IR 05000313/1981017
| ML20009A578 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/05/1981 |
| From: | Callan L, Hunnicutt D, Johnson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20009A575 | List: |
| References | |
| 50-313-81-17, 50-368-81-15, NUDOCS 8107130338 | |
| Download: ML20009A578 (14) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND FORCEMENT
REGION IV
Dockets 50-313/81-17 Licenses OPR-51 50-368/81-15 NPF-6 Licensee:
Arkansas Power and Light Company P. O. Box 551 Little Rock, Arkansas 72203 Facility Name:
Arkansas Nuclear One (ANO), Units 1 and 2 Inspection at:
AN0 Site, Russellville, Arkansas Inspection Conducted:
April 22 - May 21, 1981 Inspector :
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W. D. Jonnson, Senior Resident Reactor Inspector Date
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$/3/<fl s L. J. Carlan, Resident Reactor Inspector
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Approved:
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0. M. Hunnicutt, Chief, Reactor Project Section No.2 Cate
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Insoection Summary Inspection conducted during ceriod of April 22 - May 21, 1981 (Report No. 50-313/81-17)
Areas Inspected:
Routine, announced inspection including surveillance,
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observation, maintenance, follow-up on Licensee Event Reports, operational safety verification, follow-up on previously identified items, and review of plant operations.
The inspection involved 121 inspector hours on site by two NRC inspectors.
Results:
Of the six areas inspected, one apparent violation was identified l
(environmental sampling of vegetation, paragraph 9).
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Inspection conducted during period of April 22 - May 21, 1981 (Report No. 50-368/81-15)
Areas Inspected:
Routine, announced inspection including surveillance (refueling),
maintenance (refueling), follow-up on licensee event reports, follow-up on pre-viously identified items, inspection during long-term shutdown, and review of plant operations.
The inspection involved 99 inspector hours on site by two NRC inspectors.
Results:
Of the six areas inspected, one apparent violation was identified (environmental sampling of vegetation, paragraph 9).
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DETAILS SECTION 1.
Persons Contacted J. P. O'Hanlon, ANO General Manager D. Rueter, Director, Technical / Environmental Services G. H. Miller, Engineering and Technical Support Manager M. Pendergrass, Director, Generation Engineering 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 P. Whitfield, Analysis Services Supervisor P. Collopy, Health Physics Consultant to AN0 M. Bolanis, Health Physics Supervisor L. Taylor, Operations Technical Engineering L. W. Schempp, Manager, Nuclear Quality Control B. A. Terwillinger, Operations Assessment Superintendent W. E. Converse, Operations Assessment Engineer C. S. Petzel, Production Engineer L. W. Humphrey, Administrative Manager P. Jones, Instrumentation & Controls Superintendent H. R. Tucker, Electrical Maintenance Superintendent V. C. Pettus, Mechanical Maintenance Superintendent J. M. Ray, Quality Control Engineer T. Baker, Chemistry / Environmental Supervisor J. C. Garrett, Material Management Supervisor R. Gillespie, Assistant Chemistry Supervisor R. Pool, Radioactive Waste Coordinator T. Pugh, Emergency Planning Corrainator C. Burchard, Assistant Health Physics Supervisor The inspectors also contacted other plant personnel, including operators, technicians and administrative personnel.
2.
Licensee Event Reports Followup (Units 1 and 2)
Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to deter-mine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with Technical Specification.
Unit 1 Unit 2 80-11 79-26 80-12 79-65 80-14 80-12 80-15 80-40 80-24 80-41 80-28 80-49 80-34 80-72 80-35 80-79 80-38 80-90 81-01 81-01 81-02 81-08 81-04 81-12 81-05 81-13 81-06 81-15 3.
Follow-up on Previously Identified Items (Units 1 and 2)
(Closed) Open Item 313/7906-02, 368/7906-02; Infraction 313/8001-02, 368/8001-02; and Deficiency 313/8001-03, 368/8001-03:
Failure to provide an adequate means of identifying, scheduling, per-forming, and documenting protective relay inspection and testing for safety-related switchgear.
The licensee has established a relay testing group consisting of an electrical supervisor and three additional personnel who are permanently assigned to Arkansas Nuclear One.
With the help of outside consultants, this group has identified and categorized the various safety-related protective relays in Units 1 and 2.
Relay testing procedures have been written, approved, and issued to cover the different classes of protective relays, and relay testing has been made an integral part of the licensee's pre-ventive maintenance program.
The licensee completed the testing of protective relays for Unit 1 safety-related switchgear in February, 1981, and for Unit 2 safety-related switchgear in May, 198 I
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(Closed) Unresolved Item 313/7916-13; 368/7914-12:
Effectiveness of Quality Control Since initiation of this unresolved item, the licensee has upgraded the effectiveness of the site Quality Control Depart-ment.
Key items in this upgrading include:
Appointment of a Manager of Nuclear Quality Control
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Appointment'of a QC Engineer
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Appointment of a QC Supervisor
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Increasing size of QC staff
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Use of contract QC inspectors during outages
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Implementation of Revision 5 to the ANO QA Manual for
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Operations.
Implementation of Procedure 1000.23, Quality Control Program
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Implementation of Procedure 1004.01, Quality Control Program
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Implementation, and other QC Program implementation pro-cedures More direct involvement of QC with plant operstions and
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maintenance.
(Closed) Open Item 313/8006-05; 368/8006-06; Correction of conditions requiring jumpers and bypasses.
The licensee has issued and implemented Procedure 1000.28, Jumper and Lifted Lead Control.
This procedure includes a requirement for the Assistant Operations Superintendent to conduct a monthly check of outstanding temporary modifications to assess their continued applicability.
It also requires that temporary modifications installed for greater than three months be reviewed quarterly by the Plant Safety Committee.
(Closed) Violation 368/8009-01:
Failure to comply with requirements of I
Procedure 1005.04, Control and Use of Bypasses and Jumpers.
i The licensee's corrective action for this item has been reviewed by the NRC inspector.
This procedure (1005.04) has been replaced by Procedure 1005.28.
(Closed)
Infraction 313/8010-01, 368/8010-01; and Severity Level V Violation 313/8108-01, 368/8107-01:
Failure to survey the Reactor Auxiliary Buildings for alpha activity and failure to maintain records of alpha surveys.
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The licensee has modified their Health Physics monthly routine radiation survey schedule to ensure that Reactor Auxiliary Building alpha surveys are taken and the data recorded.
(Closed) Deviation 368/8011-05:
Hydrazine additions and ammonia sampling
not in accordance with FSAR commitments.
The NRC inspector has reviewed the licensee's corrective actions for this item and has found them to be adequate.
(Closed) Open Item 368/ A11-06:
Failure to isolate test gages after performance of High Pressure Safety Injection (HPSI) surveillance.
Supplements 1, 2, and 3 to Operating Procedure 2104.39 have been modified to require isolating the suction and discharge pressure test gages after performance of surveillance.
(Closed) Open Item 368/8011-07:
Failure to include a diesel fuel oil system supply valve (F0-5) in the pre-critical valve lineup.
Plant Operating Procedure 1104.36 has been modified to include F0-5 as part of the pre-critical valve lineup.
(Closed) Violation 368/8017-02:
Failure to properly conduct containment purge operation.
The licensee has taken appropriate corrective action for this item, including counseling of involved individuals, training of other staff members and revision of Procedure 2104.33 to better control the operation and include specific caution statements.
l (Closed) Violation 368/8021-07:
Degraded operability of High Pres:,ure Safety Injection Pump.
i The licensee's corrective action for this item has been satisfac-l torily completed.
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Severity Level IV Violation 368/8103-02:
Failure to provide an adequate Health Physics escort.
The NRC inspector has reviewed the licensee's corrective actions for this item and has found them to be adequate.
(Closed) Violation 368/8103-03:
Missing Pipe Support The licensee's corrective action for this item has been satisfac-torily complete '
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(Closed) Violation 368/8107-03:
Failure to perform monthly channel check as required on ACS-8002, Triaxial Time-History Accelerograph.
The instrument has been added to the monthly channel check per-formed under Procedure 1304.68.
(Closed) Violation 313/8108-02:
High radiation area not properly posted.
The licensee has satisfactorily completed the required corrective action for this item.
4.
Maintenance (Refueling) (Unit 2)
The NRC inspector reviewed several major maintenance activities performed during the current refueling outage to ascertain whether they were conducted by qualified personnel in accordance with approved procedures.
The activities selected for review were, (1) Reconstitution of Fuel Bundles, Fork Plan 2409.51,(2) Replacement of Shutdown Cooling Heat Exchanger Tube Bundle, OCP-80-2199, Job Order 2825, and (3) Installation of Redundant Main Feed-water Block Valves, DCR 2-84, Job Order 8105.
The NRC inspector's review included the following items:
Administrative controls over system removal from and
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return to service Inspection Hold Points
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Provisions for Post-Maintance Testing
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Ignition Source Controls
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Fire Watch Requirements
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Material Certifications
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Satisfaction of Technical Specifications
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Personnel Qualifications
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The NRC inspector also witnessed portions of the three activities listed
above.
No violations or deviations were identified.
5.
Monthly Maintenance Observation (Unit 1)
Station maintenance activities of safety-related systems and components listed below were observed / reviewed to ascertain that they were conducted
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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 (LCO) 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:
Calibration of RE-1237, Failed Fuel Monitor
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Repair of starter for the electric motor driven fire pump
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Repair of the protective relay circuit for Unit 1 Train 'B'
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Diesel Generator (Job Order: 13098).
Following completion of maintenance on the fire pump, the inspector verified that this system has been returned to service properly.
No violations or deviations were identified.
6.
Operational Safety Verification (Unit 1)
The NRC 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 excessive 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 physical 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 lead hydrogen purge, standby hydrogen purge, and trains 'A'
and 'B' High Pressure Injection systems to
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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.
No violations or deviations were identified.
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7.
Monthly Surveillance Observation (Unit 1)
The NRC inspector observed the Technical Specification required surveillance testing on the Lead Hydrogen Purge System (1104.33, Supplement 1) and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for oper-ation 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 individ-ual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
The inspectors also witnessed portions of the following test activities:
Reactor Building Cooling Units Flow Test (1104.33, Supplement VII), Test #2 Diesel Generator (1104.36, Supplement I), Penetration Room Ventilation System Test (2104.43, Supplement II), and 'C' High Pressure Injection Pump (P-36C) Monthly Test (1104.02, Supplement III).
No vic!ations or deviations were identified.
8.
Inspection During Long-Term Shutdown (Unit 2)
The NRC inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during this inspection period.
The inspector verified surveillance tests required during the shutdown were accomplished, reviewed tagout records, and verified applica-bility of containment integrity.
Tours of accessible areas, including exterior areas were made to make independent assessments of equipment conditions, plant conditions, radiological controls, safety, and adher-ence to regulatory requirements and to verify that maintenance requests had been initiated for equipment in need of maintenance.
The inspector observed plant housekeeping / cleanliness conditions, including potential fire hazards, and verified implementation of radiation protection controls.
The inspector, by observation and direct interview, verified that the physical security plan was being implemented in accordance with the station security plan.
The inspector reviewed the licensee's jumper / bypass controls to verify there were no conflicts with Technical Specifications and verified the implementation of radioactive waste system controls.
The inspector witnessed portions of the radioactive waste systems controls associated
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with radwaste shipments and barreling, including the surveying, loading and shipping of nine crates of trash included in shipment number RSR 56-81.
The inspector made independent radiation measurements on five of tile crates and on the tractor / trailer.
No violations or deviations were identified.
9.
Review of Plant Operations (Units 1 and 2)
A.
Procurement and Storage The NRC inspector ascertained that selected aspects of the licensee's procurement and storage operations are being accomplished in accor-dance with regulatory requirements.
Included in the review was an inspection of the licensee's storage areas in order to verify that:
non-conforming items are segregated and tagged accordingly
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preventive maintenance on stored items is performed as appropriate.
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housekeeping and environmental requirements in storeroom areas
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are being met.
In addition, the NRC inspector reviewed the procurement records of the following safety-related items to verify traceability:
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4" X 6" 430 psig Lonergan Relief Valves (Model No. DB-32P/SP/54)
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Purchase Order:
6600-M-2235A-AC
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6" Schedule 120 pipe, Class I (ASME B&PV Code,Section III)
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Purchase Order:
6600-F-34844Q
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Included in the review was confirmation that the records contained:
Letters of Certification
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Statements of Conformance
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Test Reports
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Radiograph packets
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Certificates of Compliance
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Certificates of Acceptance for Welds l
No violations or deviations were identified.
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B.
Training During the course of discussions with licensee personnel, the NRC inspector noted that radiation protection training is only provided to those persons who are considered radiation workers and who receive
" permanent" personal dosimeters.
Other categories of personnel (e.g.,
visitors, transient workers) who need to enter restricted areas on a one-time or one-day basis are generally issued " temporary" personal dosimeters and receive no radiation protection training, although such
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individuals are required to be escorted at all times by a qualified radiation worker when in restricted areas.
However, Regulatory Guide 8.27, issued March, 1981, now requires that all persons who enter a licensee's restricted areas must receive a certain minimum amount of radiation protection training.
The licensee, therefore, is urged to modify the existing radiation protection program to comply with Regulatory Guide 8.27, and in particular, to commence providing radia-tion of protection training at the earliest possible date for all categories of persons who enter restricted areas.
This item will remain open pending confirmation of the licensee's implementation of Regula-tory Guide 8.27 (313/8117-02); 368/8115-02).
No violations or deviations were identified.
C.
Environmental Protection The NRC inspector checked two of the licensee's seven environmental monitoring stations and verified that the air pumps were operating and that the 'odine fi7ters were properly installed.
The NRC inspector also observed the gathering of vegetation samples at two local dairies and confirmed through discussions with the dairy operators that milk l
and vegetation samples have been taken in an adequate manner and at the frequency require.d by Unit 1 Environmental Technical Specification i
4.2.11.
The NRC inspector reviewed the latest Annual Environmental Operating Report submitted by the licensee in conformance with Unit 2 Environ-
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mental Technical Specification 5.6.1 and discussed its contents with
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various memoers of the licensee's Environmental Monitoring organization.
The NRC inspector noted that a milk producing cow was on a farm located about 1.5 miles from the ANO plant boundary.
The licensee
conducted surveys in March 1980 and again in September 1980 in
I accordance with Environmental Technical Specification 4.2.10 and identified this cow as producing milk for human consumption.
Since
the cow was kept at a location less than three miles from the plant,
Environmental Technical Specification 4.2.10 required that this
cow's milk be sampled every two weeks.
However, the licensee had
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not sampled this cow's milk during 1980 because the owner of the cow had reported that the cow was no longer producing milk.
The NRC inspector discussed with licensee representatives the need
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to document the explanation for such apparent discrepancies in the data published in their Annual Environmental Operating Report submitted to the Commission.
Additionally, the NRC inspector noted that in May, 1980, milk samples could no ionger be obtained from one of the milk sample locations (Harm's Dairy), but that the compensatory step, required by Environ-mental Technical Specification 4.2.10, of obtaining monthly pasturage samples at the location was not fully implemented.
The licensee instead had continued to obtain the quarterly pasturage samples required by Environmental Technical Specification 4.2.11 at that location.
This item will remain open until the licensee replaces the milk sampling location with another or increases the pasturage sampling frequency to monthly (313/8117-03; 368/8115-03).
The NRC inspector further noted that during 1980 vegetation samples were not collected and analyzed in accordance with Environmental Technical Specification 4.2.11, which states, in part:
"... Food crops and pasturage in the vicinity of the plant also shall be collected as available at harvest time."
Contrary to the above, only pasturage samples were collected during 1980.
This constitutes an apparent violation (313/8117-01; 368/8115-01).
D.
Review and Audits The NRC inspector attended a Plant Safety Committee (PSC) meeting on May 12, 1981.
The inspector verified that the PSC meeting membership met the quorum requirements of Technical Specification 6.5.1.5 and that the meeting agenda covered the PSC responsible areas defined by Tech-
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nical Specification 6.5.1.6.
Through a review of previous PSC meeting minutes and discussions with PSC members, the inspector determined that the licensee has an effective system of following up on PSC identified items and that the licensee's responses are timely.
The NRC inspector witnessed portions of a Safety Review Committee management audit conducted May 19-20, 1981.
The audit covered the management controls of the Engineering and Technical Support Depart-ment and represents the second such management audit conducted by the SRC of Arkansas Nuclear One (ANO) activities.
It is the intention of the licensee to conduct management audits of all functional areas of ANO so that the entire ANO organization is audited at least once a year.
It should be noted that these management audits are distinct from and in addition to the required audits of Technical Specification 6.5.2.1.
No violations or deviations were identified.
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10.
Surveillance (Refueling) (Unit 2)
During the current refueling outage, the licensee conducted preventive maintenance inspections on the emergency diesel generators.
This inspec-tion for the "A" diesel generator was performed under Job Ordcr 11206 and Maintenance Procedure 2304.57.
The NRC inspector reviewed this job order and procedure and observed a portion of the work.
Items checked by the NRC inspector included the following:
Properly approved procedure in use
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Ccap;etion of prerequisites
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Calibration of test equipment
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Proper recording of data
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Use of qt>.lified maintenance personnel
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Use of quality control hold points
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Ne violations or deviations were identified.
11.
Venting and Purging Containments During Operation The inspectors determined that the licensee has not purged and/or vented either Unit 1 (ANO-1) or Unit 2 (ANO-2) containment building during reactor operation since the licensee received an NRC letter dated November 29, 1978, that identified generic concerns related to purging and venting of contain-ment buildings.
On May 15, 1981, the Commission issued Amendment No. 55 to Facility Operating License No. DPR-51 for ANO-1.
This Amendment modifies the AN0-1 Technical Specifications to require ANO-1 purge talves to be closed whenever the reactor coolant system temperature is equal to or greater g
than 200 F.
ANO-2 has been operated under Technical Specification 3.6.1.6, which requires that i nc containment purge supply and exhaust valves shall be closed when in Modes 1, 2, 3, and 4.
In addition, Technical Specification 4.6.1.6 requires that the containment purge supply and exhaust isolation valves shall be determined closed at least once per 31 day,
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12.
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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