IR 05000289/1993005
| ML20034G108 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/23/1993 |
| From: | Chaudhary S, Gray E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20034G107 | List: |
| References | |
| 50-289-93-05, 50-289-93-5, NUDOCS 9303090076 | |
| Download: ML20034G108 (6) | |
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I U. S. NUCLEAR REGULATORY COMMISSION l-
REGION I
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REPORT / DOCKET NOS.: 50-289/93-05
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LICENSE NO.:
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LICENSEE:
GPU Nuclear I
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FACILITY NAME:
Three Mile Island, Unit 1 j
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INSPECTION AT:
Middletown, Pennsylvania
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INSPECTION DATES:
February I-5,1993 i
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i INSPECTOR:
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~2 S. K. Chaufary, Sr. Rfactor Engineer,
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Materials Section, EB, DRS l
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APPROVED BY:
W9 2/23/93 E. Harold Gray, Chief,T1aterials Section, Date Engineering Branch, DRS i
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i 9303090076 930226 PDR ADOCK 05000289 G
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l Areas Inspected: Snubber and pipe support examination and surveillance program for ISI and IST requirements.
Results: The results of the inspection indicated that the snubber / pipe support inspection and surveillance program was acceptable in program scope and procedure implementation. No violation of regulatory requirements was identified.
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1.0 PURPOSE AND SCOPE OF TIIE INSPECTION
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The scope of the inspection was to determine through direct observation and independent evaluations of the licensee's program, whether the control system was functioning properly for installation, modifications, and/or maintenance of safety-related supports and restraints; and to determine that these suppons and restraints were in compliance with NRC
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requirements, licensee commitments, and applicable codes.
The areas reviewed included:
ISI/IST program for snubbers and other pipe supports (Program & Practices),
Snubber maintenance shop and bench test program and procedures,
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Visual examination of accessible snubbers, and l
General walk through inspection of the plant.
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t 2.0 FINIMNGS 2.1 Program e
The ISI/IST program for snubbers and component suppons is described in the program document TMI-1-ISI-BASIS-4, Revision 1. The inspector reviewed the ISI/IST program for y
supports and snubbers, and held discussions with the responsible supervisors and engineers to
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determine the basis and technical adequacy of the program.
By review of the pertinent documents and discussion with personnel, the inspector determined as follows: The snubber surveillance and maintenance, and the ISI/IST pragram are based on the plant Technical Specification, and the requirements of the Section XI of the
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ASME Code. The plant is in the first period of the second 10-year interval of the ISI l
program. The ASME Code,Section XI, requires preparation of an inspection plan that includes code requirements by category and item numbers for each component, and examination or tests to be performed.
Sections 2, 3,4 and 5 of this document (TMI-1-ISI-BASIS-4) provide tallies of component
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and piping supports by Section XI category and item number and system. The basis for scheduling of specific components and supports to be examined is also included in these sections. This document will be updated periodically (generally after each refueling outage)
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to correspond to the 10-year schedule changes required by code requirements or good
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practice. ISI-BASIS-4 includes the initiative to replace the seals of snubbers at periodic l
intervals. This scheduled seal replacement enhances the operability of snubbers.
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Procedure TMI-1-ISI-002 implements the code inspection requirements, and is planned to be
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l updated following a refueling outage to reflect changes required and/or allowed by Code.
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The 10-year interval minimum examination sample requires examination of at least 25% of the Class 1 piping supports,15% of the Class 2 piping supports, and 10% of Class 3 piping
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supports. TM1-1 Technical Specification, Section 4.17, addresses surveillance testing and inspection of snubbers. The Section XI visual examinations comply with Section XI
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requirements and the technical specification visual examinations comply with the requirements as described in the technical specification.
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Snubber testing required by the plant technical specification is performed, but the i
requirements of IWF-5000 are not considered applicable to the Section XI ISI program. The
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technical specification requirements are considered more conservadve than IWF-5000 because it requires a 50% sample size during the 10-year interval based on 24 month fuel cycles.
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The technical specifications also require notification to the NRC regarding the use of sample l
plans.Section XI would require testing only 30% of the snubbers rated for 50 kips or less l
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2.2 Procedures The requirements of the plant Technical Specifications and the code are implemented through approved surveillance procedures. Procedures 1301-9.9 and 1303-9.9 cover the examinations, tests, and refurbishment of snubbers. To determine the adequacy of the -
surveillance procedures, the inspector reviewed these procedures for technical adequacy, clarity of requirements, and acceptance criteria. The procedure was also walked through
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I with the responsible ISI personnel to determine the process of implementation and the i
knowledge level of personnel responsible for implementing these procedures.
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Based on the above reviews, the inspector determined that surveillance procedures were adequate to effectively implement the program requirements.
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Class 1 Pining Component Supports The core flood, decay heat, makeup and purification, and the reactor coolant systems contain a total of 258 Class I piping component suppons. It is required that 25% or 65 supports be
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examined by the end of the second interval. To assure a minimum of a 25% sample from each of the above mentioned systems, a total of sixty-seven (67) supports have been selected
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for examination.
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i Class 2 Pinine Component Suonorts
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The decay heat removal, emergency feedwater, feedwater, hydrogen purge, main steam, l
makeup and purification, reactor building emergency cooling water, and the reactor building j
spray systems contain five hundred eighty-four (584) Class 2 piping component supports. It
is required that 15% (88) supports be examined by the end of the second interval. To assure i
a minimum of a 15% sample from each of the above mentioned systems, ninety-four (94)
supports have been selected for examination.
Class 3 Pioine Comoonent Suonorts The condensate, decay heat closed cooling, emergency feedwater, main steam, nuclear services, and the river water systems contain four hundred thirteen (413) Class 3 piping l
component supports. It is required that 10% or 41 supports be examined by the end of the second interval. To assure a minimum of a 10% sample from each of the above mentioned j
systems, forty seven (47) supports have been selected for examination.
Component Suncorts (Class 1. 2 and 3) Other Than Pinine Suonorts
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The condensate, decay heat closed cooling, decay heat removal, emergency feedwater, main
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steam, makeup and purification, nuclear services, reactor coolant, and the river water
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systems contain one hundred twenty-four (124) component supports other than piping supports which are, classified as Class 1,2 or 3. It is required that 100% of these supports be examined by the end of the second interval with the exception that only one component is required to be examined when there are multiple components of similar design, function, and service within a system. Taking this into account, fifty (50) component supports are required to be examined during the second interval.
3.0 CONCLUSIONS
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Based on the above findings, the inspector concluded that the snubber / pipe support inspection / surveillance program at Three Mile Island, Unit I was acceptable in its program scope and procedure implementation.
4.0 EXIT INTERVIEW l
At the conclusion of the inspection on February 5,1993, the inspector met with the licensee i
representatives, as indicated in Attachment 1, where the inspector summarized the scope and
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the findings of the inspection.
The licensee did not indicate that any proprietary maierial was included within the scope of this inspection.
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ATTACHMENT 1
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Persons Contacted GPU Nuclear T. Basso I2ad Mechanical Engineer
f D. Covil Manager, NDE/ISI F. S. Giacobbe Manager, Plant Engineering l
W. Heyser TMI Licensing l
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J. Jandovitz Supervisor, NDE/ISI
M. R. Knight Licensing Engineer R. E. Rogan Licensing Director
C. W. Smyth NSCC Staff
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G. F. Stillman Plant Engineer L. E. Stouffer ISI Specialist H. L. Wilson TSS/ISI-Plant Maintenance
Commonwealth of Pennsylvania R. Janati PA DER /BRP U.S. Nuclear Reculatory Commission J. Segala Resident inspector - Intern
F. Young Senior Resident Inspector
Indicates those who attended exit meeting