IR 05000409/1980017
| ML19341D529 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/16/1981 |
| From: | Hopkins J, Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19341D525 | List: |
| References | |
| 50-409-80-17, NUDOCS 8103050760 | |
| Download: ML19341D529 (4) | |
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Q U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-409/80-17 Docket No. 50-409 License No. DPR-45 Licensee: Dairyland Power Cooperative 2615 East Avenue - South La Crosse, WI 54601 Facility Name:
La Crosse Boiling Water Reactor Inspection At: La Crosse Site, Genoa, WI Inspection Conducted: December 12-18, 1980
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Inspector:
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Approved By:
J. F. Streeter, Chief, IL[8%
Support Section 1 Inspection Summary Inspection on December 12-18, 1980 (Report No. 50-409/80-17)
Areas Inspected: Routine announced inspection of the containment integrated leak rate test. The inspection involved a total of 48 inspector-hours onsite by one NRC inspector including 13 inspector-hours onsite during offshifts.
Results: No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
- J. Parkyn, Assistant Plant Superintendent G. Boyd, Operations Supervisor
- L. Goodman, Operations Engineer R. Ganser, Shift Supervisor
- R.
Brimer, Electrical Engineer
- W. Forney, USNRC Senior Resident Inspector
- M. Branch, 'USNRC Resident Inspector
- Denotes those present during the exit interview.
2.
Containment Integrated Leak Rate Test a.
Procedure Review The inspector reviewed procedure "LACBWR Operating Manual, Volume XI, Reactor Containment Building," as revised May 1979 and verified that the procedure was technically adequate and consistent with regulatory requirements.
b.
Instrumentation The inspector reviewed the calibration data associated with performing the CILRT. A multipoint calibration of all instrumentation was per-formed. Correction values were generated based on the difference between measurements of resistance from a NBS verified resistance box and actual resistance measured. All corrections were placed as an array or equation into the CILRT computer.
The following instrumentation was used in the CILRT:
Type Quantity Serial Number RTDs
5477,RTDs 1-12 Flowmeter
7901H66516 Pressure Gauge
766 Deweells
5477, Deweells 13-18 During the test, deweells 17 and 18 were declared inoperable and the weighting factors were reassigned. A new ISG (instrument selection guide) was then performed and the criteria of ISG $0.25 La was met.
c.
Witness of Test The inspector witnessed portions of the CILRT on December 14-17, 1980 and verified that:
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Appropriate revision of procedure was in use by test personnel.
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l Test prerequisites were met.
Proper plant systems were in service.
The inspector observed that Local Leak Rate Tests were performed in conjunction with the CILRT.
Two valves (reactor cavity purge and reactor vent header) failed the acceptance critwiia of 0.375 scfh for these tests. These valves will be repaired and the acceptance criteria f
met prior to resumption of plant operation.
d.
Direct Observation of Valve Lineups The inspector verified by direct visual observation that valve lineups were completed in accordance with the test procedure.
e.
Blowdown and Containment Inspection The inspector verified that blowdown was within Technical Specifica-tion radioactivity release limits. The resident inspector conducted a post CILRT containment inspection for equipment degradation after blowdown and did not identify any degradation.
f.
CILRT Data Evaluation The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CILRT was started on December 16, 1980, at 12:05 p.m.
The inspector independently monitored and evaluated leak rate data to verify the licensee's calculation of the leak rate. There was acceptable agreement between the inspector's and licensee's leak rate calculations as indicated in the following summary (units are in weight percent per day):
Measurement Licensee Inspector Leakage rate measured (Lam)
0.08920 0.0881 during CILRT Lam at 95% confidence level 0.09192 0.0933 The Technical Specification Acceptance Criterion = La = 0.1wt %/ day.
As indicated above, the Lam was less than the Technical Specification limit; however, the Technical Specifications require the leakage rate to be lesg than 0.75 La (0.075 wt%/ day) prior to resumption of plant operation. As allowed by the Technical Specifications, repairs will be made to known leak paths, including the two valves that failed the Local Leak Rate Tests, and the Lam at the 95% confidence level will be adjusted downward to 0.075 wt%/ day or less.
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Supplemental Test Data Evaluation After the satisfactory completion of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test on December 17, 1980, a known leakage of 0.06181 weight percent / day was induced. The inspector independently monitored and evaluated leak rate data to verify the licensee's calculation of the supplemental leak rate. There was acceptable agreement between the inspector's and licensee's leak rate calculations as indicated in the following summary (units are in weight percent per day):
Heasurement Licensee Inspector Measured Leakage (Lc) rate 0.13328 0.1432 during supplemental test Induced leakage rate (Lo) -
0.06181 Appendix J Acceptance Criterion:
Lo+ Lam-0. 25La < Lc dC Lo+ Lam +0. 25 La. As indicated above, the supplemental test results satisfied the requirements of 10 CFR Part 50, Appendix J.
No items of noncompliance or deviations were identified.
3.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on December 18, 1980. The inspector summarized the purpose and the scope of the inspection and the findings.
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