ML20151Z586

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Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/98-03 Issued on 980717
ML20151Z586
Person / Time
Site: Oyster Creek
Issue date: 09/11/1998
From: Eselgroth P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Roche M
GENERAL PUBLIC UTILITIES CORP.
References
50-219-98-03, 50-219-98-3, NUDOCS 9809220031
Download: ML20151Z586 (2)


See also: IR 05000219/1998003

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September 11,1998

Mr. Michael B. Roche -

Vice President and Director

GPU Nuclear, Inc.

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Oyster Creek Nuclear Generating Station

P.O. Box 388

Forked River, New Jersey 08731

SUBJECT:

INTEGRATED INSPECTION 50-219/98-03

Dear Mr. Roche:

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This letter refers to your August 14,1998 correspondence, in response to our

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July 17,1998 letter.

Thank you for informing us of the corrective and preventive actions documented in your

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letter. These actions will be examined during a future inspection of your licensed program.

Your cooperation with us is appreciated.

Sincerely,

Original Signed By:

Peter W. Eselgroth, Chief

Projects Branch 7

Division of Reactor Projects

Docket No.: 50-219

cc w/o cv of Licensee Resoonse Letter:

M. Laggart, Manager, Licensing and Vendor Audits

G. Busch, Manager, Nuclear Safety and Licensing

ec w/cv of Licensee Resoonse Letter:

State of New Jersey ,

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Mr. Michael B. Roche

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Distribution w/cv of Licensee Response Letter

Region 1 Docket Room (with concurrences)

Nuclear Safety information Center (NSIC)

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PUBLIC-

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NRC Resident inspector

H. Miller, RA/W. Axelson, DRA

P. Eselgroth, DRP

N. Perry, DRP

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D. Haverkamp, DRP

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C. O'Daniell, DRP.

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J. Yerokun, DRS

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B. McCabe, OEDO

C. Thomas, PD1-3, NRR

R. Eaton, PD1-3, NRR

T. Colburn, PDI-3, NRR

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R. Correia, NRR

F. Talbot, NRR

DOCDESK

Inspection Program Branch, NRR (IPAS)

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DOCUMENT NAME: G:\\ BRANCH 7\\REPLYLTR\\OC9803,RPY

T3,oceive a copy of this document, indicate in the box:

  • C" = Copy without attachment / enclosure
  • E' = Copy with attachment / enclosure
  • N' = No copy

OFFICE,

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DATE

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OFFICIAL RECORD COPY

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GPU Nuclear. Inc.

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U.S. Route #9 south

. NUCLEAR

Post Office Box 388

Forked River, NJ 087310388

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Tel 609-9714000

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August 14, 1998

1940 98-20458

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U. S. Nuclear Regulatory Commission

Attention: . Document Control Desk

Washington, DC 20555

Dear Sir:

Subject:

Oyster Creek Nuclear Generating Station

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Docket No. 50-219

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IR 98-003: Reply to Notice of Violations

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in accordance with 10CFR 2.201, the enclosed provides GPU Nuclear's response to the

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- violations identified in the subject inspection report.

If you should have any questions, or require further information, please contact Brenda

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DeMerchant, Oyster Creek Regulatory Affairs Engineer, at 609-971-4642.

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Very truly yours,

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Michael B. Ro e

{kVice President and Director

Oyster Creek

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Attachment

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cc:

Administrator, Region I

NRC Project Manager

NRC Sr. Resident Inspector

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Attachment I

Violation 1

The Code of Federal Regulations,10 CFR, Part 50, Appendix B, Criterion XV (Nonconforming

Materials, Parts, or Components) requires that measures shall be established to control materials,

parts, or components which do not conform to requirements in order to prevent their inadvertent

use or installation. These measures shall include, as appropriate, procedures for identification,

documentation, segregation, disposition, and notification to affected organizations.

Nonconforming items shall be reviewed and accepted, rejected, repaired or reworked in

accordance with documented procedures.

Oyster Creek Nuclear Generating Station (OCNGS) procedure 125.2.10, Receipt Deficiency

Reports, revision 2, requires, in part, the action party for a deficiency to provide a proposed

disposition to resolve the deficiency (Use-As-Is, Repair, Rework, Scrap, Other), and the

Configuration Maintenance Manager to evaluate the proposed disposition and either concur or

provide the required disposition.

Contrary to the above, on or about June 9,1998, the licensee failed to review and disposition a

nonconforming emergency diesel generator starter motor in accordance with OCNGS procedure

125.2.10.

This is a Severity Level IV violation (Supplement I).

Response

GPU Nuclear concurs with the violation as written.

Reason for Violation

Due to the fact that the plant was in a Technical Specification Limiting Condition for Operations,

thejob supervisor was focused on replacing the Number 1 Emergency Diesel Generator (EDG)

starter motor with an in kind replacement thus overlooking the administrative requirement to

disposition the deficiency of the nonconforming starter motor per Procedure 125.2.10.

During pre-service testing the starter motor failed to respond as required and the supervisor was

informed of the problem. During the supervisor's investigation he realized that a jumper was

installed that set up the starter motor for single operation rather than two starters in series as

required for Oyster Creek's diesels. Based on his knowledge and experience, thejob supervisor

directed that the replacement starter be configured to match the installed starters and that the

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starter be fully tested in accordance with approved procedures. The starter tested satisfactorily

and was installed in the Number 1 EDG. Post maintenance testing was performed satisfactorily

and the EDG was returned to operation.

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The fact that Procedure 125.2.10 was not followed was identified during the cognizant engineer's

post maintenance review.

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Attachment I

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1940-98-20458

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Page 2 of 6

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Corrective Stens Taken and Results Achieved

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Corrective Action Program (CAP) repons were generated to investigate the failure to document

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the deficient condition and to determine if a 10 CFR 21 report should be made. Also, a Receipt

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Deficiency Report (RDR) was written to capture action taken to configure the starter motor.

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This RDR was dispositioned to use the staner motor as configured with thejumper removed.

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Corrective Stens Taken to Avoid Further Violations

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An additional CAP was generated to document the failure to administratively control the

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configuration change to the staner motor.

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As per 10CFR, Pan 50, Appendix B, Criterion XV, measures are in effect under OCNGS

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procedure 125.2.10 to manage configuration control preventing inadvertent use or installation of

material. This event occurred due solely to an inappropriatejudgement by the supervisor. The

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superdsor has discussed configuration control with the Electrical Superintendent and the

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Configuration Control Manager. This event has also been discussed in the electrical shop

meetings.

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A review of the need to submit a 10 CFR 21 report in accordance with GPUN procedure 1000-

ADM-1290.01 is ongoing.

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Date When Full Comoliance was Achieved

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Full compliance was met when the Receipt Deficiency Report (RDR) was dispositioned as stated

above.

Violation 2

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License Condition 2.C.3, Fire ProteGinn, of Facility Operating License DPR-16, for the OCNGS,

states, in part, "GPU Nuclear Co9 oration shall implement and maintain in effect all provisions of

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the approved Fire Protection Program as described in the Updated Final Safety Analysis Report

for the facility and as approved in the Safety Evaluation Report dated March 3,1978, and -

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supplements thereto.'.."

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Section 9.5.1, Fire Protection Systems, of the Updated Final Safety Analysis Repon, states that

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OCNGS procedure 101.2, Fire Protection Program, is considered included in the Fire Protection

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Program.

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Att chment I

1940-98-20458

Page 3 of 6

Contrary to the above, GPU Nuclear Corporation did not implement and maintain in effect all

provisions of the approved Fire Protection Program as indicated by the following examples:

A.

OCNGS procedure 101.2, Fire Protection Program, directs that fire watches be

established in accordance with OCNGS procedure 120.2, Fire Watch Instructions.

Section 4.2.2, OCNGS procedure 120.2, Fire Watch Instructions, Subsection 4.2.2.1.3

requires that a fire watch turnover shall include a review of the Fire Watch Assignment

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Forms.

On May 18,1998, the fire watch turnover failed to include a review of the Fire Watch

Assignment Forms.

B.

Section 4.4, OCNGS procedure 101.2, Fire Protection Program, states, in part, that fire

watches shall provide required notification and possible extinguishment of a fire when a

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fire protection system is impaired or inoperable.

On August 1,1997, no fire watch was assigned to provide notification and possible

extinguishment of a fire in the exciter when the turbine generator exciter high pressure

CO system was inoperable.

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This is a Severity Level IV violation (Supplement I).

Response to Examnie "A"

GPUN concurs with the violation and offers the following additional information:

Reason for Violation

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Due to their familiarity with the existing impairments, the firewatch personnel used the Fire Watch

Inspection Log which provides a listing ofimpairments rather than the individual Fire Watch

Assignment Forms as described in the procedure. Even though the individual forms were not

reviewed, the firewatch was knowledgeable of the impairments and performed an appropriate

tour.

Corrective Steps Taken a d Results Achieved

Management's expectations were reviewed with all firewatch personnel regarding their roles and

responsibilities. In addition, a review of proper turnover techniques including usage of the

Inspection Log and the Assignment forms, and the purpose for both of these documents was held

with all firewatch personnel.

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Attichment I

1940-98-20458

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Corrective Stens Taken to Avoid Further Vi' lations

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Tr.e Fire Protection Coordinator has distributed these violations and the associated NRC

Inspection Report to the fire watch personnel and operations supervisors in order to heighten their

awareness and sensitivity to these issues.

The Fire Protection Coordinator has reinforced management's expectations and standards

regarding procedure compliance and proper turnover techniques with all fire watch personnel.

The Fire Protection Coordinator will review and revise (as appropriate) the Fire Watch

Instructions regarding the turnover process to enhance and simplify our existing process. The

appropriate revisions will be completed by November 1,1998.

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Date When Full Comoliance Was Achieved

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Full compliance was achieved on August 7,1998 with issuance of a memorandum reinforcing

management's expectations and standards regarding proper turnover techniques.

Response to Example "B"

GPUN concurs with the violation as written.

Reason For Violation

When the turbine generator exciter high pressure CO2 system was removed from service to

support routine maintenance activities, a fire watch was not assigned because of a procedural

deficiency. The turbi::e generator exciter high pressure CO2 system is not contained in the Oyster

Creek Fire Protection Program Technical Requirements (Attachment 101.2-3). This attachment

provides fire watch requirements for inoperable fire detection equipment, suppression systems and

associated instrumentation in safety related areas and zones. Since the exciter is not a safety

related or safe shutdown required component, no specific compensatory measures are contained

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within Attachment 101.2-3. As such, a firewatch was not assigned when this system was

removed from service contrary to the requirements of the plant's Fire Protection Program.

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Attachment I

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1940-98-20458

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Page 5 of 6

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Corrective Stens That Have Been Taken And The Results Achieved.

Procedural changes have been implemented to define and clarify the compensatory measures for

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. balance of plant systems and components within the Oyster Creek protected area. Revision 28

was issued to Procedure 101.2, effective June 15,1998, which provides clarification and

additional directions.

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Corrective Stens That Will Be Taken To Avoid Further Violations

Following the exciter fire, the following additional precautions were instituted to preclude

recurrence:

Revised the PM task for exciter maintenance to add a precaution for portable fire

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extinguishers to be staged prior to removing the system from service and for personnel

exiting the area to ensure the doors to the area are closed.

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Instmeted Operations to minimize the time period that the CO2 Suppression System was

out of service.

Established a requirement to assign an hourly firewatch whenever the exciter suppression

system is out of service for longer than eight hours.

Date When Full Compliance Was Achieved

Full compliance with the requirement to appropriately identify and assign firewatches for non-

safety related/ safe shutdown areas was ach eved on June 15,1998 when the revised procedure

became effective.

Violation 3

License Condition 2.C.3, Fire Protection, of Facility Operating License DPR-16, for the OCNGS,

states, in part, " GPU Nuclear, Inc. shall implement and maintain in effect all provisions of the

approved Fire Protection Program as described in the Updated Final Safety Analysis Report for

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the facility and as approved in the Safety Evaluation Report dated March 3,1978, and

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supplements thereto..."

Section 3.2.4, Communications Equipment, of Supplement No. 3 to the Safety Evaluation Report

dated March 3,1978, requires the licensee to install fixed repeaters to assure that adequate

communications capability would be available for fire fighting and safe shutdown activities.

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Attachment I

1940-98-20458

Page 6 of 6

Contrary to the above, on or before August 1,1997, communications that were required for fire

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fighting and safe shutdown activities were inadequate. Specifically, the licensee failed to

adequately maintain and test the installed radio repeater backup battery power supply.

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This is a Severity Level IV violation (Supplement I).

BEWPER

GPUN concurs with the violation as written.

Reason for Violation

The violation occurred due to inadequate preventive maintenance. The preventive maintenance

on the radio communication system did not adequately maintain and test the installed radio

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repeater backup battery power supply.

Corrective Stens That Have Been Taken and The Results Achieved

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The radio communication repeater's backup batteries were replaced on November 24,1997. The

repeater was then tested on battery power only to verify proper operation. Radio repeaters are

working normally with backup battery power on a float charge.

Corrective Stens That Will Be Taken to Avoid Further Violations

A preventive maintenance task was written to replace repeater batteries every four years. In

addition, a preventive maintenance task was developed to perform a yearly float voltage check on

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the repeater backup battery power supply. All preventive maintenance tasks have been written

and scheduled.

Date When Full Compliance Was Achieved

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Full core; mee for the repeater backup batteg power supply was achieved on November 24,

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1997, when the batteries were replaced and tested.

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