ML20214J915
| 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: |
| 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:
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
J. Jr.Japia, Operagns Section, Reactor
Date'
8
S Wety Branch
Reviewed:
. I9 k bo-p6
5/4/f7
D. M. Hunnicutt, Chief, Operations Section
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)
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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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8705280250 870519
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.