IR 05000353/1986013

Insp Rept 50-353/86-13 on 860804-08.No Violation Noted.Major Areas Inspected:Completed Work & Work in Process Associated W/Reactor Vessel & Internals Installation & RCPB Piping

ML20203M851
Person / Time
Site:	Limerick
Issue date:	08/21/1986
From:	Gregg H, Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20203M850	List: IR 05000353/1986013 ML20203M847
References
50-353-86-13, NUDOCS 8609050022
Download: ML20203M851 (5)

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P U.S. NUCLEAR REGULATORY COMMISSION Region I Report N _0-353/86-13 Docket N License N CPPR-107 Category A Licensee: Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 Facility Name: Limerick Nuclear Generating Station, Unit 2 Inspection At: Limerick, Pennsylvania

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Inspection Conducted: August 4-8, 1986 Inspector: h NM 8 vNS H. I. Gregg,' Lead Reactor Engineer date Approved By: OD1l na j / '.' WYggi n G(ief, Material and Processes date ction, E Mering Branch, DRS Inspection Summary: Inspection on August 4-8, 1986 (Report No. 50-353/86-13)

Areas Inspected: Routine unannounced inspection of completed work and work in process associated with: 1) reactor vessel and internals installation, 2)

reactor coolant pressure boundary piping, and 3) safety related mechanical components. The major effort during this inspection involved direct observa-tions and evaluation of work. Also, verification was made that installation specifications, procedures and drawing requirements were met, and that adequate controls were in plac Results: No violations were identifie ~

PDR ADOCK 05000353 G PDR IR LIM 2 86-13 - 0003. /15/86

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DETAILS

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1.0 Persons Contacted 1.1 Philadelphia Electric Company (PECo)

• D. Bowie, QA Document Coordinator R. Crofton, QA Engineer L. Dyer, QA Engineer

• G. Lauderback, Field QA Branch Head

• K. Meck, QA Engineer J. Niemanski, Field Engineer W. Ramer, Field Engineer

• R. Sheibley, QA Engineer 1.2 Bechtel Corporation

• M. Drucker, Lead Residen't QA Engineer M. Fisher, Senior Contract Engineer J. -Fraim, Senior Contract Engineer

• D. Harder, Quality Engineer D. Henry, QC Engineer H. Johnson, Welding Engineer

• G. Kelly, lead QA Engineer

• D. Madden, Lead Quality Engineer J. McVeigh, Piping QC Engineer

• B. Mukherjee, Resident Project Engineer G. Perry, QC Engineer D. Roof, Valve Engineer Lead D. Trent, Piping Engineer N. Wypych, Level II Film Reviewer 1.3 General Electric (Nuclear Field Service)

D. DiFilippo, Site QC Lead C. Vandepass, Welding Supervisor U.S. Nuclear Regulatory Commission

• R. Gramm, Senior Resident Inspector

• Denotes presence at exit meeting

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2.0 Reactor Vessel and Internals Installation The inspector reviewed GE Specification 22A4111, " General Instructions for Reactor Vessel Installation," with specific attention directed to the shroud installation since this major work effort was in process. Work traveler

1. 2-140T which detailed the operctions, examination, hold points, and sign off requirements was also reviewe The inspector went into the reactor vessel and observed the shrcud being -

welded to the shroud support base. The weld was being made by 4 welders, each welding in a separate quadrant. The weld was presently in its 19th pass which represented approximately 9/16" of the 2" weld groove. These weld passes were being made with MMA process using 1/8" Inconel 182 rod (rect pass was TIG).

The radial and plumb measurements that are taken each morning were reviewed and compared to the specified allowed tolerance of 0.030" on the radius and 0.060" on plumbness. The measurement of roundness hac gone ur. der tolerance and the inspector discussed the changing cf weld start and stop location being utilized to bring the out af round condition back into toleranc The inspector reviewed NCRs and FDDRs relating to the vessel installation (at this time there were only 26 FDDRs) to verify appropriate-ness of the corrective action No violations were identified

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3.0 Reactor Coolant Pressure Boundary Piping ,

Observations of the Recirculation Pump Base "B" being automatic welded (28" joint B-5, 1.291" min. wall) were made during several of the weld passes. The inspector also reviewed the on-location Work Package VRR-2RS-2B which contained the general instructions and the WR5 weld card specific requirements of weld rod, shielding gas, and interpass temperature. The inspector verified that the pump base alignment was being monitored. Upon completion of the weld pass being observed, the plane of the pump base was determined to be 0.025" off horizontal (0.030" is allowed). By changing the next pass weld start and stop location, this condition was decreased to 0.022". The inspector noted that there were dirt inclusions on the pump base casting side of the weld groove after each pass and none on the pipe side (the pump base is cast 300 series St. Stl. and the pipe is made

from plate). These inclusions were filed away after each pas The inspector also observed the work being performed on the 30" removable spool piece on the suction side of RHR pump 2DP202 and the installation of piping work being performed on the reactor core isolation cooling i system at butt weld joint. (Field Weld 2) of Valve M02F084.

, In addition to the work observations in the plant, the inspector reviewed

! the "In process Rework Notice Log" to determine if there were major l

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problem areas. The log indicated minor type work. Additionally, the inspector reviewed specific rework notices to verify that corrective action was appropriat No violations were identifie .0 Safety Related Components 4.1 MSIV Installation The inspector reviewed the QC Inspection Record for the 26" Atwood Morrill MSIV installation, and observed the in process installation of the outboard MSIVs. The outlet side of valve C was being welded by automatic machine TIG, and the outlet side of valve B was being welded by manual TIG. The inspector observed the filing of the weld stop, the wire brushing of an intermediate pass, and the grinding to remove the positioning lug tack welds on valve C. The valve A outlet grinding clean-up of the weld preparation and the tack welding of the insert ring on the outlet of valve D were also observe (Joints made with automatic machine utilize inserts and joints made man illy don't).

During a subsequent walk-through of this same area, the inspector observei part of the valve C weld being ground out because the infor-mationa RT showed an indication thought to be a tungsten inclusio Upon further examination, it was determined that there was one spot of insert build-up in the pipe-I.D. This was ground out and blended smooth from the I.D. and the 0.D. weld was repaired and the next weld +

pass was made. The inspector independently verified that the radio- h graph of the repaired weld was satisfactor L

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No violations were identifie .2 RCIC Pump The inspector observed the preliminary alignment of the RCIC pump at 177' elevation. The determination was that the pump was high/ turbine was low; and that additional shimming of the turbine may be per-formed. The construction forces were observed to be carrying out the alignment procedure using acceptable method No violations were identifie .3 Limitorque Rework Program The inspector observed the work in progress typical of that being performed on all limitorque operators under the plant's Limitorque Rework Program. The work is performed by Bechtel under Procedure 8031-FM-4 and includes total cleaning of the operator, changing the grease to Exxon Nebula EP-0, inspection of the operating mechanism,

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removal of tandei torque switches, verification that 0 rings are viton or they are replaced, verification of correct color coded terminal block material, replacement of all improper parts, and bench testing after assembl No violations were identifie .4 Adjustment and Setting of Limitorque Operators Within the Limerick 2 program, all vaive assemblies (valve with oper-ator) with limitorque operators are shop tested and set for torque and or limit by PECo personnel. Each valve assemble with rising stems are tested with MOVATS equipment. The work is performed under -

PEco Procedure FE-1 The inspector observed the M0 VATS testing of a 4" Walworth Gate Valve with a 000 Limitorque Operator. Oscilloscope traces are used to determine spring pack motion and thrust loads. The minimum and maximum thrusts ara determined and the torque switches are set at the minimum load. Then a blocking plate is set in place so that maximum thrust cannot be exceede No violations were identifie .0 Exit Meeting The inspector met with the licensee's representative (identified in paragraph 1.0) at the conclusion of the inspection on August 8, 1986, to i summarize the findings of this inspection. The NRC Resident Inspector, i R. Gramm, was also in attendanc !

During this inspection, the inspector did not provide any written aaterial >

to the licensee, t