IR 05000280/1985039
| ML18149A049 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/07/1986 |
| From: | Jape F, Larry Nicholson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18149A048 | List: |
| References | |
| 50-280-85-39, 50-281-85-39, IEB-78-10, NUDOCS 8602180289 | |
| Download: ML18149A049 (4) | |
Text
Report Nos.:
50-280/85-39 and 50-281/85-39 Licensee:
Virginia Electric and Power Company Richmond, VA 23261 Docket Nos.:
50-280 and 50-281 License Nos.:
DPR-32 and DPR-37 Facility Name:
Surry 1 and 2 Inspection Conducted:
December 30, 1985 - January 3, 1986 Inspector: <~ ~
L. Nie son
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Approved by:
~~
F. Jape, Section Chief, Test Engineering Branch Division of Reactor Safety SUMMARY
'ofu Signed ol/7/?6 Date Signed Scope:
This routine, unannounced inspection entailed 27 inspector-hours on site in the areas of maintenance and survei 11 a nee testing of the pressurizer code safety valves and the main steam code safety valve Results:
No violations or deviations were identifie PDR ADOCK 05000280 G
PD r REPORT DETAILS Persons Contacted Licensee Employees
- R. F. Saunders, Station Manager E. Brennan, Supv. Mechanical Maintenance J. Patrick, Supt. of Maintenance R. Blount, Performance Engineering Sup *D. L. Benson, Assistant Station Manager
- H. L. Miller, Assistant Station Manager
- E. S. Grecheck, Supt, of Tech. Services
- W. D. Craft, Licensing Coordinator Other licensee employees contacted included engineers, technicians, operators, mechanics, and office personne NRC Resident Inspectors
- D. Burke, Senior Resident Inspector M. Davis, Resident Inspector
- Attended exit interview Exit Interview The inspection scope and findings were summarized on January 3, 1986, with those persons indicated in paragraph abov The inspector destribed the areas inspected and discussed in detail the inspection findings listed belo No dissenting comments were received from the license Unreso 1 ved I tern 280, 281/85-39-01, Determine Temperature Comp en sat ion Required for Set Point Testing of Pressurizer Safety Valves, paragraph The 1 ack of temperature compensation during pressurizer safety va 1 ve set point testing was questioned by the inspector, yet appeared to be in accordance with the valve manufacturer 1 s instructio Subsequent research and review by Region II indicates an unresolved item does exist as discussed in a January 8, 1986 telephone conversation between the inspector and plant managemen See paragraph 5 for detail The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio ' -*
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2 Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or deviation One new unresolved item identified during this inspection is discussed in paragraph.
Surveillance Testing of Pressurizer Safety Valves (61701) The inspector examined periodic test number 1-PT-12, Pressurizer Safety Valve Setpoin This procedure was developed from Crosby Valve & Gage Company Instruction No. I-1105-2 to verify the setpoint of the pressurizer safety valves, SV-1551A, SV-15518, and SV-1551C as required by Technical Specification Table 4.1-2A, Item The valves are tested by nitrogen actuation at ambient temperature on a test bench inside the containmen The inspector verified test prerequisites were specified, test instructions and objectives were clearly stated, and the correct acceptance criteria were specifie A valve is considered acceptable with one actuation within +/-1%
of setpoint in either the as-found test or following adjustmen A review of test results obtained since 1980 revealed no significant problems, although the small capacity of the test rig prevented obtaining an as-found setpoi nt in severa 1 cases where seat 1 eakage was presen The 1 i cen see indicated that consideration is being given to increasing the capacity of the test ri Although the inspector considers the test method used to be acceptable, one area of concern was the possible influence of ambient temperature on valve setpoin Electric Power Research Institute (EPRI)
Report NP-4235, Set-Point Testing of Safety Valve Using Alternate Test Methods, indicated that ambient temperature is a significant setpoint influencing parameter for actual installations. This finding is consistent with results obtained at both the va 1 ve manufacturer and severa 1 va 1 ve testing 1 aboratori e The influence of ambient testing does not appear to be constant with each valve, yet the findings indicate there i~ a consistent downward setpoint drift ~ith an increase in medium temperatur This would result in a lower actual setpoi nt at norma 1 operating temperature Further discussion of this matter was held with the licensee by telephone on January 8, 198 The licensee agreed to review this finding as a possible cause of past valve weepag This item is identified as Unresolved Item 280,281/85-39-0 Within the areas examined, no violations or deviations were identifie Surveillance Testing of Main Steam Safety Valves (61701)
The inspector examined periodic test number 1-PT-13.1, 11A 11 Main Steam Safety Valve Setpoin This procedure verifies the setpoint of the main steam safety valves on 11A11 steam generator as required by Technical Specification Table 4.1-2A, Item Valves are tested in place using a hydraulic assist devic The inspector verified test prerequisites were specified, test
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instructions and objectives were clearly stated, and the correct acceptance criteria specifie The valve is considered acceptable if the initial as-found actuation is within +/-1% of the required setpoin If the valve requires adjustment, however, two consecutive satisfactory tests are re qui re A review of past data verified the survei 11 ance test was performed within the required time frequency with no abnormal result Within the areas examined, no violations or deviations were identifie.
Followup of Inspector Identified Items (92701)
(Closed) IFI 281/83-30-02, Rod Drop Time Test Procedures Discrepancie The periodic test procedure PT-7 has been completely rewritten to correct the noted discrepancie Based on a review of the revised procedure, this item is considered close.
Followup on IE Bulletins (92703)
(Closed)
IE Bull et in 78-10 Bergen-Paterson Hydraulic Shock Suppressor Accumulator Spring Coils - Unit 2 The licensee submitted its response to IEB 78-10 for Surry Unit 2 to NRC Region II in letters dated August 17, and August 30, 197 These letters stated that B-P snubbers would be inspected at the next scheduled refueling outage to determine if these snubbers had corrosion suscept i b 1 e type accumulator springs and summarized the number and location of B-P snubbers installed in Unit Design Change Package (DCP) 85-05 has been completed for Unit 2, resulting in the permanent removal of six of the snubbers, and replacement of the other six with newer model snubber Based on review of the completed DCP 85-05, this item is considered close.
Review of 10 CFR 50 Appendix J 90 Day Report - Unit 2 (90712)
The licensee's 90 day report verified the preliminary data reviewed in inspection report 85-2 The measured leakage rates for the type A test and the as-found containment conditions were within the plant's maximum allowable leakage rat In addition, the 95% upper confidence limit for both the total time method and mass point were below.75L This test is considered a successful test.