IR 05000267/1980010
| ML19320B828 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/06/1980 |
| From: | Collins R, Dickerson M, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19320B823 | List: |
| References | |
| 50-267-80-10, NUDOCS 8007150091 | |
| Download: ML19320B828 (12) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-267/80-10 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: May 1-31, 1980 Inspectors:
3-6[t[fo
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/3M.W.Dickerson,SeniorResidentReactorInspector Date
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C/4/90 pR.E.'-Collins,ResidentReactorInspector
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Cb/70 G. L. C#nstable, Reactor Inspector
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4N[.fd Approved by: /
'T. F. Westerman, Chief, Reactor Projects Section Date Inspection Summary Inspection May 1-31, 1980 (Report No. 50-267/80-10)
Areas Inspected: Routine, announced inspection of review of surveillance testing and calibration control program; review of plant operations; review of event reports; follow-up on inspector identified and unresolved items; surveillance; maintenance; operational safety verification; and revicu of bulletins.
The inspection involved 242 inspector-hours on-site by three (3) inspectors.
Results: Within the eight (8) areas inspected, two items of noncompliance was identified (Infraction - Failure to meet fire watch and extinguisher
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requirements, paragraph 3; and Infraction - Failure to obtain approval for changes made to procedures, paragraph 9).
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DETAILS 1.
Persons Contacted L. Brey, QA Manager W. Craine, Maintenance Supervisor W. Franek, Results Supervisor
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W. Franklin, Shift Supervisor J. Gama, Supervisor Technical Services E. Hill,-Operations Superintendent F. Mathie, Operations Manager L. McInroy, Superintendent of QA Services
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J. Oliver, Shift Supervisor J. Van Dyke, Shift Supervisor D. Warembourg, Manager Nuclear Production V. Wetzbarger, Scheduling and QC Supervisor The inspectors also contacted other plant personnel including reactor operators, maintenance men, electricians, technicians and administrative personnel.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (50-267/7512) Records procedure.
Procedure IWP-3, Revision 1, dated May 13, 1980, has now been issued for use which provides for record retention times and vault turnover procedures.
(Closed) Open item (50-267/8006-1) Indicating lights on I-49 out.
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failed lights have been replaced and a check of the panel has been added to PMO-28 in Revision 5, dated April 16, 1980.
3.
Operational Safety Verification The inspector reviewed licensee activities to ascertain that the facility
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is being operated safely and in conformance with regulatory requirements, and that the licensee's management control system is effectively dis-charging its responsibilities for continued safe operation.
The review was conducted by direct observation of activities, tours of the facility, interviews 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:
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4 Shift Supervisor Logs
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Reactor Operator Logs
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Technical Specification Compliance Log
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Operat:' g 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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During tours 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 Piping Vibration
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Hanger / Seismic Restraints
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Clearance Tags
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Control Room Manning
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The operability of selected systems or portions of systems were verified by.walkoown of the accessible portions. The observations were for the:
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Hydraulic Power System Reserve Shutdown System Emergency Diesel Generator Fire Protection System Purification Cooling Water System Procedures were also reviewed and observations were made of survei~ lance procedures for gas release No. 438 (SR 5.8.labc-M Racioactive Gaseous
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Effluent System Test) and for liquid release No. 385 (SR 5.8.2bc-M Radioactive Liquid Effluent System Instrumentation Functional Test).
Both tests were performed satisfactorily.
a.
Welding Observations During a tour c! the facility on May 15, 1980, while observing work on S2504 Nitrogen Recondenser, the inspector noted sparks falling from the level above where velding was being performed.
The inspector went to the level where welding was in progress and observed that there was no fire extinguisher in the area. Moreover, the fire watch required to be present during welding was helping hold a fire blanket with a third person while the welder was welding. The welder and
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two helper's vision were obscured below due to the fire blankets and they could not observe any hazardous conditions which could have been created by the falling sparks.
When the inspector inquired where the required fire extinguisher was, one of the individuals holding the fire blanket indicated the extinguisher on the next level below, about 50 feet away by the nearest path.
He then went and stood by the fire extinguisher. Technical Specifications 7.4 states in part:
" Written procedures shall be established, implemented and maintained." Admin-istrative Procedure, ADM-29, Control of Ignition Sources During Main-tenance, states in part in Section 4.1.1:."All welding operations
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another man who shall watch for sparks.
And in Section 4.1.3
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it states that:
"At the site of welding operations will be a fire extinguisher suitable for the local hazards." Discussica with
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representatives of the licensee confirmed that the fire watch is l
to have no other duties but to watch for sparks while welding is in operation and the fire extinguisher should be no greater than 5-6 feet from the fire watch.
The failure to comply with the Technical Specification requirement and FSV Administrative Procedure, ADM-29, was discussed with the licensee who was informed that this was an apparent item of noncom-pliance for failure to adhere to the procedural requirements.
The inspector had no additional questions in this area.
b.
Circulator Buffer Helium System Upset (1)
Introduction On May 1, 1980, at approximately 2130, a Circulator Buffer Helium System upset occurred which resulted in the release of contained helium to the reactor building and subsequently to the stack. The activities preceding the release as deter-mined from review of logs, instrument, charts, records and discussion with personnel were as follows.
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(2) Activities Preceding and During Release At 1340, reector power had been raised to 57% and held to observe the magnitude of the total oxidanta in the primary coolant.
This power level was held until approximately 1800 when reduction of power was initiated due to total oxidants greater than 10 ppm.
Reduction in power continued until 2040, at which time the reactor power was approximately 45% and the core outlet temperature was
less than 12000F. This powar level was held during and after the system upset.
During this period of time the Buffer Helium return flows were being adjusted en the circulators in an attempt to minimize the moisture (total oxidants) being observed in the primary coolant system. At about 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, activity in the low pressure sep-arator on RT-21251 was noted to be 3000 cpm (peak). Normal background activity on the LP Separator is about 30 cpm.
This occurred a short time after the return ficv on "D" circulator had been adjusted (reduced). The Buffer Helium return flow was then in.reased and the activity in the low pressure separator began to decrease. A check of the new stack monitors RT-73437-1 and RT-73437-2 indicated a beta activity level of 80 cpm above background (N100 c7m) with no increase on the Iodine channel.
The Constant Air Monitor (CAM) located on the lowest level of the reactor building peaked at 6000 cpm (k mr/hr) at approximately 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />. Normal background on the CAM was N100 cpm. The time coincided with the times of the peaks seen on the stack monitor and the LP separator.
(3) Discharge Path The apparent discharge path of the activity was down the shaft of "D" circulator to LP separator tank T-2111 to the helium dryer. Valve packing leaks (found later) at the discharge of the LP separator and the helium dryer released the activity to the reactor building and then to the reactor building stack.
(4) Radiological Considerations (a) The total release was calculated from the information avail-able from RT-73437-2, stack beta monitor, as 11 pC1.
This is based on a total release time.of two and one-half hours (2130 to 2400).
(b) The initial indications seen on all three monitors (RT-73437-2, RT-21251 and the CAM) started, peaked and returned to back-ground levels at approximately the same times.
These were
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the only radiation monitors which showed any indications above background.
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'(c) The MDA values calculated on the stack monitor charcoal cartridges were < 1.98E-14 uCi I-131/cc on RT-73437-1 and
< 2.70r-14 pCi I-131/cc on RT-7325.
These figures were based on the tetal run period April 28 to May 2, 1980.
(d) The activity release determined in (a) above was apparently due to Noble gases (88Kr, 138Xe).
This is based on the results of Gamma Spectroscopy of the particulate filters and charcoal cartridges which indicated no significant gamma activity.
(e) A grab sample in the reactor building at the peak of the activity indicated a concentration of 7.19E-9 pCi/cc and resulted in restrictions for entering the building.
This continued until 0100 on May 2, 1980 at which time the restrictions were lifted when the concentration had returned to background levels (N 1.87E-10 pC1/cc.).
(f) Radiation Monitoring Instrument Readings.
Highest Alarm Present Set Instrument Count (yes/no)
Point Location 21251 3000 No 10,000 cpm Low Pressure Separator Drain to Liquid Waste Sump 7324-1 Bkgnd No 77,000 cpm Reactor Plant Exhaust
7324-2 Bkgnd No 2,000 cpm Reactor Plant Exhaust 7325-1 Bkgnd No 3,200 cpm Reactor Plant Exhaust 7325-2 Bkgnd No 10mR/ER Reactor Plant Exhaust 73437-1 Bkgnd No 6,000 cpm Reactor Light only Plant Exhaust
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73437-2 180 No 2200 cpm Reactor Light only Plant Exhaust i
No items of noncompliance or deviations were identified.
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Maintenance The inspector reviewed records and observed work in progress to ascertain that maintenance of activities were being conducted in accordance with approved procedures, Technical Specifications and appropriate codes and standards.
The following maintenance activities were reviewed:
PTR 5-16, Repair S2504-Nitrogen Recondenser PTR 5-158 Repair Helium Dryer Knock-out pot drain PTR 5-033 'B' Getter Outlet Valve T-143 Center the meter adjust potentiometer for the wide range power instruments.
No items of noncompliance or deviations were identified.
5.
Surveillance (Monthly)
The inspector reviewed 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 5.4.1.1.14.a-M Plant 480V Power Loss Scram Test.
SR 5.4.1.1.13.a-M Two Loop Trouble Scram Test SR 5.2.20.a-W ACM Generator Load Test No items of noncompliance or deviations were identified.
6.
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:
R0 78-05 RO 79-49 RO 79-02 RO 79-51 RO 79-03 R0 80-11 RO 79-19 R0 80-14 RO 79-22 R0 80-15 RO 79-29 R0 80-18 RO 79-41
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7.
IE Bulletins The' inspector verified by record review, observation and discussion with representatives of the licensee, the action taken in response to IE
Bulletins.
The following bulletins were reviewed:
79-02 Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts - Review completed.
See inspection Reports 50/267-79-19 and 80-02.
Unresolved item 79-19-01 remains open regarding correction of unidentified drawing discrepancies but will be carried as part of Bulletin 79-14 as indicated in report 79-19.
79-27 Loss of Non-class IE Instrumentation and Control Power System Bus During Operation - The licensee has submitted their reply, P-80087 dated April 25, 1980 and the inspector has reviewed the emergency procedures relative to Item 2 of the Bulletin and they i
appear be acceptable. The two items identified in the licensee's reply which will be completed by August 1, 1980 will be carried as an open item subject to their satisfactory resolution.
i No items of noncompliance or deviations were identified.
8.
' Review of Plant Operations i
The inspector reviewed several aspects of facility operations to deter-mine if they were being accomplished in accordance with regulatory require-ments. Reviewed were procurement and storage; corrective action; and review and audit.
The inspector reviewed the following purchase orders, receipt records, storage and certification records:
P0 N-2060H - 2 inch tees PO N-2234C Code #1774244 - 2 inch valves PO N-2261 Code #1772945 - 3/4 inch globe valves PO N-2707C Code #1770145 - Pipe Nipples During the review of material storage it was observed that material which is not qualified for use in safety-related systems is stored in the same general area as material qualified for use in safety-related systems.
Much of this material is tagged as such with a nominal 4k x 2 inch manila tag and not with the type of Tag now required by QACP 2-2, Quality Assurance Control Procedure, since the revision of January 11, 1980.
The manila tags are usually placed on a single item in a bin of many items and for those items tagged prior to January 11, 1980 constitute the main control for assurance that they will not be issued for use in a safety-
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related system. The licensee is presently investigating the replacement of these tags with the pre printed tags required by QACP 2-2 and of placing tags on each item where it is feasible.
This will remain as unresolved item 8010-1.
.The inspector had no additional questions in the areas of procurement and storage; corrective action; and review and audit.
9.
Surveillance The purpose of this inspection effort was to review the licensee's program for surveillance of safety-related systems and components.
During the course of the inspection discussions were held with engineers, operators and technicians on their respective roles regarding surveil-lance.
Portions of surveillance activities were witnessed, and the follow-ing surveillance test results and their respective procedures were reviewed for technical adequacy and to verify compliance with procedures and regula-tory requirements.
Procedure Number Title Dates SR 5.1.3 - R Temperature Coefficient July-August, 1979 SR 5.2.1 C2 - A PCRV Relief Valve Indica-May 24, 1979 tors Calibration and June 1 and 7, 1979 Functional Test SR 5.2.1C1 - M/A PCRV Pressure Switches August-December 1979 and alarm functional test.
SR 5.2.1b - X Steam Generator and Cir-February 28, 1979 culator Penetration Safety Valve Test SR 5.2.la - A PCRV Rupture Disc and December 10, 1979 Safety Valve Test SR 5.2.1c - A PCRV Relief Valve Indi-December 12, 1979 cators Calibration and Functional Test
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SR 5.2.13 - X PCRV Helium Permeability October 29, 1979 Test SR 5.2.20a - W ACM Generator Lead Test October-December 23, 1979 (Weekly)
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Procedure Number Title Dates SR 5.2.20b - M ACM Generator Load Test June 15 - December 12, 1979 (Monthly)
SR 5.2.21 - SA ACM Pneumatically and May 5 and December 29, 1979 Electrical Operated Valves and Transfer Switch Functional Test SR 5.2.10 - A Engine Driven Fire Pump August 1, 1979 Instrumentation Calibration SR 5.2.10 - M Engine Driven Fire Pump January 10 - August 5, 1979 Instrumentation Functional Test During the review of SR 5.1.3 - R, Temperature Coefficient of Reactivity, the inspector observed that the data that was collected and used in the analysis was different from that data specified in the procedure. The procedure required that data be collected at certain power levels listed below. The power levels at which data was actually collected for use in the analysis is listed for comparison.
Procedure Requirements Actual Data Used 0 - 2%
No Data at 0 or 2%
2% - 5%
No Data 5% - 8%
5.0% - 7.7%
8% - 11%
8.3% - 10.5%
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9.3% - 10.6%
11% - 18%
11.6%
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13.5% - 17.2%
18% - 27%
23.4% - 26.5%
27% - 40%
No Data 40% - 60%
42.4% - 62.8%
60% - 70%
No Data The results of the analysis appear to verify that the actual technical specification requirements for temperature coefficient are being met.
However, the wide variation between procedural requirements and what
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was actually done represent unauthorized changes to the procedure.
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Apparently no attempt was made to have deviations from the procedure approved nor did subsequent management reviews recognize that unauthor-ized changes had been made. This is an item of noncompliance.
During the review of SR 5.2.20b-M, ACM Generator Lead Test, it was noted that in step 1, the breaker position was changed from verify open to verify closed.
In addition, the names of some breakers had been changed and a step (7a) had been added to the procedure. These changes to the procedure were not authorized in accordance with technical specifi-cation requirements and therefore represent on item of noncompliance.
10.
Unresolved Items i
Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncom-pliance, or deviations. One unresolved item (8010-1) disclosed during the inspection is discussed in paragraph 4.
11.
Exit Interviews 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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