IR 05000369/1987027

Insp Repts 50-369/87-27 & 50-370/87-27 on 870810-14.No Violations or Deviations Noted.Major Areas Inspected: Action on Previous Enforcement Matters & IE Bulletin 86-002 Static O-Ring Differential Pressure Switches

ML20235C800
Person / Time
Site:	Mcguire, McGuire
Issue date:	09/15/1987
From:	Jape F, Taylor P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20235C790	List: IR 05000369/1987027 ML20235C786
References
50-369-87-27, 50-370-87-27, IEB-86-002, IEB-86-2, NUDOCS 8709250020
Download: ML20235C800 (7)

Text

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I l Report Nos.: 50-369/87-27 and 50-370/87-27

Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: 50-369 and 50-370 License Nos.: NPF-9 and NPF-17 i Facility Name: McGuire 1 and 2 Inspection Conducted: Au.ust 10-14, 1987 Inspector: /m-

  . A. Taylor  V M '

Date Signed Approved by: F. Jape, Ch'ief h erJL__

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Testing Programs Section Division of Reactor Safety SUMMARY Scope: This routine, announced inspection was in the areas of licensee action on previous enforcement matters; IEB 86-02 Static "0" ring differential pressure switches; TI 2500/16 Seismic interactions incore flux mapping system and seal table and review of inspector followup items (IFI).

Results: No violations or deviations were identifie . 8709250020 870918 PDR ADOCK 05000369 G PDR _ _ _ _ _ _ _ - .

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4 REPORT DETAILS Persons Contacted Licensee Employees

* N. Smith, Test Engineer, Performance
* F. Banner, Associate Engineers, Compliance
* E. LeRoy, Licensing Engineer, General Office
* B. Nardoci, Associate Engineer, Compliance N. Atherton, Associate Engineer Compliance J. Lee, Design Engineer, General Office G. Gilbert, Operating Engineer, Operations D. Trapp, Engineer Mechanical Maintenance M. Hatley, Engineer, Mechanical Maintenance Other licensee employees contacted included technicians, operators, and office personne * Attended exit interview Exit Interview The inspection scope and findings were summarized on August 14, 1987, with those persons indicated in paragraph I 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 identi fy some material as proprietary during this inspection, but this material is not included in this inspection repor . Licensee Action on Previous Enforcement Matters (Closed) Violation 370/86-16-01, Failure to determine "as-found" leak rate Unit 2 containment. The licensee specified corrective action concerning the violation in a letter dated September 4, 198 Station memorandum dated March 9, 1987, S. E. Synder Performance Group to G. A. Copp Planning Section, established requirements to conduct pre-maintenance leak rate testing on containment isolation valve Station Directive 3.2.2, Identifying and Performing Plant Retesting, is scheduled to be issued September 198 This document lists the containment isolation valves and details the planning and coordination requirements between Performance, Operations and Maintenance groups to ensure that pre-maintenance leak rate testing is accomplished as require . _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ _ ___-___ -____ __ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _

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(Closed) Violation 370/86-18-02, Failure to follow QA procedure QCK-1 where conditions adverse to. quality are identified and resolved in a timely manner. This violation was related to several specimen access hole plugs that were found loose and lying on the core barrel support ledg Subsequently, the upper intervals and reactor vessel head were installed .

with loose objects left in the reactor vessel. The licensee concluded

.that the violation occurrence was due to personnel error in that the senior reactor operator failed to properly document and follow up on his observation of these objects. The inspector reviewed MP/0/A/7150/43, Upper Internals Removal and Replacement procedure which now has steps in the procedure to control the removal and reinstallation of the specimen access plug The procedure was revised on May 29, 198 (Closed) Violation 369/86-19-02, Failure to control material entering the primary coolant system. During an inspection inside the reactor vessel for debris from a damaged fuel. assembly,two terry cloth towels were found beneath the lower core support plate. The inspector reviewed licensee corrective action which was to implement procedure   MP/0/A/7150/12, Refueling Canal Cleanliness Watch. This procedure established a watch for the refueling canal area to ensure that all items taken over the refueling canal are tied off and items brought into the building are logged in and out. The watch also ensures that if anything is dropped into the system, action will be taken to remove i The inspector reviewed training records and required reading conducted for all mechanical maintenance personne The training provided has given the mechanics more direction in their responsibilities for implementing the cleanliness program In addition, Station Directive 3.11 has been changed to clarify the     i cleanliness program requirement . Unresolved Items Unresolved items were not identified during this inspectio . (Closed) IE Bulletin 86-02, Static  "0" Ring Differential Pressure Switches (92703)

The licensee responded to IE Bulletin 86-02 in a letter to the NRC dated July 28, 198 The licensee sated that the model type D/P pressure switches identified in the bulletin were not installed at the McGuire l facilit No further action is require . (Closed) Part 21 Defective Detector Computer Code, August 83 Version for Core Maps A letter, dated May 24, 1984, from Shanstrom Nuclear Associates reported to the NRC under 10 CFR Part 21 that the August 83 version of the detector code had been utilized for the D. C. Cook Unit 1. The letter also stated 1 that Duke had purchased the August 83 detector code but had used an j earlier version for current operational analysis for McGuire Units 1 and 2. The inspector held discussions with Duke's Nuclear Design Engineering group and noted that an April 82 detector code had been installe l l J

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  - (Closed) TI 2500/16, Potential Seismic Interaction Between In-Core Flux Mapping Syste IE Notice 85-45, dated June 6, 1985, was issued to inform licensees tha potential generic problem may exist because portions of the flux mapping
   . system that have not been seismically analyzed are located directly above the in-core instrumentation tubing / seal tabl The inspector verified that the licensee had received the notice and' action had been undertaken-to review its application to the McGuire facility. The licensee had conducted inspections and performed a seismic interaction analysis. The analysis verified that there would be no seismically induced ' interaction between the movable incore frame assembly and the seal tabl However, two recommendations were made as a result of the analysis and are currently being reviewed for implementation. The recommendations are to upgrade the classification of existing restraints to QA condition 4 (Presently classified as nonsafety-related) and to install lower restraints at the isolation valve leve . Previously Identified Inspector Followup Item (92701)
    (Closed) IFI . 369/83-46-03; 370/83-53-03, Review temperature effects on tank levels. The licensee changed periodic test procedure 4150/01B to remove temperature corrections to the inventory changes in the nuclear drain tank, pressurizer relief tank and volume control tank when L    calculating reactor coolant system leakage. The temperature corrections were removed because tank level as measured by the differential cells are calibrated at fixed temperatures.

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    (Closed) IFI 370/83-03-01, Discrepancy between ESF test procedure and diesel generator test description in FSAR Table 14.1. The FSAR tabl described D/G tests for a loss of normal power for each D/G un lizing one D/G at a - time. This testing was accomplished as part of the 18 month Technical Specification surveillance testing for each D/ Appropriate amendments to the FSAR Table were made dated December 198 (Closed) IFI 370/83-15-04, Procedures to inspector ropes, hooks and grapples on fuel handling equipment. The inspection of this equipment has  i been incorporated into the following procedures: MP/0/B/7650/90, 91 and .

0 (Closed) IFI 369/84-29-01, Positive Displacement (PD) Pump Control of l Pressurizer Level at 30% Power. Appropriate IFI number for this item should have been for Unit 2. The testing of pressurizer pressure and ' level control was included in TP2/A/ 2650/25 using the PD pump. The same controls 'were previously tested by the centrifugal changing pumps in 4 TP/2/A/2600/11 and the PD pump procedure has been delete (

    (Closed) IFI 369/85-24-01 and 370/85-25-02, Adequacy of review of completed test results. The inspector had identified a concern with the

, test procedure completion verification process in that main steam safety l- valve set point test procedure (PT/0/A/4250/01) had gone through two .

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levels of review and some of the steps in the test procedure had not been signed off for three of the safety valves. To correct this problem, the licensee has' issued changes to the test procedures as well as other safety valve test procedures to require additional reviews and job completion sign off steps which will improve the review proces (Closed) IFI 370/85-25-01, Determination of Unit 2 delta T decrease. This IFI will be closed since Unresolved Item 370/85-41-01 was opened when LER 370/85-24 was issued by the licensee concerning this subjec Unit 2 delta T decrease was first noted following startup on its second fuel cycle (cycle 2) in May 1985. LER 370/85-24 was written November 13, 1985 describing the event and planned corrective action Since Unit 2 is in fuel cycle 4 the inspectors requested that data collected since cycle 2 be made available for revie Such data should include delta T circuitry calculations, calorimetric calibrations, trends noted during power operations, delta T stabilit In addition, a final assessment from the licensee as to root causes, effectiveness of on going programs and their use in the futur This area remains open under the aforementioned unresolved ite (Closed) IFI 369/86-16-01 and 370/86-16-02, Review results of licensee examinations of maintenance records to determine Unit 2 "as-found" leak rat The licensee provided the additional data in letters dated September 30 and December 1, 198 This information was needed to complete our evaluation relating to Violation 370/86-16-01, Failure to Determine the Containment "As-Found" Leak Rate. Region II issued a letter, dated February 24, 1987, completing our review in this are (Closed) IFI 369/86-18-01 and 370/86-18-01, Licensee to review overall program on housekeeping to control objects from falling into critical system The licensee reviewed all generic procedure requirements that effect refueling activitie Changes were made to the following procedures as necessary to address securing materials used over the reactor vessel or spent fuel poo PT/0/A/4150/14, Post Irradiation Examination Controlling Procedure

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PT/0/A/4550/03c, Core Verification

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PT/0/A/4550//23, Rod Control Cluster (RCCA) Examination

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PT/0/A/4550/03B, Spent Fuel Pool Inventory

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PT/0/A/4550/24, Fuel Assembly Examination (Closed) IFI 369/86-19-01, Followup corrective actions on fuel assembly damag Damage to a fuel assembly was discovered during the refueling outage following cycle 3 on June 26, 1986. Several fuel pins in the fuel assembly were breached with an estimated 50 to 150 fuel pellets release The damage is believed to have occurred from the vibrations and fuel rod rotation induced by water jetting through core baffle joints. The damage fuel assembly (D-03) was remove to the spent fuel pool and the loose fuel

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pellets were vacuumed' from the core and vessel regions. Video. inspection of.all other fuel assemblies at baffle joint locations revealed no further Gap ' measurements taken at ' baffle joint' areas

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fuel assembly damag indicate' further jetting . action on fuel rods will . occur at these locations. 'Further corrective action taken by the licensee was to remove eight fuel rods from the two fuel . assemblies that face the baffle joint areas and install stainless steel (SS) fuel rods. Water jetting on the SS fuel rods would. not damage fuel rods due to the SS material'. .Following Unit 1 startup, water chemistry was monitored for iodine activity (I-131, 133, 134 Np 239). This' iodine activity appeared normal' and no additonal fuel damage is indicated. .The ' licensee has taken corner joint baffle gap measurements for both Units and further measurements are planned during refueling outages in 1987 for each Unit. Clips have been installed on the fuel assemblies facing the baffle joints at the grind straps. The clips prevent fuel rod rotation due to water jetting. The. licensee currently has under review a Reactor Internals Upflow modification for.both units (1988 Unit 2,1990 Unit 1). The upflow modification will seal off the baffle joints resulting in reducing the D/P across the baffle plates o eliminating baffle jettin Inspection in this area is continuing on a I routine base (Closed) IFI 369/86-25-01 and 370/86-25-01, Review licensee action to-develop plant procedure for inspection of supports and restraints-after a plant transient. Changes were made of the following Station Directive

which requires notification of mechanical maintenance following a reactor

trip or transient for possible equipment support and restraint inspectio .SD 3.1.1 Action to take for Exceeding of Limits

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SD 3.1.6 Notifying Management of Operating Conditions ! - SD 3.1.10 Investigation of Reactor Trips l - S0.3.1.22 Management Followup of Abnormal Plant Events id O*

    (0 pen) 369/LER85-29 Analysis error in containment  m nonconservativ The licensee planned corrective action, pres to condsure.0cto additional analysis, is not complete : 0 o g )
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