ML20148T907

Insp Rept 50-331/97-09 on 970426-0529.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support

ML20148T907
Person / Time
Site:	Duane Arnold
Issue date:	06/27/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20148T892	List: ML20148T886 ML20148T907
References
50-331-97-09, 50-331-97-9, NUDOCS 9707090370
Download: ML20148T907 (17)

See also: IR 05000331/1997009

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U. S. NUCLEAR REGULATORY COMMISSION

REGION lil ,

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Docket No: 50-331 l

License No: DPR-49 i

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Report No. 50-331/97009

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! Licensee: IES Utilities Inc.

200 First Street S.E. I

P. O. Box 351

Cedar Rapids, IA 52406-0351 ,

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l Facility: Duane Arnold Energy Center l

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Dates: April 26 - May 29,1997 j

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Inspectors: K. Riemer, Senior Resident inspector

C. Lipa, Senior Resident inspector l

l M. Kurth, Reactor Engineer

M. Jordan, Chief I

Approved by:

Reactor Projects Branch 5 l

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9707090370 970627

i PDR ADOCK 05000331

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EXECUTIVE SUMMARY

Duane Arnold Energy Center

NRC inspection Report 50-331/97009

This inspection report included resident inspectors' evaluation of aspects of licensee

operations, engineering, maintenance, and plant support.

The inspectors and licensee identified several concerns. This included tagout errors,

inattention to detail by plant operators and procedure violations.

Operations

• The inspectors concluded that shutdown and startup activities were well controlled

and conducted in a slow and conservative manner. (Section 01.2).

• The inspectors identified incorrect labelling on handswitch tags on the control

panels and concluded that the operators demonstrated poor attention to detail.

This was an example of a violation. (Section 01.3).

• The inspectors identified that the automatic start selector switch for river water

supply pump "A" was in the wrong position. Similar to the tagout issue discussed

above, the inspectors were concerned with the multiple opportunities that were

missed to identify the switch out of position. The inspectors concluded that the

operators demonstrated poor attention to detail. Also, Operations failed to

recognize the significance of the issue until further questioning and research by the

inspectors. This was an example of a violation. (Section 01.4).

Maintenance l

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• The inspectors noted several examples where the operators or technicians reviewed

procedures ahead of time to identify discrepancies, which were then resolved prior l

to beginning the test. However, as discussed below, in two cases, procedure

discrepancies were not identified until after the activity was completed.

(Section M1.1).

• The licensee identified inadequate work instructions during maintenance; however,

this was not identified until after the step was completed. This was a non-cited

violation. (Section M1.2).

e The inspectors identified that the work document for river water supply motor

replacement did not include post maintenance testing on ventilation dampers l

removed to allow access for work on the river water supply pump. This was an

example of a violation. (Section M1.2).

• The licensee identified that there were steps missing from a diesel generator

surveillance due to loss of control of a procedure change. (Section M3.1).

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e Engineering effectively resolved the identified rnateriel condition issues and provided l

support to operations to continue turbine valve testing in the three steam line  !

configuration. (Section E1). I

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Plant Suonort l

e The inspectors identified that the licensee failed to post notices to workers as i

required by 10 CFR 19.11. This was a violation. (Section R1.1). l

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Report Details

Summarv of Plant Status

The plant began this inspection period at 100 percent power. On May 18,1997, power

was reduced to approximately 65 percent for main steam isolation valve (MSIV) testing

and a control rod sequence exchange. During testing, the "C" inboard MSIV failed to

indicate fully closed. The "C" outboard MSIV was closed and deenergized to comply with

Technical Specifications for containment isolation. With one steam line isolated, power

was limited administratively to approximately 80 percent until a shutdown was

commenced on May 23 to repair the "C" inboard MSIV limit switch. The plant was

brought to a cold shutdown condition to perform other repans. A reactor startup was

commenced on May 26, however, a packing leak on steam line drain valve V03-10 was

identified during the 400 psig inspection. The plant was brought to a subcritical condition

on May 27 to repair V03-10. Startup was recommenced on May 28 and the plant was at

full power on May 31.

l. Operations

01 Conduct of Operations

01.1 General Comments 71707)

The inspectors conducted frequent reviews of plant operations. This included

observing routine control room activities, attending shift turnovers and crew

briefings, and performing panel walkdowns. In general, conduct of operations

during shutdown and start-up activities were well controlled, with good

coordination with deliberate and conservative decision making. However, concerns

were identified with tagouts and operators' attention to detail. 4

01.2 Shutdown and Startuo Activities to Suooort MSIV Limit Switch Reoair

a. Insoection Scone

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During testing on May 18,1997, the "C" inboard MSlV failed to indicate fully

closed, therefore plans were made to bring the plant to a shutdown condition and

perform repairs. The inspectors observed portions of shutdown activities and

startup activities, mostly from the control room. The inspectors performed the

inspections on all three shifts.

b. Observations and Findinas i

The inspectors observed effective oversight and coordination of activities, formal  ;

communications between operators, and strict procedural compliance. Reactivity l

changes were performed in a deliberate and conservative manner. The inspectors

also observed excellent management briefings and reactor engineering briefings,

that included lessons learned from industry operating experience.

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c. Conclusions

The inspectors concluded that shutdown and startup activities were well controlled

and conducted in a slow and conservative manner.

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01.3 Incomotete Warnina Taas on Containment Sorav Switches i

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b. Observations and Findinas

On May 27,1997, during the conduct of routine control room panel walkdowns,

the inspectors identified that operators had established an incomplete tagout to  ;

support a drywell entry associated with the maintenance outage. Integrated Plant I

Operating Instruction (IPOI) 7 required that warning tags be placed on the drywell I

and torus spray valve hand switches stating "Do not spray Drywell/ Torus without I

verifying all personnel are clear of the Drywell/ Torus". Operators prepared and

placed the warning tags on the referenced hand switches; however the inspectors

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identified that the tags were blank (i.e., the warning was not stated on the tags as

required). The tags had been established and placed on the hand switches May 24,

1997 as part of tagout SD2960. The licensee initiated Action Request

(AR) 97-1526 to document the event and assign corrective actions.

c. Conclusions

The inspectors verified that operators were aware of drywell maintenance activities 1

and the need to clear people from the drywell prior to initiating drywell spray.

While the safety consequences of the incomplete tagout were minor, the inspectors

were concerned with the multiple opportunities (tagout hanger, checker, crew

turnovers) that were missed to identify the tagout deficiency. The inspectors

concluded that the operators demonstrated poor attention to detail and that this  ;

item was similar to the panel awareness issue discussed in Section 01.4 of this l

report. Part 50 of 10 CFR, Appendix B, Criterion V, required in part that 1

procedures affecting quality shall be accomplished in accordance with instructions  ;

and procedures. The operators' failure to establish a tagout in accordance with the '

IPOl 7 requirements is an example of a violation of 10 CFR 50, Appendix B,

Criterion V (50-331/97009-01).

01.4 River Water Sucolv (RWS) Pumo Selector Switch Found in Wronn Position

a. Insoection Scone

While reviewing tagouts and walking down the control room panels, the inspectors

identified that the n lactor switch for the RWS pump was in the wrong position.

The inspectors * Jowed up to determine the cause and extent of the licensee's

corrective actions.

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b. Observations and Findinas  :

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On May 12,1997, at 7:00 a.m. the inspectors reviewed the control room panel for l

the RWS system where the "C" pump had been deenergized for maintenance since ,

4:28 a.m. per tagout number 970550. Operations considered the "A" pump in the  ;

same train operable and there was no Limiting Condition for Operation (LCO) j

entered. However, the inspectors identified that the selector switch for the RWS  :

pump auto start was selected to the "C" pump. With the switch selected to "C", l

l the "A" pump would not auto start if needed and the train was thus rendered i

inoperable.

When questioned, the licensed operator at 7:15 a.m. promptly repositioned the

switch to select the "A" pump for auto start. The shift supervisor also reviewed

the tagout to determine whether there was a requirement to tag the selector switch

and found that there was not. A revision to the tagout was made and a tag was  ;

j hung on the selector switch specifying to select pump "A".

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l The inspectors were concerned that the incorrect position of the switch was not }'

l identified by the operator who hung the tagout, the operator who checked the

l tagout. or by the crew of operators and shift supervisors who walked down the  !

panels as part of the shift turnover at 6:30 a.m. >

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Later in the day, the inspector questioned the shift supervisor whether an AR had  ;

been written and he indicated that no AR was written and the train was considered

operable even with the selector switch in the incorrect position because the pump  :

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could be manually started. The inspectors were concerned with this answer  !

because UFSAR Section 9,2.2.3 discussed the response of the system to a loss of l

offsite power or loss of coolant accident and took credit for automatic start of the

selected pump. A Design Change Package Safety Evaluation (DCP 1496) dated

December 7,1990, indicates that the system could survive a complete loss of RWS

for at least 6.2 minutes. Therefore, on an assumed loss of offsite power with  ;

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failure of the "B" emergency diesel generator, depending on the configuration, l

operators may only have up to 6.2 minutes to take manual action to start the "A" j

pump to provide cooling water for the "A" emergency diesel generator.

! Following further discussions with Plant Management, an AR was written i

documenting the condition and the fact that the "A" train was in an unrecognized

7-day LCO from 4:28 a.m. until 7:15 a.m. on May 12,1997.

j c. Conclusions

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l Similar to the tagout issue discussed in Section 01.3, above, the inspectors were

concerned with the multiple opportunities that were missed to identify the switch

out of position. The inspectors concluded that the operators demonstrated poor

attention to detail. Also, Operations failed to recognize the significance of the issue

until further questioning and research by the inspectors.

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10 CFR 50, Appendix B, Criterion V required that procedures be appropriate to the

circumstances. The inadequate tagout 970550 was an example of a violation

(50-331/97009-02).

07 Quality Assurance in Operations

07.1 Licensee Self-Assessment Activities (71707)

During the inspection period, the inspectors reviewed multiple licensee self-

assessment activities, including:

• Safety Committee

• Action Request Screening Meetings

• Operations Committee

The inspectors observed active management participation at the meetings.

Identified deficiencies were being tracked by the licensee's AR process. The

inspectors were concerned however, with the number of human performance issues

that occurred during the inspection period. Most of these issues were NRC

identified and occurred during the performance of routine, fundamental tasks.

08 Miscellaneous Operations issues (92700)

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08.1 (Closed) Unresolved item 50-331/95009-01: Extraction Steam Valves Found Out

of Normal Position. As discussed in Inspection Report 95009, the licensee

discovered that five extraction steam valves were out of their required closed

position. The inspectors reviewed the licensee's immediate corrective actions and

formal root cause evaluation and had no subsequent concerns with either. The

extraction steam valves were non-safety related and their as-found positions had no

effect on plant operations. The inspectors concluded that no procedural violations

existed. This item is closed.

08.2 (Closed) IFl 50-331/96005-02: HPES Conclusions and Corrective Actions on

Technical Support Center (TSC) Diesel Failure to Start. Inspection Report 96005

documented operator difficulties in transferring the TSC heating, ventilation, and air

condition (HVAC) power supply to the TSC diesel. The inspectors verified that a

Training Management Action Request (TMAR) was generated and introduced into

the operator training program. The inspectors also verified that the applicable

operating instruction (01) had been revised to clarify operation of the TSC diesel.

This item is closed.

08.3 LQlosed) IFl 50-331/96007-02: Configuration Control issues. Inspection Report

No.96-007 documented inspector observations with respect to an increasing trend

in balance-of-plant, non-safety configuration control issues. The licensee performed

complete valve lineups on all systems prior to the startup following the refueling

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outage. The licensee performed a successful startup with no configuration control

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sssues identified. This item is closed.

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11. Maintenance

M1 Conduct of Maintenance

M1.1 General Comments

a. Insoection Scone (S2707) (61726)

The inspectors observed or reviewed all or portions of the following work activities:

• Residual heat removal service water (RHRSW) auto vent repair

• RHRSW valve repack

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• Standby diesel generator semiannual surveillance

• Standby transformer preventive maintenance

• Turbine valve testing

• River water supply pump motor replacement

• Main steam isolation valve (MSIV) testing

• MSIV temporary modification

• Hydrogen-oxygen analyzer troubleshooting

b. Observations and Findinos

As discussed in Inspection Reports 50 331/97004 and 97007, the inspectors

identified several examples where procedures were inadequate and this was not

always identified by plant staff prior to or during testing. While observing activities

discussed above, the inspectors noted improvement in the licensee's use of

procedures. The inspectors noted several examples where the operators or

technicians reviewed procedures ahead of time to identify discrepancies, which

were then resolved prior to beginning the test. However, as discussed below, in

two cases, procedure discrepancies were not identified until af ter the procedure

was completed,

c. Conclusions

The inspectors concluded that improvements have been made in establishing an

awareness of the importance of procedure adherence and in identifying and

correcting procedure discrepancies during testing. However, as discussed below,

there were cases where this was not fully effective in ensuring that procedure

discrepancies were identified ahead of time.

M1.2 "C" River Water Sunolv (RWS) Pumo Motor Reolacement

a. Insoection Scone (62707)

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The inspectors observed the replacement of the RWS motor according to corrective

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maintenance action request (CMAR) A22898 in detail. This included determination,

removal, reinstallation, and retermination of the "C" RWS motor on May 12 and 13,

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1997. The inspectors identified concerns with the accuracy of work instructions

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and the specified post-maintenance testing.

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On May 12, the inspector observed the removal of interference items, such as l

i intake structure roof hatch and ventilation damper that were necessary to support  ;

4 the removal of the old RWS motor. The inspector had three concerns with the  ;

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e The Maintenance Instruction Form (MIF) specified to " Remove D07713A as j

< required." This was the incorrect damper and should have read to remove '

, D07716A (damper operator) and 1VAD58-M (ventilation damper). Both  !

items were clearly labelled in the intake structure, therefore the planning .

could easily have specified the correct items to remove.

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o The mechanical maintenance technicians removed the correct ventilation f

I damper for the job, however, they did not realize until afterwards that this

j was not the damper listed on the MIF provided as part of the CMAR. The- ,

i inspectors were concerned that the mechanics assumed that they knew i

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! what to do rather than carefully reviewing the MIF and identifying the error

[ before the damper was removed. When the mechanic identified the

discrepancy on the MIF, they contacted the planner who made the

,_ appropriate corrections. The licensee also initiated AR 971625 to document

j the issue. The licensee identified and corrected the deficiency. This

violation is being treated as a non-cited violation consistent with Section Vil

of the NRC Enforcement Policy. (50-331/97009-03)

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, e The inspectors identified that the CMAR did not specify any post

j maintenance testing following reinstallation of the safety related ventilation

- dampers. Maintenance Directive MD-24, " Post Maintenance Testing-

Program," Revision 12 specified that one of the purposes of post

! maintenance testing is to ensure that no new problems or deficiencies have.

4 been created. The removal and reinstallation of the dampers could have

i affected the function of the safety related ventilation for the RWS system.

l The failure of the CMAR to specify post maintenance testing for this activity

! according to MD-24 is an example of a violation of 10 CFR 50 Appendix B, .

I Criterion V, which requires that activities affecting quality shall be

accomplished according to procedures. (50-331/97009-04) ,

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l In response to the inspectors' concern, the licensee documented the l

l, condition on AR 971626 and revised the CMAR to include the post

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maintenance testing.

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c. Conclusions

The inspectors were concerned that the licensee failed to recognize the procedure

deficiency until after the work was completed. Also, the post maintenance testing

in this case was inadequate until identified by the inspectors.

M2.1 Plant Materiel Condition

a. Insoection Scope

The inspectors noted that there were several materiel condition issues and self-

revealing equipment failures during the report period. The inspectors reviewed the

issues to determine if there was any affect on equipment operability or plant safety.

In each case, the inspectors observed appropriate licensee response to repair or

schedule maintenance and to determine root cause. The examples are listed below:

• On May 18,1997, the "C" inboard MSIV failed to indicate fully closed.

Because of this item, the plant was shutdown on May 23 and the closed

limit switch was replaced. (AR 971289) '

• On May 24,1997, with the plant in a hot shutdown condition at 400 psi

reactor pressure, the licensee identified a steam leak on a reactor ,

recirculation discharge decontamination flange. The plant was brought to a  !

cold shutdown condition and repairs were made according to ,

CMAR A35988. This included replacement of the gasket and fasteners.  !

Other recirculation decontamination flanges were evaluated prior to startup. )

(AR 971507) i

• On May 24,1997, one of the "H" torus vacuum breaker closed indication

lights failed to indicate fully closed when the vacuum breaker was cycled. l

Repair was made prior to plant startup.

• On May 27,1997, during a routine start of tha "C" RWS pump, the motor l

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did not start because the breaker failed to close. The licensee initiated

AR 971513 to determine the cause and replaced the breaker with a spare.

The licensee classified this as a " maintenance rule failure to operate," which

required a cause determination.

M3 Maintenance Procedures and Documentation

M3.1 Missina Steos From Standbv Diesel Generator Surveillance

a. inspection Scone (61726)

, The inspectors observed portions of the Surveillance Test Procedure

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STP 48A001-SA, " Standby Diesel Generators Semi-Annual Operability Test,"

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Revision 24 on May 1,1997. Following the test, the system engineer realized that

the test did not include additional steps intended due to earlier resolution of an l

issue. Action Request (AR) 960495 had been closed on May 30,1996, with the  !

intention of adding steps to test the diesel fuel oil transfer pump control switches, ,

however, the change had not yet been made to the STP. Following identification

of the issue on May 1,1997, AR 970857 was written to document the issue and

require a root cause. Also, the procedure was revised and the testing was

accomplished as intended. The inspectors reviewed the licensee's cause

determination and corrective action plans.

b. Observations and Findinas

When AR 960495 was closed on May 30,1996, the intention was to updato i

STP 48A001-SA to include additional steps to test the diesel fuel oil transfer pump

control switches. The AR was originally written to review whether this test was

required due to discussion in the TS bases that the control switches would be

checked at the end of the monthly test during refill of the day tank. The TS

requirements only required that operation of the fuel oil transfer pumps would be

demonstrated during the monthly tests. The STP at the time met the TS

requirements but not the intent of the TS bases.

The AR was closed to a Procedure Work Request (PWR) , which provided the

details to make the changes, but did not immediately implement the changes. If the

engineer had used a Document Change Form instead of a PWR, the change would

have been immediate and would likely not have been missed. The inspectors were

concerned that a PWR was used to close out an AR since that did not ensure the

condition was corrected prior to closure of the AR.

At the time the PWR was initiated, it was assigned a due date c' October 1,1996,

that would have ensured revision of the procedure prior to the next scheduled test.

The inspectors were also concerned that the PWR due date was not adhered to or

noticed when it was passed.

Also, the inspectors were concerned that the procedure problem was not identified

until after the test war completed. This is similar to problems with procedures

discussed in recent inspection reports 50-331/97004 and 97007.

c. Conclusions

The inspectors concluded that there was a weakness in both the control of

procedure changes and in the AR process that allowed an AR to be closed prior to

positive corrective actions being accomplished. This did not constitute a violation

because the test met the TS requirements as written. The intended additional steps

would have been an enhancement to the procedure.

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M8 Miscellaneous Maintenance issues (92902)

M8.1 (Closed)IFl 50-331/95011-02: Loose Piping Supports Identified. Inspection Report

No. 95011 discussed inspector identified concerns with questionable or damaged

piping supports associated with the RHR system. Further plant walkdowns and

discussions with the system engineer revealed that the piping in question was

actually not RHR system piping (i.e., radwaste lines and chemical waste tank

overflow lines). The inspectors reviewed the licensee's closure of the associated

' Action Request and had no substantive concerns. This item is closed.

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E1 Conduct of Engineering

a. Insoection Scoce (37551)

The inspectors evaluated engineering involvement in resolution of emergent rnaterial

condition problems and other routine activities. The inspectors reviewed areas such

as operability evaluations, root cause analyses, safety committees, and self

assessments. The effectiveness of the licensee's controls for the identification,

resolution, and prevention of problems was also examined.

b. Observations and Findinas

The inspectors reviewed engineering evaluations of issues such as MSIV limit

switch failure, torus vacuum breaker limit switch failure, and increasing oxygen ,

levels in the drywell. In each case, engineering promptly addressed and resolved l

the issues. l

Following the suspended turbine valve testing on May 18,1997 (see inspection

Report No. 50-331/97011), engineering located an evaluation dated May 1,1990,

that provided engineering considerations associated with three steam line operation. ,

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By May 23,1997, engineering conducted a line by line review of the 1990

evaluation to determine if the constraints and considerations used at the time were

still valid. The review included all plant mods performed since May 1990.

Following this review, engineering provided limitations to allow Operations to

conduct the turbine valve testing in the three steam line configuration.

(AR 971290)

c. Conclusions

The inspectors concluded that engineering effectively resolved the identified l

materiel condition issues and provided support to operations to enable turbine valve

testing in the three steam line configuration.

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IV Plant Support

R1 Radiological Protection and Chemistry Controls

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i R 1.1 Inadeouate Postina of Notices to Workers

a. Insoection Scoce (71750)  ;

The inspectors reviewed the adequacy of radiological controls using Inspection

Procedure 71750. This included observing radiological work practices, checking i

radiological postings and locked doors, and reviewing adequacy of posting of .

notices to workers. i

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b. Observations and Findinas

The inspectors identified that the licensee failed to post a notice of violation (NOV)

involving radiological work practices as required by 10 CFR 19.11. NRC Inspection

Report 50-331/97002, dated March 6,1997, contained a NOV involving

radiological work practices. Additionally, the licensee's response, dated

April 4,1997, was not posted as required by 10 CFR 19.11. The licensee's

Administrative Control Procedure ACP 114.6 "10 CFR 19.11 & 21.6, Posting

Requirements," Revision 0 correctly specified the requirements regarding posting of i

notices to workers; however, this ACP was not followed, as discussed above,

in response to the inspectors' concerns, the licensee initiated AR 971014 and

promptly posted the required documents.

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c. Conclusions  ;

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The inspectors were concerned that the licensee failed to recognize the

requirements to post the NOV when the report was received on March 6,1997.

Failure to post the NOV and the response was a violation of 10 CFR 19.11  ;

(50-331/97000-05).

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R1.2 Hioh Radiation Area Door Found Unlocked

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a. Insoection Scooe (71750) I

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The licensee informed the inspectors on May 4,1997, that AR 971209 was written

to document the fact that during routine high radiation area (HRA) door checks, a

locked HRA (LHRA) door was found to be uniatched.

b. Observations and Findinas

On Sunday, May 4,1997, during a routine high radiation area door check, a health

physics technician (HPT) discovered an LHRA door to be unlatched. The HPT

checked the door (door #103) between the turbine building and condenser bay,

located on the north end of the basement. The door opened when the HPT gave it

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a strong pull. The door lock was actually locked, however, a metal strip had been

placed over the strike plate, and the door was not appropriately latched. The

licensee indicated that this door may have been unlatched since the last forced

outage in March 1997 when the room was downgraded to a radiation area.

Subsequent to the March outage, HPTs had not discovered that the door was

uniatched, since the door was difficult to open (the ventilation flow path made the

door difficult to open). The condenser bay is entered weekly by operations staff,

however, these individuals enter through a south end door.

Upon discovering the door open, the HPT contacted the control room and initiated

AR 971209. The metal strip covering the strike plate was removed, and the door

was locked. The licensee performed door checks on all of the LHRA doors, and

determined they were appropriately locked. Licensing personnel planned to perform

interviews with various personnel to determine who placed the metal over the strike

plate.

Areas accessible through door #103 include the condenser bay and heater bay.

Within these areas, dose rates greater than 1000 mrem /hr have been documented

during surveys. Technical Specification 6.9.3 required that areas accessible to

personnel with radiation levels greater than 1000 mrem /hr shall be provided with

locked doors, and doors shall remain locked except during periods of access by

personnel under an approved radiation work permit. This constitutes a violation of

TS 6.9.3, however, this licensee identified and corrected violation is being treated

as a non-cited violation, consistent with Section Vil of the NRC Enforcement Policy

(50-331/97009-06).

c. Conclusions

The licensee identified that the door was unlocked and appeared to be taking

appropriate corrective action.

V. Manaaement Meetinas

X1 Exit Meeting Summary

The inspectors presented the inspection results to members of licensee management at the

conclusion of the inspection on May 29,1997. The licensee acknowledged the findings

presented.

The inspectors asked the licensee whether any materials examined during the inspection

should be considered proprietary. No proprietary information was identified.

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PARTIAL LIST OF PERSONS CONTACTED

Licensee '

J. Franz, Vice President Nuclear

G. Van Middlesworth, Plant Manager

J. Bjorseth, Maintenance Paperintendent

D. Curtland, Operations Manager

R. Hite, Manager, Radiation Protection

M. McDermott, Manager, Engineering

K. Peveler, Manager, Regulatory Performance

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INSPECTION PROCEDURES USED

IP 37551: Onsite Engineering

IP 40500: Effectiveness of Licensee Controls in Identifying, Resolving, and

Preventing Problems

IP 61726: Surveillance Observation

IP 62707: Maintenance Observation

IP 71707: Plant Operations

IP 71750: Plant Support

IP 92700: Onsite Followup of Written Reports of Nonroutine Events at Power

Reactor Facilities

IP 92901: Followup - Operations

IP 92902: Followup - Engineering

IP 92903: Followup - Maintenance

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ITEMS OPENED AND CLOSED

Opened

50-331/97009-01 NOV Inadequate drywell spray tagout

50-331/97009-02 NOV inadequate river water supply tagout

50-331/97009-03 NCV Inadequate maintenance instruction form

50-331/97009-04 NOV Failure to specify post-maintenance testing for ventilation

dampers

50-331/97009-05 NOV Failure to post notices to workers

50-331/97009-06 NCV Locked high radiation door unlatched

Closed

50-331/95009-01 URI Extraction steam valves found out of normal position

50-331/95011-02 IFl Loose piping supports identified

50-331/96005-02 IFl HPES conclusions and corrective actions on TSC diesel failure

to start

50-331/96007-02 IFl Configuration controlissues

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LIST OF ACRONYMS USED

ACP Administrative Control Procedure  !

AR Action Request i

CFR Code of Federal Regulations J

CMAR Corrective Maintennnce Action Request l

DAEC Duane Arnold Energy Center

DCP Design Change Package  :

HPT Health Physics Technic an

HRA High Radiation Area

IFl inspection Followup item

IPOl Integrated Plant Orserating Instruction  !

IR Inspection Report j

LCO Limiting Condition for Operation  ;

LER Licensee Event Report '

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LHRA Locked High Radiation Area i

MD Maintenance Directive i

NCV Non-cited Violation )

NOV Notice of Violation j

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NRC Nuclear Regulatory Commission l

l 01 Operating instruction

l OSS Operations Shift Supervisor i

OA Quality Assurance  !

RHR Residual Heat Removal  ;

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RHRSW Residual Heat Removal Service Water

RWS River Water Supply

SBDG Standby Diesel Generator

SBGT Standby Gas Treatment System

STP Surveillance Test Procedure ,

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TS Technical Specification

UFSAR Updated Final Safety Analysis Report  !

URI Unresolved item  :

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