IR 05000261/1980024
| ML14175B236 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/10/1980 |
| From: | Herdt A, Modenos L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B232 | List: |
| References | |
| 50-261-80-24, IEB-79-02, IEB-79-14, IEB-79-2, NUDOCS 8012180194 | |
| Download: ML14175B236 (4) | |
Text
o UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report No. 50-261/80-24 Licensee: Carolina Power & Light Company 411 Fayetteville Street Raleigh, North Carolina 27602 Facility Name: H. B. Robinson License No. DPR-23 Docket No. 50-261 Inspection at:
obinson near Hartsville Inspecto :
_/ odeno Datd SIgned Approved by:
/9/let
/0/ k A. R. Herdt Date Signed
.
SUMMARY Date of Inspection: September 8-11, 1980 Areas Inspected This routine, announced inspection involved 27 inspector-hours onsite in the areas of seismic analysis for as-built safety-related piping systems (IE Bulletin 79-14) and pipe support base plate design using concrete expansion anchor bolts (IE Bulletin 79-02)
Results Of the two areas inspected, two items of noncompliance were found in one are (Infraction - failure to establish adequate procedures paragraph 5; Infraction failure to follow procedures paragraph 5).
80121BU1
DETAILS Persons Contacted Licensee Employees R. B. Starkey, Jr., Plant General Manager
- S. Zimmerman, Technical and Administrative Manager
- R. Cornwel, Director of QA
- M. F. Page, Project Engineer NRC Resident Inspector
- A. Hardin
- Attended exit interview Exit Interview The inspection scope and findings were summarized on September 11, 1980 with those persons indicated in Paragraph I abov.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviation. New unresolved items identified during this inspection are discussed in paragraph.
(Open) Seismic Analysis for As-Built Safety-Related Piping System (IE Bulletin 79-14)
CP&L had committed on a previous response to the bulletin, to complete all inspections on safety-related supports that were inaccessible during operations of the plan At the time of this inspection, H. B. Robinson was in a refueling outage and all inspections for the inaccessible supports with the exception of the containment spray headers had been complete The inspection packages were being reviewed by the stress analyst and engineering personnel of Ebasco Services, the A/E, for satisfaction of the requirements to the bulletin and CP&L procedure O The inspector reviewed the following ISO packages for compliance with the requirements of the bulletin:
Package No. SI-1 System: Safety Injection ISO-SI-1 Rev. 0 Package No. SW-6 System: Service Water ISO-SW-6 Rev. D Package No. SW-7 System: Service Water ISO-SW-7 Rev. 1 Package No. SI-8 System: Safety Injection ISO-SI-8 Package No. RC-4 System: Reactor Coolant ISO-RC-4 Rev. 0 Package No. CH-3 System: Chemical Volume Control ISO-CH-3 Rev. 1 Package No. RC-2 System: Reactor Coolant ISO-RC-2 Rev. 0 In ISO-SI-1 Support N the stress analysis showed the support as a two-way restrain The inspection support details identified the support as a two-way restraint, but had excessive dimensional tolerances that would allow the pipe to move in both directions and prevent the support to restrain the pipe. The stress engineers reviewed each support, on a case by case basis for any potential over stressin The procedure used by the stress engineers to evaluate the inspection data is "Procedure for Pipe Stress Review and Analysis" Rev. This procedure does not address the acceptable dimensional tolerances to be used by the stress enginee The failure to identify acceptable dimensional tolerance in the procedures mentioned above, appears to be noncompliance with the Techinical Specifica tion Section 6.8.1 and is identified as an infraction,Item No. 261/80-24-01, Failure to establish adequate procedure The inspector reviewed package No. RC-4 and re-inspected portions of the system and discovered that penetrations were identified on the isometric sketch and were not inspected for clearance as designed in procedure SP-205 Rev. 0 section 6.2.8 "clearances shall be measured and recorded on all four sides of pipe at penetrations
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-3 The failure to follow the procedure mentioned above, appears to be noncom pliance with Technical Specification Section 6.8.1 and is identified as infraction,Item No. 261/80-24-02, Failure to follow procedure The inspector reviewed the cross reference checks of loads from the re analysis of safety-related systems to the Factor of Safety of anchor bolts and discovered that the unaccessible systems identified had records of the cross referenc The systems inspected earlier that were considered access ible had not been cross reference This item will be identified as an Unresolved Item and would be identified as 261/80-24-03, Cross reference checks of new loads of reanalyzed safety related piping system Review of ISO-SI-8 and re-inspection of the system revealed that at support No. 15 and No. 17, U-bolts were used for both supports. Support No. 15 was utilized as a 2-way restraint while support N was used as a dead weight suppor On ISO-SI-1 support No. 148 calls for a dead weight suppor Field inspection found a U-bolt at that poin The thermal analysis at Support No. 148 showed the point to be moving up 0.5 inch, when in fact it cannot because it is restricted by the U-bol These examples are indicative of the misuse of U-bolts and the way the analyst utilize them in the stress analysis.' This item will be identified as an Unresolved Item No. 261/80-24-04, Proper use and installation of U-bolt The inspector discussed the findings and unresolved items mentioned above with licensee management and agreed that prior to start up the plant will complete all inspections on IE Bulletins 79-14 and 79-02 (Anchor bolt inspec tions) and complete all required modification Prior to start up, the resolution of the items on the U-bolts would be discussed with Region I Final evaluations and reporting for both Bulletins will be due by December 31, 1980, including valve, penetration and all re-analysi IE Bulletin 79-14 remains open until all inspections and evaluations are completed and evaluated by the NRC.