IR 05000280/1991016
| ML18153C662 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/24/1991 |
| From: | Blake J, Lenahan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18153C661 | List: |
| References | |
| 50-280-91-16, 50-281-91-16, NUDOCS 9107080187 | |
| Download: ML18153C662 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report Nos.:
50-280/91-16 and 50-281/91-16 Licensee:
Virginia Electric and Power Company Glen Allen, VA 23060 Docket Nos.:
50~280 and 50-281 Facility Name:
Surry 1 and 2 License Nos.: DPR-32 and DPR-37 Inspection Conducted:
Date Signed SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of the snubber surveillance program and follow-up on licensee action on previous inspection finding Results:
In the areas inspected, violations or deviations were not identifie Snubber surveillance procedures were explicit and well-stated fbr control of surveillance activities. Approach to resolution of technical issues was sound, thorough, and conservativ Staffing was adequate and training of inspection personnel was effectiv PDR ADOCK 05000280 Q
PUR
REPORT DETAILS Persons Contacted Licensee Employees
- R. Bilyeu, Licensing Engineer
- D. Hart, Supervisor, Quality Assurance
- T. Huber, Inservice Inspection Supervisor
- M. Kansler, Station Manager
- E. Smith, Site Quality Assurance Manager
- M. Whitt, Civil Design Supervisor D. Wong, Snubber Engineer NRC Resident Inspectors W. Holland, Senior Resident Inspector
- M. Branch, Senior Resident Inspector S. Tingen, Resident Inspector
- Attended exit interview Inspection of Pipe Supports and the Snubber Surveillance Program, Units 1 and 2 (70370)
The inspector examined procedures and qua 1 ity records re 1 ated to the snubber surveillance program and inspected snubbers and pipe supports on safety-related piping system Acceptance criteria utilized by the inspector are specified in Technical Specification 4.1 Review of Snubber Surveillance Procedures The inspector examined the foll owing procedures which control snubber surveillance activities:
(1)
Procedure numbers 1-PT-39A-1 and 2-PT-39A-1, Visual Inspection -
Accessible Snubbers - As Left (2)
Procedure numbers 1-PT-398-1 and 2-PT-39B~l, Visual Inspection -
Accessible Snubbers - As Found (3)
Procedure numbers 1-PT-39A-2 and 2-PT-39A-2, Visual Inspection -
Inaccessible Snubbers - As Left (4)
Procedure numbers 1-PT-39B-2 and 2-PT-39B-2, Visual Inspection -
Inaccessible Snubbers - As Found (5)
Procedure numbers 1-PT-39.3 and 2-PT-39.3, Mechanical Snubbers -
Functional Testing
(6)
Procedure numbers 1-PT-39.4 and 2-PT-39.4, Snubber Functional Test (7)
Procedure number PT-39.5, Snubber Surveillance Program Update (8)
Procedure numbers l~PT-39.6 and 2-PT-39.6, Large Bore Snubbers Functional Test (9)
P~ocedure number O-MPT-PR-001, Snubber Selection for Functional Testing (10)
Administrative Procedure SUADM-M-34, Snubber Surveillance and Testin Inspection of Snubbers and Pipe Supports The inspector performed a walkdown inspection to examine selected mechanical and hydraulic snubbers installed on safety-related piping systems in the Units 1 and 2 safeguards buildings and in the Unit 2 containment buildin The piping systems included portions of the reactor coolant, main steam, auxiliary feedwater, main feedwater, and residual heat remova During the walkdown, the inspector verified that snubbers were not damaged, that attachment to the supporting structure and piping was secure, that the fluid level in the hydraulic snubber reservoirs was higher than target levels, and that leakage of the fluid was not occurrin During the wa lkdown inspection, the inspector also examined selected spring cans and rigid restraints installed on the safety-related piping systems listed above and verified that the supports were not damaged and that attachment to the piping and supporting structure was secur During the walkdown inspection in the Unit 2 containment building, the inspector accompanied licensee personnel and the NRC resident inspectors performing a containment closeout inspection (inspection performed by the licensee prior to startup after an outage).
The inspector noted that numerous grating clips had not been properly re-attached in some areas after performance of maintenanc The purpose of the clips is to secure the gratin Other housekeeping deficiencies were also identified by the Resident Inspectors. These problems were identified to licensee management and are documented in the Resident Inspectors' monthly reports, Rep_ort Nos. 50-280/91-14 and 50-281/91-1 * Review of Quality Records The inspector examined the following quality records:
(1)
Results of visual inspections performed on Unit 1 accessible and inaccessible snubbers in November, December 1990
..
(2)
Results of the visual inspection performed on Unit 2 accessible and inaccessible snubbers i~ April,* May 1991 (3)
Results of functional tests performed on Unit 1 snubbers in December 1990 and on Unit 2 snubbers in April, May 199 (4)
Calibration data for the Wyle Snubber Testing Machine, Model Number 100, Serial Number 104 (5)
Service life records for the seals installed in Units 1 and 2 hydraulic snubbers (6)
Engineering Work Request (EWR)90-351, Evaluation of visual inspections and functional tests performed on Unit 1 snubbers during the 1990 refueling outage (7)
EWR 91-056, Evaluation of visual inspection and functional test performed on Unit 2 snubbers during the spring 1991 refueling outage Within the areas inspected, violations or deviations were not identifie.
Action on Previous Inspection Findings (92701) (Closed) Inspector Follow-up Item 280/89-29-01, Reanalysis of Pipe Support to Account for Unsymmetric Members During review of Calculation Number 14937.53-NZ(B) -005-ZB -0.07, Revision 0, titled Re-analysis *of Support H-34, dated June 24, 1988, a regional based specialist inspector noted that the unsymmetrical members in the supports were not properly analyzed for the possible effect of loading-induced torsional stresse The licensee referred this concern to Stone and Webster engineers, who revised the ca lcul at ion to account for the effects of the unsymmetri c angle member The inspector reviewed the revised calculation, Number 14937.53-NZ(B) -005-ZB-007, Revision The stresses within the support members and the anchor bolt loadings were within design allowable value (Closed) Unresolved Item 280,281/89-29-02, Survey of Calculations of Supports with Unsymmetrical Member Due to the concern identified regarding failure to analyze support H-34 for effect of loading induced torsional stresses in unsymmetrical members, as discussed above, the regional specialist inspector requested that the licensee perform a survey of pipe support calculations to determine if other supports with unsymmetrical members had been properly analyze The inspector reviewed the results of the licensee 1s calculation survey conducted to resolve this concer The licensee selected a random sample of approximately 10 percent of all pipe supports and identified 173 supports with one or more non-symmetric member The calculations for these supports were reviewed to
determine if the effect of torsipnal stresses had been conservatively addressed in the design process.. As a *result of this review, 14 supports were identified which required additional calculation review to ascertain whether the supports met design requirement Addenda to the calculations were prepared to document this additional evaluatio The inspector reviewed the calculation addenda which showed that the stresses in the unsymmetri ca 1 members in these 14 supports were within design allowable value No pipe support modifi~ation were require Further discussions with licensee engineers disclosed that a similar concern was identified during the pipe support calculations performed to closeout IE Bulletin 79-14, in late 1979 or early 1980. A similar review was conducted at that time, although the results were not well documente The inspector also reviewed Virginia Power Civil Engineering Nuclear Standard STD-CEN-0018, Nuclear Pipe Support Standard, which addresses evaluation of unsymmetrical structural shapes in design of pipe support Based on review of the license's survey, the inspector concluded that the effect of torsional stresses in unsymmetrical members had been addressed in the design proces.
Exit Interview The inspection scope and results were summarized on May 31, 1991, with those persons indicated in paragraph The inspector described the areas inspected and discussed in detail the inspection result Proprietary information is not contained in this repor Dissenting comments were not received from the licensee.