IR 05000409/1979011
| ML19254A690 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/24/1979 |
| From: | Reyes L, Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19254A687 | List: |
| References | |
| 50-409-79-11, NUDOCS 7907240191 | |
| Download: ML19254A690 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report No. 50-409/79-11 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: May 15-17, 1979 C
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Inspector:
L. A. Reyes 2.Ll!,/ g1 tTc&Ts Approved By: J F. Streeter, Chief M., [~l#i Nuclear Support Section 1
[nspect_ ion Summay Inspection on May_15-17, 1979 (Report No. 50-409/79-11)
Areas in spec _t ed : Routine, unannounced inspection of the performance of the containment integrated leak rate test.
The inspection iuvolved 27 inspector-hours onsite by one NRC inspector.
_R e s ul t s :
No items of noncompliance or deviations were identified.
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i DETAILS 1.
Persons Contacted
- R. Shimshak, Plant Superintendent J. Parkyn, Assistant Plant Superintendent
- L. Papworth, Operations Engineer
- L.
Kelley, Security Director H. Towsley, QA Supervisor G. Boyd, Operations Supervisor P. Wiley, Training and Relief Supervisor The inspector also contacted several other licensee employees, including members of the technical and engineering staffs, reactor and auxiliary operators, and clerical personnel.
- Denotes those attending the exit interview.
2.
Previous Inspection Findings (Closed) Unresolved Item (Inspectio-Report 50-409/78-14, Paragraph 6.a).
The volume weighting factors for the resistance temperature detectors and dewpoint detectors were revised so their summation is equal to unity.
3.
Containment Integrated Leak Rate Test (CILRT)
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 May 16, 1979, at 0010. The inspector independently 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) during 0.05121 0.05145 CILRT Lam at 95% confidence level 0.05317 0.05341 Appendix J Acceptance Criterion at 95% confidence level = 0.75 La
= 0.75 (0.1) = 0.075.
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As indicated above, Lam at the 95% confidence level was less than the maximum allowable by 10 CFR Part 50, Appendix J.
No items of noncompliance or deviations were identified.
4.
Supplemental Test Af ter the satisf actory completion of the 24-hour test on May 17, 1979, a known leakage of 0.06028 weight percent p.c day was induced.
The inspector independently evaluated leak rate data to verify the licensee's calculation of the supplemental leak rate.
There was acceptable agreement ce tween 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 Measured leakage (Lc) rate during 0.10855 0.10879 supplemental test Lc at 95% confidence level 0.13554 0.13577 Induced leakage rate (Lo) = 0.06028 Appendix J Acceptance Criterion:
Lo+ Lam-0.25La 4; Lc ( Lo+ Lam +0.25La 0.06028 + 0.05145 - 0.25 (0.1) 4 Lc c 0.06028 + 0.05145 +
0.25 (0.1)
0.08673 z. Le e;0.13673 As indicated above, Lc satisfied the requirements of 10 CFR Part 50, Appendix J.
No items of noncompliance or deviations were identified.
5.
Instrumentation The inspector reviewed the calibration data associated with performing the CILRT.
A multipoint calibration of all instru-mentation was performed.
Correction values were generated-3-
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t 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
776 Dcwcells
5477, Dewcells 1-6 No items of noncompliance or deviations were identified.
6.
CILRT Procedure Review The inspector reviewed a copy of the test procedure, "LACBWR Operating Manual, Volume XI, Reactor Containment Building,"
Revision May 1979, for technical adequacy and conformance with regulatory requirements. The inspector noted that the procedure did not contain data rejection criteria.
The inspector stated that past experience with CILRTs indicates that individual data points are sometimes erroneous for various reasons and that these erroneous data points cannot be rejected without a definitive data rejection criteria.
The inspector stated that the draft Alls 274 standard contains acceptable data rejection criteria. There were no data points rejected during the 1979 CILRT.
No items of noncompliance or deviations were identified.
7.
Valve Lineup The inspector reviewed the valve lineup by checking the tags and valve position indicators in the control room versus the test procedure valve lineup.
No items of noncompliance or deviations were identified.
8.
LACBWR ILRT Report No. LAC-TR-066 The inspector reviewed the report for the 1978 ILRT. The inspector noted that information available on electrical penetration failure history indicated that repairs performed,
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e which consisted of cleaning and recoating the affected cable penetration glanda and adjacent containment wall areas with epoxy sealant compound, only provided temporary leak tightness.
The licensee stated that during the refueling outage repairs were effected which consisted of replacement of the entire individual MI cable penetration at penetration locations 6A, 13B, and ISB on Unit No. 3 and SB, 8A, ISB, and 19A on Unit No.
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The licensee also stated that penetrations llA and 14B glands on Unit No. 3 were cleaned and coated with Velodour Metal, a sealing product that is believed to provide signif-icant improvement over the previously used sealing material.
The licensee also stated that addiational replacements will be made if further degradation involving cracked fittings of electrical penetration gland seals is observed during subse-quent leak tests.
No items of noncompliance or deviations were identified.
9.
Exit Interview An exit intttview was conducted at the conclusion of the inspection with tne licensee representatives denoted in Paragraph 1.
The total leak rate after all corrections were included was determined by the licensee to be 0.05341 weight percent / day.
The CILRT confirmed tha the containment leak rate was acceptable.
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