IR 05000313/1981001
| ML19350B885 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/29/1981 |
| From: | Callan L, Hunnicutt D, Johnson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19350B884 | List: |
| References | |
| 50-313-81-01, 50-313-81-1, 50-368-81-01, 50-368-81-1, IEB-79-05C, IEB-79-5C, NUDOCS 8103231026 | |
| Download: ML19350B885 (9) | |
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m U. S. NUCLEAR REGULATORY COMMISSION U
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Docket Nos. 50-313/81-01 License No. OPR-51 50-368/81-01 NOF-6 Licensee:
Arkansas Power and Light Company
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P. O. Box 551 Little Rock, Arkansas 72203 Facility Name:
Arkansas Nuclear One (ANO), Units 1 and 2 Inspection at:
ANO Site, Russellville, Arkansas Inspection Conducted:
December 22, 1980 - January 21, 1981 Inspectors:)
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/ v W. D. Johnson, Senior Resident Inspector
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L. J. Callan, Resident Inspector
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Approved:
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D. M. Hunnicutt, Chief
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Reactor Projects Section No. 2 Inspection Summary Inspection conducted during ceriod of December 22, 1980 - January 21, 1980 (Recort No. 50-313/81-01)
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Routine, announced inspection including Surveillance l
Observation, Maintenance, Operational Safety Verification, Preparation for l
Refueling, Followup on Previously Identified Items, Followup on IE Bulletin 79-05C, and Followup on Three Mile Island Action Plan Requirements.
The inspection involved 45 inspector hours on site by two NRC inspectors.
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Results:
Within the seven areas inspected, no violations or deviations were identified.
Inspection conducted during period of December 22, 1980 - January 21, 1981 (Report No. 50-368/81-01)
Areas Inspected:
Routine, announced inspection including Operational Safety Verification, Surveillance Observation, Maintenance, Follow-Up on Licensee Event Reports, Followup on Previously Identified Items, and Followup on Three Mile Island Action Plan Requirements.
The inspection involved 30 inspector hours on site by two NRC inspectors.
Results:
Within the six areat inspected, no violations or deviations were identified.
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DETAILS SECTION
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1.
Persons Contacted J. P. O'Hanlon, ANO Ceneral Manager G. H. Miller, Engineering & Technical Support Manager 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 C. Shively, Plant Pesformance Supervisor D. Glenn, Health Physics Supervisor D. Gregory, Electrical Maintenance Supervisor A. M. Armstrong, Mechanical Maintenance Supervisor R. Tucker, Electrical Maintenance Superintendent J. Ray, Quality Control Engineer P. Rogers, Nuclear Support Supervisor A. Cox, Nuclear Engineer D. Lomax, Nuclear Engineer R. Turner, Electrical Engineering Supervisor M. Stroud, Electrical Engineer J. Vandergrift, Training / Counselling Supervisor J. Simmons, Training Coordinator J. Constantin, Training Coordinator T. Green, Training Coordinator The inspectors also contacted other plant personnel, including operators, technicians and administrative personnel.
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2.
Followuo on Previously Identified Items (Units 1 & 2)
(Closed) Unresolved. Items 313/7916-11; 368/7914-10:
Quality Control Review of Completed Job Orders.
The licensee has issued and implemented procedure 1000.24, " Control of Maintenance." This procedure requires that completed job orders and associated records be forwarded to Quality Control for review.
The implementation of this procedural requirement was reviewed by the inspector with the ANO Quality Control Enginee.
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(Closed) Unresolved Item 313/7923-01; 368/7922-01: Quality Control Inspec-tion Points.
The licensee has issued and implemented procedure 1004.01," Quality Control Program Implementation." This procedure requ'res that the Quality Control Engineer review procedures, job orders and design changes and verify establishment of any necessary Quality Control hold points or notification points.
Some hold points have been inserted during the procedure review process, but most hold points are being inserted during the QC review of job orders.
- 1osed) Deficiency 313/8005-32:
Unreviewed Safety Question Evaluatiori.
The inspector has reviewed the licensee's corrective action on this item, including the safety evaluations for Design Change Packages 633 and 660.
Licensee procedures now require unreviewed safety question evaluations for all design changes.
3.
Licensee Event Reoorts Followuo (Unit 2)
Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with technical specifi-cations.
80-09 80-52 80-71 80-21 80-53 80-73 80-24 80-55 80-74 80-31 80-56 80-75 80-35 80-58 80-76 80-37 80-59 80-77 80-38 80-61 80-78 80-43 80-62 80-80 80-44 80-63 80-81 80-47 80-65 80-84 80-51 80-68 80-85 No violaticns or deviations were identified.
4.
Followuo on IE Bulletin 79-05C (Unit 1)
The licensee has revised ANO-1 Emergency Procedure 1202.32, " Loss of Decay Heat Removal System." Revision 3 to this procedure addresses use of the diverse core cooling methods suggested by the Babcock & Wilcox guidelines (EOS 69-1106921-00).
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This Bulletin remains open pending comoletion of the remaining items addressed in Inspection Report 80-15.
These items involve procedurally addressing the B&W guidelines for recommended actions starting from severely degraded core cooling condition; and submittal of a design to assure automatic tripping of the Reactor Coolant Pumps.
5.
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
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i fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of main-tenance.
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 Unit 1 'A'
and 'B' Diesel Generators, and Unit 2125 VDC Distribution system to verify operability.
The inspector also witnessed portions of the radioactive waste system controls associated with radwaste shipments and barreling.
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These reviews and observations were conducted to veriff that facility i
operations were in conformance with the requirements established under technical specifications, 10 CFR, and administrative procedures.
No violations or deviations were identified.
6.
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
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codes or standards and in conformance with technical specifications.
The following items were considered during this review:
the limiting conditions for operation were met wnile components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were intr.cted as applicable; functional testing and/or calibrations were
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performed prior'to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified perso1nel; parts and materials used were properly certified;
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radiological controls were implemented; and, fire prevention controls were implementea.
Work requests were revicwed 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:
Job Order 3561, Preventive Maintenance on Terry Turbine (P7A)
Procedure 1405.02, Preventive Maintenance on Unit ' 'B' Diesel Generator Procedure 1405.01, Supplement III, Test Discharge of Unit 1 Station Battery No. 2.
Job Orders 8713 (Unit 1) and 7602 (Unit 2), Preventive Maintenance On Safety-Related, Non "Q", Service Water Instrumentation Following completion of maintenance on the Unit 1 Station Battery (Procedure 1405.01), and the Unit 1 No. 1 Diesel Generator, the inspector verified that these systems had been returned to service properly.
No vio tions or deviations were identified.
7.
Monthly Surveillance Observation (Units 1 and 2)
The inspector observed the technical specification required strve;11ance testing on the Unit 1 Reactor Internals Vent Valves (1304.093', and verified that testing was performed in accordance with adequate procedures, that limiting conditions for operation were met, that removal and restora-
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l tion of the affected components were accomplished, that test results conformed with technical specifications and procedure requirements and wcre 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.
l The inspector also witnessed portions of the following test activities:
Procedure 2104.03, 5t pplement 1, Monthly Surveillance of the Unit 2 "A"
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Boric Acid Makeup Pump (2P39A)
Procedure 2102.01, Attachmment B, Unit 2 Containment Integrity Checklist
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l While observing the monthly surveillance on the Unit 2 'A' Soric Acid
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Makeuo Pump, 2P39A, the inspector noted that the pump and its associated val' c3 and gages were encrusted with boric acid crystals.
As a result, the operator had to first scrape the boric acid crystals from the pump l
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components prior to starting the pump surveillance run.
This accumula-tion of boric acid crystals appears to be caused by three of the boric acid makeup system's pressure relief valves (2PSV-0466, 2PSV-4923, and 2PSU-4933) leaking through and dripping onto the boric acid makeup pumos below.
The i..5pector is concerned that this encrusting of the boric acid makeup pump components (Pump lube oil signt glasses, suction / discharge gages, valves, electrical junction boxes, etc.) prevents tne plant operato -
from adequately perforsing their routine visual checks of the system and has the potential to affect the operability of the boric acid makeup system.
Discussions with licensee representatives indicate that these leaking pressure relief ualves (or whatever else is causing the boric acid accumulation) will bi repaired during the upcoming refueling outage for Unit 2.
This item will remain open pending the inspector's confirma-tion that this proolem has been remedied (368/8101-01).
No violations or deviations were identified.
8.
Precaration for Refueling (Unit 1)
The inspector reviewed procedure 1409.29, Revision 0, " Fuel Sipping With CE Equipment," and procedure 1502.04, Revision 4, " Refueling Shuffle."
Fuel assembly holddown springs will be visually inspected for failure during the performance of procedure 1502.04.
Procecure 1502.04 contains the necessary linits, precautions, and prerequisites for fuel handling.
No violations or deviations were identified.
9.
Followuo on Three Mile Island Action Plan Recuirements (Unit 1 & 2)
The NRC's Office of Nuclear Reactor Regulation issued NUREG-0737 entitled,
" Clarification of THI Action Plan Requirements," to the license? as a letter dated October 31, 1980.
This document incorporates all THI-related items approved for implementation by the NRC as of October 31, 1980, and includes a listing of requirements and implementation schedules.
The inspector 13..,. ewing, on a continuing basis, the licensee's actions in response to the requirements of NUREG-0737.
The inspector's review of certain of the licensee's actions in this regard is summarizec below.
The numbering system and short titles correspond to those used in Enclosure 1 of NUREG-0737.
I.A.1.1 Shift Tecnnical Advisor (STA) Units 1 & 2)
The STA interim staffing requirements was met as reported in Inspection Report 8003.
Tecnnical Specifications relating to the STA cualifications and staffing were proposed by the licensee in a letter dated October 31, 1980.
The present STA's have comoleted their initial training program and the licensee described the long term STA training program in his letter of Decemoer 31, 198.
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I.A.1.2 Shift Suoervisor Resoonsibilities (Units 1 & 2)
Completion of the requirements of this item was reportad in Inspection Report 80-03.
Since that time the licensee has taken further eetion to delegate certain non-safety duties of the Shift Supervisor to Shift Administrative Assistants (SAA's).
Ten SAA's have been hired and have been given indoctrination training.
One SAA has been assigned to each operating shift for each unit.
I.A.1.3 Shift Manning (Units 1 & 2)
The licensee has taken the required steps to limit the working hours of operators as recommended by IE Circular 80-02.
This Circular was closed out in Inspection Report 80-22.
The licensee's letter of October 31, 1980, addressed the AP&L schedule and plans for meeting the increased shift manning requirements.
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I.A.2.1 Immediate Uograding of R0 and SR0 Training and Qualifications (Units 1 & 2)
The licensee has issued procedure 1023.08, " Operations Training Program."
This procedure implements the requirements of this item except for the one requiring three months on-the-job-trcining as an extra person on shift for SR0 applicants.
Following discussions with an AP&L training coordinator, the inspector understands that this procedure will be revised to include this requirement.
Licensee certifications of appli-cants' readiness for licensing examination are Laing signed by the Vice President / Generation and Construction.
The inspector reviewed the implementation of the licensee's operator training and requalification. training in heat transfer, fluid flow, ther:adynamics, and plant transients.
These areas were addressed in the recent license training classes and are planned to be included in the next requalification trainir.s gycle following the refueling outages of early 1981.
Training to mitigate an accident with a degraded core is addressed separately in Item II.B.4.
I.A.2.3 Administration of Training Programs (Units 1 & 2)
The AP&L training coordinators assigned as instructors for license and requalification training hold Senior Reactor Operators (SRO) licenses for the appropriate units.
I.C.1 Short-Term Accident and Procedures Review (Units 1 & 2)
The licensee's small break loss of coolant accident procedures were reviewed in connection with IE Bulletin 79-05C/06C and reported in Inspection Reports 79-21, 79-25, 80-03 and 80-15.
The licensee's approach
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to the requirements concerning inadequate core cooling and other transients and accidents was outlined in-letters to the NRC dated December 19, 1980, and December 31, 1980.
I.C.2 Shift and Relief Turnover Procedures (Units 1 & 2)
I.C.3 Shift Supervisor Resoonsibility (Units 1 & 2)
I.C.4 Control Room Access (Units 1 & 2)
Completion of these items was noted in Inspection Report 8003.
I.C.5 Feedback of Goerating Experience (Units 1 & 2)
The licensee has implemented procedure 1000.29, " Operating Experience Assessment Program" to meet the requirements of this item.
I.C.6 Verify Correct Performance of Goerating Activities (Units 1 & 2)
The licensee has revised and implemented procedures 1000.28, " Jumper and Lifted Lead Control," and 1000.27, " Hold and Caution Card Control," in addressing the requirements of this item.
I.D.1 Control Room Design Reviews (Units 1 & 2)
The licensee's letter of December 19, 1980, to the NRC stated that commitments to meet this requirement will be made after issuance by NRC of the guidance necessary to do the review.
No violations or deviations,ere identified.
This inspection effort will continue in the next inspection period.
10.
Exit Interview (
.The inspectors cet 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 l
inspection.
At these meetings, che inspectors summarized the scope of the inspection and the findings.
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