ML20216D055

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Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-483/98-04
ML20216D055
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 05/12/1998
From: Johnson W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Maynard O
WOLF CREEK NUCLEAR OPERATING CORP.
References
50-482-98-04, 50-482-98-4, NUDOCS 9805200026
Download: ML20216D055 (4)


See also: IR 05000483/1998004

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ARLINGTON, TE XAS 76011-8064

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MAY I 21998

Otto L. Maynard, President and

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Chief Executive Officer

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Wolf Creek Nuclear Operating Corporation

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P.O. Box 411

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Burlington, Kansas 66839

SUBJECT: NRC INSPECTION REPORT 50-482/98-04 AND NOTICE OF VIOLATION

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Thank you for your letter of April 28,1998, in response to our letter and Notice of

1

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Violation concerning: (1) the operators failure to log entry into a Technical Specification Action

Statement for shutdown rod insertion; (2) failure to perform surveillance testing on auxiliary

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feedwater pumps and emergency diesel generators on a staggered test basis; and (3) a quality

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control inspectors failure to follow radiation protection requirements regarding hot spots and

performing work without appropriate health physics coverage. We have reviewed your reply and

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find it responsive to the concerns raised in our Notice of Violation. We will review the

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implementation of your corrective actions during a future inspection to determine that full

compliance has been achieved and will be maintained.

Sincerely,

W. D. ohnson, Chief

Project Branch B

Division of Reactor Projects

Docket No.:

50-482

License No.: NPF-42

cc:

Chief Operating Officer

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Wolf Creek Nuclear Operating Corp.

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P.O. Box 411

Burlington, Kansas 66839

9005200026 980512

PDR

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Wolf Creek Nuclear Operating Corporation

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Jay Silberg, Esq.

Shaw, Pittman, Potts & Trowbridge

2300 N Str!iet, (!W

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Washington, D.C. 20037

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Supervisor Licensing

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Wolf Creek Nuclear Operating Corp.

P.O. Box 411

Burlington, Kansas 66839

Chief Engineer

Utilities Division

Kansas Corporation Commission

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1500 SW Arrowhead Rd.

Topeka, Kansas 66604-4027

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Office of the Governor

State of Kansas

Topeka, Kansas 66612

Attorney General

Judicial Center

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301 S.W.10th

2nd Floor

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Topeka, Kansas 66612-1597

County Clerk

Coffey County Courthouse

Burlington, Kansas 66839-1798

Vick L. Cooper, Chief

Radiation Control Program

Kansas Departmect of Health

and Environment

Bureau of Air and Radiation

Forbes Field Building 283

Topeka, Kansas 66620

Mr. Frank Moussa

Division of Emergency Preparedness

2800 SW Topeka Blvd

Topeka, Kansas 66611-1287

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Wolf Creek Nuclear Operating Corporation

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Project Engineer (DRP/B)

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RIV File

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DOCUMENT NAME:' R:\\_WC\\WC804AK.JFR

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DOCUMENT NAME: R:\\_WC\\WC804AK.JFR

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WQLF CREEK

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NUCLEAR OPERATING CORPORATION

Otto L Maynard

President and Chief Executive Officer

April 28, 1998

WM 98-0025

U. S. Nuclear Regulatory Commission

ATTN:

Document Control Desk

Mail Station Pl-137

Washington,

D.

C.

20555

Reference:

Letter dated April 1,

1998, from T.

P.

Gwynn,

URC, to 0.

L. Maynard, WCNOC

Subject:

Docket No. 50-482:

Reply to Notice of Violations

50-482/9804-01, 50-482/9804-03, and 50-482/9804-07

.

Gentlemen:

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

to Notice of Violations 50-482/9804-01, 50-482/9804-03, and 50-482/9804-0/.

Notice of Violation 50-482/9804-01 ider.tified that WCNOC Operations personnel

performed a technical specification surveillance on the control rod shutdown

banks that required entry into the Limiting Candition for Ogeration (LCO) for

the specification, but the procecure did not indicate entry into the LCO was

required and the Cperators did not log the entry into the control room log.

Notice of Violation 50-482/9804-03 identified ineffective corrective actions

on an LER concerning surveillance testing on a staggered test basis.

The

inspection report indicated that no response is reqaired for this violation.

Notice of Violation 50-482/9804-07 identified weaknesses in the radiation

protection program and in individual radiation worker performance that

resulted in two examples of

noncompliance with radiation work permit

requirements.

WCNOC' s response to these violations is provided in the

Attachment.

If you have any questions concerning this matter, please contact me at (316)

364-8831, extension 4000, or Mr. Michael J. Angus, at extension 4077.

Very truly yours,

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Otto L. Maynard

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OLM/rir

Attachment

cc:

W.

D.

Johnson (NRC), w/a

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E. W.

Merschoff (NRC), w/a

J. F.

Ringwald (NRC), w/a

K.

M. Thomas (NRC), w/a

RW {$ lk

PO. Box 411/ Burhngton, KS 66839 / Phore:(316) 364 8831

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An Equat Opporturuty Emp6 oyer M F NCVET

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Attachment to WM 98-0025

Page 1 of 5

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Response to Notice of Violations

Violation 50-402/9804-01

" Technical Specification 6.8.la requires, in part, that written procedures be

established, implemented, and maintained covering the applicable procedures

recommended in Appendix A of Regulatory Guide 1.33, Revi:: ion 2,

February 1978.

Regulatory Guide 1.33,

Revision 2,

February 1978, Section 2,

recommends, in

part, that procedures be establi.=hed for general plant operations.

Technical Specification 3.1.3.5

states that,

'All shutdown rods shall be

limited in physical insertion as specified in the Core Operating Limits

Report' in Modes 1 and 2.

The cora operating limits report limits shutdown

rod insertion to no less than 222 steps.

The action statement associated with

Technical Specification 3.1.3.5 limits the number of shutdown rods inserted

beyond the insertion limit to a maximum of one rod, except for surveillance

testing pursuant to Technical Specification 4.1.3.1.2.

The action statement

requires that rods be restored to within the rod insertion limit within 1

hour.

Procedure AP 21-001,

' Operations Watch Standing Practices,'

Revision

8,

requires that all entries into short-term limiting conditions for operation be

logged in and out of the control room log.

Contrary to the above, on February 18,

1998, operators failed to log entry

into the action statement for Technical Specification 3.1.3.5

fer shutdown

rods inserted beyond the rod insertion limits.

This is a Severity Level IV violation (Supplement I)(50-482/9804-01)."

Description of Violation:

WCNOC Control Room personnel failed to acknowledge entry into the Action

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Statements for Technical Specifications 3.1.3.5,

SHUTDOWN ROD I'ISERTION LIMIT,

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and

3.

3. 6,

CONTROL ROD INSERTION LIMITS,

when performing testing in

accordance with Technical Specification Surveillance Requirement 4.1.3.1.2.

The failure to log the entrance into the Technical Specification Action

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Statements 3.1.3.5 and 3.1.3.6,

represented no safety significance.

This is

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based on the information contained within the Action Statements for Technical

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Specifications 3.1.3.5 and

3.1.3.6.

Specifically, the Action Statements for

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Technical Specifications 3.1.3.5 and 3.1.3.6 exempts the operators from having

to take any actions as long as surveillance testing pursuant to Technical Specification 4.1.3.1.2 is being performed.

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Reason for Violation:

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This violation was determined to be the result of a failure to develop

adequate procedural guidance within surveillance test procedure STS SF-001,

" Control And Shutdown Rod Operability Verification."

Specifically, this

procedure did not alert the implementers that the associated testing activity

would

result

in

an

entry

into

the

action

statements

for

Technical Specifications 3.1.3.5 and 3.1.3.6.

The wording of Technical Specifications 3.1.3.5

and

3.1.3.6

are unique in nature.

No other WCNOC technical

specification contains an exception statement within an action statement.

The

failure to adequately develop STS SF-001 is an isolated case and does not

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Attachment to WM 98-0025

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Page 2 of 5

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Response to Notice of Violations

represent a generic concern.

A contributing factor was determined to be the

failure of the Control Room Personnel to identify the applicability of

Technical Specifications 3.1.3.5

and

3.1.3.6

and to log entry into these

action statements.

Corrective Steps Taken and Results Achieved:

STS SF-001 was refised to provide enhanced guidance on the applicability of

Technical Specifications 3.1.3.5 and 3.1.3.6.

This activity was completed on

March 31, 1998.

As a good practice, management expectations on 1) reviewing all applicable

technical specifications before the performance of an activity, 2) literal

compliance to all applicable specifications, and 3) compliance with all

established (both programmatic and technical) requirements were reinforced

with Control Room persor.ael.

This activity was completed on March 10, 1998,

during the Shift Supervisor's Meeting.

Corrective Steps To Be Taken:

Operations' Management ~ will issue an essential reading assignment to all

licensed individuals to ensure the events surrounding this issue,

the

associated corrective actions, and management's expectations asrociated with

logging Technical Specification action statements entered due to surveillance

testing, are clearly understood.

Further, this reading assignment will stress

the importance of reviewing surveillance procedures for applicability of other

Technical Specifications during the performance of the surveillance.

The

projected completion date of this activity is May 31, 1998.

Date When Full Compliance Will Be Achieved:

Full compliance was achieved on March 20, 1998, when Control Room Personnel

appropriately logged into the Control Room Log entry into and exit from

Technical Specifications 3.1.3.5

and

3.1.3.6

during the next scheduled

performance of STS SF-001 (a monthly surveillance).

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Attachment to WM 98-0025

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Page 3 of 5

Response to Notice of Violations

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Violation 50-482/9804-03

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" Technical Specifications 4.7.1.2.1.a and 4.8.1.1.2 require surveillance tests

the auxiliary feedwater pumps and emergency diesel generators be performed

on

on a staggered test basis.

Contrary to the above, between August 1994 and May 1996, the licensee failed

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to perform surveillance testing on the auxiliary feedwater pumps and emergency

diesel generators on a staggered test basis.

This is a Severity Level IV violation (Supplement I)(50-482/9804-03)."

WCNOC Response

Inspection Report 50-482/98-04 states that Licensee Event Reports 50-482/96-

009-00 and 50-482/96-009-01 adequately addressed the corrective actions taken

and planned to correct the violation and prevent recurrence and the date when

full compliance was achieved.

The inspectlen report also indicates that no

additional response is required for this violation unless the referenced

licensee event reports do not accurately reflect NCNOC's corrective actions

for, or position on,

this issue.

WCNOC has determined that the referenced

licensee event reports accurately describe our corrective actions and position

on this issue and that no additional response is required.

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Attachment to WM 98-0025

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Page 4 of 5

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Response to Notice of Violations

violation 50-482/9804-07

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" Technical Sp,nfication 6.11 requires, in part, that radiation protection

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technicians

and

workers

adhere

to

procedures

for

personnel

radiation

prottetion consistent with the requirements of 10 CFR Part 20.

Administrative Procedure AP 25B-100, Radiation Worker Guidelines, Revision 5,

1

Section

6.3.6,

requires individaals to comply with radiation work permit

requirements.

)

Radiation Work Pelait 98009, Revision 0,

required intermittent health physics

coverage and required the radiation worker to avoid all posted hot spot

locations.

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Contrary to the above, on February 18, 1998,

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a.

A quality control inspector worked within 18 inches of two posted

hot spots for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, and

b.

No health physics coverage of the work was provided during this 3-

hour period.

This is a Severity Level IV violation (Supplement IV) (50-4 82/9804-07) ."

Description of Violation:

A Quality Control (QC) inspector involved with work in Containment Spray Room

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"A"

was working near a posted hot spot, not utilizing As Low As Reasonably

Achievable (ALARA) principles.

Investigation identified that the QC inspector

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did not check in with the Health Physics (HP) Shift Technician for a briefing

of radiological conditions.

The individual was not aware of the dose rates in

the area and did not check the survey map at the entrance to the

"A"

Containment Spray Room.

Radiation Work Permit (RWP) 980009, under Special

Instructions

3,

states:

" Avoid all posted hot spot locations."

The worker

was not aware of the hot spots.

Therefore, the individual did not meet the Radiation Worker expectation of

kn' wing the expected dose rates and contamination levels encountered.

The

individual did not conform to AP 25B-100, " Radiation Worker Guidelines," steps

5.3 and 6.1.9.

Reason for Violation:

The QC inspector failed to meet the expectations of RWP 98-0009, specifically

Special Instruction 3,

which states: " Avoid all posted hot spot locations."

The QC inspet'

did not adequately review the survey map prior to entering

the area and was urs

re of the radiological condittons in the work area.

As

a result, the OC ins actor performed work in close proximity to

posted hot

spot area and, aue to not checking in with the HP Shift Tech, intermittent HP

coverage was not provided.

When the QC inspector noted the posted hot spots

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on the piping he did not challenge the ALARA aspects of the situation by

.hysics to evaluate the working conditions.

Theretore, both

asking Health

aspects of this violation were the result of inadequate work practices on the

part of the QC inspector.

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