ML20003J248

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IE Insp Rept 50-409/81-02,on 810201-28.Noncompliance Noted: Increasing Number of Operator Errors,Resulting in Reactor Trips on 810116 & 0201
ML20003J248
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 04/08/1981
From: Branch M, Forney W, Warnick R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20003J240 List:
References
50-409-81-02, 50-409-81-2, NUDOCS 8105110108
Download: ML20003J248 (8)


See also: IR 05000409/1981002

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U.S. NUCLEAR REGULATORY COMMISSION

OFFICE-0F INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-409/81-02

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: February 1-28, lil81

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Inspectors:

W. L. Forney

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M. W. Branch

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R FLt.)a& m Uc

Approved By:

R. F. Warnick, Chief

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Projects Section 2B

Inspection Summary

Inspection on February 1-28, 1981 (Report No. 50-409/81-02)

Areas Inspected: Routine, resident inspection of the licensee's Op.erational'

Safety, Surveillance, Maintenance, Followup Action on IE Bulletins, IE

Circulars, Licensee Event Reports, Open Inspection Items and Reactor Plant

Trips, Temporary Instructions 2515/42, Rev. 1, dealing with TMI Task

Action Plan, and day-to-day surveillance of licensee's Physical Security

Plan and Procedures. The inspection involved a total of 280 inspector-hours

onsite by two NRC inspectors including 24 inspector-hours during offshifts.

Results: Of the ten items inspected, no items of noncompliance or deviations

were identified in nine of the areas; one item of noncompliance was noted

in the area of operational safety, Paragraph 3.c (operator error causing

loss of offsite power)

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DETAILS

1.

Persons Contacted

  • J. Parkyn, Assistant Plant Superintendent
  • G. Boyd, Operations Supervisor
  • L.-Goodman, Operations Engineer
  • L. Krajewski, Health and Safety Supervisor
  • H. Towsley, Quality Assurance Supervisor
  • S.

Rafferty, Reactor Engineer

  • W. Angle, Process Engineer
  • H.

Polsean, Shift Supervisor

  • W. Nowicki, Supervisor, Instrument and Electric

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  • R. Very, QA Specialist
  • G. Joseph, Security and Fire Protection Supervisor
  • L. Kelley, Assistant Operations Supervisor
  • Denotes those present at the exit interview.

In addition, the inspectors observed and held discussions with other

engineers, plant equipment operators, reactor operators, assistants,

and plant attendants.

2.

General

The plant has been operating at power since February 2, 1981.

The plant staff is presently developing their Radiological Emergency

Plan utilizing outside consultants as necessary. This plan was due

to be issued to the United States Nuclear Regulatory Commission for

review on January 2, 1981, but because of limited staff that date was

not met.

Plant management's present schedule is for March 31, 1981.

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3.

Operational Safety Verification

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The inspector observed control room operations, reviewed applicable

logs and conducted discussions with control room operators during the

month of February. The inspector verified the operability of selected

emergency systems, reviewed tagout records and verified proper return

to service of affected components. Tours of the reactor building and

turbine building were conducted to observe plant equipment conditions,

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including potential fire hazards, fluid leaks, and excessive vibrations

and to verify that maintenance requests had been initiated for equip-

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ment in need of maintenance. The inspector by observation and direct.

interview verified that the physical security plan was being imple-

mented in accordance with the station security plan.

The inspector observed plant housekeeping / cleanliness conditions and

verified implementation of radiation protection contrals. During the

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month of February, the inspector walked down the accessible portions

of the Control Rod Drive Hydraulic systems to verify operability.

The inspector also witnessed portions of the radioactive waste system

controls associated with radwaste shipments and barreling.

These reviews and observations were conducted to verify that facility

operations were in conformance with the requirements established

under technical specifications, 10 CFR, and' administrative procedures.

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The inspectors noted the following matters requiring licensee action:

Maintenance personnel were noted exiting a radiological controlled

a.

area without frisking. This item was brought to the attention of

plant management and a meeting was held with maintenance department

personnel.

Piant management committed to clarify requirements _in

a Health c.nd Safety memo. This is considered to be an unresolved

item (50-409/81-02-01).

b.

The inspectors noted that several Security Control Procedures

(SCP's 3.0, 4.1B, 4.1C and 6.3) were changed prior to receiving

prior NRC approval of the change to the Physical Security Plan.

This item was brought to the attention of plant management and

interoffice memo " Burns" dated February 26, 1981, was issued to

clarify the proper procedures to follow until " PSP" is approved

by the NRC.

The inspectors noted that there has been an increasing number of

c.

operator errors and that three such errors occuring on January 16,

1981, and again on February 1, 1981, resulted in reactor trips.

The reactor trip on February 1,1981, due to an operator switching

error left the plant without offsite power (all backup systems oper-

ated as required). This item is considered to be an item of

noncompliance and is discussed in Appendix A to the letter trans-

mitting this report.

4.

Monthly Maintenance Observation

Station maintenance activities of safety related systems and components

listed below were observed / reviewed to ascertain that they were conducted

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in accordance with approved procedures, regulatory guides and industry

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codes or standards and in conformance with technical specifications.

The following items were considered during this review:

the limiting

conditions for operation were met while components or systems were

removed from service; approvals were obtained prior to initiating the

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work; activities were accomplished using approved procedures and were

inspected as applicable; functional testing and/or calibrations were

performed prior to returning components or systems to service; quality

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control records were maintained; activities were accomplished by

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qualified personnel; parts and materials used were properly certified;

radiological controls were implemented; and, fire prevention controls

were implemented.

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Work requests were reviewed to determine status of outstanding jobs

and to assure that priority is assigned to safety related equipment

maintenance which may affect system performance.

The following maintenance activities were observed / reviewed:

1.

Repair / replacement of fluid coupling on number IB force cir-

culating pump.

2.

Trouble shooting of NI Channel Number 8.

Following completion of maintenance on the number 1B Force Circulat-

ing Pump, the inspector verified that these systems had been returned

to service properly.

No items of noncompliance were identified.

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5.

Monthly Surveillance Observation

The inspector observed technical specifications required surveillance

testing on the 1A and IB Emergency Diesel Generators, IA and IB HPSW

diesels and verified that testing was performed in accordance with

adequate procedures, that test instrumentation was calibrated, that

limiting conditions for operation were met, that removal and restora-

tion of the affected components were accomplished, that test results

conformed with technical specifications and procedure requirements

and were reviewed by personnel other than the individual directing

the test, and that any deficiencies identified during the testing were

properly reviewed and resolved by appropriate management personnel.

The inspector also witnessed portions of the following test activities:

Verification of deployment capabilities for emergency service water

system needed for liquification issue resolution at LACBWR.

The inspector expressed to plant management the need to ensure adequate

personnel are trained and technically adequate procedures are in place

for the use of the emergency service water system.

No items of noncompliance were identified.

6.

Licensee Event Reports Followup

Through direct observations, discussions with licensee personnel,

and review of records, the following event reports were reviewed to

determine that reportability requirements were fulfilled, immediate

corrective action was accomplished, and corrective action to prevent

recurrence had been accomplir.hed in accordance with technical specifi-

cations.

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LER 80-05 - Unauthorized' Modification to Shutdown Condenser

LER 80-09 - Mechanical Interlock on Air Lock Was' .Inoperab]e

LER 80-10 - Late Accomplishment of Technical Specification Test

LER 80-11 - Violation of Cooldown Rate on Reactor Vessel

No items of noncompliance were identified.

7.

IE Bulletin Followup

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For the IE Bulletins listed below the inspector verified that the

written retpcnie was within the time period stated in the bulletin,

that the written response included the .information required to be

reported, that the written response included adequate corrective

action connitments based on information presentation in the bulletin

and the licensee's response, that licensee management forwarded

copies of the written response to the appropriate onsite management

representatives, that information discussed in- the licensee's written

response was accurate, and that correctiva action taken by the licensee

was as described in the written response.

IEB 80-23

Failure of Solenoid Valves Manufactured by Valcor-

Engineering Corp.

No items of noncompliance were identified.

8.

IE Circular Followup

For the IE Circulars listed below, the inspector verified that the

Circular was received by the licensee management, that a review for

applicability was performed, and that if the circular were applicable

to the facility, appropriate corrective accions were taken or were

scheduled to be taken.

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IEC 80-23

Potential Defects in Beloit Power System Emergency

Generators

No items of noncompliance were identified.

9.

Review of Plant Operations

During the month of February, 1981, the inspectors reviewed the

following activities:

a.

Procurement

The inspectors reviewed procurement and storage activities to

ascertain whether the purchase of components, materials and

supplies used for safety related functions are in conformance

with the licensee's approved QA program and implementing pro-

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cedures. Non-conforming items are segregated and marked accord-

ingly. Applicable preventative maintenance is performed, house-

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keeping and environmental ~ requirements are met and limited

shelf-life items are controlled-.

The inspector's review revealed several work areas in the li-

censee's system dealing with the labeling and storage of limited

shelf-life items. The licensee has started a program to properly

' identify shelf-life of items and to develop a system to purge

out old and order new items if necessary.

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The inspectors also reviewed FC-71-80-01 and determined that

stainless steel seamless tubing, Items 1 and 2 of Purchase Order

A76958, was not stamped as a QC item as required by ACP-05.1.

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FC 71-80-01 states that this material will be used in a safety.

related system. This item has been identified to plant manage-

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ment for resolution.

The above items are considered unresolved item 50-409/81-02-02.

10.

Plant Trips

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Following the plant trips on January 31, 1981 and February'1, 1981,.

the inspector ascertained the status of the reactor and safety

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systems by observation of control room indicators and discussions

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with licensee personnel concerning plant parameters, emergency system

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status and reactor coolant chemistry. ~The inspector verified the

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establishment of proper connunications and reviewed the corrective

actions taken by the licensee.

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All systems responded as expected, and the plant was returned to

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operation on February 2, 1981.

The trip on February 1, 1981 was caused by an operator opening the

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wrong disconnect that divorced the plant from offsite power. This

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item is an item of noncompliance and is also discussed in Paragraph

3, Operational Safety Verification.

11.

TMI Action Plan Inspection of Procedures and Staffing (TI 2515/42,

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Rev. 1)

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The inspectors verified that the following tasks were completed by

the licensee:

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(a)

I. A.1.1 - Shift Technical Advisor Staffing and Training Program

Implementation

(b)

I. A.1.2 - Shif t Supervisor Responsibilities -

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(c)

I.A.2.1 - Immediate Upgrading of R0 and SRO Training and

Qualifications

(d)

I.C.2

- Shift Relief /Turnoverf

(c)

I.C.3

- Shift Supervisor Responsibilities

(f)

I.C.4

- Control Room Access

(g)

I.C.5

- Procedure for Operating Experience Feedback

The inspectors did not complete the review of items I.C.6 (Verifica-

tion of Operating Activities) or II.F.2 (Identification of and

Recovery from Conditions Leading to Inadequate Core Cooling), the

licensee is to provide additional information to the inspectors.

This is considered to be unresolved item 50-409/81-02-03.

12.

Followup on Previous Items of Noncompliance and Open Inspection Items

(OII)

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1/ - Failure of licensee to conduct proper

a.

(Closed) OII 80-09-NC-1

10 CFR 50.59 review of modification to shutdown condenser. The

licensee's response to this item included dissemination of

information to all plant employees.

1/ - Failure to provide the required

b.

(Closed) OII 80-09-NC-2

two valves in series for containment isolation on the unauthorized

modification to the shutdown condenser. The licensec's response

to this item included dissemination of this item of noncompliance

to all plant employees.

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c.

(Closed) OII 80-09-NC-3

- Violation of containment integrity

while the reactor was operating at power. The licensee's response

to this item concluded that if 50.59 review was accomplished,

this item would not have occurred.

d.

(Closed) OII 80-09-NC-41/ - Failure to make notification to

NRC Operations Center of an event that resulted in automatic

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actuation of the reactor protection system. The licensee's

response indicated that Operations Department Supervisors have

been re-instructed.

e.

(Closed) OII 80-14-NC-1_/ - Failure to maintain main steam

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bypass valve control setting at 15 psig above its nominal value.

The licensee's response established a requirement to monitor

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and log hourly,

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1/ IE Inspection Report 50-409/80-09,

2_/ IE Inspection Report 50-409/81-14.

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f.

(Closed) OII 80-14-NC-2SI - Failure to follow procedures.

The

licensee's response indicates that the reason the procedures

were not followed was because of a misunderstanding of procedure,

but has now been clarified to all operating personnel.

g.

(Closed) OII 80-14-NC-3_/ - Failure to conduct the required two

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year review of the refueling section of the operating manual.

The licensee provided additional documentation that proved the

two year review was accomplished.

h.

(Closed) OII 80-14-NC-4E! - Failure to follow procedures.

(1) The licensee indicated that the licensee considered the one

hour logging of source range NI's meet the necessary require-

ments. This was discussed with licensee management and

commitments were received that indicate continuous monitor-

ing would be required during fuel loading and that procedures

used during the next refueling would contain those words.

(2) Necessary initials were obtained on the Fuel Element Transfer

Record.

(3) The licensee pointed out additional paragraphs in the brief-

ing book and it appears that this section of Item No. 4 was

not an item of noncompliance.

13.

Unresolved Items

Unresolved items are matters about which more information is required

in order to ascertain whether they are acceptable items, items of

noncompliance, or deviations. Unresolved items disclosed during the

inspection are discussed in Paragraph 3, 9 and 11.

14.

Exit Interview

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The inspector met with licensee representatives (denoted in Paragraph

1) throughout the month and at the conclusion of the inspection and

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summarized the scope and findings of the inspection activities.

2/ IE Inspection Report 50-409/80-14.

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