IR 05000313/1977001
| ML19319E496 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/25/1977 |
| From: | Hermann R, Madsen G, Rosenburg A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19319E493 | List: |
| References | |
| 50-313-77-01, 50-313-77-1, NUDOCS 8004110649 | |
| Download: ML19319E496 (9) | |
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J U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-313/77-01 Docket No. 50-313 Licensee:
Arkansas Power and Light Company License No. DPR-51 Sixth and Pine Streets Pine Bluff, Arkansas 71601 Category C Facility:
Arkansas Nuclear One, Unit 1 Location:
Russellville, Arkansas Type of Licensee: B&W, PWR, 2568 Mwt
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Type of Inspection: Routine, Announced Dates of Inspection: January 4-7 and 17-19, 1977 Dates of Previous Inspection: December 6, 1976
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/~2 I" 77 Principal Inspector:
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A. B. Rosenberg, Reactor Inspector Date
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Accompanying Inspector:
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/ - A f-7'7 R. A. Hermann, Reactor Inspection (Details II) Date Reviewed By:
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'G. L. Madsen, Chief, Reactor Operations Date and Nuclear Support Branch (
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-2-V SUMMARY OF FINDINGS I.
Enforcement Action N ne o
II.
Ilcansee's Action on Previously Identified Enforcement Mhtters
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Not inspected.
III. Design Changes i
Not inspected.
IV.
Unusual Occurrences None V.
Other Significant Findings A.
Current Findings l.
Deviations (
None 2.
Unresolved Items a.
7701-1 Procedure Control--Local Leak Rate Testing The procedure used for the last set of local leak rate tests was not in conformance with 10 CFR 50, Appendix J.
The licensee is revising the effected procedure.
(DETAILS I, paragraph 3)
b.
7701-2 Review and Approval of 10 year In-service
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Inspection Program, Revision of Operating Procedure, and Preparation of QA Surveillance Checklist The following activities for the forthcoming in-service inspection have not been completed by the licensee:
(1) Review and approval of the 10 year ISI program by the licensee (2) Revision of Operating Procedure 1304.58
/'~'N (3). Preparation of a QA Audit Checklist i
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The licensee's Plant Superintendent and QA Engineer stated the above stated activities would be completed
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priot to the inception of the ISI.
(DETAILS II, paragraph 3)
B.
Status of Previously Reported Items Not inspected.
VI.
Management Interview A.
Entrance Interview An entrance interview was held on January 4, 1977 with J. W. Anderson and L. Alexander. A second entrance interview l
was held with L. Humphrey, January 17, 1977, on Mr. R. A.
Hermann's return. The inspectors outlined the scope of the inspection which included the following items:
1.
Review of local leak rate procedures and documentation.
2.
Review of the in-service inspection program tor the upcoming refueling outage, and 3.
Inspect new spent fuel racks.
B.
Exit Interview An exit interview was held on January 7, 1977 at the site.
The following licensee personnel were in attendance:
J. W. Anderson, Plant Superintendent L. W. Humphrey, Quality Assurance Engineer
L. Alexander, Quality Control Engineer On January 19, 1977 a second exit interview was held by Mr. R. A. Hermann. The following licensee personnel were in attendance:
L. Humphrey, Quality Assurance Engineer The following items were discussed by the inspectors:
1.
The unresolved item concerning local leak rate procedures and conformance to 10 CFR 50, Appendix J.
The licensee is revising the procedure concerned.
(DETAILS I, paragraph 3)
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In-service Inspection (ISI) Program a.
The unresolved item concerning the review and approval of the ISI program by the licensee. The licensee indicated the program would be reviewed and approved prior to starting the inspection.
(DETAILS II,
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paragraph 3)
b.
The inspection of the new spent fuel racks and their installation.
(DETAILS II, paragraph 4)
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50-313/77-01 DETAILS I Principal Inspector:
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A. B. Rosenberg, Reactor Inspector Engineering Support Section Reviewed By:
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R. E. Hall, Chief, Engineering Support Section 1.
Persons Contacted i
a.
Arkansas Power and Light (AP&L)
J. W. Anderson, Plant Superintendent R. T. Elder, Assistant Instrument & Control Supervisor L. Alexander, QC Engineer D. R. Hamblen, QC Inspector S. S. Strausner, QC Inspector
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2.
The scope of this inspection included review of local leak rate procedures and records of local leak rate tests performed since O
initial fuel loading.
3.
Local Leak Rate Test Procedura - OP-1304.23 The local leak rate test procedure OP-1304.23, Rev. I with Temporary Changes Nos. 1, 2 and 3, was reviewed for conformance to Appendix J to 10 CFR 50 and the station Technical Specifications (TS), Section 4.4.1.
The inspector discussed concerns with OP-1304.23 with the licensee's. representative regarding normal closure of isolation valves and venting on the low pressure side of valves to prevent artificial leakage barriers. The inspector was informed by the licensee representative that procedure OP-1304.23 was in the process of being revised and that several items of concern had already been included in the draft revision.
This item will remain unresolved pending review of the completed and approved procedure reviston for conformance to Appendix J to 10 CFR 50.
4.
Local Leak Rate Test Records
Five penetrations were selected, from procedure OP-1304.23, for documentation review of type "C" tests.
Penetration Nos. 11 Rad Waste (q'j 38 Domestic Water 42 Heating
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54 Intermediate Cooling
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55 Service Water I-l
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v Documentation for penetrations numbered 11, 42 and 54 were found to be in accordance with procedure OP-1304.23. However, although the system diagram on the test documents identified the valves involved, the specification of which were open or closed was not included.
Documentation ~for penetrations numbered 38 and 55 were not included in the data package for the type "C" tests.
The inspector was informed that tests of these systems were covered during type
"A" tests.
No discrepancies were noted during this portion of the inspection.
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50-313/77-01 DETAILS II Accompanying Inspector:
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vN w-R. A. Hermann, Reactor Inspector Engineering Support Section
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!r Reviewed By:
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b Ac R. E. Hall, g af, Engin ering Support Section 1.
Persons Contacted Arkansas Power and Light Company (AP&L)
C. Shively, Performance Engineer L. Alexander, QC Engineer L. Humphrey, QA Engineer C. Bean, QA Inspector J. Anderson, Plant Superintendent A. Huebner, QA Engineer 2.
Scope of Inspection The scope of this inspection included: review of the program for i
the in-service inspection scheduled for the upcoming refueling
outage and inspection of the new spent fuel racks and the welding
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associated with their installation.
3.
In-service Inspection - Review of Program The in-service inspection program to be conducted during the forthcoming refueling outage will be composed of four major documents: OP-1304.58,
"In-Service Inspection"; a Quality Surveillance Checklist for the activity; the Babcock & Wilcox In-Service Inspection Manual for ANO-1, Unit 1; and B&W Construction Company Quality Assurance Manual for In-Service Inspection. Arkansas Power and Light Technical Specification, paragraph 4.2.2, commits to the performance of in-service inspection Per the requirements of the ASME B&PV Code,Section II,1971 edition, including all addenda through Winter 1971. The AP&L Operational QA Program for ANO-1, Unit 1, was submitted to the NRC as AP&L Top 1CEl Report APL-TOP-1A and approved for use November 19, 1976. QA program requirements for control of lu-service inspection are established in the AP&L Operational QA Progtam and are implemented through station Quality Control and Qelity Assurance Procedures.
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d Procedure OP-1304.58, "In-Service Inspection," was reviewed for conformance with ASME B&PV Code requirements for the~in-service inspection and identified areas of concern were discussed with the Performance Engineer and Quality Control Engineer who have responsibilities for the ISI activities.
The licensee represen-tative stated the procedure would be~ revised and approved prior to ISI. Following approval, the procedure will be inspected.
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The inspector. discussed QA activities with the QA Engineers and was advised that audits would be conducted by the QA Engineer (Audit) and the QA rngineer (Operations) during the ISI activities.
Audits will be conducted per the AP&L established QA Procedures.
Checklists will be prepared prior to audit activities.
The inspector reviewed the Babcock & Wilcox In-Service Inspection Manual fer ANO-1, Unit 1, Rev. 1, controlled copy RC-4, and found the document generally in accordance with ASME B&PV Code require-ments. However, the inspector had difficulty ascertaining the extent of inspection to be performed at a particular refueling during the ten years when a percentage of the exam is specified.
The inspector discussed the matter with the Performance Engineer who stated the issue would be clarified.
Control of B&W ISI activities are to be maintained in accordance with the B&W ISI QA Manual and the referenced administrative procedures.cc.tained in the ISI Inspection-Manual. The inspector found the d&W QA
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program consistent with 10 CFR 50, Appendix B requirements for the activity. During subsequent inspections, the implementation
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of the program for control of ISI activities will be assessed.
Since the entire ISI~ program was not complete at the time of this inspection, the item is considered unresc1ved.
The completed program will be evaluated during subsequent inspections.
4.
Replacement Spent Fuel Racks The inspector reviewed the Middle South Utilities (MSU)/AP&L Quality Assurance Audit (Report #E 76-10 (ANO-1)) dated 12/7/76 -
12/8/76, of Precision Metal Fabrication (PHT), the fabricators of
,l the spent fuel racks. The audit identified three findings:
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nonconforming material not controlled according to PMF QA-201;
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material storage not in conformance with PMF QA 317; and ineffective j
material control and QC inspection per PMF Q-305 and 306. The
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inspector reviewed a letter from the QA Manager, MSU, to Exxon which documented MSU audit findings of PMF and stated Exxon concurred with the findings. The letter contained MSU's concerns with implemen-j tation of the PMF QA Program on the AP&L project. MSU acknowledged the corrective steps taken by Exxon to ensure the racks are fabricated in accordance with the Technical Specifications and approved PMT
. program appears satisfactory.
The corrective steps outlined in the
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v letter included, but were not limited to, the assigning of Exxon QC personnel to the PMF shop and the preparation of detailed Exxon QC inspection requirements to be on the AP&L project prior to shipment of the completed racks.
'The inspector entered the spent fuel pool and visually examined the weldments used to fabricate the support beams. The visual examination requirements of Exxon Spec. XN-NS-S-004, Rev. 1, are the ASME B&PV Code,Section III, 1975 Edition through Winter 1975 Addenda, paragraph NF-5232. The weldments inspected conformed with the ASME B&PV Code requirements. Welding and NDE examination of the attachment members were being performed by the J. A. Jones
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Company. The TIG welding procedure, WP-P8-8 was qualified by PWR JAJ-280-GTA to ASME BP&V Code,Section IX requirements. The weldments examined appeared in conformance with the above stated requirement. The inspector verified the vacuum box testing procedure, QAP-1029, was approved by Exxon and that test personnel were certified with SNTC-TC-1A requirements.
Three of the four spent fuel racks were visually inspected for conformance with requirements stated previously. The inspector examined approximately 75-100 welds in the grid plates, shims and reinforcing bars. The welds were in conformance with the require-p ments of ASME B&PV Code as stated previously. The licensee intended g
to perform selected liquid penetrant examination of the rack weldments as a part of the receiving inspection. However, the temperature of the racks, maximum 200F, was too cold for the examination. The licensee will try to perform this extra examination if the rack temperatures become suitable, greater than 400F.
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No discrepancies were noted during this part of the inspection.
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