IR 05000395/1980039
| ML19341D079 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/30/1981 |
| From: | Girard E, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19341D077 | List: |
| References | |
| 50-395-80-39, NUDOCS 8103040825 | |
| Download: ML19341D079 (5) | |
Text
{{#Wiki_filter:1 i d [[ (C % UNITED STATES A% NUCLEAR REGULATORY COMMISSION g j REGION 11 '"
101 MARIETTA ST., N.W., SulTE 3100 '%,.. **f ATLANTA, GEORGIA 30303 a 'JAN 3 01981 Report No. 50-395/80-39 Licensee: South Carolina Electric & Gas Company Columbia, SC 29218 Facility Name: Summer Docket No. 50-395 License No. CPPR-94 Inspection at Summer Site near Columbia, South Carolina - Inspector: [ M /hBf 8/ E. H.
1 ar Dite Signed I kft Approved by: A. R. Herdt, Section Chief, RCES Branch Date Signed SUMMARY Inspection on December 16-19, 1981 Areas Inspected This routine, announced inspection involved 23 inspector-hours onsite in the areas of licensee action on previous inspection findings, licensee identified items (50.55(e)), review of reactor coolant pressure boundary piping records, review of preservice inspection program, review of preservice inspection procedures, and observation of preservice inspection.
- Results No violations or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- 0. S. Bradham, Station Manager
- J. F. Algar, Site Manager
- D. R. Moore, Quality Assurance Manager-
- S. J. Smith, Ibintenance Supervisor
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- A. A. Smith, Site QA Coordinator
- J. Turkett, Maintenance Engineer
- R. M. Campbell, Mechanical Engineer
- A. G. Alvarez, Senior Mechanical Engineer
- T. A.,McAlsiter, QA Surveillance Specialist
~0ther Organizations W. L. West, Project Quality Manager, Daniel Construction Company
- J. R. Fletcher, Project Quality Engineer, Daniel Construction Company NRC Resident Inspector
- J. L. Skolds
- Attended exit interview 2.
Exit Interview - The inspection and scope and findings were summarized on December 19, 1980, with those persons indicated in Paragraph 1 above.
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Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item (395/79-35-09): Pipe Not Properly Backed Out of Sockets.
The inspector discussed this item with cognizant licensee engineering personnel. They indicated they were continuing to examine this matter.
(Closed) Infraction (395/80-03-01): Adequacy of UT Utilized to Upgrade Class 2 Piping to Class 1.
South Carolina Electric and Gas Company's (SCE&G) letter of response-dated March 12, 1980, has been reviewed and determined acceptable by Region II. The inspector reviewed the licensee's corrective , action (which had resulted in identification of item 395/80-25-15, paragraph
5.c below) and concluded that SCE&G had determined the full extent of the subject noncompliance, performed the necessary survey and followup actions i and taken steps ' to preclude recurrence. The corrective actions identified in the letter of response have been implemented.
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2 ~ 4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
License Identified Items (50.55(e)) a.
(Closed) Item 395/79-05-02: ASME Code Radiography.
The licensee submitted a final report on this item to Region II on November 12, 1980.
The inspector reviewed the licensee's corrective actions including documentation of continued attention to the matter as contained in their Corrective Action Report, (CAR) 49 file.
In addi-tion, the NRC inspector reviewed radiographic examination reports and film for the following Reactor Coolant System piping welds: Weld Isometric Drawing FW-2 SE-RC-05 FW-7 SE-RC-05 FW-4R1-SE-RC-09 FW-11 SE-RC-10 FW-16R1 SE-RC-10 Other examples of radiographic film relative to this item were reviewed by Region II as described in reports 395/79-16, 395/79-17 and 395/80-12.
The inspector has no further questions on this item and it is closed.
b.
(Closed) Item 395/79-30-05: Welded Hilti Bolts. The licer see submitted a final report to Region II on November 14, 1980.
The NRC' inspector examined the licensee's corrective action on this item and has no further questions. The item is closed.
c.
(Closed) Item 395/80-25-15: Class 1 Pipe Supplied Without 4-Way UT.
The licensee submitted a final report to Region II October 9, 1980.
The inspector reviewed the licensee's Noncomformance Notices 2206 and 3398 on the item and a response letter from the vendor responsible for the violation (letter dated 9/8/80 from R.P. Burns of Southwest Fabrica-ting & Welding Co. to A. A. Smith of South Carolina Electric & Gas Co.). The NRC inspector examined the licensee's corrective action and has no further questions. The item is closed.
d.
(Closed) Item 395/80-28-01: Class 1 Pipe Supplied Without 4-Way UT.
This item is identical with item 395/80-25-15 above. It was opened in error and is being closed.
e.
(Closed) Item 395/80-37-04: Piping Burn Thru. The licensee informed Region II in their. letter dated December 9,1980, that they had deter-mined that this item was not reportable.
The inspector has reviewed the item and has no further questions. The item is closed.
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(Ocen) Item 395/80-39-01: Craft Doing Unauthorized Work on Pipe Hangers. -On December 16, 1980, the licensee informed Region II that final inspected and accepted pipe hangers had been found disassembled.
The licensee is investigating the item, 6.
Reactor Coolant Pressure Boundary Piping - Review of Quality Records The NRC inspector reviewed selected records for reactor coolant pressure boundary (RCPB) piping installation to determine conformance with NRC requirements and FSAR comitments. The appifcable code for RCPB piping is ASME Section III (71S73). Licensee procedures applicable to the installa-tion records are QCP-VII-02, WP-VII-02, QCP-VII-09 and WP-VII-09.
The records reviewed were for pipe spool pieces identified 1-RC-09-03,1-RC-05-01, and 1-RC-10-06. The records were reviewed to confirm that the proper inspection had been performed and recorded as evidence of compliance with installation specification and procedure requirements.
No deviations or violations were identified.
7.
Preservice Inspection - Review of Program The NRC insoector reviewed the licensee's orogram to determine conformance with reculatory requirements and FSAR comitments in the area of audits.
The code aonli. cable to the preservice insoection (PSI) is ASME Section XI (74 edition). The licensee's aporoved orocedures relative to the area of audits are OAP-2R1, QAP-19R1 and QAP-23. These were reviewed to determine whether the.v would assure control and accomolishment of audits and would orovide for: a.
Detailed procedures and/or checklists b.
Scope and purpose of audits . c.. Frequency of audits, audit criteria, basis for re-audit, management review, followup, corrective action d.
Qualifications and responsibilities of auditors l No violations or deviations were identified.
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Preservice Inspection - Review of Procedures The NRC inspector selectively reviewed the licensee's "Preservice Inspection , l Plan" (Revision 1) for compliance with regulatory requirements and licensee l commitments relative to the scope of PSI. The code applicable to PSI is ! ASME Section XI (74 edition). The "Preservice Inspection Plan" was reviewed l to ascertain whether if. properly specified examination category, examination i l
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method and extent of examination in accordance with requirements for the ' following areas as defined by the code: Letter Designation Area Name B-M-1 Pressure-Retaining Welds in Valve Bodies - B-M-2 Valve Bodies B-N-3 Removable Core Support Structures C-A Pressure-Retaining Welds in Pressure Vessels C-E-2 Support Component; for Piping, Valves, and Pump's C-F Pressure-Retaining Welds in Piping, Pumps, and , Valves in Systems Which Circulate Reactor Coolant No violations or deviations were identified.
9.
Preservice Inspection-Observation of Work and Work Activities > The inspector observed PSI work activities for compliance with regulatory requirements and licensee commitments. -The code for PSI is ASME Section XI (74 edition). The inspector observed the performance of visual examination on a weld identified 27BC (drawing CGE-1-4302).
This is a-piping branch connenction weld in the Reactor Heat Removal system. This examination was part of a penetrant examination being performed in accordance with procedure ISI-11 (Rev. 9 with changes 1 and 2). The NRC inspector observed the work for proper performance relative to: a.
Type of examination (direct or indirect) b.
Lighting level c.
Surface cleanliness d.
Acceptance criteria and corrective measures The licensee's examiner rejected the weld for inadequate surface conditions.
No violations or deviations were identified.
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