IR 05000395/1982024
| ML20051A240 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/15/1982 |
| From: | Girard E, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20051A195 | List: |
| References | |
| 50-395-82-24, NUDOCS 8205140482 | |
| Download: ML20051A240 (5) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
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REGION ll b[
101 MARIETTA ST., N.W., SUITE 3100 Q
ATLANTA, GEORGIA 303o3
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Report No. 50-395/82-24 Licensee:
South Carolina Electric and Gas Company P. O. Box 764 Columbia, South Carolina 29218 Facility Name:
Summer Docket No. 50-395 License No. CPPR-94 Inspection at Summer site near Columbia, South Carolina Inspector:
[8A E. H. Gj rard
'/Da s Signed
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Approved bv:
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/I d A. R. Herdt, Section Chief Dats Signed Engineering Inspection Branch Division of Engineering and Technical Programs
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SUMMARY Inspection on March 23-26, 1982 r
Areas Inspected This routine, announced inspection involved 24 inspector-hours on site in the areas of licensee action on previous inspection findings, inspector follow-up items, preservice inspection - review of program, and preservice inspection -
data review and evaluation.
Results No violations or deviations were identified.
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REPORT DETAILS.
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1.
Persons Contacted
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- Licensee Employees
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- W. A. -Williams, General rianager, Nuclear Operations
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- 0. S. Bradham, Station Manager !
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- H. I. D6nnelly. Licensing Enginder
- S. S. Howze, Licensing Engineer
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- L. B. Collie, Welding Supervisor
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- G._ Putt, Mechanical Maintenance Supervisor x
F. Lamphere, Director of Administration
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- D. M. Quinton, Nuclear Engineering
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- T. A. McAlister, QA Surveillance Specialist '
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NRC Resident'70spector
h,rl. Skolds~
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, Attended exit interview
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E'xitTInterview
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The inspection scope and findings were summarized on March 26, 1982, with
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those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings
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a.
(Closed) Unresolved Item (395/81-17-02): Inspection of Weld Root With 41 Refracted Longitudinal Wave Transducer. Region II had previously
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agreed that this' item would be considered closed when the licensee provided a letter to Region II regarding the completion status 'of its
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preservice inspection (PSI), as described in IE Repcrt 395/82-13. The
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' licensee informed the inspector that the letter had been prepared for
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transq(ttal to Region II rand a copy was provided to the inspector. The inspector reviewed the. letter and agreed that This item is glosed.
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it was satisfactory,.
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b.
(Closed) Unresolved Item (395/82-02-01): Pressurizer Integral Support Weld PSI Exam.
This item addressed the inspector's concern 1. hat the
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licensee had not fdentified the location oft the pressurizer ' integral support weld to adequatelyrassure that,it would be completely examined in PSI. The licensee identified these' concerns on -its Nonconformance
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l Notice (NCN) 545. The inspector reviewed the disposition of NCN 545,
'which provided for re-examination of the weld and identification of its location for future reference. ' Thel~ inspector also reviewed the final examination report for the weld and' identification of its centerline location on sketch CGE-1-2100. The inspector noted that ths width of
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the weld was not indicated on the sketch. The* licensee-agreed to add-the width. The inspector is satisfied that item 395/82-02-01 may' be closed based on his review and discussion with licensee personnel. The
licensee's proper identification of weld width on:the weld sketch will
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~be verified in subsequent inspection in relationLto previously identi--
fied inspector follow-up item 395/79-27-02, " Identification. of Welds
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i for Inservice Inspection."
c.
(0 pen) Unresolved Item (395/82-13-01):
Installation of -Locking Devices. This item was opened to identify improperly installed locking devices on main steam isolation valves..The inspector questioned the licensee on this item and was informed that it was still under evalu-
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ation.
d.
(Closed) Unresolved Item (395/82-13-02): Head Lifting Structure Welds and Bolting. This item identified an NRC inspector's concerns for missing locking devices and weld defects on the lifting structure for the reactor vessel head. The inspector reviewed the. licensee's docu-
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mentation'and disposition of the weld defects as described on-NCN542.
In addition, the inspector visually verified that locking devices had l
been properly installed on the structure and that the licensee's
' procedure requires verification ~ of locking device installation.
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inspector is satisfied that this item may be closed.
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4.
Unresolved Items
~ Unresolved items were not identified during this inspection.
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Inspector Follow-up Items a.
(0 pen) Inspector Follow-up Item (395/79-27-02):
Identification of
welds for inservice inspection. This item was opened for followup of the inspector's concern that some welds had not been adequately identi-
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fied to permit them to re readily located for inservice inspection examination. An additional related Econcern was identified in unre-solved item 395/82-02-01, as described in paragraph 3.b above.
The licensee's actions for the conditions questioned-in item 395/82-02-01 were considered sufficient to permit the item be closed. However, one concern from that item, that the weld width was not specified for use in future inservice inspection examinations, continues. As noted in paragraph 3.b, the licensee indicates that the weld width will be added
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to the sketch identifying the weld's location.
The inspector will
verify this addition 17 future inspection addressing item 395/79-27-02.
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l b.
(Closed) Inspector Follow-up Item (395/81-17-03): Ultrasonic Inspec-tion Reporting Inconsistencies.
This item identified an inspector's concern for inconsistencies and errors found in the licensee's pre-
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service inspection (PSI) ultrasonic inspection reports. In the current l-inspection the NRC inspector was informed that licensee personnel had performed a thorough review of the PSI reports and had obtained l
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corrections or identified for correction any errors or inconsistencies-found.in the data. The inspector reviewed the licensee's listing of needed corrections.
In addition, he reviewed-examples of the PSI reports for the welds 1DM, 2, 3, 6DM, 8, 9, and 12-16DM on sketch CGE-1-4102 and welds 15 and 16 on sketch 1-4506. The inspector-is
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satisfied with the licensee's actions for this item and considers the-matter closed.
6.
Preservice Inspection - Review of. Program
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The inspector reviewed the licensee's programatic and implementing proce-dural' documents to verify that they establish maintenance responsibilities and storage controls for PSI' records which meet regulatory requirements and FSAR commitments - including a code commitment to ASME Section XI (74S75).
Programatic and procedural documents reviewed by the inspector were as follows:
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Operations QA Plan Rev. 8, Sect.14 b.
Administrative Procedure AP-014 Rev. 7, "Preservice. Inspection" c.
Administrative Procedure AP-301.2 Rev. O, Change 4, " Nuclear Operations Records Control Procedure" The inspector reviewed the above documents and their implementation with the
' responsible licensee personnel to specifically determine whether they adequately establish:
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The storage facilities that may be used for the various types of records b.
The storage facility custodian c.
The filing system
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A method for verifying the records to be stored are as indicated in the
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transmittal document I
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Provisions governing access to records and maintaining accountability
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for records removed from the files f.
Methods for filing supplemental information Within the areas inspected, no violations or deviations were identified.
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- Preservice Inspection - Data Review and Evaluation
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The inspector reviewed selected examples of reactor vessel autcmated ultra-sonic examination weld records to verify that the data indicated adequate
i examinations and proper disposition of any adverse findings in accordance with the requirements of the applicable code (ASME Section XI).
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records of the reactor vessel weld automated examinations were not available
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l at the Summer site, as they are maintained by the contractor who performed the esaminations. The inspector's review was limited to final reports of
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the examinations rather than detailed data. The reports examined were for the following welds:
Circumferential upper to middle course vessel weld (Weld 2 on Sketch 1-1100)
Circumferential middle to lower course vessel weld (Weld 3 on Sketch 1-1100)
Primary irlet nozzle safe end weld at 25 (Weld IDM on Sketch 1-4100)
The reports for the above wclds were reviewed by the inspector to verify that they indicated that a.
The method, extent and technique of examination complied with the PSI program and applicable examination procedure b.
Acceptance criteria were met c.
Recording, evaluation and disposition of findings were in compliance with the procedure and code requirements d.
The examination method used was sufficient to determine the extent or acceptance of indications Within the areas inspected no violations or deviations were identified.
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