IR 05000280/1979054
| ML18136A266 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/18/1979 |
| From: | Herdt A, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18136A265 | List: |
| References | |
| 50-280-79-54, 50-281-79-76, NUDOCS 7912060495 | |
| Download: ML18136A266 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report Nos. 50-280/79-54 and 50-281/79-76 Licensee:
Virginia Electric and Power Company Richmond, Virginia 23261 Facility Name:
Surry Power Station Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37
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Inspectio~.- at~~) ;~er Station near Williamsburg, Inspectof:-' U)'\\ p/(,14 Virgin~: /,
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7 c (fa E. J. ~/h~\\'.
Approved by: u{/£Nfltl/
A. R. Herdt, Section Chief, RCES Branch SUMMARY Inspection on September 10-13 and 19-21, 1979 Areas Inspected
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This special, unannounced inspe~tion involved 34 inspector-hours onsite in the area of pipe support base plate designs using concrete expansion anchor bolts -
IE Bulletin (!EB) 79-0 Results No items of noncompliance or deviations were identifie *-~
DETAILS Persons Contacted Licensee Employees
- W. L. Stewart, Sr., Station Manager R. Barryman, Staff Engineer R. ij. Woodall, Associate Engineer C. M. Robinson, Jr., Supervisor Civil Engineering Services Other licensee employees contacted included six technicians, and four mechanic NRC Resident Inspector
- D. J. Burke
- Attended exit interview Exit Interview The inspection scope and findings were summarized on September 13 and 21, 1979 with the person indicated in Paragraph 1 abov.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inspectio.
Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts - IE Bulletin 79-02 During a conference phone communciation on September 7, 1979, between the licensee and RII management, confirmed by a letter dated September 7, 1979 from RII to the licensee four subjects were discussed as requiring resolu-tion concerning the completion of the requirements of IEB 79-02 for Unit 1; these were: A random sample of safety-related piping six inches in diameter or less) inside the containment will be analyzed for conformation with the FSAR and design criteria using manual calculation method The analyzed piping will be inspected to determine that supports and restraints are properly located and are of correct desig A random sample of anchor bolts will be selected for inspection in accordance with IEB-79-0 This sample will include samples from all
-2-size bolts supporting safety-related piping within the containment, but will exclude bolts f-rom supports which were modified as a result of the NRC Show Cause Order and those from supports which were pre-viously inspected under IEB-79-0 Stringent QA/QC controls will be exercised during these inspection A representative sample of baseplates will be analyzed for flexibility using the methods developed by Stone and Webster Engineering Corporatfo *. A visual inspection will be made of all bolted base plates which would be inaccessible during operation This inspection w_ould be to detect defects such as missing or loose bolts and nuts andskl!wed bolts which would adversely affect the ability of the support to perform its intended functio During this inspection the following documents were reviewed within the purview of the IEB requirements and as discussed with the licensee's re-
. *presentatives during the referenced phone conference on September 7, 1979: "Baseplate Visual Inspection and Anchor Bolt Test Program Surry Power Station Unit No. 1., ST-75". "Visual Inspection of Baseplates Containing Concrete Expansion Anchors, ST-75-P-1".
c.* "Field Inspection and Testing of Self-Drilling (Shell) Type Concrete Expansion Anchors, ST-75-P-2".
- "Grouting Repair, ST-75-P-3A" "Hanger Repair Procedure Replacement of Concrete Expansion Anchor with Self-drill Type Anchor, ST-75-P-3B" "Installation of a Wedge Type Concrete Expansion Anchor in a New Hole in an Existing Hanger BasePlate".
Using ST-75 and ST-75-P-l as guidance, two of the visual inspection crews were observed during their inspection and data taking activities within the Unit 1 containment building. The hangers on the lORS-9, 6RC-37, 2Sl-74 and 6Sl-153 were observed to be inspected and the resulting data was confirmed by QC inspectors who were members of the crew About one-half of the systems inside the containment were inspected when selection of accessible anchor bolts was started, in preparation for torque testin The data resulted from the ST-75 procedure walkdown visual inspection and the anchor bolt test program, ST-75-P-2 was reviewed. One set of data on hanger 1 of MKS 10261-3 was questioned by the inspector and hence was later remeasured and the first dimensions confirmed by the inspector and the licensee's inspection cre Findings indicate that a safety factor of two was adequately demonstrated for these bolts and that an acceptable percentage of failures existe These findings fulfill the requirements of paragraphs band d cited earlier in this report ite Ebasco Services Incorporated is contracted to perform the IEB-79-02 activi-ties in Unit 2 within the time frame of the steam generator replacement
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outage. The licensees representative stated that Ebasco's effort at present concerns with the generation and approval of procedures to accomplish the wor No items of noncompliance or new unresolved items were identified.