IR 05000382/1986034

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/86-34

ML20236K439
Person / Time
Site:	Waterford
Issue date:	08/04/1987
From:	Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Dewease J LOUISIANA POWER & LIGHT CO.
References
NUDOCS 8708070120
Download: ML20236K439 (2)

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.*'s In Reply Refer To:

Docket: 50-382/86-34

$1W Louisiana Power & Light Company ATTN: J. G. Dewease, Senior Vice President Nuclear Operations 317 Baronne Street New Orleans, Louisiana 70160 Gentlemen:

Thank you for your letter of June 18, 1987, in response to our letter and Notice of Violation dated May 19, 198 We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine

Sincerely,

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• :ct Signed by; WLU J. E. Gagliardo, Chief Reactor Projects Branch cc:

Louisiana Power & Light Company ATTN: G. E. Wuller, Onsite Licensing Coordinator P. O. Box B Killona, Louisiana 70066 Louisiana Power & Light Company ATTN: N. S. Carns, Plant Manager P. O. Box B Killona, Louisiana 70066 Middle South Services ATTN: Mr. R. T. Lally P. O. Box 61000 New Orleans, Louisiana 70161 f'

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Louisiana Power & Light Company 2 Louisiana Power & Light Company ATTN: K. W. Cook, Nuclear Safety and Regulatory Affairs Manager 317 Baronne Street P. 0. Box 60340 New Orleans, Louisiana 70160 Louisiana Radiation Control Program Director bec to DMB (IE01)

bec distrib. by RIV:

• RPB *D. Weiss, RM/ALF

• RRI R. D., Martin, RA

• Section Chief (RPB/A) DRSP RPSB *RSB

• MIS System * Project Inspector, RPB

• RSTS Operator *R. Hall

• RIV File *J. Wilson, NRR Project Manager J. Tapia SectionChief(RSB/05)

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LOUISI& AN POWER A LIGHT / 317NEW BARONNESTREET * P. O. BOX 60340 ORLEANS, LOUISIANA 70160 + (504) 595-3100

$@i?O sYsVIO June 18, 1987 W3P87-1700 A4.05 QA U.S. Nuclear Regulatory Commission I IN@[5IlV//:

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ATTN: Document Control Desk 'I f

Washington, D.C. 20555 j M l 9 lg8'[

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w Subject: Waterford 3 SES l Docket No. 50-382 -

License No. NPF-38 NRC Inspection Report 86-34 Attached is the Louisiana Power and Light Company (LP&L) response to l Violation No. 8634-01 identified in Inspection Report No. 86-3 If you have any questions on the response, please contact G.E. Wuller, Operational Licensing, at (504) 464-349 Very tr y yours, jk Ye .v

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K.W. [ook Nuclear Safety and Regulatory Affairs Manager KWC:PTM:pmb Attachment cc: R.D. Martin, NRC Region IV J.A. Calvo, NRC-NRR J.H. Wilson, NRC-NRR NRC Resident Inspectors Office E.L. Blake W.M. Stevenson 54 ~

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( "AN EQUAL OPPORTUNITY EMPLOYER" fc41 1%i

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1. , o Attachnsnt to W3P87-1700 Sheet 1 of 2 LP&L Response to Violation No. 8634-01 VIOLATION NO. 8634-01 Failure to Quantify Containment Isolation Valve Leakage The requirements of Appendix J to 10CFR Part 50.54(o), are invoked as a condition of the license for all water cooled power reactors. Appendix J requires that a continuous running tum of local leak rates for penetrations and isolation valves subjected to this testing not exceed 0.6 times the maximum allowable leakage rate at the calculated peak containment internal pressure related to the design basis loss of coolant acciden Contrary to the above, it was found during the week of December 8-11, 1986 that the local leak rates for six valves required to be tested had recorded as-found leak results of "off-scale" with no recorded value, so that the continuous running sum of local leak rates was not known and the required comparison with the Appendix J criterion could not be made for the as-found conditio This is a Severity Level IV violatio RESPONSE (1) Reason for the Violation The requirements of Appendix J Section III.C.3 to 10CFR Part 50 as invoked through Part 50.54(o) states in part: "The combined leakage rate for all penetrations and valves subject to Type B and C tests shall be less than 0.60 La." At the time the local leak rate testing was being performed the plant was in Mode As the result of local leak rate testing, six valves had as-found leak rates which exceeded the capability of the test equipmen The data as recorded was identified as "off scale" with no numerical value identified. During this inspection the NRC inspector noted that because of the recorded values of "off scale" he was unable to ascertain if the criterion of 0.60 La for leakage was satisfie (2) Corrective Action That Has Been Taken Prior to performing maintenance on the six valves the local leak rate test configuration was modified to provide a greater flow measuring capability. Of the six valves identified as having leak rates of "off scale", numerical values were identified for 5 of these valves. The sixth valve, a 24 inch contc1nment vacuum check valve (CVR-102) could not be pressurized with the modified test unit, thus r.o leak rate could be establishe Correctiva action was initiated by maintenance on all six valves and the appropriate retests were conducted. Acceptable leak rates were .

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identified for these valves prior to returning to Mode 4. In accordance with the Appendix J criterion the required comparison for

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1. '# Attachment to W3P87-1700 Sheet 2 'f 2 the as-found condition could not be made for CVR-10 For the purpose of this test it was assumed that the leakage for CVR-102 wculd result in exceeding the 0.60 La limi As per Appendix J Section V. requirements this valve will be reported in a separate accompanying summary report to the " Reactor Containment Building Integrated Leak Rate Test" repor The ability to indicate and quantify leakage ratea has been increased to account for valves with larger leak rate A continuous running sum total leak rate has been established to be able to, at any time, identify present leakage as compared to the 0.60 La limi It is conceivable in the future that a gross leskage may exceed the capability of our test uni In this event, alternative test methods or evaluations will be conducted to determine whether the 0.60 La criteria for Type C testing is met and a summary report will be prepared in accordance with Appendix J Section V. (3) Corrective Action To Be Taken Surveillance Procedure (PE-5-002) " Local Leak Rate Test (LLRT)" will be modified to maintain a continuous running sum of leak rates that fall within the 0.60 La criteria. Failed valves will be reworked and retested to ensure the total leakage is less than 0.60 La prior to entering a mode where the requirement exist (4) Date When Full Compliance Will Be Achieved Changes to the surveillance Procedure " Local Leak Rate Test (LLRT) are expected to be complete by July 15, 198 .

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