IR 05000267/1981013
| ML20010A523 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 07/16/1981 |
| From: | Dickerson M, Plumlee G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20010A506 | List: |
| References | |
| 50-267-81-13, NUDOCS 8108110504 | |
| Download: ML20010A523 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report:
50-267/81-13 License DPR-34 Docket:
50-267 Licensee:
Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Facility Name:
Fort St. Vrain Nuclear Generation Station Inspection at:
Fort St. Vrain Site, Platteville, Colorado Inspection Conducted:
June 1-30, 1981 Inspectors:
E jfn 7[L/Al M. W. Lickerson, Senio ' Resident Reactor Inspector
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G. L. Plumlee, I.;1, R ident Reactor Inspector
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Approved b :
p T. F. Westerman, Chief, Reactor Project Section Date
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No. 1
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Inspectio Summary Inspection conducted June 1-30,1981 (Report: 50-257/81-13)
Areas Inspected:
Routine, announced inspection of Surveillance; Maintenance; Operational Safety Verification; Plant Operations; Refueling Activities; IE Bulletin / Circular Follow-up; Licensee Action in Previous Inspection Findings; Review of Periodic and Special Reports; and Licensee Event Follow-up. The inspection involved 190 inspection-hours on site by two NRC inspectors.
Results: Within the nine areas inspected, seven violations were identified (failures to adhere to Technical Specification limitations, paragraphs 3.A(1)a., 3.A(1)b., 3.A(2); and failure to follow procedural requirements, paragraphs 3.A(1)c., 3.B., 3.C, 6.)
8108110504 810723 PDR ADOCK 05000267 G
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DETAILS 1.
Persons Contacted D. Warembourg, Manager Nuclear Production
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F. Mathie, Operation Manager L. Brey, QA Manager J. Gahm, Supervisor Technical Services L. McBride, Site Engineering Coordinator L. Singleton, Superintendent Operation QA
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W. Hillyard, Administrative S9rvices Manager V. Wetzbarger, Scheduling QC Supervisor M. Denistun, Shift Supervisor
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D. Hood, Shift Supervisor E. Hill, Superintendent of Operations V. Lucero, Plant Chemist The NRC inspector also contacted other plant personnel including reactor.
operators, maintenance men, electricians, technicians and administrative personnel.
2.
Licensee Action on Previous Inspection Findings
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(Closed) Violation (50-267/8106) Failure to Properly Complete PTR.
The personnel involved were notified in writing by internal memo dated
June 11, 1981, that their performance level must be improved.
(Closed) Open Item (50-267/8012-02) SR 5.10.3 M/5.4.2A Requires Modification.
The surveillance procedure and Procedure P-10 have been modified to permit the use of cigarettes in the reactor building for the purpose of checking smoke detectors.
Additio ally, the surveillance
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procedure now provides for removal of material inserted in the detectors
to aid in the test.
The number of the SR has been changed to SR 5.10.3-b SA/5.4.2A.
3.
Operational Safety Verification The NRC inspector reviewed licensee activities to ascertain that the facility is being operated safely and in conformance with regulatory requirements, and the licensee's management centrol system is effectively discharging its responsibilities for continued safe operation.
The review was conducted by direct observation of activities, tours of the facility, interviews and discussion with licensee personnel, independent verificatio" of safety system status and limiting conditions for opera-
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tions, and review of facility records.
Included in the inspection were obserystion of control room activities, review of operational logs, records, and tours of accessible areas.
Logs and records reviewed included:
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Shift Supervisor Logs
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Reactor Operator Logs
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Equipment Operator Logs
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Auxiliary Operator Logs
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Technical Specification Compliance Logs
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Operations 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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During tours of accessible areas, par +.icular 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 Vibrations
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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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The operability of selected systems or pcetions of systems were verified by walkdown of the accessible portior.s.
The NRC inspector verified the opera-bility of the Water Treatment System.
Findings are documented in paragraph 5.A, "Non-Radioactive Liquid Effluent," cf this report.
Procedures were also reviewed and implementation observed for Gaseous Effluent Releases No.
545 and No. 547 and Liquid Waste Release No. 472.
The releases appeared to have been made in a satisfactory manner.
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A.
Non-Radioactive Liquid Effluent The NRC inspector performed a complete walkdown of the accessible portions of the Water Treatment System.
In conjunction with this system operability verification, the NRC inspection reviewed logs, records, and procedures to verify compliance with Non-Radiological Technical Specifications.
(1) During the review of 20 completed weekly surveillances titled NR 1.1-W Chemical Concentrations, and five completed monthly surveillances titled NR 1.3-M Turbine Building Sump, the NRC inspector noted the following:
i a.
For week #5, the residual chlorine daily sample concentration of 0.7 ppm taken on February 3, 1981, exceeded the Technical Specification limit of 0.5 ppm and was not reported.
This is in violation of Specification LC0 NR 1.1, " Chemical Con-
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centrations - Limiting Conditions for Operations," and LC0 7.5, " Reporting Requirements" (8113-01).
b.
For week #8. the total phosphate weekly sample concentr.. tion of 7.814 ppm taken on February 24, 1981, exceeded the 50%
limit of 7 ppm and the required daily analyses were not per-formed.
The column in the Daily Results Log for logging the phosphate concentration when daily sampling is required was marked NR (Not Required).
This is a violation of Spect-fication SR NR 1.1, " Chemical Concentrations - Surveillance Requirements" (8113-02).
c.
For 17 of the weekly surveillances which start on Fridays, Shift Supervisor permissic' to initiate the surveillance was not given until the following Monday.
For three of the weekly surveillances, Shift Supervisor permission was not given until Tuesday.
For the five monthly surveillances which start at the beginning of the month, Shift Supervisor permission to initiate the surveillances was not given until the end of the month.
This is in violation of Procedure ADM-13 (Rev. 19, January 10, 1980), " Technical Specifica-tion Surveillance" (8113-03).
(2) During the review of Water Chemistry Procedures, the NRC inspector determined that in accordance with WCP-8.5.3, " Conductivity,"
the conductivity meters are being checked with a standard solution monthly versus weekly as required by Technical Speci-fications. This appears to be a violation of Specification SR NR 1.1, " Chemical Concentration - Surveillance Requirements" (8113-04).
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(3) The NM inspector has noted that the wording in the Technical Specification SR NR 1.1.d) which in part states "... conduc-tivity and pH meters shall be calibrated using standard solutions weekly....", appears to be ambiguous in that the licensee's Water Chemistry Procedure 18, "pH, Electrode" requires a check of the pH meter against a standard solution of known concentration prior to use of the meter. Water Chemistry Procedure 8, "Conduc-tivity", requires a check of the conductivity meter to be per-formed monthly against a known standard as a determination of the cell conctant.
At this time it is unclear as to the meaning of the word " calibrated" as used in this Technical ipecification.
This is considered an unresolved item pending clarification of the intent of Technical Specification SR NR 1.1.d) (8113-05).
The above items were discussed with the licensee who was informed that those items which failed to meet the requirements of the Technical Specifications are considered violations.
B.
Radiation Monitors (1) During a tour on June ?$,1981, at 6:30 a.m., the NRC inspector observed that the printer for recorder RR 93256, " Effluent Activity Monitor," had been secured since 10:30 a.m. June 24, 1981.
After a check of the Plant Trouble Report (PTR) Log to ensure no deficiency existed, the NRC inspector notified the Shift Supervisor and the recorder printer was returned to service at 6:57 a.m. on June 25, 1981.
The licensee was not aware of the reason for the printer being secured or who had secured it.
This is in violation of Administrative Procedure P-1 (8113-06).
(2) During a tour on June 29, 1981, at 6:30 a.m., the NRC inspector observed that the printer for recorder RR 93254 " Area Monitor",
was secured since 3:30 a.m. June 29, 1981, and the recorder was monitoring only one point.
The Shift Supervisor was notified and the recorder was returned to normal at 6:45 a.m. on June 29, 1981.
The NRC inspector was informed by the licensee that failure to return the recorder to normal and occured upon completion of surveillance SR 5.4.9-W, " Area Monitor Functional Test." The NRC inspector nviewed the completed surveillance and noted that step 5.1.9, which ensures that all indications are verified normal, had been checked off and initialed indicating completion of that step.
This is in violation of Procedure ADM-13, "Techni-cul Specification Surveillance" and SR 5.4.9-W " Area Monitor
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Functional Test" (8113-36)
The above items were discussed with the licensee who was informed that the failure to meet the requirements of the Technical Specifications is considered 3 violation.
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C.
Systems Abnormalities Book During a review of the Systems Abnormalities Book on June 18, 1981, at 7:00 a.m., the NRC inspector noted nine clearances numbered 1344, 1698, 1737, 1746, 1747, 2196, 3421, 3450 and 3488 containing auxiliary tags without the check marks required after hanging of the tags.
Procedure P-2 Section 4.1.5 requires that the Reactor Operator or his delegate hang all auxiliary tags and check the Standard
Clearance Points form.
ihis item was discussed with the licensee who was informed that failure to meet the requirements of Administra-ticn Procedures is considered a violation (8113-07).
D.
During review of the Shift Supervisor's Log dated June 23, 1981, it was noted by the NRC inspector that at 7:00 p.m. when the reactor operator attemptad to run gas waste release surveillance SR 5.8.1d-W, he found radiation process instrument RIS 6314-2 in the by pass position.
Because it was by passed the surveillance was not completed and the ensuing gas waste release was not initiated.
No tag was on the instru-ment indicating it was in the by pass condition nor was it condition noted in the logs.
Discussions with representatives of the licensee on June 24, 1981, determined that a calibration of RIS 6314-2 was in progress utilizing SR 5.8. led-Q.
However, the procedure as written does not call for tagging of the instrument nor does it require a notation in the operations logs relative to the condition of the instrument.
This matter was discussed with the licensee who indicated that the procedure would be revised to include these requirements.
This matter is con-sidered as an unresolved item (8113-08).
It should be noted that RIS 6314-2 is not utilized during a gas release but is included in the weekly surveillance check as required by Technical Specification SR 5.8.1.d).
4.
Surveillance (Monthly)
The NRC 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:
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SR 5.8.labc-M Radioactive Gaseous Effluent System Test (Release #545 and #547)
SR 5.8.2bc-M Radioactive Gaseous Effluent System Instrumentation Functional Test (Release #472)
No violations or deviations were identified.
5.
Maintenance (Monthly)
The NRC inspector reviewed rccords and observed work 10 progress to ascertain that the following maintenance activities were being con-ducted in accordance with approved procedures, Technical Specifica-tions and appropriate Codes and Standards.
PTR 8-328 Repair llV-2250 in accordance with MP 22, " Maintenance and Repair of Rockwell-Edwards Valves, Pressure Seal Type," and MP 91-9, " Maintenance and Repair System 91 SAE Four-Bolt Flanges."
CN1233/CWP81-24 Inste!1ation of 2" and Under Hangers which Require Loop 1 Circulators A & B Shutdown and Isolated PTR 5-286 Remove und Replact "B" Circulator C-2102 in accordance with MP 21-15, Hellvi Circulator Change Out Procedure EHP - 4 Refueling CN 1273/CWP 80-26-1B install Mist Eliminators and Elevate Existing Valves on the Discharges of Suffer Helium Recirculators C-2105 and C-2106 FHP - 9 Verification of the Shutdown Margir During In-Core Maintenance.
PTR 12-109 Repair HV-2250 in accordance with MP 22 and MP 91-9 During a review of FHP-4, " Refueling," radiation posting require-ments, the NRC inspector noted a violation (8113-08) which is discussed in paragraph 6, " Refueling Activities."
6.
Refueling Activities The NRC inspector witnessed ongoing refueling activities to verify that all refueling activities were being performed in accordance with Technical Specification requirements and approved procedures.
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During an inspection of posting requirements for FHP-4, " Refueling,"
the NRC inspector noted on June 29,1981, at 1:30 p.m. that the barrier to the north stairwell access to the refueling floor had been removed.
Health Physics Procedure HPP-9 Section 2.5 requires that all controlled areas be clearly marked.
Access to the refueling floor was being controlled at the south stairwell access by Radiation Work Permit (RWP 02750).
Access up the north stairwell was not permitted by use of a barrier.
The licensee was notified and the barrier was replaced.
Additionally, the licensee was informed that failure to meet the requirements of Health Physics Procedures is considered a violation (8113-09).
7.
Report Reviews The NRC inspector reviewed the following reports for content, reporting requirements and adequacy:
Monthly Operating Information Report, May 1981 Monthly Operations Report, April 1981 No siolations or deviations were identified.
8.
IE C:rcular/ Bulletin The NRC inspector verified by record review, observation and dis-cussion with the licensee, the action taken in response to IE Circulars / Bulletins.
The following Circulars were reviewed:
81-03 Inoperable Seismic Monitoring Instrumentation.
The licensee performed their semi-annual surveillance S.R.5.4.10.SA and developed procedure SR-RS-17-SA which incorporates the information contained in the circular.
81-04 STA Program and Program for Reporting Operational Events.
Evaluations of each off-normal event is evaluated by the STA and those involved in the event as socn as practical after the event is written, including any recommendations.
If required the event is reported to the NRC.
81-05 Self-Aligning Rod End Bushings for Pipe Supports.
The licensee has determined that disengagement of the rod end bushing is not a potential problem at Fort St. Vrain. This conclusion was based on the manufacturer, the type of bracket /
clamp installed, method of installation and audits of the Class 1 snubbers and the seismic hangers for 10-inch and under piping systems.
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81-06 Potential Deficiency Affecting Certain Foxboro 10 to 50 Milliampere Transmitters.
The licensee has determined that this type of transmitter is not installed at Fort St. Vrain.
81-07 Control of Radioactively Contaminated Material.
The licensee's monitoring methods appear to be consistent with the information in the circular and as indicated in their letter P-81069 dated March 2, 1981.
81-08 Foundation Materials.
Not applicable to Fort St. Vrain.
The following Bulletin was reviewed:
81-03 Flow Blockage of Cooling Water to Safety System Compon-ents by Corbicula SP. (Asiatic Clam) and Mytilus SP. (Mussel).
The licensee has determined that blockage due to this mechanism is not likely since the Asiatic clam and the mussel are not inhabitants of either the South Platte River or the St. Vrain River in the vicinity of Fort St. Vrain.
The results of the licensee's inspection of equipment and a discussion of the upgraded Aquatic Biota program is contained in Public Servica Company letter P-81151 dated May 22, 1981.
No violations or deviations were identified.
9.
Review of Plant Operations The NRC inspector reviewed the physical security aspect of facility operations to determine if it was being accomplished in accordance with regulatory requirements.
To accomplish this the NRC inspector attended a training lecture given to security personnel and verified that the lesson plan objectives and the schedule were being met.
Also, observed on June 23, 1981, were three new guards in training who were conducting weapons firing.
However, during the time of observation no acceptable scores were achieved.
No violations or deviations were identified.
10.
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.
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The following reports were reviewed by the inspector:
80-53 81-34 80-67 11.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, violations or deviations.
T.le unresolved items disclosed in this inspection are:
8113-05 in paragraph 3.A(3)
8113-08 in paragraph 3.0.
12.
Exit Interview 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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