IR 05000416/1985026

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Insp Rept 50-416/85-26 on 850715-19.No Violations or Deviations Identified.Major Areas Inspected:Snubber Surveillance Program,Thermal Expansion Testing & Repairs to Div III Emergency Diesel Generator
ML20133P867
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 07/30/1985
From: Jape F, Lenahan J, Macdonald J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20133P857 List:
References
50-416-85-26, NUDOCS 8508140511
Download: ML20133P867 (5)


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Report No.: 50-416/85-26 Licensee: Mississippi Power and Light Company Jackson, MS 39205 Docket No.: 50-416 License No.: NPF-29 Facility Name: Grand Gulf Inspection Conducted: July 15-19, 1985 Inspectors: h_ #~ # ~ #

J. {/ Genahan Date Signed AM J. B. MacdUna~ d V r

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}lAOflS Date Signed Approved by: 4M ha* , d/ d '

F. Jape, Section Chief (/ f Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope: This routine, unannounced inspection involved 68 inspector-hours on site in the areas of the snubber surveillance program, thermal expansion testing, repairs to the Division III emergency diesel generator, and previously identified Inspector Followup Item Results: No violations or deviations were identifie PDR ADOCK 05000416

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REPORT DETAILS Persons Contacted Licensee Employees

  • J. D. Barley, Compliance Coordinator
  • J. F. Cross, General Manager
  • D. Cupstid, Startup Supervisor
  • C R. Hutchinson, Manager, Plant Maintenance
  • A. J. Malone, Inservice Inspection (ISI) Coordinator
  • R. Butcher
  • J. Caldwell
  • Attended exit interview Exit Interview The inspection scope and findings were summarized on July 19, 1985, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items Unresolved items were not identified during the inspectio . Independent Inspection Effort The inspectors accompanied the resident inspector on a general plant tour of portions of the control room, turbine building, secondary containment and rooms containing emergency core cooling system Observations included safety-related tag out verification, visual examination of maintenance operations, general plant conditions and housekeepin .__

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2 The inspectors witnessed repair operations on the Division III diesel generator set. The G.E. generator is driven by two E.M.D 12-645-E4 diesel engines, which are connected by flexible couplings to each end of the generator shaft. During routine diesel generator testing, the roller bearing on the generator shaft at the "A" diesel end failed causing damage to the generator shaft. The repair involved replacing the generator unit. The inspectors reviewed maintenance work order M.W.0 54336 and observed replacement of the damaged generator and the coupling of the new generator to the diesel engines. The inspectors discussed the startup testing program for the new generator with licensee engineers. The program involved testing the generator at 25%

load with ramp increases to 50%, 75% and 100% load. After testing at 100% load for four hours, the generator was run at 110% load for two hours and returned to 100% load. The testing was completed subsequent to the completion of the inspection. After successful completion of the testing, the generator was declared operabl Within the areas inspected, no violations or deviations were identified.

l 6. Snubber Surveillance Program (Module 61729)

The inspectors reviewed procedures and quality records relating to the snubber surveillance program. Acceptance criteria utilized by the inspector appears in Technical Specification 3/4. Review of Snubber Surveillance Procedures The inspectors examined the following procedure which control snubber surveillance and inspection activities:

(1) Surveillance Procedure Number 06-ME-1000-V-0001, Snubber Visual Inspectio (2) Mechanical Standard Procedure Number MP&L-MS-31, Functional l Testing Requirements for Snubbers.

! Review of Quality Records The inspectors reviewed the quality records documenting the results of

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visual inspections performed on safety-related accessible and inacces-sible snubbers in March 1985. The March 1985 inspection was the first inservice visual snubber inspection performed on the snubbers. Techni-cal Specification 4.7.4.b requires that this inspection be performed after four months, but within ten months of commencing Power Operatio (

Power Operation commenced on September 21, 1984. Snubber inspections l performed prior to this date were preservice inspection Records examined were as follows:

(1) Results of visual inspections documented on Data Sheets I and II, Procedure 06-ME-1000-V-0001. These records cover visual inspec-tion of all safety-related hydraulic and mechanical snubber ,

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(2) Materials Nonconformance Reports (MNCR) Numbers 118-85, 120-85, 124-85, 128-85, 129-85, 148-85, and 160-85. These MNCRs docu-mented and dispositioned discrepancies noted during the March 1985 visual inspection (3) Pacific Scientific Report dated March 26, 1985, Results of Functional Tests on PSA Mechanical Shock Arrestors for MP&L. This report documents the results of testing performed on snubbers with discrepancies identified during the visual inspections; or during maintenance operation As a result of the visual inspections and subsequent functional testing, the licensee identified one inaccessible mechanical snubber as being visually inoperable. None of the hydraulic snubbers, all of which are inaccessible or accessible mechanical snubbers, were found to be visually inoperabl Thus, in accordance with Technical Specification 4.7.4.b, the interval for performing the next visual inspections is as follows:

Inaccessible Mechanical Snubbers - 12 months Inaccessible Hydraulic and Accessible Mechanical Snubbers - 18 months Within the areas inspected, no violations or deviations were identifie . Thermal Expansion Test (Module 70370)

During this inspection, the inspector continued the review of the licensee's thermal expansion test program. This review involved examination of test procedures and test results for thermal expansion during initial heatup, and test conditions (TC) one and three. The thermal expansion program was previously reviewed during inspections documented in NRC Report No /83-46 and 50-416/83-49. Acceptance criteria utilized by the inspector appear in Final Safety Analysis (FSAR) Report Sections 3.9 and 14.2.12.4 and Regulatory Guide 1.6 Review of Thermal Expansion Test Procedure The inspector examined the test procedures listed below and verified that test prerequisites were specified, test instructions and objectives were clearly stated, and acceptance criteria were specifie Procedures examined were as follows:

(1) Procedure No. 1-000-SU-17-H, System Expansion, Heatup (2) Procedure No. 1-000-SU-17-1, System Expansion - T. (3) Procedure No. 1-000-SU-17-3, System Expansion - T. (4) Procedure 1-C88-ST-05, B0P System Piping Thermal Expansion Monitoring Program

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(5) Bechtel Drawing Numbers M-1661, M-1675, M-1689, M-1690 and M-1692, Pre-op. Piping Drawings Review of Thermal Expansion Test Results The inspector reviewed data documenting the results of thermal expansion testing conducted in accordance with the procedures listed above. Test data reviewed were as follows:

(1) Results of thermal expansion testing performed on NSSS piping (Main Steam and RCIC piping) during heatup and TC1 and (2) Results of thermal expansion testing performed on B0P piping systems including RHR, RWCU, SLC, and FW pipin (3) Calculation No. MC-Q1111-830027, dated December 20, 1983, Evaluation of Thermal Movement (4) Evaluation of thermal expansion test exceptions for NSSS piping noted during Heatup and TC-1 and Within the areas inspected, no violations or deviations were identifie . Previously Identified Inspector Followup Items (IFI) (Closed) IFI 416/83-49-01: For all cases where Level I trend plot acceptance boundaries were exceeded, the type of analysis or evaluation performed and the conclusions based on these analyses and evaluations will be documented in the test record. During review of the test data listed in paragraph 7.b above, the inspector verified that cases where thermal movements exceeded Level I values were documented and evaluate Resolution of all problems noted to date during heatup, TC1 and TC3 have been completed by the licensee's nuclear plant engineering department or by GE, with the exception of test exceptions FP-01 and FP-24, which are presently being evaluated. IFI 416/85-49-01 is

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close (Closed)IFI 416/83-49-02: On the first plant cooldown, confirm actual pipe movement for the points which were rebased at 260 F. Resolution of this problem is documented in calculation number MC-Q1-111-83002 The inspector reviewed the calculation and determined that the licensee verified actual pipe movement by observation of scribe marks on the piping. IFI 416/83-49-02 is close (Closed) IFI 416/83-49-03: Repair Lanyard Pots and on the next plant I heatup perform trend plot measurements to confirm initial heatup dat I Resolution of this problem is documented in calculation MC-Q1-111-83002 The inspector reviewed the calculation and also reviewed a G.E. memo dated September 27, 1984, Subject: Instrument failures durin Review of these documents disclosed that the instrumentation (gLanyard TC Pots) were repaired as required and confirmed initial heatup data was valid. IFI 416/83-49-03 is close Within the areas inspected no violations or deviations were identifie J