
| References | |
| 50-267-78-14, NUDOCS 7811030033 | |
| Download: ML19256A073 (4) | |
Text
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
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IE Inspection Report No.
50-267/78-14 Docket No.
50-267 License No.
DPR-34 Licensee:
Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Facility Name:
Fort St. Vrain Nuclear Generating Station Inspection At:
Fort St. Vrain Site, Platteville, Colorado Inspection Conducted:
September 11-15, 1978 Inspectors:
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7/i9/7R M. W. Dickerson, Reactor Inspector Date
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Accompanying C
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Personnel: d tsa,s_.--. i,(
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G. H. Verduzco,lieactoPInspector (Training)
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Approved by:
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/C. L. Madsen, Chief, Reactor Operations Date and Nuclear Support Branch Inspection Summary Inspection on September 11-15, 1978 (Report No. 50-267/78-14)
Areas Inspected:
Routine, unannounced inspection of design, design changes and modifications; plant operations; follow-up on inspector identified and unresolved problems; and follow-up on items of noncompliance.
The inspection involved thirty-four (34) inspector-hours on site by one (1) NRC inspector.
Results:
No items of noncompliance or deviations were identified.
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-2-DETAILS 1.
Persons Contacted Public Service Company of Colorado K. Armstrong, On-Site Document Control Technician G. Bissett, Supervisor, QA/QC M. Block, Senior Results Engineer
- L. Brey, Manager, QA W. Franek, Results Supervisor
- J. Gamm, Supervisor, Technical Services
- T. Howard, Senior QA Engineer J. Liebelt, Supervisor, Electrical Maintenance
- F. Mathie, Superintendent, Operations
- C. Tracy, Superintendent, Operations QA
- D. Warembourg, Nuclear Production Manager V. Wetzbarger, Shift Supervisor, Operations i
- Attended exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Item of Noncompliance - Infraction 1.b (50-267/78-08):
Failure to control weld rod.
The licensee has initiated use of a weld rod control form which is to be used by all parties performing welding.
Incorporation of the forms use into PSC, GA, and Steams-Roger procedures is being finalized.
(Closed) Inspector Follow-up Item (50-267/78-09):
Procedures require revision. The licensee has revised procedures OPOP II, OPOP V, S0P 12-05, S0P 14-02, S0P 12-01, and EMP-33, in accordance with comments contained in Inspection Report 50-267/78-09.
(Closed) Inspector Follow-up Item (50-267/78-13):
U clamps not secured to pipe support.
Plant Trouble Report 8-147 requiring the securing of the subject clamps were completed August 10, 1978.
(Closed) Inspector Follow-up Item (50-267/78-13):
Apparent errors in Technical Specification Table 4.3.10-1, list of Hydraulic Snubbers.
The errors have been corrected in the Surveillance Test procedure and a revision to 4.3.10-1 will be submitted to NRR with the next T/S revisio.
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-3-3.
Review of Plant Operations During the inspection, the conduct of plant operations was reviewed to detennine that they conform to requirements of the facility license and the licensee's procedures.
Included in the review were observation of control room activities, logs, and records.
In addition the inspector completed a tour of accessible areas.
The inspector's review of this area included:
Shift Supervisor's Log (June 6 - September 12, 1978)
Reactor Operator's Log (June 6 - September 12, 1978)
Surveillance Logs 1-3 (June 6 - September 12, 1978)
Operations Order Book Form l's (Jumper Log)
Plant Trouble Reports During the tour of the facility observations were made in the following areas:
Monitoring Instrumentation Radiation Controls
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Housekeeping Fluid Leaks Piping Vibrations Hanger / Seismic Restraints Clearance Tags
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Annunciators Control Room Manning During this tour, the inspector identified three Class I Hydraulic Snubber, HRS-131, HRS-158, and HRS-159, which appeared to be low on oil. A representative of the licensee issued a Plant Trouble Report,
(PTR) to have the snubber reservoirs filled.
No items of noncompliance or deviations were identified.
4.
Design, Design Changes and Modifications The inspector reviewed the licensee and contractor procedures for control of design changes and modifications and their implementation.
The following were selected for review:
CN 343 Inhibit in Water Turbine Speed Circuit CN 457 Add Block Valves Upstream of HV 2193, 94, and HV 21213 and 14.
CN 231 Purge System for System 46 Surge Tanks
....
-4-CN 90 Operational Amplifier Substitution - NEXUS CN 577 Ability to Transfer Housepower from UAT to RAT FCN 4244 Instrumented CRD's Modification 4277 Instrumented CRD's Modification 4282 Instrumented CRD's Modification 4310 Instrumented CRD's Modification 4316 Instrumented CRD's Modificat17n 4349 Instrumented CRD's Modification 4378 Instrumented CRD's Modification 4395 Instrumented CRD's Modification 4412 Instrumented CRD's Modification The review indicated that the design chcnges were conducted in accordance with procedures; were properly reviewed and approved and that they were verified by acceptance tests where appropriate.
Additionally each had been evaluated in accordance with 10 CFR 50.59 requirements, procedures were changed where required and those drawings selected for review had been properly changed to reflect the modifications.
No items of nonconformance or deviations were identified.
5.
Exit Interview
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An exit interview was conducted with representatives of the licensee on September 15, 1978, at the conclusion of the inspection. At the interview, the inspector discussed the findings indicated in the previous paragraphs.
The licensee acknowledged these findings.