ML20214J915

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)

See also: IR 05000382/1986034

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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

8

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 Program.

Results: Within the one area inspected, one violation was identified.

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PDR ADOCK 05000302

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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 Authorizations.

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 Testing.

for Water Cooled Power Reactors," and in Section 3/4.6.1 of the plant

Technical Specifications.

The review provided verification that the following test attributes were

correctly addressed:

a. All applicable penetration boundaries and isolation valves were

subjected to local leak rate testing.

b. Local leak rate tests were performed at peak accident pressure.

c. The local leak rate test program utilized an approved method for

testing.

d. Penetration leakage rates were determined using the maximum pathway

leakage,

e. Criteria and response were specified for local leak rate test and

combined leakage rate failure,

f. Criteria and response were specified for the failure of components

specifically cited in the Technical Specifications.

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 commitments.

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 criteria.

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 requirement.

3. 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.