IR 05000382/1990012

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Insp Rept 50-382/90-12 on 900529-0601.No Violations or Deviations Noted.Major Areas Inspected:Licensee Surveillance Procedures & Records
ML20043G793
Person / Time
Site: Waterford Entergy icon.png
Issue date: 06/12/1990
From: Seidle W, Singh A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20043G791 List:
References
50-382-90-12, NUDOCS 9006210139
Download: ML20043G793 (5)


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-APPENDIX

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NRC Inspection Report: 50-382/90-12 Operating License: NPF-38 e

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Docket: :50-382

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3@,.f Licensee:: EntergyOperationsi_Inc.(E01)

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P.O.. Box B-i

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K111ona, Louisiana.70066

!$ i QO facility.Name: Waterford-3SteamElectricStation, Unit 3.(W-3)

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Inspection'At: W-3 Taft, Louisiana

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Inspection' Conducted: May 29 through June 1, 1990-

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A nspector:

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A. Singh,. Reactor _ Inspector, Test Programs Date Section,_ Division of Reactor Safety

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Accompanied i-4

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W. C. Seidle,_ Chief, Test Programs Section

' Division of Reactor Safety (May 31 through. June l1).

. Approved:

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'W. C. Seidlei Ehief, Test Programs Section Date.

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Division 'of'.R6 actor Safety Lins'pection Sunmary-

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j l Inspection Conducted May 29 through June 1. 1990L(Report 50-382/90-12),

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. Areas' Inspected:. Routine, unannounced insp'ection of the licensee s

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surveil.lanceprocedures=(SPs)andrecords.

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ResultsiWithin the area inspected,:no violations'or deviations were identified.

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,,LThe licensee's.SPs and records' reviewed by~the inspector met the Technica1L

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L Specifications.(TS), requirements. Acceptance criteria were clearly stated-and, in-each.. instance, thf SP! records indicated the criteria had been met.

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9006210139 900615 ADOCK ODO g 2 PDR L,

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DETAILS 1.-

PERSONS CONTACTED y

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  • G. M. Davis, Event Assessment Manager I

'*C. E. DeDeaux,-Technical Specification Coordinator

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- *J.G.Hoffpauir,PlantSystemsSuperintendent(ActingPlantManager)

t J. E. Howard, Procurement / Programs Engineering Manager

  • J. Houghtailing,' Operations Technical Manager

- *L.'W. Laughlin, Site Licensing Supervisor A. S. Lockhart Quality Assurance Manager J. R. McGaha, Plant Manager

  • T. H. Smith, Plant Engineering Superintendent
  • R. S. Starkey, Operations Superintendent NRC l

S. Butler, Resident Inspector The inspector also interviewed other licensee personnel during the inspection.

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2.

SURVEILLANCE PROCEDURES AND RECORDS (61700)

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The purpose of this inspection was to ascertain whether the surveilltnce of

. safety-related systems and components was being conducted in accordance with approved procedures,~as. required by the TS.

The inspector selected the TS surveillance requirements and components listed in the inservice inspection (ISI) and inservice testing (IST) plans. The inspector reviewed the associated 20 test procedures and the ty t results records for each procedure, which involved eight different saf ety-related systems. The TS requirements of ISI and IST components together with the

. associated test procedures reviewed by the inspector are listed in the Attachment.

The inspector determined that the required tests were being scheduled and performed in accordance with approved procedures.. The acceptance criteria were

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specified in the procedures reviewed, and the records indicated that the acceptance criteria had been met. Appropriate instructions were given for

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returning equipmerit to service following testing. Also, the inspector reviewed

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selected training records for test personnel. The review indicated that the q'

personnel involved had received appropriate training and had received their certifications.

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Theuinspector reviewed Procedure 09-903-008, " Reactor Coolant System Isolation Leakage Test Data Sheet," and Procedure OP-903-098. "RCS Vent System Functional

. Check & Valve Lineup Verification." The inspector reviewed 55 data-sheets involving-the past two refueling outages that were associated with

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Procedure OP-903-008. Out of 55 data sheets reviewed, the inspector noted nine i

data entry errors. These data sheets had been independently verified, but the

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errors were not detected. These errors were perceived by the inspector to be

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~7 minor in nature; however, the potential existed whereby a more significant I

error (s) could have led to a safety concern.

It should be noted tb.Lc all of

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the data sheets reviewed by the inspector met the acceptance criceria. The errors identified on the data sheets were, for the most part, the result of=

format weaknesses with the data sheets. The licensee indicated that'it would

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take prompt action to correct the weaknesse; in the format of the data sheets, and thereby reduce the probability of data entry errors by the performer. The improved data sheets would also be more user friendly with regard to performing independent verifications.

Also, with regard to Procedure OP-903-098 the inspector noted a minor error in the

data sheet column heading; the heading should have been, "RCS Vent Header,"

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instead of "Ventline Pressure." The licensee took prompt action to correct the error in the mislabeled heading.

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Within the scope of this inspection, no violations or deviations were a

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identified.

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3. -EXIT MEETING-

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An exit meeting was held on June 1, 1990, with personnel identified-in-paragraph 1 of this report. At the exit meeting, the inspector summarized the-scope and findings of the inspection. 'The licensee did not identify as

proprietary any of the information provided to, or reviewed by, the inspector.

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ATTACHMENT Procedure No.

Title Date OP-903-001 TechnicalSpecification(TS)

4/6/90 Revision 12 Surveillance Logs OP-903-008 ReactorCoolantSystem.(RCS)

5/20/88 Revision 2 1 solation Leakage Test OP-903-010 Emergency Core Cooling System 9/26/88 Revision 2 (ECCS) Throttle Valve Position Check

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OP-903-026 ECCS Valve Lineup Verification 3/17/89

Revision 4 OP-903-030 Safety Injection Pump 8/20/86 Rev'ision 6

_0perability Verification OP-903-033 Cold Shutdown IST 2/1/90 Revision 8 Valve Tests

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OP-903-034 Containment Spray Valve 3/17/89

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~ Revision 3 Lineup Verification

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OP-903-036 Containment Spray Actuation 1/2/87-Revision 4 Signal Test OP-903-053 Fire Protection System 5/2/89-

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Revision 7 Pump Operability Test OP-903-059 Sprinkler System 9/12/89 Revision 4 Functional Test-OP-903-066 Electrical Breaker 4/27/90'

Revision 5 Alignment Check

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' 0P-903-067 Unit Power Supply 10/12/89 Revision 5 Transfer Check OP-903-068 Emergency Diesel Generator 12/1/88

Revision 6 Operability " rification OP-903-090

. Shutdown 4 < sin 3/16/90

Revision 5

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0P-903-096 Boron Flow Rate Verification 7/13/89 Revision 3

OP-903-098 RCS Vent System Functional 7/15/88

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Revision 3 Check and Valve Lineup Verification

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Procedure No.

Title Date j

.NE-04-002-Radial Peaking Factor 1/23/87

.1; Revision 2 Verification

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MI-03-126 Core Protection Calculator-7/7/87 i

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Revision 6-Functional Test MI-03-301-Pressurizer Pressure 10/27/89 -

-j Revision 4 High loop Check and Calibration

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UNT-5-010 Administrative Procedure 9/26/87-Revision 0 Independent Verification Program

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