ML20055C097
| ML20055C097 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/02/1982 |
| From: | Mclendon G LOUISIANA POWER & LIGHT CO. |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 26, W3K-82-0473, W3K-82-473, NUDOCS 8208100229 | |
| Download: ML20055C097 (3) | |
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l LOUISIANA 342 OuAnONot S1nar POWER & LIGHT P O BOX 6008
- NEW ORLEANS. LOUISlANA 70174 * (504) 366 2345
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August 2, 1982 G. D. McLENDON Senior wce President W3K-82-0473 Q-3-A35.07.26 Mr. John T. Collins, Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012
SUBJECT:
Waterford SES Unit No. 3 Docket No. 50-382 Final Report of Significant Construction Deficiency No. 26
" Main Feedwater Isolation Valves - Temperature Maintenance of Actuators"
Reference:
LP6L Letter to USNRC W3K-82-0355 dated June 17, 1982
Dear Mr. Collins:
In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Final Report of Significant Construction Deficiency No. 26,
" Main Feedwater Isolation Valves - Temperature Maintenance of Actuators."
If you have any questions, please advise.
Very truly yours, MM C. D. Mc L enlon GDMcL/LLB/grf Attactuaent h h ))\\',/[j %
cc: 1) Director Office of Inspection & Enforcement I & -- -
3 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l
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- 2) Director Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555
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(with 1 copy of report) 8208100229 820802 PDR ADOCK 05000382 5
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LOUISIANA POWER & LIGff COMPANY r
NATEREDRD SES UNIT No. 3 Final Report of Significant Constnution Deficiency No. 26
" MAIN FEEDWATER ISOIATION VAIVES -- TEMPERA'IURE MAINTENANCE OF ICTUATORS"
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,l FINAL REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 26
" MAIN FEEDWATER ISOLATION VALVES - TEMPERATURE MAINTENANCE OF ACTUATORS" J
INTRODUCTION This report is submitted pursuant to 10CFR50.55(e).
It describes deficiencies in the Main Feedwater Isolation Valve Actuators relative to the closure of the Main Feedwater Isolation Valves within a specified time from receipt of the Main Steam Isolation Signal. This problem is considered reportable and to the best of our knowledge, this problem has not been identified to the Nuclear Regulatory Commission pursuant to 10CFR21.
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DESCRIPTION The Ebasco Assistant Chief. Mechanical Nuclear Engiaee'r was informed of'this de-ficiency by Anchor Darling Valve Company via telex dated February-24,1,981,-at which time it was indicated that the Feedwater Isolation Valves will not meet the specification closing speed requirement in ambient temperatures below 65'F and may not close at all in extremely emld temperatures.
It was" furthdr identi-fied that this poses a serious design' deficiency that may jeopardize the safe operation of the plant and must be corrected. The valves affected are 2FW-V824B and 2FW-V823A which are 20-inch motor-operated gate valves, Nuclear Safety Class 2.
i SAFETY IMPLICATIONS The Waterford 3 Main Feedwater Isolation Valves are exter'nally located and there-fore exposed to the ambient environment. The Main Steam Live Break analyses, as described in FSAR Sections 6.2.1.1.3 and 15.1.3 assume closure of the Main Feed-water Isolation Valves in a specified time from receipt of'the Main Steam Isolation Signal.
Failure of these valves to clos'e'due to' cold ambient temperature in the specified time period could invalidate the results of these analyses.
CORRECTIVE ACTION Corrective action has been completed for the protection of the Feedwater Isolation Valve Actuators as follows for Valves 2FW-V8243 and'2FW-V823A. FCR-E-2654 was issued to cut and modify the protective shrouds, FCR-E-2471 was issued for the installation of the heaters and thermostats, and DCN-E-684 was issued to provide i
instructions for installation of the heater switch.
In oar referenced letter, we l
reported two nonconforming conditions resulted during the rework. These condi-tions were reported on Nonconformance Reports W3-3872 and W3-1843. The correc-t tive action required by these Noncoaformance Reports has been completed, and the Nonconformance Reports are closed. 'CIWA'8,22574 has also'bacn closed.
Corrective action take, to preclude recurrence isLas follows.
DCN-E-684, FCR-E-2654, ncorporate dssign changes which will preclude the and FCR-E-2471 were issued to i problem reported by Significant egnstruction Deficiency No. 26 from recurring.
Full corrective action was achieved.on July 28, 1982.
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