ML20217P728

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Notice of Violation from Insp on 980118-0314.Violation Noted:Nrc Identified That Control Room Supervisor Did Not Visually or Verbally Communicate Alarm Ack of an Expected Alarm That Come in on Unit 3
ML20217P728
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 05/01/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20217P725 List:
References
50-277-98-01, 50-277-98-1, 50-278-98-01, 50-278-98-1, NUDOCS 9805070042
Download: ML20217P728 (3)


Text

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o-ENCLOSURE 1 NOTICE OF VIOLATION PECO Energy Company Docket Nos. 50-277;278 Peach Bottom Atomic Pow (' station Units 2 and 3 - License Nos. DPR-44, Delta, PA DPR-56 During an NRC inspection conducted between January 18,1998, through March 14, 1998, five violations of NRC requirements were identified. In accordance with the

" General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600,

~ the violations are listed below:

1. Technical Specification 5.4.1 requires, in part, that written procedures be

. established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Appendix A, November 1972. The procedures listed in Regulatory Guide 1.33, Appendix A, include those covering procedure adherence.

Operations Manual, OM-P-7.1, Revision 0, " Alarms and Indications," Step .4.1.5, required the control room supervisor to verify an expected alarm acknowledgment visually by looking toward the alarming unit or verbally communicate alarm I acknowledgment with the reactor operator / plant reactor operator.

Contrary to the above, on January 28,1998, the NRC identified that a control room supervisor did not visually verify or verbally communicate alarm acknowledgment of an expected alarm that came in on Unit 3 because he was outside his designated work station without temporary relief.

' This is a Severity Level IV violation (Supplement 1).

2. Technical Specification Surveillance Requirement 3.4.1.1 requires, in part, that recirculation loop Jet pump flow mismatch be verified every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the reactor is in Modes 1 or 2 and both recirculation loops are in operation.

Contrary to the above, on January 3,1998, the licensee identified that recirculation loop jet pump flow mismatch had not been verified for over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with the Unit 2 reactor in Mode 2 and both recirculation loops in operation.

This is a Severity Level IV violation (Supplement 1).

3. Technical Specification Surveillance Requirement 3.4.1.2 requires, in part, that core flow as a function of THERMAL POWER be verified to be in the " Unrestricted" Region of Figure 3.4.1-1 every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the reactor is in Modes 1 or 2.

Contrary to the above, on January 3,1998, the licensee identified that core flow as j a function of THERMAL POWER had not been verified to be in the " Unrestricted" l Region of Figure 3.4.1-1 for over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with the Unit 2 reactor in Mode 2.

.This is a Severity Level IV violation (Supplement 1).

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9 Enclosure 1 2

4. Technical Specification 5.4.1 requires, in part, that written procedures be '

established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Appendix A, November 1972. The procedures listed in Regulatory Guide 1.33, Appendix A, include those covering procedure adherence, authorities and responsibilities for safe operation, equipment control, shift and relief turnover, and turbine startup.

Contrary to the above, several examples of failures to implement and maintain written procedures were identified when the Unit 2 main turbine tripped on January 1,1998. ' Specifically, IC-11-00497, Revision 4, " Alignment Procedure for the Electro-hydraulic Control (EHC) System of the General Electric Turbine Generator" and GP-2, Revision 85, "Nrmal Plant Start-up" failed to maintain instructions to restore the EHC system to the alignment required for start-up. Also, operations personnel failed to adequately implement the following procedures: 1.)SO 1 B.1.A-2, Revision 22, " Main Turbine Startup and Normal. Operation" which contained instructions to close the turbine control valves by verifying that the EHC speed -

select was at "ALL VALVES CLOSED." This procedure was required to be used by GP-2 for resetting the main turbine. 2.)OM-C-6.1, Revision 1, " Shift Turnover" and OM-P-3.3, Revision 5, " Licensed Operators" which required monitoring and recognition of equipment status and panel walkdowns with sufficient detail to understand plant conditions. Operations personnel failed to recognize the main turbine status, position of the turbine control valves, or the selection of the speed set for the EHC system prior to the main turbine trip.

This is a Severity Level IV violation (Supplement 1).

5. - Facility Operating License DPR-56, Section 2.C.(1) authorizes PECO Energy Company to operate Peach Bottom Atomic Power Station (PBAPS), Unit 3, at steady state reactor core power levels not to exceed 3458 megawatts thermal (100 percent of rated thermal power).

Contrary to the above, PECO Energy Company operated PBAPS Unit 3 at a thermal power in excess of 3458 megawatts between October 22,1995 and January 21, 1997. PECO Energy Company operated the reactor at a steady state power level up to 100.6% of rated power. This occurred due to errors in the calibration of feedwater temperature instruments in June 1995.

This is a Severity Level IV violation (Supplement 1).

_ Pursuant to the provisions of 10 CFR 2.201, PECO Energy Company is hereby required to -

submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region 1, and a copy to the NRC Resident inspector at the facility that is the subject of this Notice, within 30 days of receipt of the letter transmitting this Notice of

Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of Viola-

. tion". and should include for each violation: (1) the reason for the violation, or, if l contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further

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Enclosure 1 3  !

violations, and (4) the date when full compliance will be achieved. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response. Where good cause is shown, consideration will be given to extending the response time.

Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide l a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the basis for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a ,

request for withholding confidential commercial or financial information). If safeguards l information is necessary to provide an acceptable respense, please provide the level of l protection described in 10 CFR 73.21. j i

Dated at King of Prussia, Pennsylvania this 1st day of May,1998.

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