IR 05000280/1988019
| ML18152B031 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/28/1988 |
| From: | Jape F, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18152B030 | List: |
| References | |
| 50-280-88-19, 50-281-88-19, NUDOCS 8807120300 | |
| Download: ML18152B031 (8) | |
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,.q L:~ii"T,.\\, GEORGIP. '.'.0:,23 Report Nos.:
50-280/88-19 and 50-281/88-19 Licensee:
Virginia Electric and Power Company Richmond, VA 23261 Docket Nos.:
50-280 and 50-281 Facility Name:
Surry 1 and 2 Inspection Conducted:
May 16-20, 1988 License Nos.: DPR-32 and DPR-37 nspector:
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A. ~i ten er, Team Leader Team Members J. Zeiler B. 8. Desai Approved by:W*~f(j"
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. Test Programs Section Division of Reactor Safety SUMMARY 1.; ~zL.f I rg Dae Signed Date Signed Scope:
This routine, unannounced inspection was in the areas of local leak rate testing and containment integrit Results:
In the areas inspected, no violations or deviations were identifie One unresolved item was identified involving determining the 11as-found" containment 1 eak rate re 1 at i ve to repair of secondary sys tern leakage, paragraph 3.c.
80"701 8807120300 i5000280 PDR ADOC~
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REPORT DETAILS Persons Contacted Licensee Employees
- D. L. Benson, Station Manager
- R. H. Blount, Superintendent, Technical Services
- E. S. Grecheck, Assistant Station Manager (NS&L)
J. W. Henderson, Surveillance and Test Engineer, Technical Services
- G. D. Miller, Licensing Coordinator
- H. L. Miller, Assistant Station Manager (O&M)
- K. Sloane, Operations Shift Supervisor D. Valdivieso, Senior Engineering Technician, ISI, Technical Services Other licensee employees contacted during this inspection included records personne NRC Resident Inspector
- W. E. Holland, Senior Resident Inspector
- Attended exit interview Purpose The purpose of this inspection was to verify the development and imple-mentation of programs, controls, procedures, and test activities which ensure that containment integrity is established, monitored and maintained consistent with the requirements of the Technical Specifications and Code of Federal Regulation.
Local Leak Rate Testing An important part of monitoring and maintaining containment integrity is the periodic testing performed to verify the leak tightness of containment leakage barrier The inspector reviewed the formal procedures estab-lished by the licensee to verify local leak tightness of leakage barrier Documents reviewed either totally or in part included: l-PT-16.2, 2/19/82, Electrical Penetration Local Leakage l-PT-16.2A, 5/5/87, Conax Electrical Penetration Leakage l-PT-16.2B, 3/10/87, Westinghouse Electrical Penetration Leakage l-PT-16.3A, 9/16/86, Fuel Transfer Flange Local Leakage l-PT-16.3B, 6/27/87, Steam Generator Leakage Test l-PT-16.4, 4/8/88, Containment Isolati_on Valve Leakage (Type C tests)
- i. PT-16.5, 5/19/86, Containment Personnel Airlock Test (Full Pressure Test)
1-PT-16.6, 10/22/86, Equipment Hatch And Emergency Personnel Escape Hatch Leak Test 1-PT-16.7, 4/19/88, Personnel Airlock Leakage Test (Seal Test)
1-PT-16.11, 10/28/86, Containment Purge Leakage Test The above documents were reviewed in general for adequate instructions, control of test activity, appropriate test intervals, appropriate test parameters, approved test methods and adequate acceptance criteria. A 1 so a detailed walk-through was performed for local leak rate testing of three penetrations in Procedure PT-1 These penetrations were 28, Reactor Coo 1 ant Letdown; 53, Nitrogen to Pressurizer Re 1 i ef Tank; and 57 D, Aerated Drain Syste Partial review of other penetrations was also performed and no significant problems were identified relative to venting, draining, valve identification, valve alignment or system restoratio The inspectors further verified that valves requiring Type C testing in Technical Specification Table 3.8-1 are included in the test procedure A 1 though every procedure 1 i sted above was not reviewed for tota 1 va 1 ve alignment in step by step detail, the inspector concluded that program-matically the licensee has developed a containment local leak rate measurement progra With certain exceptions, the program is consistent with the regulatory requirements of the Technical Specification, Section 3.8 and 4.4; 10 CFR 50, Appendix J; and ANSI-N45.4-197 These exceptions are discussed belo During review of the above procedures, three matters of concern were identified and discussed with licensee engineers and management during this inspectio On June 3, 1988, Region II further discussed these matters with licensee managemen The status is as follows: PT 16. 5 In the full pressure test of the airlock the make-up airflow method is used for the test. A single cap is removed from the test connec-tion to pressurize the airlock; the test is performed; and, to restore the system for operation the cap is replace The test connection and cap are not tested for leakag Licensee management agreed to correct this condition prior to the start up of Unit 1, and during the next refueling outage for Unit The inspector considered this matter as an isolated event and is resolve PT 1 In the Type C test procedure, verification of the initial position and subsequent restoration of multiple valves is documented by a single sign-off ste In that these valves can be located in widely separated areas and may possibly be verified by more than one person,
- it appeared that more specific documentation of valve position would be usefu Licensee management agreed to correct this condition prior to Type C testing of Unit 2 and by the end of the year for Unit The inspector considered this matter a procedure weakness and is resolve PT-16.3B This procedure is to be used to correct leakage in the secondary system prior to a Type A tes The secondary side is drained and pressurized with ai Air leaks are located and repaire No quantitative measurement is made of the repaired leakage for determination of "as found" containment leak rat Possible ways of retaining the ope rational benefit of this procedure and al so obtaining the data for calculation of the "as found" leak rate are under review by the license This item is identified as Unresolved Item 280/88-19-01 and 281/88-19-01:
Review resolution for determining the "as found" containment leak rate relative to repair of secondary system leakag Implementation of the licensee's program for establishing and maintaining containment leak tight barriers was also reviewe Records of perform-ance, identification of problems, corrective actions, retest and test acceptance were reviewed for PT 16.4 (Type C isolation valve testing).
A detailed review of PT 16.4 performed on Unit 1 in the May -
June, 1986 refueling outage showed that as found, as left and retest after repair data were included in the packag The summation of leak rates is controlled by procedure Eng. 70.3 which requires review, approval and sign off at the engineer leve Retest after maintenance is controlled by the maintenance Work Order System and a Repair and Replacement Followe The follower requires that Engineering review the nature of repairs and specify the appropriate test after maintenanc Review of Type A test reports show that since 1983, the Type C tests have been performed at intervals as require No violations, deviations or unresolved issues were identified in program implementatio The inspectors concluded that both the leak rate procedures and controls are improved since previous inspections in 198 In addition to review of the local leak rate test program and results, as a part of the evaluation of overall containment integrity, the inspector reviewed plant drawings to determine that penetration valve configurations conform to the General Design Criteria 55, 56, and 57 of Appendix A to 10 CFR 5 The inspector reviewed the following:
Penetration 63 Containment Spray 64 Containment Spray 43 Radiation Monitoring Criteria
56
Penetration (cont'd)
Criteria 44 Radiation Monitoring
90 Ventilation (Purge)
91 Ventilation (Purge)
105 Post Accident Hydrogen
Monitoring*
92 Vacume Pump
100 Gaseous Waste
46 Loop Fil 1 Line
42 Service Air
47 Instrument Air (discharge)
58 Instrument Air (discharge)
112 Instrument Air (suction)
50 Safety Injection (N2 Relief)
20 Safety Injection (Accumulator
Fill Line)
19 Seal Water Return 56 Sample System
56
57 Sample System 97 Sample System Fifteen of the above penetrations conform to the General Design Criteria (GDC) 55, 56, and 57 of Appendix A to 10 CFR 5 Five penetrations differ slightly from the GDC and are under further review by the NR.
Verification of Containment Integrity (61715) - Unit 1 The adequacy and implementation of the licensee's procedures designed to ensure and maintain containment integrity and procedures designed to mitigate contamination release in the event of a loss of containment integrity following a Loss-Of-Coolant Accident (LOCA) were assessed by reviewing records of Operating Procedures (OPs) and Periodic Tests (PTs);
reviewing maintenance work orders; and conducting personnel interview Records Reviewed
0
0
0
0 OP-IE, "Containment Integrity Checklist", Rev. Date 10/23/86 PT-18.68, "Quarterly Testing of Miscellaneous Containment Trip Valves", Rev. Date 03/03/88 and 10/23/86 PT-16.5,
"Containment Personnel Air Lock Test 11,
Re Date 05/19/86
.
PT-16.6, "Equipment Hatch and Emergency Personnel Escape Hatch Leak Test", Rev. Date 05/19/86 PT-16.7, 11 Personnel Airlock Leakage Test", Rev. Date 05/19/86 PT-36.0, "Instrument Surveillance", Re Date 02/19/88 and 03/21/86 PT-2. 39, 11 Functional Test Procedure for H2 A-GW-102 Waste Gas Decay Tanks A and 8 11, Rev. Date 08/27/87 PT-2.39A, "Analyzer for Waste Gas Decay Tanks A and 8 11, Re Date 10/07/86
- 0
0
PT-2. 43, 11 Hydrogen Ana lyzer 11, Rev. Date 08/20/87.
PT-17.*l, 11 Containment Spray System 11, Rev. Date 03/21/86 PT-17.2, 11 Containment Inside Recirculation Spray Pumps 11,
Re Date 01/07/86 PT-17.3, 11 Containment Outside Recirculation Spray Pumps, 11 Re Date 06/27/86 Scope of Review The inspector reviewed records of the above surveillance tests of containment related and post-LOCA mitigating systems to ascertain system availability statu The containment related and post-LOCA mitigating system records reviewed included the following areas:
0
0
0 Containment isolation valve alignment and operability verifica-tion Personnel airlock, emergency escape and equipment hatch tests Combustible gas monitoring and control tests Containment purge supply and exhaust operability tests Containment pressure and temperature limits Containment spray system tests Records from OP-lE were reviewed from February 1987, through May 1988, to verify that the licensee had established containment integrity by observing the proper positioning of all electrical or mechanical barriers and containment isolation valves prior to heating up the reactor coolant system above 200° Records from PT-18.68 were reviewed for the past five calendar quarters to verify that the licensee had demonstrated the operability of various Technical Specification containment isolation valve This surveillance procedure involves the performance of valve isolation time tests to verify that the valve stroke times are within prescribed ASME Boiler and Pressure Vessel Code standard Records from PT-16.5, PT-16.6, and PT-16.7 were reviewed from-February 1987 through April 1988, to verify the licensee's demonstration of operability of the containment personnel airlock, equipment hatch, and emergency personnel escape hatc The daily records from PT-36 were reviewed for the months of December 1987 and February 1988 to verify the plant operated within required containment pre~sure and temperature limits as prescribed by Technical Specificatio Records from PT-2.39, PT-2.39A, and PT-2.43 were reviewed to verify the operability aspects of the pl ants combustible gas monitoring and control syste Records from PT-2.39 were reviewed from July 1987 through March 1988; those of PT-2.39A from February 1987 through March 1988; and, records of PT-2.43 were reviewed from January 1987 through March 198 The inspector al so reviewed survei 11 ance test records associated with the containment spray system to verify the operability and availability of the syste Records from PT-17.1, PT-17.2, and PT-17.3 were reviewed from October 1987 through April 198 *
6 Findings Summary The inspector's review of the above records found no instances where required surveillances were not performed at the appropriate intervals and no unacceptable conditions were identifie The findings tndicated that the containment related and post-LOCA mitigating system are in a high state of availabilit Samples of maintenance records associated with the personnel airlock equipment hatch, emergency personnel escape hatch, and containment spray system were al so reviewed over the periods describe The purpose of the review was to verify the reliability of these systems or components and to ensure that failures or deficiencies were promptly correcte It was found that in a 11 ca*ses reviewed, the post-maintenance testing was completed in a timely manner and that maintenance request forms were properly utilize No unacceptable conditions were identifie The inspector also reviewed Licensee Event Reports (LERs) related to containment penetration boundaries and LOCA contamination release mitigation systems between April 1987 and Marc.h 1988 to verify that appropriate Technical Specification required actions were performed as necessar The LERs reviewed are listed below:
LER LER LER LER LER LER LER LER LER LER LER 87-004-00 87-009-00 87-012-00 87-017-00 87-030-00 87-031-00 87-036-00 88-001-00 88-001-00 88-001-01 88-002-00 U2 Ul Ul Ul Ul Ul Ul Ul U2 U2 U2 Seven of the eleven LERs reviewed had been previously reviewed and closed by the resident inspector and are discussed in the resident inspector monthly report Three of the remaining four LERs are open and are undergoing a failure analysis by the licensee which is scheduled to be completed by October 20, 198 The fourth LER is open and is awaiting documentation regarding instruction to operators on proper locking of type T handle valve The inspector determined that the LERs reviewed met reporting requirements and no adverse trends were identified in these LERs that would endanger containment integrit Also, deviation reports and maintenance work orders relating the LERs were reviewed and the inspector concluded that appropriate corrective action was taken by the licensee as a result*
of these events.
- In summary, within the areas inspected, the inspector found reason-able assurance that the licensee is maintaining and implementing procedures to ensure containment integrit Within the areas inspected, no violations or deviations were identifie.
Exit Interview Licensee management was informed of the purpose and scope of the inspec-tion at the entrance intervie The inspection scope and findings were summarized on May 20, 1988 with those persons indicated in Paragraph The inspectors described the areas inspected and discussed in detail the inspection results listed belo The licensee did not identify as proprietary any of the material provided to or reviewed by the inspectors during this inspectio Item Number 280, 281/88-19-01 Description and Reference URI - Review resolution for determining the 11 as-found 11 containment leak rate relative to repair of secondary system leakage, Paragraph 3.c.