IR 05000280/1980022
| ML18139A638 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/01/1980 |
| From: | Compton R, Herdt A, Modenos L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18139A637 | List: |
| References | |
| 50-280-80-22, 50-281-80-25, IEB-79-14, NUDOCS 8008120314 | |
| Download: ML18139A638 (4) | |
Text
{{#Wiki_filter:* UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report Nos.: 50-280/80-22 and 50-281/80-25 Licensee: Virginia Electric and Power Company Richmond, VA 23261 Facility Name: Surry Docket Nos.: 50-280 and 50-281 License Nos.: DPR-32 and DPR-37 Inspection at Stone and Webster Engineering Corporation, Boston, MS Inspectors-, PM. C e,,-r\\-,,,~ R. M. Compton /
- .
t.,"/ /. . -~ ///..,-,../_,..,:*;:,_.. *. .-..:.*-,. L. Modeno"~~ /.,
- .
Approved by: Hl?tf/([[lj/* A. R. Herdt, Section Chief, RCES Branch SUMMARY Inspection on June 16-18, 1980 Areas Inspected .f ' I._,.f J ., tr( . ,/ '::) } Date Signed Date Signed 7/; fft: Date Signed This routine, announced inspection involved 24 inspector-hours at Stone & Webster Engineering Corporation Headquarters in the areas of IE Bulletin 79-14, "Seismic Analysis for As-Built Safety-Related Piping Systems" and licensee actions on previous inspection finding Results Of the two areas inspected, no items of noncompliance or deviations were identifie soos12 o3/i
- DETAILS Persons Contacted Licensee Employees J. L. Wilson, Station Manager
- A" ~'. Peebles, Superintendent of Technical Services MacManus, Associate Engineer Other Organizations Stone & Webster Engineering Corporation (S&W)
- C. B. Miczek, Vice President - Engineering
- N. B. Cleveland, Vice President - Quality Assurance
- kH. W. Durkin, Project Engineer
- I.A. Banerjee, Assistant Project Engineer
- J. W. Kelly, QA Program Administrator
- Attended exit intervie.
Exit Interview The inspection scope and findings were summarized on June 18, 1980, with those persons indicated in Paragraph 1 above and on June 19, 1980 by telecon with Surry Station Manager, J. L. Wilso. Licensee Action on Previous Inspection Findings (Closed) Unresolved Item 280/79-58-01 - Consistant Thermal Analysis of Vertical Supports/Restraints. During a previous inspection a situation was identified where vertical supports had not been included in thermal analysis problems and the piping at these locations had large downward motio The concern was that these points could see excessive thermal stresse The design unit procedure addressing the methods of modeling vertical supports, EMD-79-18, stated that it provided."non-mandatory guidelines".
VEPCO and S&W engineers have stated that the modeling methods where no credit was taken for rod hangers was used only during the early "show
- cause" analyse S&W provided a copy of a memorandum to responsible engineers stating that EMD-79-18 would be followed for all IE Bulletin 79-14 and long-term (OBE) "show cause" computer work for Surry 1 and The inspectors have no further questions on this matte This item is closed.
-2-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) IE Bulletin 79-14, "Seismic Analysis for As-Built Safety-Related Piping Systems," Uni ts 1 and Stone & Webster procedures governing various aspects of the IEE 79-14 effort were reviewed for content and complete coverage of bulletin item Procedures that were examined in detail included the following: "Engineering Assurance Program for Pipe Stress Analysis Review", R_evision 5, which included audit checklists for audits of problem packages, general Project activities and Division activities "Procedure for Field Verification of Valve and Operator Weights", Revision 1 "Procedure for Field Record Verification of Pipe Material", Revision 1, STF-19 The valve weight verification program is being expanded from a review of site QA records to include a 100 percent field verificatio Based on problems with existing records and vendor supplied valve weight information noted by the North Anna Project, the inspectors discussed with responsible engineers the need to verify correct weights with the manufacturers for all valves on the Surry Project. The inspectors recommended that the procedure be revised to reflect these development The inspectors also recommended that, based on the large number of discrepancies identified on the North Anna Project, the valve weight verification program be expedited and requested VEPCO to provide a schedule for completion of both field work and design review. This is being identified as an Inspector Followup Item 280/80-22-0 The following stress problems were selected for examination of the evaluation and analysis work effort: Problem 3047, MSK 1122A, Steam Generator Blowdown System Problem 2727, MKS 127C, Low Head Safety Injection System Problem 607, MKS 118G2, Auxiliary Steam Generator Feed System Problem 3033, Reactor Purification System Documentation examined included as-built configuration data, pipe stress work sketches, support as-builts and calculations, operating parameters, amplified response spectra curves, Engineering Assurance checklists, computer printouts of stress analysis and Valve Information Requests. It was noted that the valve manufacturer and types used in the analysis for two valves in problem 607 were not the same as observed in the field by this inspector. However, field verification had not yet been completed for this proble *
-3-In reviewing problem 3033 it was noted that the analysis cover sheet had been signed by the stress engineer on December 5, 1979 and signed by a chl'\\cker on December 8, 197 This analysis showed overstress conditions in two piping runs. The independent review block was not signed off until February 1, 198 The plant Technical Services Supervisor stated that the site was informed by S&W that a nonconformance existed on this piping on February 19, 1980. The plant was shut down per the Technical Specifications at 10:15 on February 19, 1980, and a Licensee Event Report initiate S&W Procedure STF-3, Revision 1, dated February 19, 1980, entitled "Procedure for the Evaluation of Stress and Reporting of Over-Allowable Stress for IE Bulletins 79-14, 79-02 and Show Cause Efforts, Surry Power Station - Units 1 and 2", outlines the evaluation and reporting process for S& However, this procedure does not specify any time limits for review or reanalysis nor does it address the two-day initial engineering judgement or the thirty-day analytical engineering evaluation specified in Paragraph 2 of IE Bulletin 79-1 The licensee committed to evaluate this situation and provide details about each nonconformance identified by S&W for Surry These details are to include the dates of initial problem identification, dates of the various reanalyses, reviews and evaluations and the date of actual notification of VEPCO personne This is identified as Unresolved Item 280/80-22-01: Timely evaluation and reporting of nonconformances identified by IEB 79-1 Paragraph P of Section 4 of SD-STEP, S&W' s "Procedure for Evaluation of Base Plates and Drilled - in Anchors" describes a method for modifying loads on base plates and anchors based on support configuration and engineering judgemen Application of this section was discussed with the responsible engineer The inspectors had no further questions concerning the intent or use of this procedur Problem 3047 was examined as an example of a situation where an anchor is common to two problem Loads from the adjacent problem had been considered in the problem examine No deviations or items of noncompliance were identified. }}