IR 05000267/1979017
| ML19257B947 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/10/1979 |
| From: | Dickerson M, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19257B946 | List: |
| References | |
| 50-267-79-17, NUDOCS 8001210306 | |
| Download: ML19257B947 (5) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-267/79-17 Docket No. 50-267 License No. DPR-34 Licensee:
Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Facility:
Fort St. Vrain Nuclear Generating Station Inspection At:
Fort St. Vrain Site, Platteville, Colorado Inspection Conducted: October 29 through November 30, 1979 Inspector:
7N[ dA
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/> -/d-77 M. W. Dickerson, Resident Reactor Inspector Date Reviewed By:
[^ d
/> -/o - 79 T. F. Westerman, Chief, Reactor Projects Section Date
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Inspection Summary Inspection conducted during the period October 29 through November 30, 1975 (Report No. 50-267/79-17)
Areas Inspected: Routine, announced inspection of review of plant oeprations; audits; physical protection; follow-up on bulletins / circulars; calibrations; and review of event reports.
The inspection involved 9C inspector-hours by one (1) NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Public Service Company of Colorado L. Brey, QA Manager W. Crane, Maintenance Superintendent R. Craun, Engineer - Site W. Franek, Results Supervisor J. Gamm, Supervisor Technical Services B. Grarnhart, Sr., Design Draf tsman, Project Engineering B. Gunderson, Senior Engineer, Project Engineering W. Hillyard, Administrative Services Manager T. Howard, Superintendent Operations, QA M. McBride, Site Engineering Coordinator C. Turner, Supervisor of Security Stohler & Company M. Fedie, Senior Engineer The inspector also contacted other plant personnel, including reactor operators, maintenance men, electricians, technicians and administrative personnel.
2.
Physical Protection The inspector reviewee portions of the licensee's physical protection program by review of selected records and observation of the activities of access control, search, escorting, and communications.
3.
Review of Plant Operations A review of plant operations was conducted to ascertain whether facility operation was in conformance with the requirements established in Technical Specifications, 10 CFR, and Administrative Procedures, or licensee commit-ments discussed in correspondence to the Commission.
Included in the inspection were observation of control room activities, review of operational log records, and a tour of accessible areas. Logs and records reviewed included:
Shift Supervisor Logs
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Reactor Operator Logs
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Technical Specification Compliance Log
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Operating Order Book
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Form 1 Log (Jumper Log)
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Plant Trouble Reports
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Selected Valve Lineups
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During the tour of accessible areas, particular attention was directed to the following:
Monitoring Instrumentation
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Radiation Controls
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Housekeeping
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Fluid Leaks
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Piping Vibration
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Hanger / Seismic Restraints
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Clearance Tags
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Fire Hazards
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Control Room Manning
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Anntnciators
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The inspector also observed installation of a portion of the core restraint devices, including removal and reinsertion of control rods. Records relative to reactivity control included in CWP 438, Shutdown Margin Verifi-cation, reviewed as well as those for CWP 440, Region Constraint Device Initial Installation.
During a tour of the control room on November 14, 1979, the inspector noted that no portable radios were available. Discussion with reactor operators and the shift supervisor indicated that no portable radios had been available in the control roon since the shutdown had commenced on October 26, 1979.
The radios are requirei for communications in case of fires or environmental disturbances. ::his matter was discussed with the licensee who indicated that a method fir control of the radios would be instituted.
This matter remains as an open item.
No items of noncompliance er deviations were identified.
4.
Calibration The inspector observed the calibration of the following instruments and verified that the calibration was in conformance with procedures.
PDT 21186 - Pressure Differential Transmitter
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PHC 21186 - Controller
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XPS 21186 - Power Supply
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The inspector also observed portions of Surveillance Procedure 5.4.1.2.2.J-R for the calibration of steam pipe rupture instrumentation.
Records of calibration of the following instruments or other measuring heating devices used as primary standards in the above calibrations were reviewed.
Fluke #M-3150
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Wallace & Tierman #M-3149
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Simpson #M-3158
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15 lb. Regulator Supply #117
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-4-s The inspector observed that no records were maintained for the required controller settings on PHC 21186 for items such as the proportional band. A discussion with a representative of the licensee indicated that this problem has been recognized and that a method for and the recording of these settings is being developed.
This remains as an open item.
No items of noncompliance or deviations were identified.
5.
Audits The inspector witnessed portions of audit QAA 1401-79-01 as conducted by licensee personnel, to verify conformance with Technical Specifications and Quality Assurance procedures.
The portions of the audit observed were those for CN 743, Installation of V-21165 and CN 990 changes to System 21.
The observed portion of CN 743 was a review of Stearns-Roger records and procedures relative to the qualification of welding procedures, welder qualifications, filler material certification and control, NDE personnel qualification, approved NDE procedures, the welding records and the post weld heat treatment.
For CN 799, the audit was of the tagging process and valve status.
No items of noncompliance or deviations were identified.
6.
IE Circulars / Bulletins The inspector verified by record review, observation, and discussion with representatives of the licensee, the actions taken in response to IE Circulars / Bulletins.
The following Circulars were reviewed:
79-18, Proper Installation of Target Rock Safety Relief Valves 79-19, Loose Locking Devices on Ingersoll-Rand Pump Impellers 79-20, Failure of GTE Sylvania Relay, Type PM Bulletin 7305, Catalog 5012-11-AC with a 120 V AC Coil The following Bulletinuwas reviewed:
79-24 (Closed) Frozen Lines The inspector reviewed the information contained in the licensee's reply P-79254, dated November 1, 1979.
Based on this review and selected observations by the inspector, this matter is considered closed.
7.
hyview of Licensee Event Reports The Inspector verified that licensee event reporting activities were in accord'nce with Technical Specification, Section 7, including identification 177t4 241
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details, corrective action, review and evaluation of aspects relative to operations and accuracy of reporting.
The following reports were reviewed by the inspector:
78-34 79-08 79-04 79-14 79-06 No items of noncompliance or deviations were identified.
8.
Exit Interviews Exit interviews were conducted at the end of various segments of this inspection with Mr. D. Warembourg (Manager, Nuclear Production) and other members of the Public Service Company staff.
At the interviews, the inspector discussed the findings indicated in the previous paragraphs.
The licensee acknowledged these findings.
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