IR 05000313/1977006
| ML19320A124 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/02/1977 |
| From: | Dickerson M, Madsen G, Spangler R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19320A121 | List: |
| References | |
| 50-313-77-06, 50-313-77-6, NUDOCS 8004140723 | |
| Download: ML19320A124 (5) | |
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O U. S. NUCLEAR REGULATORY COMISSION O
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
l,,j Report No. 50-313/77-06
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Docket No. 50-313 License No. DPR-51 Licensee:
Arkansas Power & Light Company Sixth & Pine Streets Pine Bluff, Arkansas 71601 Facility:Name: Arkansas Nuclear One, Unit 1 Inspection at: Arkansas Nuclear One Site, Rassellville, Arkansas
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Inspection conducted: April 19-22, 1977 Inspectors:
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S 4 /77 M. W. Dickerson, Reactor Inspector
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R. G. Spangler, Reactor Inspector (Intern)
Other Accompanying Personnel:
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5/?/77 C. L. Heck (Engineering Aid)
Approved By:
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G'. L. Madsen, Chief, Reactor Operations and Nuclear Support Branch Inspection Sumary
Inspection on April 19-22,1977 (Report No. 50-313/77-06)
Routine, unannounced inspection of startup testing; isothermal l Areas Inspected,fficient; power coefficient; control rod worth measurement; temperature coe plant operations; review of LER's; review of the annual report; follow up on j
inspec+,or identified and unresolved problems; follow up on items of noncom-i pliance; and tour of plant areas.
The inspection involved 58 inspector-hours on site by two NRC inspectors.
Results:
No items of noncompliance were identified.
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DETAILS
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Persons Contacted
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- J. W. Anderson, Jr., Plant Superintendent
- G. H. Miller, Assistant Plant Superintendent
- B. A. Terwilliger, Supervisor Plant Operations J. Robertson, Assistant Operations Supervisor J. Lowman, Assistant Instrumentation & Control Supervisor
- S. J. McWilliams', Planning & Scheduling Coordinator T. H. Cogburn, Nuclear Engineer G. M. Cupriest, Shift Supervisor B. Garrison, Reactor Operator J. Waxenfelter, Instrument Technician
- L. W. Humphrey, Quality Assurance Engineer
- L. Alexander, Quality Control Engineer D. R. Hamblen, Quality Control Inspector
- Attended Exit Interview 2.
Licensee Action on Previous Inspection Findings (0 pen) Noncompliance (76-15):
Inadequate drawing control.
The ir.spector determined that a revised drawing control procedure is expected to be O
completed and approved for use by May 15, 1977.
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(Closed)Noncompilance(77-05):
Failure to follow hold, caution and QC tagging procedure.
The inspector has reviewed the licensee's corrective action described in their letters dated March 28, 1977 and April 15, 1977 and considers this matter closed.
(Closed) Unresolved Item (76-05):
Failure to provide procedures.
The inspector d?termined that procedures 1101.01, " Plant Limits and Precautions,"
and 1101.02, " Plant Set Points," have been approved for use.
(0 pen) Unresolved Item (76-17): Procedural conflict between Quality Assurance Procedure 1004.01 and Nuclear Services Procedure NSP-5.
The licensee indicated that the procedures are currently under review.
The conflicting requirements between the design control proc.edures are expected to be resolved by May 31, 1977.
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(0 pen) Unresolved Item (77-02): Procedural requirements not clear.
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Maintenance Procedure 1401.08, "CRDM Removal and Installation," has been
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revised and is currently undergoing review.
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3.
Startup Testing Following Refueling
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I The inspector verified that the st?rtup testing related to the refueling M
outage was conducted in accordance with approved procedures and reviewed
- l test data utilized for the detennination of the isothermal temperature coefficient of reactivity, control rod worth measurement and the power coefficient of reactivity.
During c review of the test data, the inspector found errors in the use of " conservative factors" applied in the determination of the isothermal temperature coefficient at hot zero power and mathematical errors in the calculation of the power doeppler coefficient.
However, the errors did not appear to significantly affect the magnitude or the-sign of the coefficients.
These errors were called to the attention of the licensee who indicated that the test data was still under review.
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The inspector will review this data again during a subsequent inspection.
Procedures reviewed were as follows:
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1302.13 Sequence For Physics Testing Following Refueling, Rev. O, T/C #5, 4/8/77 1302.06 Determination of Reactivity Coefficients, Rev. O, 3/29/77 1302.08 Control Rod Reactivity Worth Measurements, Rev.1, T/C#1, 4/2/77 No items of noncompliance or deviations were identified.
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Review of Plant Operations - Startup Following a Refueling Outage The inspector reviewed the' plant startup procedure 1102.02, its attachments, and selected referenced procedures.
These documents indicate that all systems-disturbed during the refueling outage and required for startup (including in particular, the control rod drive and the feedwater systems) were returned to service in accordance with the approved procedures.
Further-i more, the procedures 1102.02, 1102.08 - Approach to Criticality, and 1103.15 - Reactivity Balance Calculations indicate that shutdown margin or criticality conditions stated in the licensee's Technical Specifications were met,' and that the selected rod configurations for the estimated critical position (ECP) was within the Technical Specifications and was
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attained at startup.
The inspector reviewed the following test procedures to verify that surveillance tests required by the Technical Specifications were performed during the refueling outage:
1304.52 ESAS Analog #1 Calibration 1304.08 Integrated ES Systems Test
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1105.01 Nuclear Instrumentation and Reactor Protection System Operating Procedure
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r1 No items of noncompliance or deviations were identified.
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5.
Review of Annual Report The inspector reviewed the Annual Operating Report for 1976 in conjunction with selected facility records to verify that the information required to be reported by Technical Specifications had been submitted and that the report accurately reflects information documented in facility records.
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There were several minor discrepancies that were discussed with the
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licensee as well as a statement contained in the report that "all loose parts were located, removed and the remainder of the holder tubes were removed from the internals." The latter statement is inaccurate since
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pieces of the specimen holder tubes were also removed during the recent refueling outage.
A representative of the licensee indicated that this
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discrepancy, as well as minor changes to the report, were being made and j
will be submitted to the NRC in about two weeks.
No items of noncompliance or deviations were identified.
6.
Review of Licensee Event Reports l
The inspector conducted a follow up review for several licensee event reports which had been previously reviewed during an in-office review.
i It was determined from the reviews that:
(1) reporting requirements had i
been met; (2) proper licensee reviews had been conducted; and (3) proper corrective action had been taken.
Follow up reviews of the following LER's were made:
76-29 Leak in Primary Makeup Pump P36C Suction Line 77-1 Frozen Sensing Lines to SLBIC System
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77-3 Bearing Failures of Steam Driven Emergency Feedwater Pump P-7A 77-6 Failure of the high Pressure Injection Flow Transmitters on Loop "A" and Loop "B" Transmitters Out of Manufacturers Tolerance 77-7 Damage to Fuel Pin.; in New Fuel Assembly i
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LER's which were reviewed in the office prior to the inspection were:
76-31 Failure to Comply with Surveillance Test Schedule
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l 76-32 Inoperable Valve in Reactor Building Chilled Water System 76-33 Diesel Generator #1 Inoperable
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76-34 Water Leakage from Valve SF 10 in Spent Fuel Cooling System 77-2 Leat at Weld in Resin Transfer Line for Spent-Fuel Demineralizer 77-4 Control Room Emergency Ventilation Unit Taken Out of Service
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77-5 Pinhole Leak on the Pipe for Flange Weld bewteen Valve.RBV-778 and "B" SCP Seal 77-8 R. B. Chilled Water System Isolation Valve (CV-6202) Found to be Inoperative No items of noncompliance or deviation were identified.
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7.
Plant Tour O
The inspector toured various areas of the plant and observed operations activities.
During the tour the inspector expressed concern regarding
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the observed settings on pipe spring hangers relative to the indicated settings. A representative of the licensee indicated that during the concluded refueling. shutdown hanger information had been gathered to provide input to a hanger inspection procedure which is to be developed.
Responsibility for the development of this procedure will be assigned in May 1977.
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i No items of noncompliance or deviations were identified.
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Exit Interview At the conclusion of the inspection on April 22, 1977, the inspectors met with representatives of the licensee (as noted in paragraph 1).
The inspector summarized the scope and findings of the inspection.
The licensee representative acknowledged that changes to the Annual Report were in preparation (paragraph 5) and that assignment of responsibility May 1977 (pment of a hanger inspection procedure would be assigned du for develo paragraph 7).
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