ML20004B443
| ML20004B443 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/19/1981 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| LAC-7555, RO-81-06, RO-81-6, NUDOCS 8105280246 | |
| Download: ML20004B443 (3) | |
Text
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DlDA/RYLAND h
[k COOPERAT/VE po ecx air. 2 sis east av scurs t4 c9csse uscossin s4eci 6C8) 788-4000 May 19, 1981 In reply, please refer to LAC-7555 DOCKET NO. 50-409 Mr. James G. Keppler, Director U. S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road g
Glen Ellyn, Illinois 60137 hh f.i\\
SUBJECT:
DAIRYLAND POWER COOFERATIVE g
iQ LA CROSSE BOILING WATER REACTOR (LACBWR)
$ I'MY 2 71981 PROVISIONAL OPERATING LICENSE NO. DPR-45
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REPORTABLE OCCURRENCE NO. 81-06 um %.m%, y/
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Reference:
(1)
LACBWR Technical Specifications,
! g::h Section 6.9.1.9.c 9
(2)
LACBWR Technical Specifications, Section 6.9.1.8.c
Dear Mr. Keppler:
In accordance with References 1 and 2, this is to inform you of an inadequacy in the implementation of administrative and procedural controls which caused a reduction in the degree of redundancy pro-vided in reactor protection systems and potential degradation of primary containment.
On May 17, 1981, a LACBWR Supervisor discovered a modification had been made to the Containment Building pressure sensing line leading to Pressure Switch 37-35-702 which activates IB High Pressure Core Spray Pump (HPCS) and 1B High Pressure Service Water (HPSW) Alternate Core Spray (ACS) Pump and sends half the opening signal to the AC Alternate Core Spray Valve on high Containment Building pressure of 5 psig.
The installation had been made without an approved Mainten-ance Request or Facility Change.
The modification consisted of an additional pressure switch, two additional valves and 3/8 in. copper I
tubing.
The modification had been assembled and leak tested at 60 psig without leakage prior to being installed.
i During the installation on April 1, 1981, which took less than one hour, the valve between the containment wall and the Pressure Switch 37-35-702 was closed for approximately one minute.
If the Contain-ment Building had become pressurized during this time, which it did not, the 1B HPCS Pump, 1B HPSW/ACS Pump and AC ACS Valve would not 00 81052808h
'6I I
E 21 1981 S
l Mr. James G. Keepler, Director LAC-7555 U. S. Nuclear Regulatory Commission May 19, 1981 have received a high pressure actuating signal.
The 1A HPCS Pump, lA HPSW/ACS Pump and DC ACS Valve and other starting signals, were unaffected by the installation.
Therefore, the installation process reduced the degree of redundancy in these systems, but would not have prevented system actuation if required.
A leakage test was not performed after installation.
Therefore, it cannot be proven that the swaaelok fitting connecting the modifi-cation and the sensing line would not leak in excess of Technical Specification limits when internally exposed to 52 psig and that Containment Integrity exists.
The added valves were found in the closed position and have since been tagged to ensure they are not opened.
A leakage test will be performed on the modification in the near future.
Prompt notification of this event was made to the NRC Operations Canter at 2315 on May 18, 19El, to the Resident Inspectors at approximately 0930 on May 19, 1981, and to Mr. Len McGregor of Region III at 1000 on May 19.
If there are any questions concerning this report, please contact us.
Very truly yours, DAIRYLAND PCWER COOPERATIVE Y
Ed&?
Frank Linder, General Manager FL:LSG:af cc:
Director, Office of Management Information (3) and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC Resident Inspectors _
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