IR 05000346/1982022
| ML20027B202 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/07/1982 |
| From: | Danielson D, Yin I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20027B191 | List: |
| References | |
| 50-346-82-22, NUDOCS 8209160524 | |
| Download: ML20027B202 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-346/82-22(DETP)
Docket No. 50-346 License No. NPF-3 Licensee: Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, OH 43652 Facility Name: Davis-Besse Nuclear Power Station, Unit 1 Inspection At: Davis-Besse Site, Oak Harbor, OH Inspection Conducted: July 31 and August 5-6, 1982 Inspector:
I. T. Yin JMLLn/L Approved By:
D. H. Danielson, Chief
8h Materials and Processes Section
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Inspection Summary Inspection on July 31 and August 5-6, 1982 (Report No. 50-346/82-22(DETP))
s Areas Inspected:
Inspection of the licensee's repair of a failed support on the pressurizer surge system; review of relocation of pressurizer relief valves; review of modification of steam generator auxiliary feedwater system; review of licensee measures for three failed mechanical snubbers including observation of installation and modification.
Results: No items of noncompliance or deviations were identified.
8209160524 820910 PDR ADOCK 05000346 G
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DETAILS Persons Contacted Toledo Edison Company (TECo)
- C L. Merbel, Civil and Structural Systems Engineer
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J. K. Wood, Mechanical Engineering Supervisor Bechtel Power Corporation, Gaithersburg (Bechtel)
R. Kies, PDE Group Supervisor USNRC-RIII
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Peebles, Senior Resident Inspector W. Rogers, Resident Inspector
- Denotes those attending the management exit interview on August 6, 1982.
Functional or Program Areas Inspected 1.
Seismic Restraint Failure Seismic restraint PSU-H1 and spring support PSU-H2 that are installed on a common structure were found separated from the concrete wall by 3/8" at the top of the four bolt plate. The component was installed at the 10" pressurizer r. urge line. The inspection involved evalua-tions of licensee measures to correct the adverse condition.
a.
The inspector reviewed the Bechtel calculations for PSU-R1 dated June 26, 1979, (as found) and June 23, 1982 (as modified).
The inspector commented that although he was in disagreement with the Bechtel shear distribution assumption, he was satisfied that the component structure met the Code requirements based on the fact that the tension and shear interaction are within the par-abolic allowable curve, and that the original calculation had a l
built in safety margin of 15% above the DBE values provided by B&W.
b.
From the date of inspector's request (July 31, 1982) to obtain
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the original Grinnell component calculations for the PSU-R1 and R2, to the inspector's return to the site for the followup review (August 5, 1982) no records were able to be retrieved from the ITT-Grinnell office. The measures taken by Grinnell to maintain the documents and to evaluate the upgraded loads per the IEB 79-14 program appeared to be questionable. The licensee stated that an
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audit of Grinnell is planned this fall. The licensee further indicated that an audit at ITT-Grinnell, No. 606, " Design Control SQA Records," performed on July 23-24, 1979, identified no significant problem areas. The inspector requested that the
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licensee notify the NRC-RIII office of the date of their upcoming audit of ITT-Grinnell. This is an unresolved item (346/82-22-01).
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c.
In discussion with the licensee relative to the causes of the component failure, it was determined +. hat the concrete expansion anchor bolts were improperly installed during plant construction.
To assure that there are no similar conditions existing, the inspector requested that the licensee torque test, per IEB 79-02 requirements, all concrete anchor bolts in the pressurizer spray, surge, and relief piping systems. Due to accessibility and scaffolding problems, the inspector stated that at least 75% of all the bolts should be tested. The testing progress including generation nonconformances, recording inaccessibilities, and any
expansion of the testing program due to abnormalities identified should be reported to the NRC-RIII Senior Resident Inspector (SRI).
Subsequently, the SRI informed the inspector that the licensee torque tested approximately 90% of the bolts and that the few failed bolts were within the IEB 79-02 criteria and allowables.
2.
Relocation of Pressurizer Relief Valves The two pressurizer relief valves were relocated to the top of the vessel and portions of the valve inlet piping were removed from the system. The design was performed by Teledyne Engineering Services.
The scope included:
(1) analysis of the relief valve primary and secondary loadings at the connecting nozzles, (2) design of the "T" discharge section including the rupture discs and the drain lines, (3) re-analysis of pressurizer relief to quench tank line, and (4) remeval and modification of restraints and supports.
The inspector requested the licensee to provide the above design documents for his review during a future site inspection. This is an open item (346/82-22-02).
3.
Modification of Steam Generator (SG) Auxiliary Feedwater Piping The subject modification included installation of external ring headers and risers, and portions of the piping systems connecting to the ring headers. There were seven new or modified restraints and supports installed on SG 1-1 and three installed on SG 1-2.
The inspector reviewed the stress summary of Bechtel calculations, and selectively reviewed the following new restraints:
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a.
Calc. IA, FCR 82-047, dated June 24, 1982 for SG 1-1.
Lupport No. M-1155 H3, Snubber Z Support No. M-1155 H6, Snubber Z b.
Calc. 2A, FCR 82-047, dated June 24, 1982 for SG 1-2.
Support No. M-1155 H8, Rigid X Support No. M-1155 H8, Snubber Z No items of noncompliance or deviations were identified.
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4.
Inoperable Mechanical Snubbers In accordance with IEB 82-01 requirements, the licensee inspected all the installed mechanical snubbers and found the following small Pacific Scientific Company (PSA - 1/4) snubbers inoperable (frozen):
No. M1113 H56 on the 3/4" FT-RCIA1 line
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No. M113.H61 on the 3/4" FT-RCIA3 line
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No. B4-H1 on the 3/4" PSH-RC2B4 line
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FT - Flow Transmitter PSH - Pressure Switch High The licensee performed a stress evaluation and concluded that lines FT-RCIA3 and PSH-RC2B4 were operable even with the frozen snubbers.
As for line FT-RCIA1, the pipe stresses met the Code primary stress allowables but failed in the line fatigue analysis per ASME III Class 1 piping requirements. NDE performed at the branch connection revealed no defect indication. A licensee report per Technical Specification is planned. The identified deficiencies were documented in TECo NCRs No. 419-82, dated July 8, 1982, No. 425-82, dated July 13, 1982, and No. 432-82, dated July 16, 1982.
5.
Observation of Installation The inspector observed piping modification, snubber and restraint repair, and installation at the pressurizer and SG 1-2 areas, in conjunction with matters discussed in Paragraphs 1 to 3 above.
No items of improper installation or malfunctioning hardware components were identified.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. The unresolved item disclosed during this inspection is discussed in Paragraph 1.b.
Open Items Open items are matters about which additional inspection effort is planned.
This is due to unavailability of materials for review at the site.
The open item assigned in this report is discussed in Paragraph 2.
Exit Interview The inspector met with licensee representatives at the conclusion of the inspection. The inspector summarized the scope and findings of the in-spection. The licensee representative acknowledged the findings reported herein.
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