IR 05000409/1979022
| ML19262C392 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/03/1980 |
| From: | Boyd D, Ridgway K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19262C391 | List: |
| References | |
| 50-409-79-22, NUDOCS 8002120124 | |
| Download: ML19262C392 (5) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
.
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
m Jeport No.-
50-409/79-22
%j
.
.
[DocketNo..
50-409 License No.: DPR-45 Licensee: Dairyland Power Cooperative 2615 East Avenue, South La Crosse, Wisconsin Facility Name:
LACBWR Inspection At:
La Crosse Site, Genoa, WI Inspection Conducted: December 3-6, 1979 Shfh Inspector:
K. R. Ridgway
/'- 3 -dF>'C'
$'
Approved By:
D. C'.'Boyd, Chief
/ ~43 -d7<9 Reactor Projects, Section 3 Inspection Summary Inspection on December 3-6, 1979 (Report No. 50-409/79-22)
Areas Inspected:
Routine unannounced inspection of the licensee's opera-tional activities; and followup actions relative to IE Bulletins, IE Circulars, Licensee Event Reports and special reports.
The inspection involved 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> onsite by one NRC inspector.
Results: No items of noncompliance were identified in the five areas inspected.
.
a
,
.
1948 198 80021go;g
LETAILS
.
1.
Persons Contacted
- R. Shiushak, Plant Superintendent
{f
- J..Parkyn, Assistant Plant Superintendent 1,
y G. Boyd, Operations Supervisor
'
-
L. Kelley, Assistant to Operations Supervisor
.
C. Angle, Process Engineer
-
L. Krajewski, Health and Safety Supervisor H. Towsley, Quality Assurance Supervisor P. Grey, Mechanical Maintenance Supervisor J. Gallaher, Shift Supervisor R. Cota, Shift Supervisor M. Polsean, Shift Supervisor
- G. Joseph, Security Director R. Ganser, Plant Operator P. Brandjes, Plant Operator L. Goodman, Nuclear Engineering Services (Contractor)
- C. Duchesneau, Nuclear Engineering Services (Contractor)
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 reactor had two unplanned outages since the last inspection in early October. A one day outage on November 9, 1979 was initiated by a sticking turbine governor control system which resulted in a scram from 85 percent power by a power-flow mismatch trip.
The second on November 29, 1979, a one day outage was caused by a failure in the turbine building main steam isolation valve control system, giving a scram from 85 percent power by a trip of this circuit.
The licensee has reduced power to 75 percent to extend operating time for lack of fuel storage space.
3.
Plant Operations Review The inspector observed plant outage conditions, control room mann-ing, equipment tagging, key-lock control and valve lineups on the alternate Core Spray and both emergency diesel generator systems dur-ing a plant tour. Additionally, the following records were reviewed from November 1,1979 to December 5,1979, to determine compliance
.
..
,
.
1948 199-2-
.
with Technical Specifications and regulations and to determine if the
Night Order Instructions or Operating Memos conflicted in any way with operational requirements.
a.
S0-18 Daily Log of EW-RMVA-MWH
!!
w b.
L-84 Control Rod Position Indications
}'
[
c.
L-83 Reactor Plant Log d.
L-82 Turbine Generator Plant Log e.
L-74 Controlroom Par.el A f.
L-42 Radiation Monitor and dew Cells g.
L-119 AGS and Reactor Safety System Log h.
L-72 Turbine Generator Auxilary Log i.
L-73 Reactor Plant Auxilary Log j.
L-68-71 Temperature Recorder Logs k.
Night Order Instruction Book 1.
Shift Supervisors Log October, 1979 to December 5, 1979 m.
Incident Reports n.
Jumper and Bypass Key Log o.
Reactor Vessel Heatup and Cool Down Data p.
Turbine Operators Shift Log q.
Startup Checklist for the two startups in November including a review of required hot startup surveillance tests During the valving alignment check of the 1A Emergency Diesel Generator, the inspector noted that the Day Tank Low Level pressure switch isolation valve (78-28-006) shown on Drawing No. 41-300-176 was no longer in use.
The low level pressure tap had been combined with the low low level using the same isolation valve and since both pressure switches actuate a common annunciator (A8-2) it is not considered a safety item. The Facility Change for this change was not reviewed. The inspector also noted that completion of the 1A and IB Emergency Diesel Generator valve alignment checklists were not
'
,
..
,
-
1948 200-3-
.
included in the cold startup requirements. These items are consider-
ed to be an open inspection item (0I1-79-12) which will be reviewed during a later inspection.
4.
Review of Licensee Event Reports (LER's)
!!
>
The inspector reviewed the following LER's to determine if*jhe reports
.
were correct and if the evaluations and corrective actions taken were
-
[
appropriate and that they were completed as stated in the LER:
(a)
(Closed) LER 50-409/79-14, Control Rod 10 was inadvertantly with-drawn instead of Control Rod 12 during the startup on July 8, 1979.
The error was discovered by the Shift Supervisor and misalignment corrected within 20 minutes.
Subsequent calculations by the licensee indicated that the Technical Specifications requirements for the minimum critical power ratio, linear heat generation rates and maximum average planar linear heat generation rate were never approached, however, control rod position is the only operating control of these parameters and the importance main-taining control rod positions within the program was emphasized to the operators.
(b)
(Closed) LER 50-409/79-15, A valving error released 2500 gallons of unanalized liquid waste to the Mississippi River. The operator, by mistake, released the wrong waste tank and after about onehalf the contents had been released the transfer was stopped and the remaining waste was sampled and analyzed.
It was determined that the waste was released at a more conservative dilution rate than that required and the liquid waste monitor was conservatively set, therefore, 0.'.: actual release was within limits.
The inspectors review of this event concludes that proper sampling and analysis of the tank contents had been performed and a properly authorized permit authorizing the release of the tank contents had been prepared. The cause of the event, as stated by the licensee, was found to be human error, the operator opened the wrong value.
This is considered to be an item of noncompliance found, corrected, and reported by the licensee. No additional NRC action is considered to be warranted.
5.
Followup on IE Bulletins (Closed) IE Bulletin 79-24, Concerning freezing problems in a.
safety related systems. The licensee had experienced no freezing problems in safety related systems in twelve years of operations.
b.
(Closed) IE Bulletin 79-25, Concerning failures of Westinghouse BFD relays in safety related systems. The licensee does not use
these relays in the LACBWR facility.
,
.
1948 201
_,_
.
'
6.
Followup on I & E Circulars The inspector reviewed the licensee's evaluation of the following IEC's to determine that any necessary actions had been taken:
.,
IE Circular 79-20, Failure of GTE Sylvania Relay - Ty PM a.
Bulletin 7305.
y
Exit Interview Th-inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection. The following items were discussed:
a.
The open inspection item with regard to the need to include the
,
emergency diesel generator valving checklist in cold startups and after major maintenance work (Paragraph 3).
b.
The open inspection item with regard to modifications of the 1A emergency diesel generator day tank (Paragraph 3).
.
..
,
-
1948 202-3-