ML20199E885

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Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/97-19 on 971125.Finds Reply Responsive to Concerns Raised in Nov. Implementation of C/As Will Be Reviewed in Future Insps
ML20199E885
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 01/26/1998
From: Johnson W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Maynard O
WOLF CREEK NUCLEAR OPERATING CORP.
References
50-482-97-19, NUDOCS 9802020269
Download: ML20199E885 (4)


See also: IR 05000482/1997019

Text

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9'g NUCLEAR REGULATORY COMMISSION

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% / 611 RYAN PLAZA DRIVE, SulTE 400

/ AR LINGTON, TEXAS 760118064

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- JAN 2 6 1998

Otto L. Maynard, President and

Chief Executive Officer

- Wolf Creek Nuclear Operating Corporation

P.O. Box 411

Burlington, Kansas 66839

SUBJECT: NRC INSPECTION REPORT 50-482/97-19

Dear Mr. Maynard:

2

Thank you for your letter of December 23,1997, in response to our letter and Notice of

Violation dated November 25,1998. We have reviewed your reply and find it responsive to the

concerns raised in our Notice of Violation. We will review the implementation of your corrective

actions during a future inspection to determine that full compliance has been achieved and will-

be maintained.

Sincerely,

W

W. D. Johnson, Chief .

Project Branch B

Division of Reactor Projects

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Docket No.: 50-482 /

License No.: NPF-42

cc:

Chief Operating Officer

Wolf Creek Nuclear Operating Corp.

P.O. Box 411

Burlington, Kansas 66839

Jay Silberg, Esq.

Shaw, Pittman, Potts & Trowbridge

2300 N Street, NW

Washington, D.C. 20037

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9802020269 990126 i . '*

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PDR ADOCK 05000482 -

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Wolf' Creek Nuclear Operating Corporation -2-

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Supervisor Licensing _ _

Wolf Creek Nuclesr Operating Corp.

P.O. Box 411

Burlington, Kansas 66839

. Chief Engineer

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Utilities Division -

Kansas Corporation Commission

157 SW Arrowhead Rd.

. Topeka, Kansas 66604-4027

- Office of the Govemor

State of Kansas.

Topeka, Kansas 66612

Attomey General

Judicial Center

301 S.W.10th

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2nd Floor

Topeka, Kansas 66612-1597

County Clerk -

Coffey County Courthouse

Burlington, Kansas 66839-1798

Vick L. Cooper, Chief

Radiation Control Program

Kansas Department of Health :

and Environment -

Bureau of Air and Radiation

- Forbes Field Building 283

-Topeka, Kansas 66620

Mr. Frank Moussa

Division of Emergency Preparedness --

4 2800 SW Topeka Blvd

Topeka, Kansas 66611-1287

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Wolf Creek Nuclear Operating Corporation 3-

JAN 2 61998

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Regional A&inistrator - Resident inspector

DRP Director - SRI (Callaway, RIV)

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Project Enginect (DRP/B)i MIS System

Branch Chief (DRP/TSS) RIV File

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DOCUMENT NAME: R:\_WC\WC719AK.JFR

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OFFICIAL RECORD COPY

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DOCUMENT NAME: R:\_WC\WC719AK.JFR

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OFFICIAL RECORD COPY

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W@) NUCLEAR OPERATING CO CREEK ~

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Otto L Mayr.ard l

Prescent and Chef Executive Offrer -

December 23, 1997

WM 97-0151

U. S. Nuclear Regulatory Commission

ATTN Documer.t Control Desk

Mail Station 01-137

Washington, D. C. 20555

Reference: Letter dated November 25, 1997, from W. D. Johnson,

!J RC , to O. L. Maynard, WCt100

Subject: Docket No. 50-482: Response to Notice of Violations

50-402/9719-01, 9719-02, 9719-03, 9719-04, and 9719-05

Gentlement

This letter transmits Wolf Creek Nuclear Operating Corporation's (WCNOC)

response to Notice of Violations 50-482/9719-01, 9719-02, 9719-03, 9719-04,

and 9719-05. Notice of Violation 9719-01 cites use of an operator aid without -

the docunented approval of the Shift Supervisoc. Notice of Violation 9719-02

cites examples of offectiveness follow-ups for corrective action documents not

being performed as required by procedure. Notice of Violation 9719-03 cites

an example of a maintenance worker working outside cf procedural guicance

which resulted la an inadvertent opening of an atmospheric relief valve.

Notice of Violation 9719-04 addresses a failure to reinstall an equipment

hatch cover following the replacement of the associated filter cartridge,

Notice of Violation 9719-05 cites four examples of personnel failing to adhere

to radiation protection procedures.

WCNOC's response to these violations is provided in the attachment. If you

have any questions regarding this response, please contact me at (316) 364-

8831, extension 4000, or Mr. Michael J. Angus at extension 4077

Very truly yours,

. $olL

Otto L. Maynard

OLM/jad

Attachment

cc: W. D. Johnson (NRC), w/a

E. W. Merschoff (NRC), w/a

J. F. Ringwald (NRC), w/a

K. M. Thomas (NRC), w/a

PO Box 411/ Burkngton. KS 66839 Phone'(316) 364-8831

An Eoual Opportumtv Employer M F HC VET

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I* , Attachmont to WM 97-0151

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Page 1 of 9

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Violation 50-402/9719-01:

" Criterion V of Appendix D to 10 CFR 50 requires, in part, that activities

affecting quality shall be prescribed by documented i'ntructions, procedures,

and drawings appropriate to the circumstances, and shall be acccmplished in

accordance with these instructions, procedures, or drawings.

Pr ocedure AP 21D-003, " Control of Information Taggiag," Revision 1 Step 6.6.10

requires operatcr aids to be approved and documented by the Shift Supervisor.

Cont rary to the above, f rom October 8, to October 22, 1997, operators used

markings on Drawing EID-0003 as an operator aid without documented approval of

the shift supstvisor.

This is a Severity Level IV violation (Supplement 1) (50-482/9719-01)."

Reason for Violation

Engineering Information Drawing (EID)-0003, " Refuel Level Indication," was

referred to by Control Room operators between Octcber 8, and October 25, 1997.

The inspector noted that EID-0003 listed the levels in percent while the wide

range cold pressurizer level was calibrated in inches. In order to provide a

correlation between the two, a c1 :ulation was performed and EID-0003 was

marked-up with handwritten notes. EID-0003 and the hardwritten notes should

have been controlled as either an operator aid, or the notes should have been

incorporated as a revision to the drawing.

The reason for the violation is failure to follow procedures which resulted in

use of information which had not been verified and validated. AP 21D-003,

" Control of Information Tagging" das not followed when the hand written notes

were added to the drawing, and therefore not verified, validated and approved

for usage.

Corrective Steps Taken and Results Achioved:

On November 3, 1997, Revision 1 to EID-0003 wts issued. This revision removed

all Callaway site specific inf ormation and verified the tygon tubing water

<

level (feet).

Corrective Steps That Will Be Takent

The contributing cause and generic implications related to - this event are

being evaluated by PIR 97-0945 which was w-itten in association with Self

Assessment 97-017, " Evaluation of Desktops or other Informal Instructions,"

which looks at the generic implication of site wide uncontrolled nocuments.

The expected completion date is January 15, 1999.

The Superintendent Operations Support will meet with each operating crew and

review AP 21D-003, " Control of Information Tagging" in conjunction with

Performance Improvement Request (PIR) 97-3442, associated with this violation,

to ensure they understand the appropriate use of documents. This action will

be completed by February 2, 1998.

Each Operations Shift Supervisor and the Superintendents of Operations and

Operations Support will meet with their direct reports and ensure all

uncontrollad documents that could be used to make decisions in operating the

plant are removed from the Operations office spaces and the Control Room.

These uncontrolled documents are then to be either destroyeo or subritted for

processing to become controlled documents. The expected completion date fnr

these meetings is February 2, 1998.

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Pega 2 of 9

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Date When Full Compliance Will Be Achievedt

WC110C is currently in full compliance. Compliance was achieved on October 2$,

1997 wnen EID-0003 was removed from the Control Room,

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Page 3 of 9

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Violation 50-492/9719-02:

Criterion V of Appendix B to 10 CFR Fart 50 requires, in part, that activities

affecting quality shall be prescribed by documented instructions, procedures,

and drawings -appropriate to the circumstances and shall be accomplished in

accordance with these instructions, procedures, or drawings,

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Administrative Procedure AP 28A-001, " Performance Improvement Request."

Revision B, Step 6.1 1.1, requires that an effectiveness followup review be

performed for all Significance Level I and II performance improvement

requests.

Contrary to the above, on October 22, 1997, effectiveness followup reviews

were not performed for Performance Improvement Requests 96-2906 and -2989.

Both were Significance Level II performance improvement requests.

This is a Severity Lovel IV violation (Supplement 1)(50-482/9719-02).

Reason for the Violation

Additional reviews by WCNOC personnel identified 35 Performance Improvement

Requests (PIbs) past their effectiveness follow-up review due dates. Twenty-

seven of these were significant PIRs which are required to have an

effectiveness follow-up review. Eight of the PIRs were non-significant which

are not required to have an effectiveness follow-up review. Eight different

groups had effectiveness follow-up reviews past due.

The reason for the violation is that during initial development of the PIR

program, mechanisms were not designed to provide management all of the tools

to effectively monitor effectiveness follow-up reviews. Specifically, though

the requirement was in place to perform effectiveness follow-up reviews,

guidance for reporting and trending and the responsibility for performing

these actions were not established.

Contributing cause

The controls to execute a computer search for effectiveness followup review

dates were not user friendly and were different from the usual search

techniques.

Corrective Steps Taken and Results Achieved

Responsible managers were contacted to advise them of the concern and request

they review their PIRs or re-schedule them to an appropriate time. Immediate

actions included the Operations department complet ing six effectivenens

follow-ups and the Maintenance department re-scheduling four follow-ups and

deleting one follow-up date that was assigned to a non-significant PIR. By

October 29, 1997, all the overdue effectiveness follow-up reviews had been

completed or re-scheduled.

Sn October 26, 1997, the PIR data base was modified to make the search for

effectiveness follow-up review dates more user friendly. PIR Logkeepers were

then interviewed and on-the-job training performed to ensure they know how to

search for effectiveness follow-up review due dates and have adequate

knowledge to find PIR due dates.

The Licensing and Corrective Action group began monitoring effectiveness

follow-up review due dates on October 29, 1997 A 30-day "look ahead" report

is now provided to managers to advise them of effectiveness follow-up reviews

coming due. This corrective action was implemented on Decerber 19, 1997.

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Corrective Steps That Will Be Taken

The p'ogram for monitoring effectiveness follow-up reviews will be modified to

ass 19a PIR Coordinators the responsibility to monitor effectiveness follow-up

review due d a'.e s . Procedure AP 28A-001, " Performance Improvement Request,"

will be rev; sed by December 31, 1997, to clearly state the PIR Coordinator

responsibility for this rnonitoring function.

Licensing and Correction Action will develop performance indicators for

tracking corrective action effectiveness follow-up reviewa. These performance

indicators will be developed by February 2, 1998.

PIR Coordinators will be trained by - December 31, 1997, to use the search

functions in the PIR data base to find effectiveness follow-up review due

dates.

Date When Full Compliance Will Be Achieved:

Full compliance was achieved on October 29, 1997, when the overdue

effectiveness follow-up reviews were either performed or rescheduled.

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. Attachment t o WM 97-0151

Page 5 of 9

Violatien 50-482/9719-03:

" Technical Specification 6.B.l.a requires, in part, that written procedures be

established, implemented, and maintained covering the applicable procedures

reconcended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. .

Regulatory Guide 1.33, Revision 2, February 1978, Section 3.f., recommends, in

part, that procedures be established for surveillance tests.

Surveillance Procedure STS MT-008, " Main Steam Safety Valves Settings,"

Revision 8, Section 4.3, ree" ires the test performer to not operate the root

valves indicated on Attacb"* a

Contrary to the above, on S 9 ;q? 5e 30 ,1997, the test performers closed then

opened Valve AB V0028, the inst rt.ae nt root valve indicated on Attachment C of

Procedure STS MT-000, causing an inadvertent opening of Valve AB PV0003,

atmospheric relief valve for Steam Liae C.

This is a Severity Level IV violation (Supplement 1) (50-482/9719-03)."

Reason for Violatient

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The reason for this violation is personnel error in that Maintenance personnel

failed to comply with procedural requirements. The procedure, STS MT-000, did

not contain step for operating val ~e ABV0028, a root valve. It contained a

caution note telling the worker not to operate the valve.

Contributing '.o the event were two additional causes:

1. There was inadequate communication between personnel involved in the work

activities. There were missed opportunities to provide more specific

direction, to confirm what was misunderstood or to call " time-out".

2. The pre-joo briefing was 2ncomplete in that there was a failure to cover

- specific responsibilities, procedural precautions, and procedure use

requirements. The failure to cover these items in the pre-job briefing was

a missed opportunity to make sure everyone understood their roles and

responsibilities.

Corrective Steps Taken and Resulta Achieved:

The Manager Maintenance met with Mechanical Maintenance personnel, first line

Maintenance supervisors, and contractors on September 30, and October 1-2,

1997, to reinforce the limits and expectations for maintenance personnel

operating plant equipment. Additionally, the expectation that the Control

Room be contacted immediately upon recognizing a component or system

manipulation error was reinforced.

Training for all Mechanical Maintenance personnel, reaffirming the

requirements of procedure AP 15C-002, " Procedure Use and Adherence," was

completed on October 2, 1997 The training also included instructions for use

of three-way communication and the expected elements of pre-job briefings.

Fact .inding discussions and job counseling were done with those personnel

involved. These actions were completed on October 7, 1997.

s Procedure STS MT-008 was revised en October 9, 1997, to correct valve

misnomers, add caution notes and incorporate other human factor improvements.

" Communication for Error Preventien" training was given to Maintenance craft

persennel. This training was completed on December 22, 1997.

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Fage 6 of 9

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Corrective Steps that will be Takent

The lessons learned from this event will be shared with the other maintenance

groups through review of Performance Improvement Request (PIR) 97-2959 during

group safety meetings. This corrective action will be ecmpleted by February

27, 1998.

Date When Full Compliance Will P.s Achievedt

WCtmC is currently-in full compliance. Compliance was achieved on September

30, 1997, when ABV00;d was opened.

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Page 7 of 9

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Violation 50-402/9719-04:

" Technical Specification 6.6.1.a requires, in part, that written procedures be

established, implemented, and maintained covering the applicable procedures

recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

Regulatory Guide-1.33 Revision 2, February 1970, Section 3.f., recommends, in

part, that procedures be established for replacement of important filters."

Procedure MCM M7230-01, "NSSS Filter Changeout," Revision 9, Section. 8.4,

requires maintenance personnel to reinstall the hat 9h cover over the equipment

compartment as part of the restoration.

Contrary to the above, on October 12, 1997, maintenance personnel signed for

the completion of Procedure MCM M723Q-01 fe' lowing the replacement of - the

filter cartridge without reinstalling the equipaent hatch cover. The failure

to replace the hatch cover resulted in the area near the filter to be

accessible as radiation levels increased to 3 Rem per hour 12 inches from the

filter housing after operators returned the filter to service.

This is a severity Level IV violation (Supplement 1) (50-482/9719-04)

Response to Violation

The reason for the above stated violation and the associated corrective

actions were documented in WCNOC's response to violation 97-020-01, in letter

WM 97-0133, dated December 12, 1997, which pertained to the same event,

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. Attachment to WM 97-01$1

Page 9 of 9

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Other actions implemented by the Health Physics organization included the

s stablishment of the RCA access control area as a "No Talking Zone" to allow (

for greater concentration, and posting of a security officer at the RCA access

door as an interim control during outage activities.

i Correctiva Steps That Will Be Takent

Performance Improvement Request (PIR) 97-2389 was initiated by Health Physics

on August 7, 1997, to identify general adverse trends regaroing violations of

the Radiation Protection Program. Short term corrective actions for this PIR

were completed as of October 2, 1997. Long term corrective actions including

evaluation of changes to radiation worker training are due to be complete by

January 30, 1998,

in an effort to improve human performance in the Access Control area, WCNOC

Health Physics personnel will submit a proposed facility change to be

evaluated using the design change process. This proposal will be submitted by

January 1, 1998.

Date When Fuli Compliance Will Be Achieved:

WCMOC is currently in full compliance. Full compliance was achieved on the

date of occurrence of each event when the individuals involved were brought

into compliance with WCNOC's radiation protection program requirements.

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l Violation 50-482/9719-05:

" Technical Specification 6.11 requires, in part, ti.at radiation workers adhere

to procedures for personnel radiation protection consistent with the

requirements of 10 CFR Part 20.

Administrative Procedure AP 25A-100, " Radiation Protection Manual" Revision 2,

6ection 6.7.4, requires that access to the RCA [ radiologically controlled

areal be controlled by an approved RWP [ radiation work permit].

Contrary to the abovet

a. On October 5, 1997, a mechanic accessed the radiologically

controlled area using Radiation Work Permit 970009 and used an,

internally contaminated gauge while pe r f orraing work in the

radiologically contrc11ed area, an activity prohibited by the

radiat on work permit,

b. On October 10, 1997, a radiation worker exited the radiologically

controlled area and logged out of Radiation Work Permit 972601.

The worker subsequently reentered the radiologically controlled

area without logging onto a radiation work permit and without

obtaining any dosimetry.

c. On October 26, 1997, a radiation worker entered containment

without an alarming dosimeter as required by Radiation Work Perrit

970034

d. On October 27, 1997, a radiation worker entered the radiologically

controlled area without the thermoluminescent dosimeter required

by Radiation Work Permit 970009.

This is a Severity Level IV violation (Supplement IV) (50-482/9719-05)."

Reason for Violations

As the above examples are similar in nature and pertain to violations of. the

radiation worker practices they were researched together to determine the root

cause and appropriate corrective actions.

In the case of example b. it was concluded that the initial cause was a human

error resulting from either a short-cut being taken or failure to implement

rules learned in radiation worker training.

In the remaining examples it was determined that the radiation workers

exhibited inattention to detail that caused them to violate radiation

protection program requirements. The errors were unintentional and occurred

either due to overconiidence on the part of the employee or due to an

unplanned interruption that took the employees' attention away from the

radiation protection program requirements.

Corrective Steps Taken and Results Achieved:

Corrective actions for each example included these common actions:

  • Each employee or contractor had their access to the radiologically

controlled area (RCA) revoked.

  • Employee retraining or counseling was periormed which met the standards of

management.

  • Job performance counseling was performed.
  • Each event was discussed during group or safety meetings to ensure lessons

learned were shared.