IR 05000313/1976009
| ML19326B608 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/18/1976 |
| From: | Dickerson M, Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19326B606 | List: |
| References | |
| 50-313-76-09, 50-313-76-9, NUDOCS 8004160387 | |
| Download: ML19326B608 (9) | |
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h U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION IV
IE Inspection Report No. 50-313/76-09 Docket No. 50-313 Licensee:
Arhansas Power & Light Company License No. DPR-51 Sixth and Pine Streets Pine Bluff, Arkansas 71601 Category C
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Facility:
Arkansas Nuclear One, Unit 1 Location:
Russellville, Arkansas Type of Licensee: B&W, PWR, 2568 Mwt Type of Inspection: Routine, Unannounced Da'tes of Inspection: August 10-13, 1976 Datea of Previous Inspection: June 16-18, 1976 Principal Inspector:
u.J. /
h cf[#/76 M. W. Dickerson, Reactor Inspector Date
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Accompanying Inspector: None
Reviewed By:
I T [ocOd/ h k'P/7 6
'G.
L. Madsen, Chief, Reactor Operations and Date Nuclear Support Branch O
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8004160387
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- SUMMARY'OF FINDINGS
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Enforcement' Action A.
' Violation
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None identified during this inspection.
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B.
' Infractions
Technical Specification 3.5.2.5.4 requires that, "Except for physics tests, power shall not be increased above the power level cutoff unless the Xenon reactivity is within 10 percent of the equilibrium value for operation at rated power and asymptotically approaching stability."
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Contrary to the above, the power level cutoff was exceeded i
due to an operator error without proper Xenon reactivity worth.
(DETAILS, paragraph 6)
This item is an infraction.
C.
Deficiencies
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None identified during this' inspection.
II.
Licensee's Action on Previously Identified Enforcement Matters
75-02 IA/3 Failure to Document Temporary Changes
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The corrective action discussed by AP&L in their undated letter to the NRC relative to temporary changes to procedures 1104.04, " Decay
Heat Removal Operating Procedure," and 1104.05, "RB Spray System
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Operation," has been reviewed and there are no additional questions
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at this time. This matter is considered closed.
(DETAILS,
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paragraph 2)
i 75-02 IB/2 Reporting Requirements
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The inspector reviewed the heensee's response in their undated letter to the NRC relative to consideration of a trip from 100% full power on February 22, 1975, as an unusual event, and their subsequent letter to the NRC dated July 25, 1975. As a result of this review i
there are no further questions at this time. This matter is
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considered resolved.
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'75-06'IC'
Reporting' Requirements
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The inspector reviewed the licensee's response relative to reporting
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l of UE 75-2 contained in their letter to the NRC dated July 21, 1975.
(c'ontinued)
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As a result of this review there are no additional questions at this time and this matter is considered resolved.
75-07 IC/2 Training'of' Maintenance' Personnel A training program has been formulated which includes training for maintenance personnel. A schedule in support of the training has also been developed. This matter is considered resolved.
(DETAILS, paragraph 4)
76-07 IB
~ Changes'to Procedures Without' Appropriate Review and Approval The inspector reviewed the licensee's response described in their letter dated July 20, 1976 with respect to changes to procedures 1104.02, " Makeup and Purification S stem," and 1104.06, " Spent f
Fuel Cooling System," which had bec.n changed without review by the Plant Safety' Committee and/or without evidence of approval as required by TS 6.7.
As a result of the review, there are no additional questions at this time and this matter is considered resolved.
(DETAILS, paragraph 2)
III.
Design Changes Not inspected.
IV.
Unusual Occurrences None identified during the inspection.
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V.
Other Significant Findings i
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Current Findings
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1.
Plant Status During the inspection, the plant was in a shutdown status to replace reactor coolant pump seals on RC pumps B, C and D.
Additionally, maintenance was being performed on the control
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rod drive stator for group 2 rod 3, which had failed.
The plant had been down since 9:54 p.m. on August 6, 1976.
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Startup of the facility was anticipated to take palce August 14, 1976.,
2.
' Unresolved Items
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No ne'r unresolved items were noted during this inspection.
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B.
' Status ~of'Previousiv' Unresolved Items
75-2/1' ' Sodium Thiosulphate' Tank' Dilution The system is being modified to,accomodate a separate J
recirculation pump for each tank (sodium thiosulphate and rodium hydroxide tanks) so that dilution will not occur.
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Installation of the pumps are in progress and is expected
to be completed about January 1977. This matter is considered closed.
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'75-2/2'
control' Room' Fire' System A report of the failure of the halon fire system to maintain the required concentration for the specified ten minute period in.the testing of the control room was sent to NEL-PIA by
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AP&L letter NDC-4481, dated June 9, 1976. This matter will remain open pending an NEL-PIA reply.
~75-2/3'
Retention'of' System' Procedure' Checklists
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A review of procedure 1102.02, Rev. 5, dated August 3, 1976,
" Plant Startup," and procedure 1005.09, Rev. O, dated May 31, i
1975, " Plant Records Management," established that-neither g
procedure specifically require,s the retention of electrical or mechanical alignment checklists. This matter is considered j
resolved.
t 75-2/4 Changes ~in ES Breaker'A11gnment Checklist The additional components noted on the ES breaker alignment checklist as reported in inspgetion report 75-02 have been incorporated in checklist G by revision 2, temporary change 2,
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to procedure 1107.01, "ES Switchgear Alignment," as approved August 13, 1975. This matter is considered closed.
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75-2/5 Reactor Building Cooler Backdraft Darper Backdraft dampers on the reactor building coolers are maintained
' in the open position and Checklist G to procedure 1107.01 has been revised to reflect this condition. Revision 2 to this precedure with temporary change 2 providing for the open damper was approved August 13, 1976. This matter is considered resolved.
(DETAILS, ppragraph 3)
VI.
Management Meeting-A.
' Entrance Meeting l
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A preinspection meeting was held with Messrs. J. W. Anderson and
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G. H. Miller ca August 10, 1976.
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-5-Mr. Anderson was informed that the following items would be
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reviewed during the inspection:
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Organization and Administration 2.
Training 3.
Requalification Training 4.
Licensee Event Reports
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Previous Items of Noncompliance 6.
Previous Unresolved Items i
B.
Management' Interview
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At the conclusion of the inspection o'n August 13, 1976, an
exit meeting was held with representatives of the ANO-1 plant
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staff. The following individuals were present:
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J. W. Anderson, Jr., Plant Superintendent r
G. H. Miller,~ Assistant Plant Supervisor L. W. Humphrey, Quality Assurance Engineer l
L. Alexander, Quality Control Engineer
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The inspector discussed the following items:
1.
The noncompliance as a result of the power increase in violation of TS 3.5.2.5.4.
(DETAILS, paragraph 6)
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The resolution of previous items of noncompliance.
(Section II of the Summary of Findings)
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The status of previously identified unresolved items.
(Section V R of the Su1mtsry of Findingc)
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DETAILS
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P,ersons ' Contacted
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The following individuals, in addition to those listed under the
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Nhnagement Interview section of this report, were contacted during the inspection:
Arkansas ' Power & Light ' Company (AP&L)
J. Robertson, Assistant Operations Supervisor H. L. Grubbs, Shift Supervisor, Operations B. T. Moon, Shift Supervisor, Operations D. C. Trimble, Training Coordinator T. L. Green, Assistant Training Coordinator
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R. G. Carroll, Health Physics Supervisor 2.
Previously Identified' Enforcement Matters
i 75-02'IA/3 Failure to Document' Temporary Changes j
The inspector reviewed the corrective action described in the AP&L undated letter to the NRC relative to temporary changes to procedures
1104.04, " Decay Heat Removal Operating Procedure," and 1104.05, "RB Spray System Operation."
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The review established that revision 4 and temporary change 2 to 1104.04, including supplement 1, had been approved June 10, 1975.
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Additionally, revision 3 and temporary change 2 to 1104.04, including supplement 3 had been approved June 10, 1975. Each of the approved procedures now contain those temocrary changes which previously had not been properly approved. This matter is considered resolved.
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76-07 IS Changes to Procedures Without Appropriate Review and l
Approval The inspector reviewed the licensee's response described in their letter dated July 20, 1976 to NRC relative to changes to procedures l
without the appropriate review by the Plant Safety Committee and/or proper approval as required by TS 6.7.
The review established that changes to procedures 1104.02, " Makeup and Purification System," and 1104.06, " Spent Fuel Cooling System," had been made, reviewed, and were properly. approved. The changes were contained in revision 4, temporary change 1. to 1104.02 and in revision 4, temporary change 2
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to 1104.06. The approval dates were July 20, 1976 and July 16, 1976, respectively. This matter is considered resolved.
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3.
Reactor Building' Cooler'Backdraft'Damners~(75-2/5)
The inspector reviewed records relative to the maintenance of the RB cooler backdraft dampers in the open position rather than closed as originally specified by checklist G to procedure 1107.01, "ES Switchgear Alignment," as noted during the referenced inspection.
The review established that revision 2, with temporary change 2 to
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this procedure approved August 13, 1976, now reflects that the dampe s are to be maintained in the open position. Additionally, AP&L j
letter to Bechtel, dated September 8, 1975, "ANO-1 Containment Cooler Backdraft Dampers," evaluates this condition and concludes, "Even under the worst condition with'the backdraft dampers and bypass dampara of two idle units open, the two units can be expected to maintain the required temperature during the DBA."
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As a result of the above review by the staff of ANO-1 and the approved procedure, dated August 13, 1976, this matter is considered resolved.
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Training'and Resualification fraining
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The training and requalificatien training program for ANO-1 is contained in the memorandum JWA-1554, dated September 23, 1975,
" Arkansas Nuclear One Training Plan," and in the Special Order OPS-2, l
dated June 23, 1975, " Implementation of Standardized Hot. License
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T Training Program." The plan contains the formal training and
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retraining required for new employees, temporary employees, non-licensed personnel, licensed person.sel, technicians, and craft Personnel.
Included is training relative to administrative controls, radiological health and safety, industrial safety, controlled access, security procedures, emergency plans, an initial QA indoctrination and QA retraining. For technicians and craft personnel the plan also includes on-the-job training and formal technical train-ing.
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Responsibility for the training program is assigned to the Training
Coordinator. His responsibilities are described in a position description and in the FSAR Section 12.1.3.F and were reviewed by the inspector. The Training Coordinator is assisted in his duties by an Assistant Training Coordinator.
A review of the schedule for requalification training established that it is composed of tsn lecture groups to be covered on a yearly basis.
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The ten lecture groups include a total of 34 separate lectures. Each-l group-lecture is given once per week for five weeks and provides for attendance by each of the rotating shifts. Documentation of attendance at these lectures is provided by completion of an attendance report TF-07.
Training; aids utilized are drawings, procedures and a variety of projection media.
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Records were reviewed for two new employees, two temporary employees and two existing employees including inexperienced craftsmen,
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technicians, and the training required for operator requalification.
The records reviewed were considered. satisfactory and containad l
records relative to reactor control manipulation, reviews of
changes in facility design, procedures, the facility license, reviews of abnormal and emergency procedures, and other records required by the approved requalification program.
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5.
organization'and' Administration
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The inspector reviewed proceduress shift schedules, time attendance sheets, committee meeting minutes, the FSAR, Technical Specification and conducted a discussion with representatives of the licensee to verify that a.
The licensee's on-site organizational structure is as described in the facility Technical Specification and application.
b.
Personnel qualification levels are in conformance with
applicable codes or standards as described in the Technical Specifications.
c.
Authorities and responsibilities are in conformance with the
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Technical Specifications and applicable standards,
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d.
Minimum shif t crew composition and licensed personnel riquire-ments were in conformance with the Technical Specifications.
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The Safety Review Committee and the Plant Safety Committee membership and qualifications,are as described in the Technical Specificacions.
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No discrepancies were found.
6.
Review of Licensee Event Reports The, inspector reviewed plant records related to the following licensee
event reports and verified that: the details were clearly reported to j
NkC and facility management; the corrective action described had been initiated to prevent recurrence; that they were evaluated as required
by the Technical Specifications; and, that safety limits, limiting
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not exceeded.
76/07 Control Room Ventilation System Isolation Damper Closure Time
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'J 76/08 Failure of DG #1 to start on simulated ES actuation 76/10 Leak in socket weld, decay heac flow element instrument tap 76/12 Socket veld leak in Primary Makeup Pump P36C suction relief line 76/13-Leak in emergency feedwater line to "A" steam generator
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76/17 Exceeding power level cutoff (82.5%) without proper xenon reactivity conditions per Technical Specification 3.5.2.5.4.
Witti respect to 76/17, the licensee was informed that this was considered an infraction and would be identified in this report as a nonconformance. However, no response would be required since the event had been reported in a timely manner and that the required corrective accion, as described in Reportable Occurrence Report 76/17 dated July 26, 1976, had been completed.
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