IR 05000267/1980018
| ML19338F959 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/08/1980 |
| From: | Collins R, Dickerson M, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19338F953 | List: |
| References | |
| 50-267-80-18, NUDOCS 8010280121 | |
| Download: ML19338F959 (1) | |
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U. S. NUCLEAR REGULATORY COMMISSION O
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-267/80-18 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:
August 1-31, 1980 Inspectors:
7- [.
b 7-9-30 cuw M. W. Dickerson, Senior Resident Reactor Inspector Date 7. f, h
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9~ $'t 0 R. E. Collins, Resident Reactor Inspector Date
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Approved by:
7' 7-f- ? - Fe T. F. Westerman, Chief, Reactor Projects Section No.1 Date Inspection Summary
Inspection conducted on August 1-31, 1980 (Report No. 50-267/80-18)
Areas Inspected: Routine, announced inspection of plant operations; review of event reports; followup on previous items of noncomplaince; surveillance; maintenance, operational safety verification; and review IE Bulletins / Circulars.
The inspection involved 169 inspector-hours on site by two (2) NRC Inspectors.
Results:
With the seven (7) areas inspected, one item of noncompliance was identified (Infraction - Failure to comply with procedural requirements, Paragraph 3a).
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DETAILS 1.
Persons Contacted D. Alps, Lead Security Officer L. Brey, QA Manager W. Franklin, Shift Supervisor J. Gamm, Supervisor Technical Services E. Hill, Operations Manager W. Hillyard, Administrative Services Manager R. Lamb, Electrical Supervisor J. Liebelt, Maintenance Supervisor F. Mathie, Operations Manager L. McInroy, Superintendent QA Services T. Orlin, Superintendent Operations QA L. Singleton, QA Engineer G. Turner, Supervisor of Security J. Van Dyke, Shif t Supervisor D. Warembourg, Manager Nuclear Production V. Wet:barger, Scheduling & QC Supervisor 2.
Licensee Action On Previous Inspection Findings (Closed) Item of Noncompliance (50-267/8012-01a):
No seals on three Reserve Shutdown valves.
All reserve shutdown valves are now secured in their required positions by padlocks and chains.
(Closed) Item of Noncomplainee (50-267/8012-Olb):
Storage basin recorder not operating.
All operations personnel involved in chart maintenance have reviewed the relevant sections of ADM 23 and Operations Order 80-28.
The licensee has reposted and rerouted an internal memo dated June 19, 1980, regarding disciplinary action for failure to comply with requirements of Procedures.
(Closed) Item of Noncompliance (50-267/8012-2):
No equipment control j
procedure used.
All personnel involved in this activity, have been advised not to reply on makeshift notes, but are to use the proper procedure.
The inspector confirmed this action by ;nterviewing several of those individuals involved.
(Closed) Item of Noncompliance (50-267/8012-3):
No data recorded as required by LCO 4.2.9.
The licensee has established a separate log for
recording this information.
A continuing check by the inspector has shown this new method to be effective.
3.
Operational Safety Verification The inspector reviewed licensee activties to ascertain that the facility e
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is being operated safely and in conformance with regulatory requirements, and that the. licensee's management control system is effectively discharging its responsibilities for continued safe operation.
The review was con-ducted by direct observation of activities, tours of the facility, inter-views and discussions with licensee personnel, independent verification of safety system status and limiting conditions for operations, and review of facility records.
Included'in the inspection were observation of control room activities review of operational logs, records, and tours of accessible areas.
Logs and records reviewed included:
Shift Supervior 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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System Status Log
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Form 1 Log (Jumper Log)
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Plant Trouble Reports
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Selective Valve Lineups
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Health Physics Logs
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During tours of accessible areas, particular attention was directed to the folicwing:
Monitoring Instrumentation
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Radiatioa 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 Annunciators
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The operability of selected systems or portions of systems were verified by walkdown of the accessible portions.
The observations were for the control room and service building HVAC system.
Procedures were also reviewed and observations were made of surveillance procedures for gas release No. 460 (SR 5.8.2 bc-M Radioactive Liquid Effluent System, System Instrumentation Functional Test).
The test was performed satisfactorily.
Review of Logs During the inspector's review of control room logs on August 6, 1980, it was noted that a deviation had been written for SOP 12-01 (SOP-Standard Operating Procedure).
The deviation was written because there was no indication of position for rod pair #23.
The deviation provided for a
" timed withdrawal" of rod pair #23 and verification that the rod had moved by using " Rod In" and " Rod Out" Lights and a known rod speed.
The inspector noted that rod position can normally be determined by an analog readout, digital readout, and rod position recorder ZR-1233-1.
Upon check-ing the rod position recorder and associated chart No. 2575350, the recorder was found not working.
The chart paper indicated the recorder had not been working since July 27, 1980, and no PTR (Plant Trouble Report) had been written.
Technical Specification AC 7.4.a requires in part that, " written procedures shall be established, implemented and maintained.
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administrative procedures implemented on August 4, 1980, there are two administrative procedures applicable.
Prior to August 4, 1980, Admini-strative Procedure No. 28 for Data Logs, Data Sheets and Charts, Section 3.2, states that a responsible person shall check the charts or recorders at least once per shift to be sure that the recorders are inking and that at midnight they are to stamp each chart with a new date, and if the recorder is not working properly to write a Plant Trouble Report.
Since August 4, 1980, Administrative Procedure P-1, Plant Operations, is appli-cable and Section 4.5.2.e(4) states "PTR's are initiated for any deficient recorders or integrators." The failure to fulfill these requirements were discussed with the licensee at which time it was pointed out that this was an apparent item of noncompliance for failure to follow proce-dures and was considered an infraction (8018-1).
The inspector had no additional questions in this area.
4.
Maintenance (Monthlyl The inspector reviewej records and observed work in progress to ascertain that the following maintenance activities were being conducted in accord-ance with approved procedures, Technical Specifications and appropriate e
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Codes and Standards:
PTR 10-049 Repair and Reset Safeties V-32304, V-32305, and V-32306 PTR 7-395 ACM Oil Circulating Pump Making Noise PTR 3-68
"A" Boiler Feed Pump Turning Gear Problems PTR 8-336 Snubber MSS-257 Stroke Tolerance PTR 8-351 Snubber CRS-262 Stroke-Tolerance No items of noncompliance or deviations were identified.
5.
Surveillance (Monthly)
The inspector review all aspects of surveillance testing involving safety-related systems.
The review included observation and review relative to Technical Specification requirements.
The surveillance tests reviewed and observed were:
SR 5.4.3-A Core Region Outlet Temperature Instrumentation Calibration
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SR 5.4.1.1.12a-M Main Steam Pressure Scram Test SR 5.2.1c1-M/A PCRV Pressure Switches and Alarms Functional Test SR 5.2.8abc-Q Emergency Bearing Water Makeup Pump Functional Test During observation of SR 5.10.3-M/5.4.2-A it was determined by the in-spector that:
The individual performing the test was smoking a cigarette (as a.
allowed by the surveillance procedure) in the reactor building.
This is, however, contrary to Procedure P-10, paragraph 4.3.4, which states that smoking is not permitted at any time within the reactor building.
This conflict between procedures was called to the atten -
tion of the licensee.
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For checks of the alarms in air ducts where blockage of-the effect of duct on the sensor is required, a cloth was being used.
However, the procedure did not include a procedural step (check) for the cloth's removal.
The above items were discussed with representatives of the licensee who indicated they would make the appropriate changes to the. surveillance procedure.
This item' remains as an open item (8018-2).
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l No items of noncompliance or deviations were identified.
6.
Review of Plant Operations The inspector reviewed the licensee's training program to determine if it was being accomplished in accordance with regulatory requirements.
It was determined by observation of the training program and by questioning of licensee personnel that the training program was meeting its objectives and that the appropriate training, such as for fire fighting, security, and emergencies, was as required.
No items of noncompliance or deviations were identified.
7.
Review of Licensee Event Reports The inspector reviewed licensee event reporting activities to verify that they were in accordance with Technical Specification, Section 7, including identification details corrective action, review and evaluation of aspects relative to operations and accuracy of reporting.
The following reports were reviewed by the inspector:
80-27 80-33 80-29 80-37 80-32
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No items of noncompliance of deviations were identified.
8.
IE Bulletins / Circulars The inspector verified by record review, observation and discussion with representatives of the licensee, the action taken in response to IE i
Bulletins / Circulars.
The following bulletin was reviewed:
30-11 Masonary Wall Design - The inspector reviewed the licensee's program and work schedule, schedule for response and observed six block walls of a total of 98 indicated by the licensee in his initial response P-80198 dated July 7, 1980. No problems with the schedule priority or work done to date were identified.
A discussion on September 12, 1980, with the engineer assigned the task for evaluation of the walls indicated the 50% of the analyses on category B and C walls were complete with no indicated problems.
It is to be noted that any hangers on these walls are alresuy being relocated under Bulletin 79-14.
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During the on site inspection by the inspector on August 16, 1980, it was determined that a block wall located adjacent to the fuel storage wells on level 10 in the northeast corner of the Reactor Building had not been included IT the licensee's response.
This was called to the attention of the licenset who then performed a full inspection of walls in both the Reactor Building and the Turbine Building and found that two additional walls had not been included in the initial survey.
The licensee agreed to include this information with that due in the 180 day response.
The inspector had no additional questions regarding the block walls, however, the bulletin will remain open pending completion of the licensee's final
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response.
- The following circular was reviewed:
80-14 Radioactive Contamination of Plant Demineralized Water System and Resultant Internal Contamination of Personnel - The licensee has completed a review of the circular and has concluded that no pathways exist for cross-connecting to alow contamination of the demineralized water system. Additionally, the portable water system is the only authorized water supply for consumption.
No items of noncompliance of deviation were identified.
9.
Exit Intaviews Exit interviews were conducted at the end of various segments of this inspection with Mr. D. Warembourg (Manager, Nuclear Production) and/or 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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