ML19345D663
| ML19345D663 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/10/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML19345D664 | List:
|
| References | |
| LAC-7268, NUDOCS 8012160442 | |
| Download: ML19345D663 (2) | |
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December 10, 19R0 E:g CE cdMr 2
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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 WATEP REACTOR (LACBWR)
PROVISIONAL OPERATIFG LICENSE NO. DPR-45 REPORTABLE OCCURRENCES NOS. 80-14 AND 80-15
References:
(1)
LACBWR Technical Specifications, Section 3. 9. 2.a. (3).
(2)
LACBVR Technical Specifications, Section 5.2.1.3.b.
(3)
DPC Letter, Linder to Keppler, (LAC-7253), dated November 28, 1980.
(4)
DPC Letter, Linder to Eeppler, i
(LAC-7257), dated Decenber 1, 1980.
Dear Mr. Keppler:
In accordance with Peference 1, this submittal constitutes the recuired followup report describing the occurrences which were initially reported in References 3 and 4.
The subject occurrences involved the discoveries of degradation in the primary reactor containrent during periodic Type C surveillance leakage rate testing while in a shutdown condition.
As a result of conducting periodic Type C leak tests on the Con-tainment Building Condensate Return Isolation Valve on November 27, 1980, the leakage flow rate determined from the condensate valve exceeded the permissible leakage flow rates as defined in Refer-ence 2.
The test' leakage rate was determined to be 14.3 SCFH.
The acceptance criteria is 0.375 SCFH.*
- Shall not exceed 1% of leakage rate L o, where L o is 37.5 SCFH.
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Mr. Jcmes G. Kcppler, Regional Director LAC-7268 U.
S. Nuclear Regulatory Commission December 10, 1980 The Containment Building Condensate Return Isolation Valve (73-25-021) is a Fischer, Model 667ET, 1 " valve, with a carbon impregnated teflon seal ring.
The internals of this valve were totally replaced.
Also, an evaluation of methods to improve this valve's performance is being conducted.
The post-repair leakage test performed December 2, 1980, resulted in zero leakage.
As a result of conducting periodic Type C leak tests on the Retention Tank Pump Discharge Valve on November 29, 1980, the leakage flow rate was determined to be between 0.56 and 4.0 SCFH.
The permissible leakage flow rate as defined in Reference 2, is l
0.375 SCFH.*
The Retention Tank Pump Discharge Valve (54-25-006) is a 2-inch diaphragm operated, BS&B Valve, Model 70-14-2.
This was the first failure of this valve.
The valve was relapped, the gaskets were replaced and new packing was installed.
The post-repair leakage test performed on December 4, 1980, resulted in zero leakage.
No further corrective action is considered necessary.
Licensee Event Reports (
Reference:
Appendix A, Regulatory Guide 1.16, Rev. 4) for Reportable Occurrences Nos. 80-14 and 80-15 are enclosed.
Should you have any questions regarding this submittal, please contact us.
Very truly yours, DAIRYLAND POFER COOPEPATIVE Frank Linder, General Manager FL:LSG:af Attachments cc:. Director, Office of Inspection and Enforcement (30)
U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
. Director, Office of Management Information (3) and program Control U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
.NRC Resident Insnectors
- Shall not exceed 1% of leakage rate L where L is 37.5 SCFH.
pg, pg.--
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