IR 05000281/1979079
| ML18136A332 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/07/1979 |
| From: | Brooks E, Burnett P, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18136A331 | List: |
| References | |
| 50-281-79-79, NUDOCS 7912310353 | |
| Download: ML18136A332 (4) | |
Text
Report N Licensee:
Facility:
Docket N License N /79-79 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Virginia Electric Power C P. 0. Box 26666 Richmond, Virginia 23261 Surry Power Station, Unit 2 50-281 DPR-37 Inspection at Surry Site near Williamsburg, Virginia Inspectors: LJ=/.d,,.1 £,*~!*of" &_,)~< -;t;t c. r H.' L. Whitener'
P?i?crg~
E. H: Brooks Approved by:~'2uCC~-
P. T~ Burnett,. Acting Section Chief, RONS Branch SUMMARY Inspection on October 15-19, 1979 Areas Inspected:
11 /1 /zr Datk Signed D~!J7s~Zel 11-ha Date Signed This announced inspection involved 58 inspector hours onsite in the areas of containment leakage rate testing and pipe support and restraint system Results:
Of the areas inspected, no apparent items of noncompliance or deviations were identifie <912310
,* Persons Contacted Licensee Employees
- W. Stewart, Plant Manager DETAILS R. Blount, Test Coordinator (CILRT)
M. Kansler, Associate Engineer Other licensee employees contacted included two operator NRC Resident Inspector
- D. Burke
- Attended exit interview Exit Interview The inspection scope and findings were summarized on October 19, 1979, with those persons indicated in Paragraph 1 abov.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inspectio.
Containment Leakage Rate Testing The following procedures relating to leakage rate testing were provided by the licensee and were reviewed by the inspectors:
16.1 - Containment Leak Monitoring System 16.2 - Containment Penetration Local Leakage 16.3 - Containment Leakage Rate (Class A Test at 39.2 PSl~)
16.4 - Containment Isolation Valve Leakage 16.S - Containment Personnel Air Lock Test 16.6 - Equipment Hatch Leak Test 16.7 - "After Opening" Personnel Airlock Test
~
-2-Procedure 16.1, Containment Leak Monitoring System, is used in conjunction with containment leakage rate testing utilizing the reference_vessel syste This system of testing was used initially at Surry*Power Station, but will be replaced with the absolute method and accordingly Procedure 16.1 will be eliminate Procedure 16.3, Containment Leak Rate (Class A Test at 39.2 PSIG), is in
,
the process of revisio This procedure will be submitted to Region II for review prior to initiation of containment leakage rate testing which is tentatively scheduled for December 14, 197 Proposed changes to appendix J to 10 CFR 50 that are presently under con-
. sideration by NRR were discussed with the license Those changes which appear to be immediately pertinent to the Surry Plant are: Personnel airlock testin.
Definition of integrat.ed*Leakage Rate Test (I.L.R.T.) failur.
Venting and draining requirement.
Hydrostatic testing of isolation valves. Administrative control and periodic surveillance over test, vent and drain (TVD) connection The purpose of the discussion was to alert the licensee to potential areas of concern so that leakage rate testing, both integrated and local, will be conducted within the intent of the proposed changes to appendix J. The licensee indicated that no problems were anticipated in meeting appendix J or the' intent of the proposed changes as discusse By the letter of September 22, 1978, the licensee submitted to NRR a proposed change to technical specifications which would permit airlock testing every 4 months instead of after each opening as required by appendix J. The proposed change was not approved by NRR. However, the NRR position which provides an alternate method of testing airlock door seals within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the first series of openings was transmitted to the licensee by NRR on November 29, 197 The licensee advised the inspectors that airlock door seals will be tested in accordance with the NRR position to meet the intent of appendix During the period of this inspection, the licensee had completed approxi-mately 50% of Unit 2 containment isolation valve (Type C) leakage rate tests as schedule No testing was being conducted during the inspectors visi The results of previous isolation valve tests were reviewed along with preliminary review of schematics and drawings depicting containment isolation valve lineu Due to the complexity involved, a more detailed review of the Surry Power Station isolation valve testing procedure will be conducted to provide assurance that all valvesthat constitute containment boundary are tested in accordance with the requirements of appendix * *
-3-Hydraulic Snubber Functional Tests Due to a 50% failure rate the licensee functionally tested all snubbers in Unit 2 which are subject to the technical specification functional test surveillance requirement (,000 pound design load or less).
Review of these data show that 61 of the 65 failures were due to lock up or bleed velocities which were less than the procedure minimum velocity requiremen '
'
Two snubbers failed on high bleed velocity and two appeared to be in lock-up as foun All snubbers were reset within the procedure vel~city specifica-tion The licensee said that the snubber problem in Unit 2 appears to be the same as that identified in Unit Specifically, the licensee believes that either a velocity set point drift is occurring or a test machine problem is yielding inconsistent velocity reading Investigation of the cause of failure is in progress.