IR 05000289/1982028
| ML20028G031 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/21/1983 |
| From: | Conte R, Keimig R, Young F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20028G026 | List: |
| References | |
| 50-289-82-28, NUDOCS 8302070335 | |
| Download: ML20028G031 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION-50289-820831 50289-821005 Region I 50289-821103 50289-800306 50289-810702 Report No.
50-289/82-28 50289-811823
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Docket No.
50-289 License No. DPR-50 Priority
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Category C
Licensee:
GPU Nuclear Corporation P.O. Box 480 Middletown, Pennsylvania 17057 Facility:
Three Mile Island Nuclear Station, Unit 1 Inspection at: Middletown, Pennsylvania Inspection conducted: December 6,1982 - January 4,1983 Inspectors: kD ffits kS R. Conte, Senior Resident Inspector (TMI-1)
date s'igned OVPM >
kn17IWS
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F.Yg19, nspector (TMI-1)
gatesisned Approved by:
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/- 2 /- 13 V. Keimi'g. Acti49 Chi Reactor Projects date signed F Section No. 2C, Pro cts Branch No. 2, DPRP Inspt.ction Summary:
Ins aection conducted on December 6,1982 - January 4,1983, (Inspection Report Num)er 50-289/82-28)
Areas Inspected: Routine safety inspection by resident inspectors of licensee action on previous inspection findings; plant operations including steam generator repairs; and 1icensee event reports. The inspection involved 85 inspector-hours.
Results: No violations were identified.
8302070335 830124
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PDR ADOCK 05000287 O
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Details l
1.
Persons Contacted General Fublic Utilities (GPU) Nuclear Corporation
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R. Barley, Lead Mechanical Engineer THI-1
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J. Colitz, Plant Engineering Director TMI-1
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- J. Garrison, Quality Assurance (QA) Auditor T. Hawkins, Manager TMI-1, Startup and Test, Technical Functions i
R. Harper, Corrective Maintenance Manager TMI-1
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- C. Kimball, QA Monitor J. Kuehn, Manager, Radiological Controls TMI-1
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S. Levin, Maintenance and Construction Director THI-1 F. Paulewicz, Mechanical Engineer TMI-1 4 -
- S. Pruitt, TMI-1 ISI (Inservice Inspection) Supervisor
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H. Shipman, Engineer III, TMI-1 C. Smyth, Supervisor TMI-1 Licensing, Technical Functions
- R. Szczech, Nuclear Licensing Engineer, Technical Functions
- R. Toole, Operations and Maintenance Director TMI-1 Other personnel in the operations, engineering, and quality assurance staffs were also interviewed.
- denotes those present at an exit interview.
2.
Licensee Action on Previous Inspection Findings i
(Closed)UnresolvedItem(289/80-30-01):
Licensee to evaluate the need for further submittals for Licensee Event Report (LER) No. 80-04, Pipe Support Analysis Error for DH-V1 and V2, Decay Heat Removal Isolation
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Valves. The licensee completed this evaluation and submitted additional LERs No.81-007, dated July 17, 1981, and No.81-014, dated January 8, 1982. These LERs summarize the significant deficiencies noted as a result of the licensee's eviluation in response to NRC Bulletins 79-02 and 79-14.
Procrammatic Corrective Actions were reviewed in NRC Inspection Report 50-289/82-19. Selected inplant verifications of
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corrective action for the 1981 LERs will occur in a subsequent
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inspection.
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i (Closed) Licensee Event Report (289/80-LO-04):
Pipe Support Analysis Error for DH-V1 and V2.
As a result of licensee evaluation in response to NRC Bulletin 79-14, additional hydraulic snubbers were added to DH-V1 (Snubber No. DH-34) and to DH-V2 (Snubber No. DH-33).
The modification packages ECM 107-5, Revision 1, dated August 22, 1980, Pipe Support DH-34, and ECM 107-2, Revision 3, dated August 27, 1980, Pipe Support
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DH-33, were reviewed to assess the scope, nature and testing of work performed for the subject snubbers. Observations of the completed work occurred inside and outside the "D-Ring" in the Reactor Building at DH-V1
and 2.
The inspector noted that DH-33 was removed to support corrective
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maintenance on DH-V2 but support brackets for this snubber were noted to
i be installed. The inspector had no further comments on this item.
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(Closed)UnresolvedItem(289/81-28-02):
Licensee argreval of final corrective actions in response to a quality deficient.y report (QDR) cn support anchor installation documents (AIDS). The st.bject report (QDR No. ~KMT-183-81) involved the improper copying of two AIDS. The licensee's QA (Quality Assurance) monitor verification of corrective action occurred on November 12, 1981, with final documented clo:eout by.
licensee management on November 13, 1981. Anchor bolt rcplacement (for RM-5C, Reactor Building Isolation on Reactor Trip) was verified by NRC during the subject inspection (50-289/81-28).
Licensee measures to prevent recurrence included increased vendor personnel awareness on the proper completion of AIDS, for these individuals involved with that type of work; and a more timely signoff/ notification to Maintenance and Construction Department by Quality Control personnel on completed work.
3.
Plant Operations During Long Term Shutdown a.
Plant Operations Review Inspections of the facility were conducted to assess compliance with general operating requirements of Section 6 of Technical Specifica-tions in the following areas:
licensee review of selected plant parameters for abnormal trends; plant status from a maintenance /
modification viewpoint including plant cleanliness; control of
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documents including log keeping practices; licensee implementation of the security plan including access controls / boundary integrity and badging practices; licensee control of ongoing and special evolutions including control room personnel awareness of these
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evolutions; and implementation of radiological controls.
j Random inspections of the control room during regular and back shift j-hours were conducted. The selected sections of the shift foreman's j
log and control room operator's log were reviewed for the period j
December 7, 1982, to January 4, 1983.
Selected sections of other
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control room daily logs were reviewed for the period from midnight I
to the time of review.
Inspections of areas outside the control room occurred on December 9, 14, 15, 17, 21 and 22, 1982.
Selected licensee planning meetings were also observed.
No violations were identified.
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b.
Steam Generator Tube Leak Repairs The repair process continued in the upper portion of the tube in the upper tube sheet area of the
"A" and "B" Once Through Steam Generator (OTSG) with the first phase of the kinetic expansion repair process' completed during this inspection period (see NRC Inspection Report 50-289/82-24). Candle debris removal was commenced and continues in both OTSGs. Second phase of kinetic expansion in both 0TSG is expected to start by January 7,1983.
After the completion of the second phase of kinetic expansion and cleanup, the licensee will stabilize certain tubes that cannot be
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repaired by the kinetic expansion procedure.
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-4-In addition to tube stabilization, all tube stubs protruding above the primary side of the tube sheet between the tube and the tube sheet will be milled down to prevent the formation of loose pieces during power operations' (if permitted).
Projected completion of all OTSG repair work is April 1983.
Due to the significance and nature of the OTSG tube degradation, the inspector frequently observed various aspects of the repair process. On several occasions the inspector observed the candle debris removal being performed in the OTSGs. A selected review of records, completed at the job site, was conducted. The adequacy of the procedures used at the time of observation was also reviewed.
In addition, discussions were conducted with several craftsmen and supervisors on different shifts to assess the knowledge level and understanding of work in progress.
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No violations were identified.
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4.
In-Office Review of Licensee Event Reports (LERs)
The insoector reviewed the LERs listed below, whicn were submitted to the NRC Region I office, to verify that the details of the event were clearly renorted including the accuracy of the description of cause and the adequacy of corrective sction. The inspector determined whether further information was required from the licensee, whether the event should be classified as an Abnormal Occurrence, whether the information involved with the event should be submitted to the Licensing Boards, and whether the event warranted onsite fellowup.
The following LERs were reviewed:
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LER 82-011/99X-0, on August 31, 1982, dated October 28, 1982 (Pressurizer power operated relief valve, which was installed in 1976 and removed from service in 1981 was found to have excessive internal corrosion and pitting. Source of corrosion is under investigation.)
LER 82-014/03L-0, on October 5,1982, dated November 4,1982 (Fire
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barrier penetration seal was identified to be defective. The silicone foam seal material had separated from the edges of the fire barrier penetration af ter curing.)
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LER 82-015/03L-0, on November 3,1982, dated December 1,1982 (A one and half inch diameter hole was found in the fire barrier
penetration seal on the bottom of the "C" channel Reactor Protection System cabinet.
Diameter of the opening exceeded acceptance criteria thus making the seal inoperable.)
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The inspector determined that additional causal information with respect to laboratory results for LER 62-11, PORV corrosion, was needed before restart of the unit (if permitted). Licensee representatives acknowledged the inspector's comments for this item (82-LO-11).
No violations were identified, g-gmq menn-*
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Unresolved Items
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Unresolved items are matters about which more information is required in order to ascertain if they are acceptable, violations, or deviations.
Unresolved.'tems are discussed in paragraph 2.
6.
Exit Interview The inspectors met with the licensee representatives (denoted in para-graph 1) and at the conclusion of the inspection on January 4, 1983, to discuss the inspection scope and findings, i
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