IR 05000382/1986034

Insp Rept 50-382/86-34 on 861208-11 & 870330-0401.Violation Noted:Local Leak Rates for Six Valves Tested Recorded as off-scale W/No Recorded Value

ML20214J915
Person / Time
Site:	Waterford
Issue date:	05/11/1987
From:	Hunnicutt D, Ireland R, Tapia J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20214J884	List: ML20214J881 ML20214J906 ML20214J915
References
50-382-86-34, NUDOCS 8705280250
Download: ML20214J915 (3)

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l APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-382/86-34 License: NPF-26 Docket: 50-382 Licen:,ee: Louisiana Power and Light Company (LP&L)

142 Delaronde Street New Orleans,' Louisiana 70174 Facility Name: Waterford Steam Electric Station, Unit 3 Inspection At: Taft, Louisiana Inspection Conducted: December 8-11, 1986, and March 30 through April 1, 1987

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Inspector: f.o d 5 f 6 f Bb Date'

J. Jr.Japia, Operagns Section, Reactor

S Wety Branch Reviewed: . I9 k bo-p6 D. M. Hunnicutt, Chief, Operations Section 5/4/f7 D&te'

Reactor Safety Branch Approved: [ d. C- @///F'7 R. E. Ireland; Acting Chief, Operations Date Section, Reactor Safety Branch Inspection Summary Inspection Conducted December 8-11, 1986, and March 30 through April 1, 1987 (Report 50-382/86-34) +

Areas Inspected: Routine, unannounced inspection of the Local Leak Rate Testing Progra Results: Within the one area inspected, one violation was identifie '

8705280250 870519 PDR ADOCK 05000302 G PDR

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DETAILS 1. Persons Contacted T. F. Gerrets, Nuclear QA Manager R. F. Buski, Engineering Manager N. S. Carns, Plant Manager D. Schultz, Shift Technical Advisor (STA), Supervisor R. Peters, STA K. Brewster, Licensing G. Forgala, Shift Supervisor 2. Containment Local Leak Rate Testing Program Implementation of the ongoing containment local leak rate test (LLRT)

program was addressed during an inspection conducted on December 8-11, 1986. Subsequent to that inspection, the NRC inspector performed an in-office review of all local leak rate test data and applicable Condition Identification Work Authorization LP&L Surveillance Procedure No. PE-5-002, Revision 3, " Local Leak Rate Test," was reviewed by the NRC inspector to verify compliance with the specified test requirements and acceptance criteria contained in 10 CFR Part 50, Appendix J, " Primary Reactor Containment Leakage Testin for Water Cooled Power Reactors," and in Section 3/4.6.1 of the plant Technical Specification The review provided verification that the following test attributes were correctly addressed: All applicable penetration boundaries and isolation valves were subjected to local leak rate testin Local leak rate tests were performed at peak accident pressur The local leak rate test program utilized an approved method for testin Penetration leakage rates were determined using the maximum pathway leakage, Criteria and response were specified for local leak rate test and combined leakage rate failure, Criteria and response were specified for the failure of components specifically cited in the Technical Specification The instrument calibration certifications traceable to the U.S. National Bureau of Standards for four rotometers, one pressure and one temperature

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gauge used in the local leak rate testing program were reviewed by the NRC inspector. Three local leak rate tests performed on three valves were witnessed by the NRC inspector to determine if the licensee was properly complying with regulatory and procedural commitment The continuous running sum of local leak rates for all penetrations and isolation valves required to be subjected to local leakage rate testing is required by 10 CFR Part 50, Appendix J, to be less than 0.60 La, where La is the maximum allowable leakage rate at the calculated peak containment internal pressure related to the design basis loss of coolant accident (Pa). With an La value of 0.5 percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by weight at 44 psig, 0.6 La equates to 63,070 cc/ min. The method used to obtain the continuous running sum of local leak rates is to add the new test results and subtract the previous results for the same penetrations and isolation valves tested to the combined local leak rate sum. The NRC inspector reviewed the local leak rate data sheets to determine if the sum of the local leak rates for all boundaries and valves suoject to local leak rate testing met the acceptance criteri From a review of the local leak rate data sheets, it was determined that six valves had recorded as-found results of "off-scale" with no value entered. The required comparison with the Appendix J requirement of 0.6 La could therefore not be made for the as-found condition. This is an apparent violation (382/8634-01) of the above requiremen . Exit Interview The NRC inspector met licensee representatives and the resident inspector at the conclusion of the inspection on Decembu 11, 1986. The NRC inspector informed the licensee of the apparent violation and also informed the licensee that additional in-office review would be required prior to its issuance.