IR 05000400/1986089

Insp Rept 50-400/86-89 on 861117-21.Violation Noted: Inadequate Housekeeping Controls Around Reactor Vessel During Initial Fuel Loading

ML20207K928
Person / Time
Site:	Harris
Issue date:	12/12/1986
From:	Jape F, Mathis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20207K879	List: IR 05000400/1986089 ML20207K874 ML20207K905 ML20207K928
References
50-400-86-89, NUDOCS 8701090563
Preceding documents:	ML20210U132 (10 February 1987)
Download: ML20207K928 (5)

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a [ nog . UNITE 3 STATES g jo, NUCLEAR REGULATORY COMMISSION

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$ 'j 101 MARIETTA STREET. * * ATLANTA, GEORGI A 30323

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Report No.: 50-400/86-89 Licensee: Carolina power and Light Company P. O. Box 1551 Raleigh, NC 27602

' Docket No.: 50-400 License No.: NPF-53 Facility Name: Harris Inspection onducted: November 17-21, 1986 Inspector: .[. h & n J. 2. Mathis' _

( 12.\ 8 (o Oats Signed Approved by: NI hkN. v ' h ~

l2./12/ f/7 F. ' Jap'e,' Section Chief DatW Sfgnaid Engineering Branch' ,

Division of Reactor Safety

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SUMMARY Scope: This routine, una'nnounced inspection was in the~ areas of initial fuel loading witnessin '

Results: One violation was identified - Inadequate housekeeping controls around the reactor vessel during initial fuel loadin ,

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REPORT DETAILS Persons Contacted Licensee Employees

• J. Ha ness, CP&L Asstistant Plant General Manager

• R. A. Watson, Vice President Harris iuclear Project

• R. B. Van Meter, CP&L Manager Technical Support

• D. Tibbitts, Regulatory Compliance

• J. L. Dority, Start-Up Supervisor

• C S. Hinnant, Manager Start-Up

• M. G. Wallace, Regulatory Compliance Specialist

• H. W. Bowles, CP&L Director-Onsite Nuclear Safety

• C. H. Moseley, Jr. , Manager-0PNS QA/QC

• G. L. Forehand, Director QA/QC R. Colthorpe, Power Ascension Lead Test Engineer R. Duncan, Power Ascension Lead Test Engineer D. Casada, Shift Test Coordinator C. S. Olexik, Shift Test Coordinator H. Carter, Shift Foreman C. S. Matthews, Shift Foreman T. D. Ward, Jr. , Power Ascension Technician Other licensee employees contacted included engineers, technicians, operators, security force members, and office personne Other Organization F. Baskerville, Westinghouse Ad R. Kirk, Westingh.use R. Nodvik, Westinghouse A. Sabol, Westinghouse NRC Resident Inspector

• P. E. Fredrickson, NRC, Section Chief

• F. Maxwell, Senior Resident Inspector

• Attended exit interview Exit Interview lhe inspection scope and findings were summarized on November 21, 1986, 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 One new item was identified during this inspection as follows:

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Violation 50-400/86-89-01, Inadequate Housekeeping Controls Around the

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Reactor Vessel During Initial Fuel Loading (paragraph 5).

The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector 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 . Initial Fuel Loading Witnessing (72524)

Initial fuel loading for the Shearon Harris Nuclear Power Plant (SHNPP)

Unit 1, started on November 17, 1986, at approximately 5:06 The sequence of fuel loading was in accordance with data sheet 10.d of procedure 9101-S-01, Initial Fuel Loading. Prior to the first bundle going into the

< reactor vessel, the inspector verified that the prerequisites and initial conditions which ensure the following were satisfied: (a) Readiness of equipment and associated systems required for a safe core loading (b) Veri- i fication of equipment status and plant condition during core loading to ensure planned conditions are maintained (c) compliance with the require-ments which pertain to core loading that are identified in the Final Safety Analysis Report (FSAR) and Technical Specifications (TSs).

i The initial core consists of 157 fuel assemblie Each fuel assembly

contains a 17 x 17 rod array composed of 264 fuel rods, 24 rod cluster

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control (RCC) guide thimbles and an incore instrumentation thimble. The fuel loading pattern for Cycle 1 contains three regions of 53, 52, 52 assemblies, each with a different U-235 enrichment. The first two regions, consisting of the two lower enrichments, are arranged in a checker board e pattern toward the center of the core. Region 3, which contains the highest enrichment, is arranged around the periphery of the core. Enrichments for Cycle 1 are 2.1 w/o, 2.6 w/o, and 3.1 w/o in Regions 1, 2, and 3, respec-

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tively.

. The inspector witnessed initial fuel loading from the control room, refueling floor and spent fuel pool to verify the following:

, A proper version of the procedure was in use and was being followe Inverse multiplication plots were being maintained in accordance with

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procedural requirements.

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' Boron concentration was verified by proper sampling and analysis, at the required frequenc ,

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. Shift turnover was performed in conformance with administrative procedure Personnel access to refueling floor was controlled.

' Deficiencies or difficulties encountered were recorded in the control room log. Adequacy of corrective action, and the review and approval of that action was verifie On November 18, 1986, while witnessing initial fuel loading in the reactor containment building, the inspector observed that control of personnel, material and tools was not being recorded at the entry and exit point of the access controlled area. 10 CFR Part 50, Appendix B, Criterion II and the accepted Quality Assurance Program (Final Safety Analysis Report, Section 17.2.2) collectively require that activities affecting quality shall be accomplished under suitably controlled condition Controlled conditions include the use of appropriate equipment and suitable environmental conditions for accomplishing the activity, such as adequate cleanliness. The SHNPP FSAR Section 1.8 commits to Regulatory Guide 1.39 (Rev. 2), September 1977, " Housekeeping Requirements for Water-Cooled Nuclear Power Plants," which endorses ANSI N45.2.3-1973, " Housekeeping During the Construction Phase of Nuclear Power Plants." ANSI N45. requires that for zones I, II and III a written record of the entry and exit of all personnel and material shall be established and maintained. Failure to maintain a record of the entry and exit of all personnel and material for a Class B area, which is the designated cleanliness area around the reactor vessel with the head off, is in violation of the above requirements. This item is identified as violation 50-400/86-89-01, Inadequate housekeeping controls around the reactor vessel during initial fuel loadin In addition to the above incident at approximately 1:45 a.m., on November 18, i 1986, the Lead Test Engineer in the Reactor Containment Building, overlooked the requirement to perform the statistical reliability check of the temporary nuclear instrument A and the source range instrument N31 as required by step 6.7.2 of procedure 9101-S-01. The engineer did perform the required baselining check on these nuclear instruments. The fact that the data were missing was discovered by the lead test engineer on the day shift and reported to the Shift Test Coordinator (STC) in the control room at approximately 5:00 p.m. on November 18, 1986. Fuel movement was stopped and an investigation started by the STC and the Shift Forema The lead test engineer performed a statistical reliability check (chi square test) on the detector using the baseline data taken in step 6.7.2 of procedure 9101-S-0 The detectors failed the Chi Square Test meaning that the detectors were inoperable due to excessive electronic noise. Technical Specification 6. requires that written procedures shall be established, implemented, and maintained that meet or exceed the requirements and recommendations of Appendix A of Regulatory Guide 1.3 The failure to implement a statistical reliability check per step 6.7.2 of procedure 9101-S-01 is a violation against Technical Specification requirement 6.8.1.

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Evaluation of the conditions involved in this incident in accordance with the NRC enforcement policy indicates that this is a licensee identified and corrected violation. Therefore, a Notice of Violation was not issued by the NR Fuel loading was completed at 1:46 on November 21, 1986. Soon after initial fuel loading was completed the licensee video taped the core to verify the loading pattern is in accordance with the initial core loading procedure.