IR 05000313/1986025
| ML20215E971 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/05/1986 |
| From: | Hunnicutt D, Greg Pick, Stewart R, Tapia J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20215E926 | List: |
| References | |
| 50-313-86-25, 50-368-86-26, NUDOCS 8610160037 | |
| Download: ML20215E971 (16) | |
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APPENDIX 8
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U.S. NUCl, EAR REGULATORY COMMISSION
REGION IV
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NRC Inspection Report:
50-313/86-25 Licen'ses:
OPR-51
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50-368/86-26 NPF-6 Dockets:
50-313 50-368 Licensee:
Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203'
Facility Name:
Arkansas Nuclear One, Units 1 and 2 Inspection At:
Russellville, Arkansas Inspection Conducted:
July 28 through August 1, 1986 f)/
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/hfo Inspectors:
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R. C. Stewar W Reactor Inspector, Operations Fate "
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Section, Reactor Safety Branch f
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- J. I. Tapia, Reactor Inspector, Operations D6te'
Section, Reactor Safety Branch
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7/8/ 84
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G. A. Pick, Reactor Engineer, Operations Dat(
Section, Reactor Safety Branch Approved:
k 9/f/T4 D. M. Hunnicutt, Chief, Operations Section Ddte '
Reactor Safety Branch
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8610160037 861006 PDR ADOCK 05000313
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J Inspection Summary
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Inspection Conducted During July 28 through August 1,1986 (Report 50-313/86-25;,
50-368/86-26)
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Areas Inspected:
Routine, unannounced inspection of the installation of an[
additional condensate storage tank, inservice inspection, local leak rate
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testing, and testing of pipe support and restraint systems.
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Results: Within the areas inspected, two violations were identified (failure
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to have QC coverage of contractors, paragraph 3a and failure to properly perform NRMCA checklist requirements, paragraph 2).
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s DETAILS
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1.
Persons Contacted
- E. C. Ewing, General Manager, Plant Support
- D. 'B. Lomax, Plant Licensing Supervisor
- S. M. Quennoz, General Manager, Plant Operations
- D. Howard, Special Projects Manager
- D. Horton, Quality Assurance Superintendent
- J. L. Taylor-Brown, Quality Control Superintendent
- C. Bean, Quality Control Supervisor
- J. Orlicek, Field Engineering Supervisor
- R. Lane, Manager, Engineering
- L. A. Taylor, Plant Licensing
- M. Durst, Project Engineering Superintendent
- A. B. McGregor, Engineering Services Supervisor D. Payne, Inservice Inspection (ISI) Coordinator R. West, Instruinent and Control (I&C) Superintendent J. R. Roberson, I&C Supervisor J. Sechrest, I&C Technician E. Lewis, I&C Technician B. Hillis, I&C Leak Rate Coordinator M. Browning, Mechanical Snubber Testing Coordinator
- Attended exit interview on August 1, 1986.
2.
Followup on Previously Identified Items (Units 1 and 2)
(Closed) Open Item upgraded to violation - see Appendix A (313/8615-02; 368/8615-02):
Documented evidence was not available to demonstrate that concrete batch plant water meter was within acceptance tolerances specified by National Ready Mixed Concrete Association (NRMCA), checklist Item 2.5.3.
During this inspection, the inspectors were provided a copy of an Arkansas Bureau of Standards Test Report reflecting that the meter was calibrated June 6, 1986, and was within NRMCA acceptance criterion of 11.5 percent.
During this inspection, this item was upgraded to a Category V Violation; however, since corrective measures were initiated prior to placing
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i Category I structural concrete and the NRC inspector verified corrective measures, no response is deemed necessary (see Appendix A this report).
(Closed) Open Item upgraded to Violation - see Appendix A (313/8615-03;
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368/8615-03):
Batch plant NRMCA certification agreement by plant
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superintendent to perform 90-day required checks had not been performed since November 11, 1985.
In conjunction with the batch plant conversion from a manual operation to a computerized system, all volumetric dispensers and scales were recalibrated and found to be within prescribed
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tolerances.
In addition, random documented checks are to be done by Anderson Engineering & Test Company to verify the 90-day interval checks are being performed by the Ready Mixed Concrete Company.
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(Closed) Open Item upgraded to violation - see Appendix A (313/8615-04; 368/8615-04):
Failure of material testing service contractor to provide inspection reports to AP&L (per AP&L Specification APL-C-2401, Section 9.1.1).
The NRC inspectors verified that, as of June 2, 1986, inspections of the batch plant activities conducted by Anderson Engineering were being documented and submitted to AP&L.
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(Closed) Open Item upgraded to violation - see Appendix A (313/8615-05; 368/8615-05):
Failure to provide documented evidence of truck mixer uniformity tests and blade inspections.
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During this inspection, the licensee representative provided the NRC inspector w.th copies of Anderson Engineering inspection records, dated June 2, 1986, which reflected that all delivery mixer trucks (six) had been examined in accordance with NRMCA requirements.
In addition, results of the truck mounted water tank sight gauge calibrations were recorded on the inspection documents.
(Closed) Open Item upgraded to a Violation - see Appendix A (313/8615-06; 368/8615-06):
Concrete delivery mixer truck water tank sight gauges were not calibrated prior to use.
(See Open Item 313/8615-05; 368/8615-05 above.)
3.
Followup Inspection - Condensate Storage Tank Addition - DCP-82-2086 (Units 1 and 2)
During this inspection, the inspectors conducted a followup review of activities associated with the facility modification (DCP-82-2086)
involving installation of an additional 321,000 gallon condensate storage tank (T-418) and associated piping and components. Areas reviewed during the inspection were limited to a followup review of previously identified unresolved items (see paragraph 2 above); review of the disposition of six nonconformance reports issued by the licensee during concrete prior installations; concrete Batch Plant walk-down; a review of Chicago Bridge and Iron (CB&I) procedures; and the review of QC inspection weld records related to condensate storage tank piping tie-ins.
During the inspection, the principle contractor continued installation of the concrete pipe trenches, pipe supports and piping; however, no Class 3 pipe welding was in progress.
In addition, the tank fabricator, C8&I started installation of the tank bottom and side plates.
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a.
Review of Licensee's Nonconformance Reports During the inspection, the NRC inspector reviewed the evaluations and dispositions of six nonconformance reports (NCR) initiated during concrete pier placements.
The following NCR's were reviewed:
Report Date Subject NCR 86-010-1 March 31, 1986 (excessive mixing time and entrained air)
NCR 86-011-1 February 21, 1986 (excessive slump)
NCR 86-013-1 February 26, 1986 (bottom pier " bulb" 39\\" versus 42")
NCR 86-014-1 March 4, 1986 (excessive slump)
NCR 86-017-1 March 31, 1986 (excessive entrained air)
NCR 86-015-1 May 30, 1986 (reinforce steel discrepancy)
During the review, the NRC inspector observed that the evaluations and corrective actions required appeared to be technically correct and the reviews and approvals were in accordance with AN0 procedural requirements.
- No violations or deviations were identified.
b.
Batch Plant Walk-Down During the inspection, the inspectors conducted a walk-down of the licensee's concrete supplier facility in Russellville, Arkansas, in order to confirm corrective actions taken in response to previously identified unresolved issues (see paragraph 2).
The inspectors observed that equipment calibration certifications were clearly visible on scales, water meters, and admixture dispensers.
In addition, aggregate stock piles.were being wetted and properly controlled.
It was also noted that the newly installed computerized operational system was demonstrating consistency in concrete batch production.
No violations or deviations were identified.
c.
Document Review - NDE Records In conjunction with DCP-82-2086 facility modification review, the NRC inspector examined portions of the licensee's QC inspection records relative to newly installed ASME,Section III, Class 3, condensate
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tie-in piping and supports in the Unit 2 auxiliary building, and nondestructive examination requirements in accordance with ASME code,Section XI.
Welding checklists and work travelers included the following:
150 DWG 2HCC-286-6, field welds, 1 through 7 ISO DWG 2HCC-282-2, field welds, 1 through 14 Auxiliary building pipe supports:
DWG 2HCC-282-H37, field welds, 1 through 12 DWG 2HCC-282-H38, field welds, 1 through 12 DWG 2HCC-282-H1, field welds, 1 through 8 No violations or deviations were identified.
d.
Condensate Storage Tank Procedure Review The NRC inspectors reviewed the following Chicago Bridge and Iron (CB&I) procedures for the installation and examination of the AP&L Condensate Storage Tank for Units 1 and 2 (T41-B):
Procedure Date Title Number Revision Approved Field Cleaning Procedure CPIN-0 03/17/86 Class 3 Stainless Steel Tank
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Plate Cleanup Procedure Nuclear CUP-1
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Products Dimensional Control Procedure DCI
03/17/86 General Repair Procedure for GR17
06/27/85 Materials and Welds Class 2 and 3 Products General Welding Procedure GWPS-GTAW
12/26/85 Specification for the Gas Tungsten Arc Process Liquid Penetration Examination PT10X
03/17/86 Procedure - Class 3 Products Liquid Penetration Examination PT11X
03/17/86 Procedure - Class 3 Products
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Spot Radiographic Examination RT3
05/19/86w Procedure for Welds. Class 3 s
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vessels or storage tanks
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Radiographic Examination RT9X
12/21/85 Procedure for Piping Welds Class 3 Piping Packing, Shipping, Site Storage SH9
' 5 06/29/85 Procedure of Nuclear Product Items i
Welding Procedure Application WPAT
12/26/85 Table 42' x 32' high DRT Condensate Storage Tank AP&L Welding Procedure E3081/853600
06/17/85 Specification Vacuum Box Test Procedure VB3
12/26/85 Nuclear Products Visual Examination Procedure VT7
03/17/86 Class 2 and 3 Atmospheric Storage Tanks ASME B&PV Code 1980 edition,Section III, Division 1 (subsection ND)
and Section IX summer 1982 addenda No deviations or violations were identified.
4.
Inservice Inspection a.
Program Review During this inspection, the NRC inspectors reviewed AP&L Procedure 1032.07, Revision 4, ISI Program Requirements and discussed the ISI program with the ISI coordinator.
The NRC inspectors verified that the IEI program plan had been reviewed and approved by the onsite safety review committee and the Authorized Nuclear Inservice Inspector (ANII). The licensees' ISI program plan met the requirements of the American Society of Mechanical Engineers (ASME)
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' Boiler and Pressure Vessel Code,Section XI, 1974 Edition and Addenda through Summer 1975.
The ISI program procedure defined the authorities and l
responsibilities of the personnel involved with the final evaluation and acceptance of ISI results.
This procedure also had provisions for the type of ISI records to be maintained and how these records were to be maintained.
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The NRC inspectors reviewed the contractors quality assurance (QA)
program as specified in Procedure 00000-ESS-155, Revision 4, Quality Assurance Program for_ Service Activities, dated October 22, 1982.
AP&L quality assurance audited the contractor's: procedures,QA plan, qualifications of personnel, and equipment to assure they conform with ANO requirements. The process concerned with corrective actions, of ISI indications was controlled by the same procedures as other job orders dealing with corrective actions.
The NRC inspectors were not presented documented evidence that demonstrated ANO Quality Control (QC) had performed surveillance and/or inspected Combustion Engineering (CE) employees during the conduct of ISI activities. ANO QC was required to provide inspection and/or surveillance of contractor work activities as stated in ANO Procedure 1000.12, Revision 7, " Control of Site Contractors,"
paragraph 6.6.15.
ANO Quality Assurance Procedure QAP-7, Revision 1
"SiteContractorControl," paragraph 5.7.2(d),includedaquestion concerning ANO QC monitoring of site contractor activities in accordance with Procedure 1000.12.
Section 9.5 of the AP&L Quality Assurance Manual Operations requires that the " Performance of special processes in accordance with codes, standards, specifications, and plant procedures is verified by Quality Control personnel through their surveillances and inspection activities...."
10 CFR 50, Appendix B, Criterion IX, requires, in part, that
" measures shall be established to assure that special processes, including nondestructive testing, are controlled and accomplished in accordance with applicable codes, specifications, and criteria (i.e.,
procedures)."
Contrary to the above, the licensee representative stated that although surveillances were conducted during other contractor ISI activities, ANO QC failed to provide inspection and/or surveillance of CE activities as required by ANO procedures.
This is a violation.
(368/8626-02)
b.
Revi;w of Procedures AP&L had contracted CE to conduct the ISI work on ANO Unit 2.
The inspectors reviewed CE's procedures concerned with the various forms of nondestructive examination (NDE), the qualifications of the personnel assigned to ISI activities, and the certification sheets for the materials and equipment utilized by CE.
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The procedures listed below met the requirements of ASME Section XI:
00000-ISI-029, Revision 5,." Generic Manual Ultrasonic Examination Procedure," dated March 21, 1986 00000-ESS-066, Revision 7, " Visual Examination. Procedure for Preservice and Inservice Inspection," dated October 21, 1981~
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~ 4678-ESS-093, Revision 1, " Liquid Penetrant Examination Procedure -
for Preservice and Inservice Inspection," dated June 28, 1982 4678-ISI-058, Revision 0, " Magnetic Particle Examination Procedure,"
dated August 11, 1982 The NRC inspectors reviewed the certification sheets of the' examiners
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and verified that they were in accordance with'the requirements of SNT-TC-1A-1975.
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The certification sheets for equipment and materials were reviewed.
The NRC inspectors verified each piece of equipment had a unique serial number and all material was appropriately certified.
No violations or deviations were identified.
c.
Data Review and Evaluation The NRC inspectors reviewed selected records of NDE examinations related to ISI activities.
The records selected contained and/or referenced information concerning examination results and data sheets, equipment serial numbers and calibration data, evaluation criteria, extent of the examination including justification for deviations from the planned activity, records on disposition of findings, re-examination data after repair work, and identification of materials used.
During review of the ISI records and one repair activity, the NRC inspector verified that:
the examination methods, extent, and technique complied with the licensee's ISI program; examination data were within ASME code requirements; the methods of NDE utilized were sufficient to determine the acceptability indications, if identified; and guidance was in place for comparison of ISI data with baseline data.
A repair package was generated to repair a weld on rigid hanger 2DBB-1-H5 on the loop 1 main feedwater pump (the weld identifier was62-009).
Job order 715959 requested a weld package and ASME Section XI documentation for repair of the weld after an ISI surface examination was conducted.
Engineering generated Plant Engineering Action Request (PEAR) 86-2596 to repair the weld; however, further anclysis determined sufficient weld metal remained
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and the repair procedure was not utilized.
After grinding, subsequent NDE re-examination revealed no defects.
The NRC inspector reviewed the following welds in Class 1 and Class 2 systems:
Weld Identifier Type of Weld Location 07-005 Pipe to Ell Circ Weld S/G #2 Hot Leg to Rx Vessel 09-011 Safety Injection Nozzle Pump '1A' Cold Leg to Rx to Pipe Vessel 09-012 3" Spray Nozzle to Pipe Pump '1A' Cold Leg to Rx Vessel 13-005 Pipe Long Seam - R Side Pump '2A' to Rx Vessel Cold Leg 13-007 Pipe Long Seam - L Side Pump '2A' to Rx Vessel Cold Leg 15-009 Safe End to Pump '2B' Circ Pump '28' to Rx Vessel Weld Cold Leg 20-002 Nozzle Extension to Reducer Main Steam Loop 2 Circ Weld 38-001 Nozzle to Safe End Circ Loop '2A' - Cold Leg Weld Drain 51-004 Ell to Pipe Circ Weld Shutdown Cooling & 'A'
LPSI Pump Suction 51-004 AB Ell Long Seam Welds Shutdown Cooling & 'A'
LPSI Pump Suction 58-002 Ell to Pipe Circ Weld Shutdown Cooling Ht Exch
"B" Inlet
'58-002 AB E11 Long Seam Welds Shutdown Cooling Ht Exch
"B" Inlet 62-003 Pipe to Ell Circ Weld Main FW Loop 1 The above welds were examined by ultrasonic testing (UT) utilizing other UT procedures in addition to the one specifically reviewed by the inspecto o,
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In addition to the welds' listed,-the inspector reviewed data sheets from magnetic particle (MP) and visual NDE examinations.
No violations or deviations were identified.
d.
Ultransonic Test Procedure Review The NRC inspectors reviewed the following ANO-2 Inservice Inspection Procedures that were used by NDE personnel during the current ANO-2 refueling outage (designated as refueling outage 2RS):
Procedure No.
Revision Subject
'4678-ISI-005
Reactor Vessel Flange Ligament Areas 4678-ISI-010
Closure Head Studs and Nuts 4678-ISI-013
Pressurizer to Nozzle Welds 4678-ISI-014
Pressurizer Surge, Spray and Safety Nozzle Inner Radius Areas 4678-ISI-019
For Class I and II Austenitic Piping 4678-ISI-024
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STD-ISI-007
UT Instrument Linearity NQAI 2.4
NDE Personnel Certification No deviations or violations were identified.-
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Ultrasonic Testing Calibration Data Sheets
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The NRC inspector. reviewed the following UT calibration data sheets:
Calibration Component or Subject
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Inspected by UT i
UT-20 Reactor Pressure Vessel Nuts UT-29-71 Reactor Pressure Vessel Studs and
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UT-29-58 (total of 22 UT'd)
UT-29-12 Cold Leg Pump 1A to Reactor Vessel and UT-14 (Zone 9)
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UT-5
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UT-51 Main Steam Loop 2 (Zone.20) (Class 2)
UT-31 Safety Injection Loop 1A
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UT-FWC Four Reactor Coolant Pump Flywheels - one surface and keyways.
No MP.
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No deviations or violations were identified.
5.
Containment Local Leak Rate Testing-Implementation of the ongoing containment-local leak rate test (LLRT)
program was-addressed during this inspection.
The inspection involved procedure and records review, test witnessing and-independent calculations by the NRC inspector.
a.
Procedure Review The NRC inspector reviewed Instrumentation & Control (I&C) Test Procedure No. 2304.15, " Local Leak Rate Testing," Revision 9, and I&C Test Procedure No. 2304.22, "Ruactor Building Access and Ventilation Leak Rate Testing," Revision 2.
This review determined that the procedures provided guidelines for testing the reactor containment penetrations and isolation valves.
These procedures were reviewed by the NRC inspectors to verify compliance with the specified test requirements and acceptance criteria contained in 10 CFR Part 50, Appendix J, " Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors," and in Section 3/4.6.1 of the plant Technical Specifications.
The review provided verification that the following test attributes were correctly addressed:
(1) All applicable penetration boundaries and isolation valves were subjected to local leak rate testing.
(2) Local leak rate tests were performed at peak accident pressure.
(3) The local leak rate test program utilized an approved method for testing.
(4) Penetration leakage rates were determined using the maximum pathway leakage.
(5) Criteria and response were specified for local leak rate test and combined leakage rate failure.
(6) Criteria and response were specified for the failure of corrponents specifically cited in the Technical Specifications.
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The reviewed procedures were found to include provisions for the~
determination of the as-found leakage. Thexas-found condition of the containment boundary was the condition at the beginning of.the outage and prior to any repairs or adjustments to any containment penetration or isolation valve.
During the last periodic containment overall integrated leakage rate test (April 1985), the NRC inspector identified an unresolved item (368/8515-01).
This unresolved item dealt with the identification of the as-found leakage of two Target Rock valves and the failure to include this leakage as a penalty to the Type A test results. The review performed during this inspection partially addressed the unresolved item in that the generic requirements for the identification of as-found leakage were confirmed.
Nevertheless, the unresolved item remains open pending review of the specific actions taken by the licensee in response to the unresolved item.
b.
Instrumentation The instrument calibration certifications traceable to the U.S.
National Bureau of Standards for the Wallace & Tiernan Absolute Pressure Gauges used in the local leak rate testing program were reviewed by the NRC inspector.
A review of the calibration data sheets disclosed that test gauge No. TG-097 was found to be out-of-calibration, although the instrument was subsequently utilized in local leak rate testing.
The NRC inspector verified that an
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evaluation was made and documented to determine the validity of test results associated with the use of equipment found to be out of calibration.
The test gauge'in question was found to be out of calibration only below 30 psia, and therefore, acceptable for use at the test pressure of 70 psia.
The methods and requirements for reviewing out-of-calibration reports are delineated in I&C Administrative Procedure No. 1035.05, "M&TE Calibration and Repair,"
Revision 5.
This procedure was reviewed by the NRC inspector along with Procedure No. 1303.39, " Test Gauge Calibration," Revision 5.
The NRC inspector's review verified that an effective and operational system for the control, maintenance, and calibration of measuring and test equipment was in place and that it provided an effective notification mechanism that assured review by the responsible personnel when test equipment was found to be out-of-calibration.
c.
Test Witnessing The NRC inspector observed the performance of a local leak rate test to determine if the licensee was properly complying with regulatory and procedural commitments.
Job order No. 716863 involved verifying the as-left condition of valve No. 2SA-69 at containment penetration No. 2P43.
Valve No. 2SA-69 is the check valve for the 3-inch diameter service air to containment building line at elevation 357 fee,.
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The test method was the pressure decay method which involved pressurization to 70 psia with subsequent readings of pressure at 5-minute intervals for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or until no pressure change for 15 minutes had been verified.
The result of the observed test disclosed a leak rate of 786 cc/ min.
The acceptance limit was 100 cc/ min.
Since this valve had been repaired prior to this' test, the NRC inspector requested information regarding the licensee's evaluation of the adequacy of the repair.
The information'was not reviewed by the NRC inspector during this inspection, but will be reviewed during a subsequent inspection in conjunction with a previously identified unresolved item.
(368/8515-02)
d.
Test Results The continuous running sum of local-leak rates for all penetrations and isolation valves required to be subjected to local leakage rate testing is required by 10 CFR Part 50 Appendix J to be less than 0.60 La, where La is the maximum allowable leakage rate at the calculated peak containment internal pressure related to the design basis loss of coolant accident (Pa). With an La value of 0.1 percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by weight at 54 psig, 0.6 La equates to 20,990 cc/ min.
The method used to obtain the continuous running sum of local leak rates is to add the new test results and subtract the previous results for the same penetrations and isolation valves tested to the combined local leak rate sum.
The NRC inspector reviewed the local leak rate data sheets to determine if the sum of the local leak rates for all boundaries and valves subject to local leak rate testing met the acceptance criteria. With the exception of the equipment and personnel hatches, the summation of the leakage rates during this outage amounted to 6,937 cc/ min, this value was about 40 percent of the acceptance criteria.
The value reported for 1985 was 16,219 cc/ min, but this value remains the subject of a previously reported unresolved item (368/8515-02).
This unresolved item will be addressed during the next review of the overall integrated leakage rate test.
6.
Testing Piping Support and Restraint Systems The periodic ISI requirements for piping support and restraint systems were addressed during this inspection.
The requirements for the conduct of the inspections are mandated by 10 CFR Part 50.55a and by ANO Unit 2 Technical Specifications in order to identify, evaluate, and correct service induced deficiencies.
The NRC inspector's review covered both pipe support and mechanical snubber testing as described below:
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a.
Pipe Support Inspection The licensee's periodic pipe support inspection program was addressed in Procedure No. 1032.07, "ISI Program Requirements," Revision 4, which was revieved by the NRC inspectors.
This procedure referen'ced the requirements of Section XI of the ASME Boiler and Pressure Vessel Code.
The applicable edition of the ASME Code is the 1974 Edition through Summer of 1975 addenda.
The 1974 Edition of Section XI refers its users to Section III for evaluation criteria and acceptance standards.
Visual and surface examination criteria are not available in the referenced ASME Code,Section III, but rather are contained in Combustion Engineering Procedure No. 00000-ESS-066,
" Visual Examination Procedure for Preservice and Inservice Inspection," Revision 7.
From the ISI program plan and schedule, ten supports were randomly selected for review by the NRC inspector.
The Combustion Engineering support member visual examination reports were obtained and reviewed by the NRC inspector to verify that the results were within the established acceptance criteria.
b.
Mechanical Snubber Testing The licensee's ongoing snubber inspection program was reviewed by the NRC inspector for compliance with Section 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS) of the ANO Unit 2 Technical Specifications.
Snubbers are shock arresters used to protect piping and equipment from seismic or flow induced forces while allowing normal thermal movements.
Procedure No. 1306.23, " Snubber Functional Testing Per VT-4,"
Revision 0, was reviewed by the NRC inspector and found to correctly address the following test attributes:
(1) The force that initiates free movement of the snubber rod in either tension or compression was required to be less than the specified maximum drag force.
(2) The force to initiate or maintain motion of the snubber was within the specified range in both directions.
(3) Snubber activation or restraining rate was within the specified range of compression or tension.
(4) Snubber bleed or release rate was'within the specified_ range of compression or tension.
(5)
If a snubber fails during testing, the cause was evaluated and reported.
(6) The number of units tested was in accordance with the ANO Unit 2 Technical Specifications.
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11 6 The NRC inspector randomly' selected six " Mechanical Snubber Breakaway
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Drag Test Results" reports for review.. The overall testing program results were discussed with-the responsible licensee engineer.
During this discussion,-the NRC inspector determined the number of snubbers which are found to be either operable, degraded, lor failed.'
The NRC inspector also verified that all snubber failures were
. required to be identified to the piping analysis group for their evaluation of the potential detrimental impact on the piping-analysis.
No violations or deviations were identified.
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7.
Exit Interview.
The NRC. inspectors met with the licensee representatives denoted in paragraph 1 and Mr. W. D. Johnson, NRC Senior ResidentLInspector,lon August 1, 1986, and summarized the scope and findings of the inspectien.
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