IR 05000409/1979006
| ML19261D750 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 04/20/1979 |
| From: | Ridgway K, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19261D748 | List: |
| References | |
| 50-409-79-06, 50-409-79-6, NUDOCS 7906260315 | |
| Download: ML19261D750 (6) | |
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U.S. NUCLEAR REGl'LATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-409/79-06 Docket No. 50-409 License No. DPR-45 Licensee:
Dairyland Power Cooperative 2615 East Avenue - South La Crosse, WI Fa c ili t:, Name:
La Crosse Boiling Water Reactor Inspection At:
La Crosse Boiling Water Reactor, Genoa, WI Inspection Conducted:
March 26-29, 1979 i>
E, /s A. '.%, W. ~,'
Inspector:
K.
R.
Ridgway
?s 7,;
b!/t$ /C. /
a-,
F.Warkick, Chief 4/2e/>6 d
Approved By -
R.
C" Reactor Projects Section 2
/
Inspection Summary Inspection on March 26-29, 1979 (Report No. 50-409/79-06')
Areas Inspected: Routine announced inspection of the licensee's handling, packaging and shipping of spent fuel assemblies; compliance with Department of Transportation requirements; operations during refueling; and follovup actions re.'ative to previous items of non-compliance, IE Circulars, Licensee Event Reports, open inspection items and special reports. The inspection involved 31 inspector hours onsite by one NRC inspector.
Results:
No items of noncompliance were identified in the ten areas inspected.
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DETAILS 1.
Persons Contacted R.
Shinshak, Plant Superintendent
- J.
Parkyn, Assistant Plant Superintendent
- G.
Boyd, Operations Supervisor P. Wiley, Assistant to Operations Supervisor R. Prince, Radiation Protection Engineer L. Krajewski, Health and Safety Supervisor
- H.
Towsley, Quality Assurance Supervisor S. Rafferty, Reactor Engineer
- L.
Papworth, Operations Engineer J. Gallaher, Security and Fire Protection Supervisor N. Hoefert, Mechanical Engineer L. Kelley, Shift Supervisor P. Gray, Supervisor, Mechanical Maintenance D.
Stalsberg, Shift Supervisor J. Kegerreis, Shift Supervisor In addition, the inspector observed and held discussions with other engineers, plant equipment operators, reactor operators, assistants, and plant attendants.
- Denotes those present at the exit interview.
2.
General The plant was shutdown on March 25, 1979, for a scheduled six week refueling outage.
During the first outage week, eight spent fuel assemblies were shipped to General Electric Company's Morris Operation. The licensee plans to examine the peripheral shroud and if there is no indication of further cracking, it will not be changed out this outage.
It will be changed out after the new spent fuel racks are installed late in 1979.
This will permit unloading the core and reducing personnel exposure during the shroud replacement work.
3.
Plant Operations Review The inspector observed plant outage conditions, irradiated fuel cask loading and shipping, control room manning, and equipment tag out status during a plant tour.
Additionally, the following records were reviewed from February 26 - March 26, 1979, to determine compliance with Technical Specifications and regulations 2311 051 2-
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and to determine if Night Orders and Operating Menos conflicted in any way with operating requirements:
a.
DO-18 Log Books b.
L-84 Control Rod Position indications c.
L-83 Reactor Plant Log d.
L-82 Turbine Generator Plant Log e.
L-74 Control Room Panel A f.
L-42 Radiation Manitor and Dew Cells g.
L-119 AGS and Reactor Safety Fystem Log h.
L-72 Turbine Generator Auxillary log 1.
L-73 Reactor Plant Aux 111ary Log j.
L-68/ 71 Temperature Recorder Log k.
Night Order Instruction Book (December 1978 to Yarch 26, 1979)
1.
Shift Supervisors Log January 1, 1979 to February 10, 1979 m.
Incident Reports December 1978.
No items of noncompliance were identified.
4.
Spent Fuel Pool Activities, Routine l'se of Shippine Packages, and DOT Regulations Because of limited storage space in the spent fuel pool, it was necessary for the licensee to ship cight spent fuel assemblies to the General Electric Company's Morris Operation.
These shipments were made between March 26 and April 3, 1979, in two Nuclear Assurance Casks (NAC-1), Model NFS-4, Certificate of Compliance No. 669S, Revision No. 7, dated August 14, 1978.
The carrier was Tri State Motor Transit.
The fuel selected for shipping had been out of the reactor for fcur or more years with the decay heat generation estimated to be 0.2 KW and thus the cask was shipped dry.
Because of a restriction in one side of the internal cannisters, each shipment contained only one assembly.
During the first cask loading it was determined that the cannister spacers provided by NAC were over an inch too long, preventing the cask head to close.
The fuel assembly was removed, the spacers shortened and the assembly reloaded without further problems.
The second cask loaded, NAC-1C, had been shipped to LACBWR from Nuclear Fuel Services, New York, with the cask full of water.
Ice had formed under the cask lid with some formation also present inside the cannister. After removing the ice and completing the loading, the cask passed both the required quarterly ten minute
"0-ring" test at 200 psig and the cavity pressure test at 80 psig.
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The inspector reviewed the approved Special Procedure M-07-78, Irradiated Fuel Shipment (NAC-1/NFS-4 Cask).
The approved pro-cedureinclypedtherequestedadditionsmadeduringaprevious inspection.-
The inspector observed the loading and handling of the first two shipments and reviewed the shipping records per-taining to them.
Dose rates and removable contamination were within Department of Transportation (DOT) Regulations as follows:
Shipment DOT Ei c,by h (a )
Limit First Second
'
Dose rate package 1,000
70
surface mrem /hr Dose rate at vehicle 200
2
surface mrem /hr Dose rate at six feet
2
3 from vehicle mrem /hr Dose rate in vehicle
0. 3 0.5 0. 5 cab mrem /hr Removable coptamination 22,000 13,926 9,920 13,760 dpn/100 cn" (a) Readings of the eighth shipment were confirmed by members of the State of Wisconsin Department of Health and Social Services, Radiation Protection Section at the reactor site.
The inspector determined that DOT requirements for records, labeling and placarding were in the procedure and were followed during the shipping campaign.
No items of noncompliance were identified.
5.
Review of Licensee Event Reports (LER's)
The inspector reviewed the following LER's to determine if the reports were correct and if the evaluations and corrective actions taken were completed as stated in the LER.
a.
(Closed)
LER 50-409/79-02, Failure of three electrical penetrations (No's 3, 4 and 6) to pass the Type B contain-ment leak rate test.
The three penetrations were repaired 1/ IE Inspection Report No. 50-409/79-02.
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and satisfactorily retested.
The licensee has ordered and will test a potting material that has superior sealing properties.
b.
(Closed)
LER 50-409/79-03, Failure of the condensate de-mineralizer to seal injector reservoir makeup line contain-ment isolation valve No. 52-26-039 to pass the Type C containment leak rcte test.
The valve was repaired and retested satisfactorily.
c.
(Closed) LER 50-409/79-04, Failure of the demineralized water isolation valve to pass the Type C containment leak rate test.
The valve seat was replaced because of normal wear and the valve retested satisfactorily.
No items of noncompliance were identified.
6.
Followup on Previous Noncompliance and Open Inspection Items (OII)
a.
(Open) Deficiency (Inspection Report No. 50-409/79-02)
Failure to identify Part 21 requirements on the peripheral shroud purchase order.
The licensee's site representative had received the inspection report late and had not comnleted the reply to this deficiency.
b.
(open) Infraction (Inspection Report No. 50-409/78-02)
Regarding QA Records.
Resolution is pending completion of a new office-security building.
c.
(Closed)
OII 78-11, The licensee has sent memorandums to all of its consultants indicating that Part 21 requirements apply in their contracts.
7.
Review of Periodic and Special Reports The inspector reviewed the following reports for timeliness of submittal and adequacy of information submitted:
a.
Special Report No. 79-01, February 14, 1979.
b.
Monthly Operating Data Reports for November, December 1978 and January and February 1979.
No items of noncompliance were identified.
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d 8.
Followup on Inspection and Enforcement Circulars a.
(Closed)
IE Circular 78-18, concerning the l'nderwriters Laboratory fire tests of vertical cable tray arrays.
The licensee has reviewed this problem in conjunction with their present submittal for a full term license.
b.
(Closed)
IE Circular 79-02, Concerning the degradation c f independent offsite power sources.
The licensee, after making the requested reviews and sone independent tests concluded that the concerns listed in the circular were not problems at LACBWR.
c.
(Closed)
IE Circular 79-04, Concerning loose locking nuts on Limitorque Valve operators. The licensee has five Limitorque valves.
These were inspected and lock nut was found tight.
The lock nuts were staked as recommended on drawing No. '.1-497-0009-3.
d.
(Closed)
'.E Circular 79-05, Concerning moisture leakage in stranded wire conductors.
After reviewing this circular, the licensee concluded LAC 3WR does not have any stranded conductors in any safety related circuits.
No items of noncompliance were identfiled.
9.
Exit Interview The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection.
The inspector summarized the scope and results of the inspection.
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