ML19270F317
| ML19270F317 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/01/1979 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML19270F318 | List:
|
| References | |
| LAC-6103, NUDOCS 7902060246 | |
| Download: ML19270F317 (3) | |
Text
a Dit1EtYLitND POWEli C00PEft<tTIVE Sa Crone, Ohsconsin 54601 February 1, 1979 In reply, please refer to LAC-6103 DOCKET NO. 50-409 Mr. James G.
Keppler Regional Director U.
S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 REPORTABLE OCCURRENCE NOS. 79-03 AND 79-H
Reference:
(1)
LACBWR Technical Specifications, Section 3.9.2.a.
(2)
DPC Letter, LAC-6079, Linder to Keppler, dated January 19, 1979.
(3)
LACBWR Technical Specifications, Section 5.2.1.3.(b).
Dear Mr. Keppler:
In accordance with the provisions of Reference 1, this submittal constitutes the required follow-up report describing the occurrences which were initially reported in Reference 2.
The subject occur-rences involved the discovery of abnormal degradation in the primary reactor containment during periodic Type C surveillance leakage rate testing.
As a result of conducting periodic Type C leak testing on January 18 and 19, 1979, respectively, the leakage rate from the
" Condensate Demineralizer to Seal Injection Reservoir Makeup Line Containment Isolation Valve", No. 52-26-039, and the " Demineralized Water Containment Isolation Valve", No. 67-26-001, were both deter-mined to exceed the permissible leakage flow rates as prescribed in LACBWR Technical Specifications (Reference 3).
The test leakage rate of the seal injection makeup isolation valve was determined to be 0.684 SCFH and the test leakage rate of the demineralized water isolation valve was determined to i: 0.597 SCFH.
The Tech-nical Specification leakage rate acceptance criteria is 7 9 0 2 0 6 0 ;Z V6
Mr. James G. Keppler LAC-6103 U.
S. Nuclear Regulatory Commission February 1, 1979 0.375 SCFH* for each valve.
- The permissible leakage rate shall not exceed 1% of leakage rate L where L pg pg is 37.5 SCFH.
The seal injection n.akeup isolation valve, which is a Hancock Model 5540W check valve, was disassembled and inspected.
No abnormalities were detected in the seating surfaces that might have caused the indicated leakage rate.
However, the seat and disc were lap;>ed and the valve reassembled.
A post maintenance leak test was performed on January 18, 1979, indicating a leakage rate of 0.016 SCFH, resulting in compliance with leakage rate accep-tance criteria.
No further corrective action was performed.
The demineralized water isolation valve, which is a Crane Model 373 check valve, was disassembled and inspected.
Surface irregular-ities were noticed on the seat and disc as a result of normal Repairs consisted of replacing the seat and lapping the wear.
seat and valve disc.
A post maintenance leak test was performed on this valve on January 19, 1979, which resulted in an indicated leakage rate of 0.022 SCFH, which is within the permissible leak-age rate acceptance criteria.
No further corrective action was performed.
The plant was in Operating Condition 4, Cold shutdown,during the conduct of both tests.
In our initial written r7tification (Reference 2), the occurrences surrounding the leakage results of the two subject valves were combined unde; one reportable occurrence number (79-03).
The reportable occurrence designation has been reassigned.
Reportable Occurrence No. 79-03 shall remain assigned to the occurrence re-garding the " Condensate Demineralizer to Seal Injection Reservoir Makeup Line Containment Isolation Valve" and Reportable Occurrence No. 79-04 shall be assigned to the occurrence regarding the
" Demineralized Water Containment Isolation Valve".
Two (2) Licensee Event Reports (Ref. Appendix A, Regulatory Guide 1.16, Rev. 4) are enclosed.
Should you hat any questions regarding this submittal, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE Frank Linder, General Manager FL:LGP:af Mr. James G. Keppler LAC-6103 U. S. Nuclear Regulatory Commission February 1, 1979 cc:
Director, Office of Inspection and Enforcement (40)
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Director, Office of Management Information and (3)
Program Control U.
S. Nuclear Regulatory Commission Washington, D. C.
20555