ML20236R751

Notice of Violations from Insp on 980505-0622.Violations Noted:On 980515,inoperable B Channel Had Not Been Placed in Tripped Condition for Approx 28 H

ML20236R751
Person / Time
Site:	Peach Bottom
Issue date:	07/16/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20236R728	List: ML20236R726 ML20236R751 ML20236R766
References
50-277-98-06, 50-277-98-6, 50-278-98-06, 50-278-98-6, NUDOCS 9807220255
Download: ML20236R751 (3)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION PECO Energy Company Docket Nos. 50-277,50-278 Peach Bottom Atomic Power Station Units 2 & 3 License Nos. DPR-44, DPR-56 Delta, PA During an NRC inspection conducted from May 5,1998, through June 22,1998, four violations of NRC requirements were identified, in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600,these violations are listed below:

A. Technical specification 3.3.7.1 requires, in part, that when a channel of the Main Control Room Emergency Ventilation (MCREV) system instrumentation is inoperable that the channel be placed in trip within six hours.

Contrary to the above, on May 15,1998, the inoperable 'B' channel had not been placed in the tripped condition for approximately 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />. The 'B' channel of MCREV instrumentation was inoperable due to an inoperable radiation monitor (RIS-07608).

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

B. 10 CFR 50 Appendix B, Criterion XVI, " Corrective Action," requires, in part, that

-measures be established to assure that conditions adverse to quality, such as failures, malfunctions, and deficiencies are promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure that the

.cause of the condition is determined and corrective action taken to preclude repetition.

Contrary to the above, site engineering personnel failed to take prompt and effective

corrective actions following the identification of errors affecting several procedures for the residual heat removal system. Specifically, Quality Assurance personnel

' identified and reported the errors in September 1997, but the Unit-2 procedures were not revised until around March 24,1998. The failure to revise the Unit-2 procedures resulted in the residual heat removal system valve, HV-2-10-65, being left incorrectly positioned when plant operators used an unrevised procedure on

' March 4,1998. '

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

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? C. Technical Specification 3.4.1 requires, in part, that with one recirculation loop in operation, the Reactor Protection System (RPS) Instrumentation, " Average Power Range Monitors Flow Biased High Scram," allowable value shall be f wet for single

, , recirculation loop operation. .The reset of the " Average. Power Range Monitors Flow Biased High Scram" allowable value for single loop operation may be delayed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after transition from two recirculation loop operation to single loop operation.

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' Enclosure 1 2 Contrary to the above, the inspectors identified that on June 8,1998, plant personnel did not reset the Unit 3 RPS Instrumentation, " Average Power Range

, , Monitors Flow Biased High Scram" within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after transition from two recirculation loop to single recirculation loop operation.

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

D. Technical Specification Surveillance Requirement 3.4.9.4 requires, in part, that the difference between the temperature of the reactor coolant in the recirculation loop to be started and the coolant in the reactor pressure vessel be verified s 50*F. This verification is to occur once within 15 minutes prior to each startup of a recirculation pump and is required when in operating modes 1,2,3, and 4.

Contrary to the above, the licensee identified that from June 25,1996 until March 23,1998, Surveillance Requirement 3.4.9.4 had not been performed when the first recirculation pump of a unit was started. The re niired surveillance e < verification was not performed during six recirculation pump starts which occurred on both units during this time period. In addition, during one of these six

. recirculation pump starts on October 29,.1997 on Unit 3, the temperature differential was 84*F within_15 minutes of the recirculation pump start.

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

j, , x 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, E l ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional -

, Administrator, Region I, and a copy to the NRC Resident inspector at the facility that is the

-subject of this Notice, within 30 days of the date 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 Hm W r ; contested, the basis for disputing theiviolation or severity level, (2) the corrective steps l that have been taken and the results achieved, (3) the corrective steps that will be taken to

. ' avoid further 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. If an adequate reply is not l received within the time specified in this Notice, an order or a Demand for Information may l

be issued as to why the license should not be modified, suspended, or revoked, or why such other action ~as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time, if you contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.

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O Enclosure 1 3 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 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 mWJi1 specifically identify the portions of your response that you seek to have withheld and provide in detail the basis for yotir 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

- information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.

Dated at King of Prussia, Pennsylvania this 16th day of July,1998.

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