IR 05000313/1981003
| ML20003J199 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/12/1981 |
| From: | Callahan C, Hunnicutt D, Johnson W, Spangler R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20003J190 | List: |
| References | |
| 50-313-81-03, 50-313-81-3, 50-368-81-03, 50-368-81-3, NUDOCS 8105110015 | |
| Download: ML20003J199 (9) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report Nos. 50-313/81-03 License No. OPR-51 50-368/81-03 NPF-6 Licensee:
Arkansas Power and Light Company P. O. Box 551
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Little Rock, Arkansas 72203 Facility Name:
Arkansas Nuclear One (ANO), Units 1 and 2 Inspection at:
ANO Site, Russellville, Arkansas Inspection conducted:
January 22 - February 21, 1981 Inspectors:
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W. D. Johnson, Senior Resident Reactor Inspector
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s,65 S//2/Sl L. J. Callan, Resident Reactor Inspector
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R. G. Spangler, Reactor Inspector
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Approved by:
0. M. Hunnicutt, Chief
' Date Project Section 2 Insoection Summary Inspection conducted during ceriod of January 22 - February 21. 1981 (Report No. 50-313/81-03)
Areas Insoected:
Routine, announced inspection including Surveillance Observa-tion, Maintenance, Operational Safety Verification, Refueling Activities, Review of Qualified Electrical Equipment and Follow up on Previously Identified Items.
The inspection involved 82 inspector hours on site by three NRC inspectors.
Results:
No violations or deviations were identified.
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Inspection conducted during period of January 22 - February 21, 1981 (Report No. 50-368/81-03)
Areas Inspected:
Routine, announced inspection including Operational Safety verification, Surveillance Observation, Maintenance, and Follow up on Previously Identified Items.
The inspection involved 83 inspector hours on site by two NRC inspectors.
- Results:
Within the four areas inspected, three apparent violations were identified in two areas (failure to conduct adequate radiation surveys, paragraph 3; missing pipe hanger, paragraph 3; and reactor protective instru-mentation surveillance deficiency, paragraph 4).
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DETAILS SECTION 1.
Persons Contacted
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J. P. O'Hanlon, ANO General Manager G. H. Miller, Engineering & Technical Support Manager
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B. A. Baker, Operations Manager
T. N. Cogburn, Plant Analysis Superintendent E. C. Ewing, Plant Engineering Superintendent L. Sanders, Maintenance Manager J. McWilliams, Unit 1 Operations Superintendent J. Albers, Planning and Scheduling Supervisor D. D. Snellings, Technical Analysis Superintendent L. Bell, Unit 2 Operations Superintendent D. Howard, Licensing Engineer R. T. Elder, Project Engineer 0. Glenn, Health Physics Supervisor P. Jones, Instrumentation and Controls Superintendent J. Benham, Instrumentation and Controls Supervisor The inspectors also contacted other plant personnel, including operators, technicians and administrative personnel.
2.
Follow up on Previously Identified Items (Units 1 and 2)
(Closed) Open Item 313/8003-02; 368/8003-01:
Compliance with requirement for trend analysis in Procedure 1004.10
" Calibration Control."
A new Procedure, 1005.01 " Maintenance M&TE Control," has been issued replacing Procedure 1004.10 " Calibration Control." This new Procedure establishes a satisfactory method of trending calibration data.
(Closed) Open Item 313/8003-03; 368/8003-02:
Control of vendor test equipment.
Procedure 1005.01 " Maintenance M&TE Control" has been implemented and establishes a satisfactory method of controlling the calibra-tion of vendor test equipment.
(Closed) Unresolved Item 313/8006-06; 368/8006-07:
Control of Radiation Work Permits (RWP)
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The ir,pector has determined that the licensee controls over RWP
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acti<ities are adequate.
Problems encountered with Bechtel worke s not complying with the established Procedures seem to be l
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attributable to individual cases of workers not being adequately trained or supervised and not to a general insufficiency of nanagement controls. - Further investigation is unwarranted.
(Closed) Open Item 368/8007-03:
Operation of 2SI-5091-3.
Adequate controls exist to ensure that 2SI-5091-3 is shut for
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shutdown cooling mode.
(Closed) Deficiency 313/8010-03; 368/8010-03:
10 CFR 19 posting requirements.
Permanent Change 4 to Procedure 1000.02 " Plant Safety Committee Operation," implemented on February 19, 1981, establishes satis-factory administrative controls to ensure that the 10 CFR Part 19 posting requirements are met.
(Closed)
Infraction 313/8015-01; 368/8015-01:
Anti-contamination clothing.
The licensee's corrective action on this item was satisfactorily completed.
(Closed) Open Item 313/8015-02; 368/8015-02:
Training for Health Physics Technicians.
Procedure 1023.05 "on-the-Job-Training Program," implemented on December 16, 1980, establishes a training program for Health Physics Technicians.
(Closed) Open Item 313/8015-03:
Operator Training in the Control Room Halon System.
Operators have received the necessary training.
(Closed) Level V Violation 358/8021-01:
Failure to take an Iodine Sample.
The licensee's corrective action on this item has been satis-factorily completed.
(Closed) Unresolved Item 313/8021-01; 368/8021-02:
Security Battery Capacity.
The inspector verified that the security battery is being main-tained at greater than 80% capacity by reviewing recent surveil-lance records.
The licensee has revised the necessary Procedures to ensure that the security battery undergoes surveillance, and that the surveillance documentation is auditabl (Closed) Level V Violation 368/8021-04: Failure to close 2CV-0706 when required by Procedure.
The licensee corrective action on this item has been satisfactorily completed.
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(Closed) Open Item 313/8021-02; 368/8021-03:
Security Diesel Surveillance.
A satisfactory surveillance has been established by procedure 1307.18
" Security Systmi Emergency Diesel Generator Surveillance."
3.
Operational Safety Verification (Units 1 and 2)
The inspectors observed control room operations, reviewed applicable logs and conducted discussions with control room operators.
The inspectors verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components.
Tours of accessible areas of the units were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessi',2 vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance.
The inspectors, by observation and direct interview, verified that the physcial security plan was being implemented in accordance with the station security plan.
The inspectors observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls.
The inspector walked down the accessible portions of the Unit 2 Train A High Pressure Safety Injection and Containment Spray systems to verify operability.
The inspector also witnessed portions of the radioactive waste system controls associated with radwaste shipments and barreling.
These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under Technical Specifications,10 CFR, and administrative procedures.
While attempting to walk down the accessible portions of the Unit
- n A High Pressure Safety Injections system, the inspector was escorted into a posted High Radiation area on 317' level of the Unit 2 Auxiliary Building by a health physics technician.
The escort allowed access to the high radiation area without adequate knowledge of the radiological hazards in the area and without the possession of a radiation survey instrument to determine the radiological hazards.
This appears to be contrary to 10 CFR 20.201(b) which states, "Each licensee shall make or cause to be made such surveys as may be necessary for him to comply with the regula-tions of this part."
(368/8103-02).
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While conducting a tour of the Unit 2 Auxiliary Building, the inspector observed that a pipe hanger was missing from the service water return line from switchgear room cooler 2VUC-2A.
Small pipe isometric drawing 2HBC-92-2 shows the locations of six seismic Class I critical pipe hangers for line number 2HBC-92-2".
The missing pipe hanger was one of these.
This is an apparent violation.
Upon being notified of this condition by the inspector, the licensee took prompt action to install the pipe support as required by plant drawings.
(368/8103-03)
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4.
Monthly Surveillance Observation (Units 1 and 2)
The inspector observed the Technical Specification required surveillance testing on the Plant Protective System, Channel C (Procedure 2304.39) and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with Technical Specifications and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
The inspector also witnessed portions of the following test activities:
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Ex-Core Instrumentation B Test (2304.101)
CEDMCS-Post Trip Verification (JO 9085)
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Control Rod Drive System Calibration and Functional Test (1304.47)
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Monthly Post Accident Log (Unit 2)
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Monthly Remote Shutdown Channel Checks (Unit 2)
While reviewing the results of the monthly functional test surveillance on Channel C of the Unit 2 plant protective system (Procedure 2304.39),
the inspector noted that the procedure's acceptance criteria did not require that the "as found" data be compared to the allowable Values of Table 2.2-1 of Technical Specification 2.2.1.
As a result, the operability of the plant protective system channels could not be demonstrated as required by Technical Specification 3.3.1.1 wnich states, in part:
"Each reactor protective instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1."
Further investigation by the inspector verified that the licensee has not routinely compared the data taken during channel functional tests or channel calibrations with the Allowable Values of Table 2.2-1 during the past year.
This is an apparent violation.
(36E/8103-01)
5.
Monthly Maintenance Observation (Units 1 and 2)
Station maintenance activities of safety-related systems and components listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with Technical Specifications.
The following items were considered during this review:
the limiting
conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and fire prevention controls were implemented.
Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety-related equipment maintenance which may affect system performance.
The following maintenance activities were observed / reviewed:
Unit 2 Job Order 5918 - Charging Pump 2P36C control p~oblems r
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Unit 2 Job Order 7609 - Repair Filter Handling Cask
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Unit 1 Low Pressure Safety Injection Pump Coupling
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Unit 1 F-11 Replacement
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DCP 79-1065 - Installation of Containment Water Level Monitor
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DCP 80-1004 - Installation of RCS High Point Vents
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OCP 1178 - Install new indicators and CRT in control room (AT0G)
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OCP 79-1032A - Install Reactor Anticipatory Trip
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Unit 2 Job Order 7909 - Recalibrate Feedwater Flow Instrumentation
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Following completion of maintenance on the Unit 2 Charging Pump, the inspector verified that this pump had been returned to service properly.
No violations or deviations were identified.
6.
Refuelina Activities (Unit 1)
The inspector reviewed certain Technical Specifications pertaining to refueling and verified that licensee activities were in compliance with the following Technical Specifications:
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3.8.1 Radiation level monitoring requirements in the reactor building refueling area and in the spent fuel storage area 3.8.2 Neutron flux monitoring requirements 3.8.3 Decay heat removal system requirements 3.8.4 Boron concentration
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3.8.5 Communications between the control room and the reactor building 3.8.6 Personnel, emergency, and equipment hatches 3.8.7 Operability of containment isolation valves 3.8.10 Operability of reactor building purge isolation system 3.8.11 Required shutdown period prior to removing irradiated fuel from the reactor 3.22.1 Reactor building purge filtration system operability 3.15.1 Fuel handling area ventilation system operability 6.2.2 Shift crew composition The inspectors observed several periods of fuel handling activities from the reactor building, spent fuel storage area, and the control room.
It was observed that qualified per3annel were performing the activities in accordance with Procedure 1502.04, " Refueling Shuffle," Procedure 1506.01,
" Fuel Handling," and Work Plan 1409.29, " Fuel Sipping with CE Equipment."
The inspector also observed the core verification.
Good housekeeping practices were observed in the refueling area.
No violations or deviations were identified.
7.
Tour of the Unit 1 RB to Observe the Installation of Qualified Electrical Equipment (Reference TI 2515/35)
The inspector conducted a walkdown for selected instruments and components in the ESF Systems in the Unit 1 Reactor Building in order to verify the licensee's response to IE Bulletin 79-01B and to observe the as-installed conditions for this equipment.
The installations were compared to the
"as-built" drawings and no deviations were identified.
Observations made during this tour were reported by memorandum to IE Headquarters for eventual consideration by the appropriate reviewers in NRR.
The following minor discrepancies were identified:
1)
Cover on penetration WR-34 missing, 2)
Two-inch hole found in TB-133,
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Cover missing on pull-box at shield wall for SR1011 conduit run between TB-133 and TB-137, 4)
Rubber gasket missing on conduit fixture located at PT1020.
The licensee has indicated that these items will be corrected by the end of this refueling outage.
8.
Exit Interview The inspectors met with Mr. J. P. O'Hanlon (Plant General Manager) and other members of the AP&L staff at the end of various segments of this
inspection.
At these meetings, the inspectors summarized the scope of the inspection and the findings.
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