IR 05000382/1987012

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Insp Rept 50-382/87-12 on 870518-22 & 0615-19.No Violations or Deviations Noted.Major Areas Inspected:Design Changes & Mods & Followup Insp of Calibr Program Activities Re Tech Spec Requirements
ML20235U551
Person / Time
Site: Waterford Entergy icon.png
Issue date: 07/09/1987
From: Hunnicutt D, Stewart R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20235U534 List:
References
50-382-87-12, NUDOCS 8707220516
Download: ML20235U551 (5)


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APPENDIX

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U.S.'= NUCLEAR REGULATORY COMMISSION

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REGION IV '

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NRC' Inspection Report: '50-382/87-12' License: NPF-38

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'i ( -. Docket: 50-382:

y Licensee: Louisiana Power & Light Company (LP&L).

N-80 '317<Baronne Street New Orleans, Louisiana .70160

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Facility Namei Waterford Steam Electric Station, Unit 3

~ Inspection At: Taft, Louisiana Inspection Conducted: .May.18-22 and June 15-19, 19

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Inspector:.

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R.~ Stewart,-Reactor' Inspector, Operations _Dat'e

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Section, Reactor Safety. Branch Approved: W

& D. M. Hunnicutt, Chief, Op'erations Section 7/9/I7 Date ' '

  1. Reactor Safety Branch Inspection Summary Inspection Conducted May 18-22 and June 15-19, 1987 (Report 50-382/87-12)

L . Areas-Inspected: Routine, unannounced followup inspection of design changes and modifications, and followup inspection of calibration program activities relative to Technical Specification requirements.

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sResults: Within the two areas inspected, no violations or deviations were identifie l

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8707220516 870716 gDR ADOCM 05000302 PDR

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DETAILS 1. Persons Contacted

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Principal Licensee Employees N. S. Carns, Plant Manager R. F. Burski, Engineering and Nuclear Safety Manager L. L. Bass. Technical Support Supervisor R. V. Seidl, I&C Supervisor R. G. Pittmen I&C Engineer G. S. Matharu, Electrical Engineer J. Judge, Mechanical Engineer W. A. Brinker, I&C Technician R. H. Janquine, I&C Technician W. Laporte, Quality Assurance Engineer 2. Followup Review - Design Changes and Modifications In conjunction with a previous inspection in this area (NRC inspection Report 50-382/86-12), the NRC inspector conducted a followup review of randomly selected station modification packages (SMPs) which are implemented via the Condition Identification and Work Authorization (CIWA), which is used to authorize plant work activit Addendum pages to the CIWA are provided to document work instructions, acceptance criteria, test or retest requirements, contain or reference approved procedures and drawings, etc., required to accomplish the wor Three CIWAs were selected for review which were the work authorization packages for:

SMP-84-257; CIWA 20266, et al, "Radwaste Liquid Storage Capacity Addition."

SMP-84-593; CIWA 016564, " Associated Circuits Analysis for Isolation Panel."

SMP-84-412; CIWA 011880, "EFW & LPSI Amber Light in Maintained Off Position."

The NRC inspector reviewed the CIWA work packages in conjunction with LP&L Procedures PE-Z-006, Revision 8, dated July 16, 1986, " Administrative Procedure Plant Engineering Station Modification;" and UNT-5-002, Revision 5, dated January 6, 1986, " Administrative Procedure Condition Identification and Work Authorization." The NRC inspector verified that the completed packages contained documented evidence that design change activities were conducted in accordance with the appropriate

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I specifications, drawings, approved procedures, work instructions, QA/QC requirements, and related applicability to 10 CFR 50.59 requirement No violations or deviations were identifie i 3. Followup Inspection of Calibration Program Activities Program Review In conjunction with a previous inspection relative to. Technical ]

Specification.(TS) calibration requirements (NRC Inspection j Report 50-382/86-29), the NRC inspector conducted a followup review I of celebration activities not addressed in the TS, but using test ]

eouipment that may be used to make TS related measurement During this review, the NRC inspector reviewed the measuring and test i equipment (M&TE) program requirements as prescribed by the principle 1 LP&L Procedures UNT-5-011, " Calibration and Control of Measuring and i Test Equipment;" MD-01-015. "M&T Equipment Control;" MD-01-02, "M&TE j Accountability Procedures;" and QP-12-001, " Calibration and Control of andMeasuring (and Control I&C) Test Equipment (M&TE) and Installed Instrumentation Devices."

In conjunction with the program review, the NRC inspector conducted a

"walkdown"'of M&TE components from the metrology laboratory through tool crib storage and check-out for usage. During the "walkdown,"

the NRC inspector reviewed records of calibration data, record of accountability cards, and calibration frequencies and expiration dates. During observations in the metrology laboratory, the NRC inspector witnessed an in-process calibration of response time test component. Electro-mechanics Model 39300, using Calibration Procedure MI-5-159, Revision 0, dated October 15, 1984. The NRC inspector observed that the' procedure had been reviewed end approved, the calibration procedural steps were being initialed and the i necessary values were being entered, including "as-found" value No violations or deviations were identifie M&TE Nonconforming Components During the inspection, the NRC inspector reviewed the metrology laboratory supervisor's log, which among other tracking functions, identifies M&TE components found to be out-of-calibration during a recalibration cycle. LP&L Procedure UNT-5-009, dated October 12, 1986, requires that when an M&TE component "as-found" condition a reflects an out-of-tolerance condition, a CIWA be initiated and issued by the metrology laboratory supervisor. The CIWA identifies the component, nonconforming condition, and accountability card (previoususers). The CIWA is then forwarded to the appropriate M&TE user department (s) for record search and evaluatio . . . .

The NRC inspector randomly selected five CIWAs, issued subsequent to the last plant outage, documenting M&TE nonconforming conditions which may or may not have impacted on previous calibrations performed on permanently installed plant instrumentatio The following were the five CIWAs selected for review:

CIWA 031565, issued March 4, 1987 CIWA 031566, issued March 4, 1987 CIWA 031598, issued March 24, 1987 CIWA 031599, issued March 26, 1987 CIWA 031600, issued March 26, 1987 In an attempt to locate the documents for review, the NRC inspector contacted the cognizant plant engineering document control enginee Two of the documents (CIWAs 031596 and 031599) were readily obtainable from the permanent records vault. A record search, utilizing the computerized plant engineering maintenance tracking system (MTS) indicated that the remaining three CIWAs were still in-process and retained by the plant maintenance Instrument and Control (I&C) department. In further pursuit of the documents, the NRCinspectorcontactedthecognizantI&C(acting) supervisor,whoin turn queried his MTS computer, which indicated all three CIWAs were closed and the documents were not in the possession of the I&C departmen LP&L Procedure UNT-5-009, " Administrative Procedure Dispositioning of M&TE Nonconformances," Revision 0, dated October 12, 1986, states in paragraph 4.3, "The Nuclear Quality Assurance Manager is Responsible I for the Final Acceptance and Closeout of the M&TE Nonconformance

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Evaluation." In discussing this matter with the cognizant quality

, assurance engineer, it was established that CIWAs 031565, 031566, and 031600 were not received by the QA engineer for final closecut, nor was there any immediate information as to where the documents could be located. The QA engineer stated that he would pursue a records l search in order to locate the specific CIWAs and determine the discrepancy reflected in the MTS computer tracking syste In discussing this matter with the plant manager, the NRC inspector expressed concern that there is an appearance that the current system of handling M&TE nonconformances could present a potential for an inordinate time delay in identifying an out-of-tolerance condition affecting the operability of TS equipment or other safety-related equipmen The NRC inspector identified this matter as an unresolved ite (382/8612-01)

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.4., 'UnresolvhdItems- '

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. . l Unresolved 11tems are matters 7about which more.information is required in- 'I torder to: ascertain.whether:or not-the' items are.. acceptable, violations, or:

deviations. iThe following unresolved' item was discussed in this report: 1 paragraph 3.b. Item 382/8712-0 :)

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5. .. Exit Meetin .

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L EThe inspection scope'and findings were summarized on June'19, 1987, with- u i the olant manager and the NRC senior resident inspecto ~

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