IR 05000321/1979026
| ML19275A650 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/30/1979 |
| From: | Herdt A, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19275A643 | List: |
| References | |
| 50-321-79-26, 50-366-79-31, NUDOCS 7910180059 | |
| Download: ML19275A650 (4) | |
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UNITED STATES
7, NUCLEAR REGULATORY COMMISSION
E REGION 11
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e'[
101 MARIETTA ST., N.W., SulTE 3100 o,
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ATLANTA, GEORGIA 3o3o3 Report Nos.
50-321/79-26 and 50-366/79-30 Licensee: Georgia Power Company 270 Peachtree Street, N. W.
Atlanta, Georgia 30303 Facility Name: Hatch Nuclear Plant Docket Nos. 50-321 and 50-366 License Nos. DPR-57 and NFP-5 Inspection at Hat P an Site near Baxley, Georgia
/ /8 b 36[7f Inspect -:
E. J. Vallish Date' Signed Approved by:
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h[79 A. R. Herdt, Section Chief, RCES Branch Date ' Signed SUMMARY Inspection ou August 15-17, 1979 Areas Inspected This special, unannounced inspection involved 16 inspector-hours onsite in the areas of pipe support base plate designs using concrete expansion anchors.
Results No apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- T. V. Greene, Assistant Plant Manager
- W. A. Widner, Nuclear Operations Manager
- C. E. Belflower, QA Site Supervisor
- J. D. Peregoy, QA Field Representative
- R. M. Herrington, QC Specialist Other Organizations
- N. J. Cherish, Bechtel Site Supervisor NRC Resident Inspector
- R. F. Rogers
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on August 17, 1979 with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts (IE Bulletin (IEB 79-02) - Units 1 and 2 The licensee's interim report dated July 6, 1979 was reviewed prior to this inspection and determined to be acceptable for the information submitted, concerning both Units 1 and 2.
The licensee stated during the inspection, that their reply was almost fiaalized when they received Revision 1 of IEB 79-02, hence some details included in the Revision were not addressed in their July 6, 1979 letter. This point was expanded upon during the exit interview and the licensee stated that the forthcoming letter replying to the IEB 79-02 would be transmitted in about 30 days and would address the remaining items.
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-2-The following Unit 2 procedures were reviewed:
a.
HNP 2-11004, titled, " Surveillance Procedure for Identifying Anchors Used for Hangers in Safety Related Systems".
b.
HNP 2-11005 titled, " Inspection and Test Procedure for Concrete Expan-sion Anchors."
These procedures were similar in nature with those reviewed and reported on in RII Report 50-321/79-15 for the Unit I facility.
The sampling and inspection of anchor bolts, described latcr in this report, was performed to verify that the anchor bolt inspection and repair was performed in accordance with these procedures and also to verify that the program satis-fied the field requirements of IEB 79-02.
Also reviewed were the following QA audits pertaining to the pipe support inspection and repair efforts:
" Quality Assurance Audit of Hatch Nuclear Plant Haager Rework a.
Activities"; (QA Audit 79-SA-6) dated May 31, 1979.
b.
" Quality Assurance Audit of Hatch Nuclear Plant Unit 1 Seismic I Pipe Support Concrete Anchor Bolt Rework"; (QA Audit 79-SA-10) dated August 10, 1979. The purpose of this audit was to verify that seismic class 1 pipe supports of Unit I were reworked in accordance with the requirements of IEB'79-02; Revision 1.
The "haintenance Request" (MR) document packages which resulted from the licensee's surveillance inspection, the Bechtel redesign work and the licensee's repair efforts, were screened for representative samples of which a detailed inspection was performed. Out of about 250 MR packages concerning the 2P41 Service Water System and the 2E11 Residual Heat Removal (RHR) Service Water System, eight complex type hanger MR packages were selected, reviewed and the work inspected.
The following control numbered MR packages were selected: 2-79-1377, 2-79-1547, 2-79-1760, 2-79-1853, 2-79-1919, 2-79-1954, 2-79-2146 and 2-79-2481.
Isometric drawing sheets 2P41-107, 2P41-108, 2E11-116 and 2E1H15 were reviewed and used to verify location, orientation, description, and installation details of those hangers and base plates.
No items of noncompliance or deviations were identified.
6.
Licensee Identified Item - Unit 2 (0 pen) Item 366/79-30-01, " Seismic Restraints for Service Water Pumps in the Intake Structure".
On August 15, 1979 the licensee notified IE:II that the continued review, by Bechtel, of the original calculations for Unit 2, identified that the RHR Service Water and Plant Service Water pump seismic restraints in the intake structure had a minimum safety factor of 3.0 under the following design conditions:
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The only applied Icad is the lateral siesmic load of 4500 pounds.
a.
b.
Assuming all the expansion anchors underwater are self-drilling type.
c.
Assumed that 50% of the total number of anchors have failed on each base plate.
The licensee stated that he would attempt to determine the condition of the underwater self-drilling anchors then plan a fix for those restraints.
7.
Licensee Identified Items - Unit 1 (Open) Unit 1 LER No. 79-64, " Seismic Restraints for RllR Service Water Pumps".
On August 14, 1979 the licensee notified IE:II that two of the self-drilling type anchor bolts, supporting the seismic restraints for the RHR Service Water pumps, came out of the wall with the restraint when the restraint was removed for pump maintenance. Bechtel has redesigned this restraint so that it need not be removed for future pump maintenance. The licensee stated that the reinstallation work will be completed prior to Unit 1 startup.
(Closed) Unit 1 'IR No. 79-47, "RCIC Torus Suction Line Lateral Restraint Guide Bars".
On June 19, 1979 the liceriee notified IE:II that while reviewing the supports, for E51-RCICll-15 and E51-RCICil-17 on the RCIC torus suction line, for replacement of expansion anchors, it was noticed that the guide bars required to provide lateral restraint were not installed. The report has been reviewed and determined to be acceptable by IE:II. The inspector held discussions with responsible licensee representatives, reviewed supporting documentation and observed representative samples of work to verify that corrective actions identified in the report has baen completed.
(Closed) Unit 1 LER No. 79-43, "Radwsste Sump Discharge Piping Seismic Supports".
On June 28, 1979 the licensee notified IE:II that the radwaste sump discharge piping between the drywell penetration and the second isolation valve was not supported per seismic Class I requirements. The report has been reviewed and determined acceptable by IE:II. The inspector held discussions with responsible licensee representatives, reviewed supporting d cumentation and observed representative samples of work to verify that corrective actions identified in the report has been completed.
No items of noncompliance or deviations were identified.
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