IR 05000454/1986014

Insp Rept 50-454/86-14 on 860401-30.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings & Lers.Failure to Perform Tech Spec Surveillance within Required Time Interval Noted

ML20197J922
Person / Time
Site:	Byron
Issue date:	05/15/1986
From:	Forney W, Lerch R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20197J891	List: IR 05000454/1986014 ML20197J888
References
50-454-86-14, NUDOCS 8605200205
Download: ML20197J922 (9)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No.- 50-454/86014(DRP)

Docket No. 50-454 License No. NPF-37 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Byron Station, Unit 1 Inspection At: Byron Station, Byron, IL Inspection Conducted: April 1-30, 1986 Inspectors: J. M. Hinds, J P. G. Brochman M f//I

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Approved By:

hW. k orney, C'f f// SIP 1, Reactor Projects ection IA Da'te /

Inspection Summary Inspection on April 1-30, 1986 (Report No. 50-454/86014(DRP))

Areas Inspected: Routine, unannounced safety inspection by the resident inspectors and a regional inspector of licensee action on previous inspection findings; LERs; IEBs; GLs; operations summary; surveillance; maintenance; operational safety and ESF walkdown; management meetings and other activitie Results: Of the eight areas inspected, no violations or deviations were identified in seven areas; one licensee identified violation was identified

.in the remaining area: (failure to perform a Technical Specification surveillance within the required time interval - Paragraph 3.b). The licensee's review of computer records indicated that the parameter remained within its Technical Specification limits at all times; therefore, this event did not affect the public health or safety.

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DETAILS 1. Persons Contacted Commonwealth Edison Company

1. K. L. Graesser, Division Vice President

1. G. P. Wagner, Operations Manager

1. K. A. Ainger, Nuclear Licensing Administrator

• 1. R. Querio, Station Manager

• 1. R. Pleniewicz, Production Superintendent

• 1. R. Ward, Services Superintendent L. Sues, Assistant Superintendent, Operating G. Schwartz, Assistant Superintendent, Maintenance

• 1. T. Joyce, Assistant Superintendent, Technical Services W. Blythe, Operating Engineer, Unit 0 T. Tulon, Operating Engineer, Unit 1 D. Brindle, Operating Engineer, Unit 2 D. St. Clair, Operating Engineer, Rad-Waste A. Chernick, Compliance Supervisor

• 1. W. Burkamper, Quality Assurance Supervisor, (Operations)

• 1. M. Snow, Assistant Compliance Supervisor

• 1. E. Zittle, Compliance Staff

1. Gary Toleski, Nuclear Security Administrator

• 1. Bud Erickson, Master Mechanic

1. Robert Lucas, Security Administrator

1. Gary Buettner, Assistant Security Administrator

1. J. M. Brennan, Nuclear Security Director

1. K. T. Weaver, Station Health Physicist

• 1. R. A. Flahive, Rad-Chem Supervisor

• 1. K. E. Yates, Nuclear Safety Staff

• F. Hornbeak, Technical Staff Supervisor

• A. Britton, Quality Assurance Inspector

• Joe Langan, Compliance Staff The inspector also contacted and interviewed other licensee and contractor personnel during the course of this inspectio # Denotes those present during the management meeting on April 22, 198 * Denotes those present during the exit interview on April 30, 198 . Action on Previous Inspection Findings (92701 and 92702) (Closed) Unresolved Item (454/85042-05(DRP)): Questions on previous similar events for LER 454/85069. The inspector discussed LERs 454/85017 and 454/85040 with the licensee's staff and agreed with the licensee position that LERs 454/85017 and 454/85070 were not specifically similar to LER 454/85069 to require that they be reported as " previous similar events" under 10 CFR 50.73. Therefore, this item is considered close l

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b. (Closed) Open Item (454/85042-06(DRP)): Use of voided documents to provide an acceptable record of activities affecting quality. The inspector reviewed a memorandum issued by operations department managers to the shift engineers which affirms that voided documents are not acceptable records of activities affecting quality, and that surveillances should not be voided at any time. Based on those actions the inspector has no further concerns regarding this matter and this item is considered close c. (Closed) Open Item (454/85043-02(DRP)): Power distribution book does not list all components powered from a common electrical source. The licensee's staff reviewed and updated the power distribution books to indicate those power supplies that feed multiple components. The inspector reviewed the changes to the power distribution books and discussed their use with the licensed operators who utilize these books when determining the electrical isolation requirements to take a component out-of-service. Based on these reviews and discussions the inspector has no further concerns regarding this matter and this item is considered close d. (Closed) Violation (454/86002-03(DRP)): Failure to take timely and effective corrective actions for a significant condition which was adverse to quality and safety and resulted in a reactor trip. The inspector reviewed the licensee's response and corrective action to prevent recurrence. The inspector reviewed the licensee's corrective actions to include a cover sheet on all instrument calibrations or surveillances which have a control switch. The inspector observed the use of templates on the Steam Generator Feedwater Regulating Valve control circuit. The inspector has observed increased management attention in the preparation of LERs and in the control

, of completion dates for corrective actions. Based on the corrective actions taken the inspector has no further concerns regarding this matter and this item is considered close e. (Closed) Violation (454/86002-04(DRP)): Failure to perform an isolation time test on containment isolation valve 1FWO39D following maintenance. The inspector reviewed the licensee's response and verified that the Byron Administrative Procedure BAP330-1, " Station Equipment Out-of-Service (00S)" for removing and returning equipment 00S had been revised to require that work being done on safety-related equipment must be done on a unique 00S rather than a blanket 00S. Based on the corrective actions taken the inspector has no further concerns regarding this matter and this item is considered close f. (Closed) Violation (454/86005-02(DRP)): Failure to install a protective covering on a class I-E circuit breaker. The inspector reviewed the licensee's response and verified that a standing order was issued by the operations department manager to require that protective covers be installed on 4.16KV and 6.9KV Class IE circuit breakers when they are removed from their switchgear cubicle. The inspector interviewed operations and electrical maintenance

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department personnel to verify their understanding of the standing order. Based on the corrective actions taken the inspector has no further c]ncerns regarding this matter and this item is considered close . Licensee Event Report (LER) Followup (90712 and 92700) (Closed) LERs (454/86002-LL; 454/86010-LL; 454/86011-LL): An in-office review was conducted for the following LERs to determine that the reportability requirements were fulfilled, immediate corrective action was accomplished and corrective action to prevent I recurrence had been accomplished in accordance with Technical Specification LER N Title 454/86002-01 Control Room Ventilation Actuation Due to Radiation Monitor OPR31J Iodine Channel Spik /86010 Control Room Ventilation Actuation Due to Shutdown of Radiation Monitor OPR34J Sample Pum /86011 Control Room Ventilation Actuation Due to High Vacuum Alarm on OPR34J Radiation Monito No violations or deviations were identifie (Closed) LERs (454/86008-LL;454/86012-LL): Through direct observation, discussions with licensee personnel, and review of records the following LERs were reviewed to determine that the reportability requirements were fulfilled, immediate corrective action was accomplished and corrective action to prevent recurrence had been accomplished in accordance with Technical Specification LER N Title 454/86008 Turbine Trip / Reactor Trip Due to Main Transformer Phase Imbalance Caused by Transmission Tower Icin /86012 Rod Position Indication Surveillance Not Performed Within Required Periodicity Due to Personnel Erro The event described ir. LER 454/86008 was previously reviewed in Inspection Report 454/86005(DRP).

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LER 454/86012 described an event from March 5-27, 1986, while in Mode Technical Specifications 4.1.3.1.1 and 4.1.3.2 both require that the Bank Demand Position Indication System for the control rods be compared against the Digital Rod Position Indication System at least once per four hours with the rod position deviation monitor and alarm inoperable. Due to communication error between Technical Staff and Operating Personnel the Technical Specifications surveillance comparing the control rod position indicators was only performed every eight hours instead of every four hours from A rch 5-27, 1986. Corrective action consisted of reinstatement of the " Band Demand Versus Digital Rod Position Indication four Hour Rod Position Surveillance" on March 27, 1986, and an investigation by Technical Staff engineers to verify that the control and shutdown banks were within the required positions at four hour intervals from March 5 to 27, 1986. A critique of this event was held with the Technical Staff with emphasis on clearly communicating to the Operating Department any identified changes related to Technical Specifications. Additionally, the Operating Engineers were directed to provide more specificity in written instructions related to matters of this nature dealing with Technical Specification Surveillances in Daily Orders. The station is also considering methodology to track the performance of specific non-routine Technical Specification Surveillances and will provide this informa-tion in a supplemental repor The failure to compare the control rod position indicators every four hours is a Violation of Technical Specifications 4.1.3.1.1 and 4.1.3.2 and is considered a violation identified by the licensee; consequently, no notice of violation will be issued (454/86014-01(DRP), and this matter is considered close No other violations or deviations were identifie . IE Bulletin (IEB) Followup (92703)

(0 pen) IEB (454/85001-BB): " Steam Binding of Auxiliary Feedwater Pumps."

The inspector verified that the written response required by the IEB was submitted within the time period stated in the IEB. During the review of the IEB response the inspector identified a concer This concern was discussed with the licensee's staff and related to Byron Abnormal Operating Procedure 1 BOA SEC-12, " Auxiliary Feedwater Check Valve Leakage, Unit 1."

The BOA requires that the Auxiliary Feedwater (AF) pumps be started to flush the IF piping following steam binding in accordance with normal AF operating procadures. However, only the procedure for operation of the motor driven AF pump was referenced, while the procedure for operation of the diesel driven AF pump was omitted. The licensee has committed to revising BOA SEC-12 to reference both AF pump operating procedure The inspector interviewed four licensed reactor operators and two licensed senior reactor operators to verify their understanding of this BOA, for which training had been accomplished. Five of the individuals did not know that BOA SEC-12 existed, one knew of a procedure but not its specific locatio However, they were aware of the concept of steam binding of AF pumps and that non-iicensed operators periodically checked AF system for evidence of back leakage through AF check valves. Subsequent

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to these interviews operating department management issued instructions to all licensed operators to review the 80A and related procedure. This IEB will remain open pending revision of B0A SEC-12 and the completion of the operators review of the 80 No violations or deviations were identifie . Generic Letter (GL) Followup (92703)

The inspector reviewed the Byron Station Program for the receipt, review and corrective actions regarding GLs. Copies of all GLs are sent to licensee corporate offices and to the Byron Statio The Nuclear Licensing Administrators (NLA) office in the corporate headquarters is responsible for assigning responsibilities for GL revie The station handling of GLs is fashioned after Byron Administrative Procedure (BAP) 1260-1,

" Operating Experience Feedback" and although not specifically listed in BAP 1260-1 with other NRC correspondence which includes bulletins, circulars and information notices, the licensee has committed to including GLs in the next revision of BAP 1260-1 and is tracking this commitment with Action Item Request (AIR) No. 6-86-109. A review of the station file indicated that the station copy was on file for GLs 85005; 85006; 85007; 85013; 85014; and 85022. The routing pages indicated that the GLs were routed through the Assistant Superintendent for review and distribution of the GLs. Each GL file was reviewed by the inspector for assignment from NLA and site response when appropriate. The inspector concluded that the administration of the Byron Station GL review program is being adequately implemented. This completes the action required by the Norelius Memorandum of February 28, 1986 " Handling of Generic Letters" and the Schweibinz Memorandum of March 20, 1986, " Review of Generic Letters."

No violations or deviations were observe . Summary of Operation The unit operated at power levels up to 98% for the entire mont . Monthly Surveillance Observation (61726)

The inspector observed Technical Specifications required surveillances Auxiliary Feedwater Pump IB monthly operability test and Reactor Trip Breakers, 1B Shunt and Undervoltage Trip Independence Test and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, th.it test results conformed with Technical Specifications and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.

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The inspector also witnessed portions of the following test activities:

SPP 86-63 Demonstration of Auxiliary Feed Operating Characteristics SPP 86-65 Demonstration of Diesel Auxiliary Feed Operating Characteristic SPP 86-67 Verification of Operability of the 1A Auxiliary Feed Pump and A-SX discharge valves No violations or deviations were identifie . Monthly Maintenance Observation (62703)

Station maintenance activities of safety related systems and components listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, r julatory guides and industry codes or standards and in conformance wit: Technical Specification The following items were considered during this review: the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and fire prevention controls were implemented. Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system performanc The following maintenance activities were observed / reviewed:

Repair of Rad Waste Evaporator 0WX16DB l

Replacement of RCP Seal Injection Filter ICV 01F Following completion of maintenance on the 0WX16DB and ICV 01FB, the inspectors verified that these systems had been returned to service properly.

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No violations or deviations were identifie . Operational Safety Verification and Engineered Safety Features System Walkdown (71707 and 71710)

The inspectors observed control room operation, reviewed applicable logs and conducted discussions with control room operators during the month of April 1986. During these discussions and observations, the inspectors ascertained that the operators were alert, cognizant of plant conditions,

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attentive to changes in those conditiohs, and took prompt action when appropriate. The inspectors verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of the auxiliary, turbine ind rad-waste buildings were conducted 'to observe plant equipment conditions, including potential fire hazards, fluid leaks and excessive vibration and to verify that maintenance requests had been initiated for equipment in need of maintenanc The inspectors by observation and direct interviews verified that the physical security plan was being implemented in accordance with the station security pla The inspectors observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection control During the month of April 1986. the inspectors walked down the accessible portions of the Residual Heat Removal and Containment Spray systems to verify operability. The inspectors also witnessed portions of the radioactive waste system controls associated with rad-waste shipments and barrelin These reviews and observations were conducted to verify that facility operations were in accordance with the requirements established under Technical Specifications,10 CFR and administrative procedure No violations or deviations were identifie . Management Meetings (30702)

On April 22, 1986, Messrs. R. F. Warnick, Chief, Reactor Projects Branch 1; W. D. Shafer, Chief , Radiological Protection and Emergency Preparedness Branch; W. L. Forney, Chief, Reactor Projects Section 1A; J. R. Creed, Chief, Safeguards Section; J. L. Belanger, Safeguards Inspector, W. B. Grant, Radiological Protection Inspector; and the NRC resident inspector staff met with licensee management and supervisory personnel denoted in Paragraph I of this report. This meeting was held to assess overall facility status, plant operations and to discuss agenda items which had developed since issuance of the operating licens . Violations Identified by the Licensee The NRC uses the Notice of Violation as a standard method for formalizing the existence of a violation of a legally binding requirement. However, because the NRC wants to enccurage and support a licensee's initiatives for self-identification and correction of problems, the NRC will not generally issue a Notice of Violation for a violation that meets the tests of 10 CFR 2, Appendix C, Section V.A. These tests are: (1) the violation was identified by the licensee; (2) the violation would be categorized as Severity Level IV or V; (3) the violation was reported to the NRC, as required; (4) the violation will be corrected, including measures to prevent recurrence, within a reasonable time period; and

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i (5) it was not a violation that could reasonably be expected to have been prevented by the licensee's corrective action for a previous violation.

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A violation identified by the licensee during the inspection for which no Notice of Violation will be issued is discussed in Paragraph . Exit Interview (30703)

The inspectors met with licensee representatives denoted in Paragraph 1

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at the conclusion of the inspection on April 30, 1986. The inspectors

summarized the purpose and scope of the inspection and the finding The inspectors also discussed the likely informational content of the r

inspection report with regard to documents or processes reviewed by the

inspectors during the inspection. The licensee did not identify any such documents / processes as proprietary.

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