IR 05000498/1988058
| ML20153D386 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 08/24/1988 |
| From: | Clay Johnson, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20153D383 | List: |
| References | |
| 50-498-88-58, 50-499-88-58, IEIN-86-003, IEIN-86-3, NUDOCS 8809020183 | |
| Download: ML20153D386 (7) | |
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APPENDIX
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U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-498/88-58 Operating License:
NPF-76 50-499/88-58 Construction Permit:
CPPR-129 Dockets:
50-498 50-499 Licensee: Houston Lighting & Power Company (HL&P)
P.O. Box 1700 Houston, Texas 77001 Facility Name:
South Texas Project, Units 1 and 2 (STP)
Inspection At: STP, Matagorda County, Texas Inspection Conducted: August 8-12, 1988
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Oh B/Jf!BB Inspector:
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C.' E.' Johnson, Reactor' Inspector, P1 ant Systems Section, Division of Reactor Safety
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Approved:
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Dater T. F. 5teck'a, Chlef, Plant 5ystems Section
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Division of Reactor Safety i
inspection Su'nmary Inspection _Condu,c_ted Augus_t P-12,,,198_8 (Report 50-498f88-58_;_ 5_0_-499/88-58)
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Areas Inspected: Routine, unannounced inspection of testing of pipe supports i
aiRT~ restraint systems; TI 2515/75; and IN 86-03.
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Results: Within the three areas inspected, no violations or deviations were idenTfTied, t
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DETAILS 1.
Persons Contacted HL&P
- J. T. Westermeier, Project General Manager
- J. Loesch, Plant Operations Manager
- L. Giles, Manager, Unit 2 Operation
- W. S. Blank, Maintenance Manager
- D. N. Brown, Construction Manager l
- M. A. McBurnett, Operations Support Licensing Manager
- S. D. Phillips, Project Cornpliance Engineer
- J. D. Green Inspection & Surveillance Manager
- M. Pollishak, Project Compliance Supervisor
- S. M. Dew Operations Support Manager
- G. Ondriska, Startup Supervisor'
- M. Wisenburg, Plant Superintendent, Unit I
- S. M. Head Supervising Project Engineer
- S. Eldridge, Plant Operations Support
- A. W. Harrison, Supervising Project Engineer
- J. Bailey, Manager, Engineering and Licensing Plan 2 Superintendent, Unit 2
- G. L. Parkey,lectrical Maintenance Manager
- E. Nichols, E
- S. L. Rosen, General Mar,ager, Operations Support
- R. W. Chewning, Chairman, Nuclear Safety Review Board (NSRB)
- J. E. Geiger, General Manager, Nuclear Assurance
- T. J. Jordan, Project Quality Assurance (QA) Manager, Unit 2
- J. A. Sla.binski, Operations Quality Control (QC) Supervisor
- M. Duke, Staff Engineer
- W. G. W211 born, Supervising Project Engineer
- S. Hill, Uni? 2, Maintenen:e Supervisor l
Bechtel Power Corporation _(Bechte_i_)
- L. W. Hurst, Assistant Project Manager
- K. P. McNeal, Project QA Engineer R. Parekh, Project Engineer
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- C. F. O'Neil. Unit 2 Engineering Manager
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- R. D. Bryan, Constrmction Manager A. Franco, Lead Stress Engineer M. Manjappa. Stress Engineer Etasco Services Inc. (Ebasco)
- R. Abel, Quality Program Site Manager
- H. M. Pardee, QA Site Supervisor
- R. C. Sisson, Site Resident Engineer
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NRC
- J. E. Bess, Senior Resident Inspector, Operations
- J. I. Tapia, Senior Resident Inspector, Construction
- D. L. Garrison, Resident Inspector, Construction
- Denotes those attending the exit interview.
2.
Testing Piping Supports _and Restrain _t Systems (70370)
The purpose of this inspection was to determine if proper installation, operation, testing, adequate surveillances, and properly maintained records for pipe supports and restraint systems are in compliance with regulatory requirements, licensee's Technical Specifications (T3),
programs, and procedures.
a.
Programs and Procedures The NRC inspector reviewed the following Unit 1 procedures for testing of pipe support and restraint systems:
o OPSP11-SN-0005, "Snubber Service Life Review and Reevaluation,"
(NQ) Revision 1, dated May 14, 1987 o
OPSP03-ZE-0009, "Snubber Testing Prograni Description," (NQ)
Revision 3, dated December 7, 1987 o
1 PSP 11-S3-0001, "Mechanical Snubbers Visual Inspection," (Q)
Revision 1, dated July 24, 1987 o
1 PSP 11-SN-0002, "Hydraulic Snubber Visual Inspection," (Q)
Revisicr. 1, dated July 24, 1987
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IPSP11-SN-0003, "Mechanical Snubbers Functional Test," (Q)
Revision 1, dated May 14, 1987 o
1 PSP 11-SN-0004, "Hydraulic Snubbers Functional Test,"
Revisicn 0, dated March 18, 1987 Since Unit 1 is operating at power, the basis for operability of pipe supports is established by TS 3/4.7.9.
This TS establishes surveillance requirements which contain visual inspection and funct fonal test acceptance criteria.
The licensee's procedures are written in compliance with TS requirements.
Unit 1 procedures appeared to be adequate and to contain sufficient inspection and functional testing criteria for mechanical and hydraulic snubbers.
The NRC inspector reviewed the following three preoperational test procedures for Unit 2 which were for thermal expansion, steady state, and transient vibration testing:
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o 2-RC-P06, "Steady State Vibration Monitoring Test," Revision 0, dated May 13, 1988 o
2-RC-P-07, "Themal Expansion Monitoring Test," Revision 0, dated May 12, 1988 o
2-RC-P-08, "Transient Vibration Monitoring Test," Revision 0, dated May 13, 1988 The procedures reviewed were detailed instructions which included the requirement to perform the following:
o Record clearances of supports at cold, intermediate, and normal operating temperature and pressure; o
Record position indication for pipe supports at temperature plateaus; o
Record expansion and contraction measurements at the temperature plateaus; o
Observe for binding of pipe support at temperature plateaus; o
Observe for excessive vibration in the piping system; o
Observe for any damage; and o
Record themal expansion of critical points in the system.
The procedurer, were comprehensive, but easy to follow instrue.tions,
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b, Observation (Unit _2)
j The NRC inspector examined approximately(26 p)ipe supports andRHR, s restraints in the residual heat removal
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reactor coolant (RC), steam blowdown (SB), and chemical volume and control (CV) systems.
The examination was done shortly after hot functional testing (HFT) with the systems at their normal operating temperatures.
The ins]ector's visual examination was performed to verify the status of tie following items:
o Physical damage, deterioration, corrosion, and/or deformation were not evident on any parts of the supports, o
All required bolts, locking devices, nuts, and washers were installed, o
Supports and restraints were not binding on the piping system.
o Correct position indication readings were as specified on snubbers and spring can support,
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Extension rods, support plates, and connecting joints were not bent, loose, deformed, or out of specification.
o Moving parts were free from weld splatter, corrosion, paint, or any material that may obstruct proper operation, o
Pipe, supports, or other associated equip 9ent or components were not in contact with other surfaces as a vesult of thermal expansion.
Any concerns noted by the NRC inspector during the examination of pipe supports were resolved by the documentation and evaluation performed by Bechtel engineering. All were within acceptable design criteria.
Supports or restraints examined are listed below:
SI 2107-SS59 RH 2101-RR03 SI 2107-HL5001 RH 2101-HL5009 SI 2106-SH80 RC 2112-HL5002 SI 2107-550061 RC 2112-HL5001 RH 2101-HL5003 RC 2419-HS5001 RH 2106-HL5003 CV 2141-HS5007 RH 2103-SH0005 CV 2141-HS5003 RH 2103-RR006 CV 2142-HS5004 RH 2103-HL5001 CV 2142-HF5037 RH 2105-HL5005 CV 2142-HF5039 RH 2105-HL5004 RH 2204-HL5004 SI 2108-HL5003 RH 2204-RR04 RC 2121-HS5002 SB 2401-HL5011
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Exanination of Unit 1 Fupports will be perfortned during the outage in i
September 1988,
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g ords Review f
The NRC inspector reviewed the following preoperational test data for l
the thermal expansion, steady state, and transient vibration test:
o 2-RC-P-06, "Steady State Vibration Monitoring Test" o
2-RC-P-07, "Thermal Expansion Monitoring Test"
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o 2-RC-P 08, "Transient Vibration Monitoring Test" l
The thermal expansion test data was not complete.
The system was at
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operating temperature, therefore, data required for Post-Test cold set could not be docurrented at the time of the NRC inspection.
Any conceins identified by the NRC inspector during the records review, were resolved by the licensee's evaluation of the results and the fact that the results were within the established acceptance criteria.
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No violations or deviations were identified in the area of pipe support and restraint testing.
3.
Inspection of Limitorque Motor Valve Operator Wirijn to Detennine if Wir_i_ng,is Envir_onmenta_lly_Qua_lifi_ed (EQ) (TI 25lT/75DY~8T-U3)
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The purpose of this inspection was to determine what wiring was installed in Limitorque valve operators, to review the licensee's EQ documentation to ensure that wiring qualification was adequately established, and to review the licensee's action relative to IN 86-03, Potential Deficiencies In Environmental Qualification of Limitorque Motor Valve Operator Wiring, for Unit 2.
a.
Procedure Review Standard Site Procedure (SSP) 47 provides instructions for performing inspections and rework necessary to identify and correct deficiencies in Limitorque valve operators. The procedure has a detailed checklist which includes inspection of wiring in the operators and requires wiring to be either Raychem Flamtrol or Rockbestos Firewall III, which is considered to be EQ wiring. The NRC inspector's review of SSP-47 indicated that it was adequate.
b.
Observation The NRC inspector selected four Limitorque motor valve operators for inspection.
The conpartment covers were removed for inspection of the internal wiring. This examination verified that all wiring was either Raychem or Rockbestos as required by SSP-47.
The following valves were examined:
o 3R202T-CC-0316 o
3R202T-CC-0774 In addition to these visual inspections, the NRC inspector reviewed the applicabic valve records.
As a result of these observations and reviews, the licensee's acticn relative to IN 86-03 is considered to be adequate. Action on IN 86-03 is considered to be conplete and this Notice is closed.
No violations or deviations were identified.
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4.
_ Exit Interview The NRC inspector met with the licensee personnel (denoted in paragraph 1)
on August 12, 1988, and sumarized the scope and findings of this inspection.
No infonnation was identified as proprietary.
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