IR 05000277/1987017

Enforcement Conference Repts 50-277/87-17 & 50-278/87-17 on 870813.Major Areas Discussed:Violation of Tech Spec 3.11.A.5 Identified in LER 87-008 & Verified by Insp Repts 50-277/87-17 & 50-278/87-17

ML20238D828
Person / Time
Site:	Peach Bottom
Issue date:	08/27/1987
From:	Johnson T, Linville J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20238D785	List: IR 05000277/1987017 ML20238D783 ML20238D803
References
50-278-87-17, 50-278-87-17-EC, NUDOCS 8709110420
Download: ML20238D828 (20)

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i U.S. NUCLEAR REGULATORY COMMISSION j REGION I 1 Report No. 87-17 50-2"/7 )

Docket Nos. 50-278 ]

EA 87-110 DPR-a4 License No. OPR-56 Category C -

Licensee: Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 39101 Facility Name: Peach Bottom _ Units 2 and 3 Meeting At: NRC Region I King of Prussia, Pennsylvania Meeting Conducted: AuLust 13, 1987

/7 Inspectors: k [ 7/ /

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QoffnsonsSp4r esident InspectoP Appreved by: O/ tyf :7 "~~

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L1n'ville, C)fpf sision of fWatter Projectr, Section 2A Meeting Summary: Enforcement Co6ferenes at NRC Region 1 on August 13, 1967 to discuss the violatica of Technical Specification 3.11.A.S identified in

Licensee Event k port 87-008 and verified by the NRC in combined inspection report 50-277/87-37; 50-278/87-17. The yielation was a result of an incorrect installation of the control room vent $ilation radiation mo61toring system sample {

tubin The licensee presented their perspecMve on the findings, impact of the condition on safety and the reasons for occurrence a?ong with proposed and '

completed corrective action a 87091104po g7090g DR t,00cg 05000g77 PDR

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DETAILS

' 1.0 Meeting Participants 1.1 EniledelphiaElectricCo.(PECO)

W. Alden, Engineer-in-Chargo, Licensing W. Birely, Licensing Engineer G. Rombold, Engineer J. Ga11tgher, Vice President G. Hunger, Engineer-in-Charge, Nuclear Safety Section C. Koppenhauer, Test Engineer A. Fulvio, Technical Engihaer-Peach Bottom ,

D. Smith, Manager, Peach '8oi.toin i W. Alder, Licensing Engineer j G. Morley, Supervising Engineer G. Swenson, Nuclear Operations l G. Leitch, Manager - Nclear Generation JL Madara, Assistant, CMef Mechanical .Enginscr l U.S. Nuclear R6gulatory Commission (URC) i

W. Kane, Director, Diyhi9n of Reaci.or Projects (DRP)

J. Linville, Chief, Reactor Proje:ts-Section 2A, DRP R. Gallo, Chief, Reati.or Projects-Branch 2, DRP T. Johnson, Ssnior Resident Inspector, Peach Bottom, DRP D. Holedy, Enforcement Officer J. Williams, Project Er71neer, ORF R.'Nimitz, Senior Radiation Specialist, DRSS R. Martin, Licensing Project Manager, NRR

L. Schall, Rector Enginee9, DRP 1.3 ,P_ublic Service Electric and Gas N. Philips 2.0 Purpose I This EnfoNewnt CenfcNnce was h&ld at the reouest of the Region J management to discuss the violations of the Tef.hnical Specification requirements identified by the licensee in Licensee Event Report'87-06 This violation was subsequently verified by the NRC and d:.curhented in combined inspection report no. 50-277/87-17 and 50-278/87-1 .0 Presentation and Diricussion ,

Following the initial introductions and the opening reinarks the licensee was asked to present their perspective and le reasons for the non-compliance. The licensee distributed documents which were used to explain how the problem was identiffid, the immedir.te corrective actions taken, ,

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the analysis of potential additional operator radiation expcsu~re, ahd

'edditional: co=rrective' actions being taken. These documents appear as l Attachment 1 to,this repor '

With regard to the!cause of the violation, the' licensee. stated that the= ',

cause was. unknown:and theLeondition.may have existed since the time of l A 'initid construction but system walkdowns and pre-operational testing had L failed to' identify the incorrect sample tubing configuration. ; The:

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, condition was identified-during 'the. investigation' of a suspected low flow in the "B" radiation. monito The licensee preserted the immediate corrective'acttans which were taken and statcd that' followup actions will resitlt in 472 instrument"line i l installations being checked to verify correct installatio To date'40 reviews have been. completed with a minimum of 68. additional ~ installations-targeted for revie The licensee-also stated that LER 87-008 would;be revised to cpdate the

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i ' analysis performed to estimate the potential.. increased radiation expocure to the aperators due to:the incertect' tubing installation. The revision to the LER will also include the results'of the licensee investigation:

being performed to determine if the' problem is limited to the Control Room

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s . Ventilation Radiation Monitoring System, (i.e., the results of the review of.the 472 instrument line installations).

The PEC0 presentation _ also included a discussion of the Nuclear Review Board's decision to have PEC0 engineering determine if there is a possibility of similar conditions existing at the Limerick Generating Statio Concludino Statements The NRC thanked the licensee for their presentation and stated that the individual responsible for initiating the investigation and following the problem through t0 a positive identification Of root causs should be commended for his actions. Additionally, it was stated that the licensee response to NRC questions displayed an appreciation for the safety significance of the issue and that the broad corrective action program '

supported this appreciatio The information provided by the licensee will be considered in the NRC determination of enforcement actions relat6d io this issu (

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s ATTACHMENT 1

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Problem Identification and immediate Corrective Action System Description e Normal Mode e High Radiation Mode Problem identification .

e Suspected Sample Tube Plugging

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Immediate Corrective Action e Retubing Solenoids e Alignment Checkout a Similar Systems Walkdown investigation l

e Pre-op & Construction Documents e MRF Records e Surveillance Testing

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- SYSTEMS-INCLUDED IN' PARAMETER SEN$p7 REUIEW r..

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Reactor Protection System

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,. Neutron Monitoring! System

- Reacto'r? Core-Isolation Cooling ~ System Thigh Pressure Coolant; Injection' System

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_ Core. Spray-System

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iLow Pressure: Coolant. Injection < System

- - RHR. Containment' Cooling

-. . Primary Containment and;ReactoraVessel Isolation System

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' Standby Gas Treatment System

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Standby AC Power Supply

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DC Power Suppl Ventilation Radiation Monitoring System-

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-Main Steam Line Flow Restrictors

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Control Rod' Velocity Limiter-p -- -

Control Rod Drive. Housing Supports ~

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Standby Liquid Control: System

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Control Rod-Drive Syste Nuclear. System Pressure Relief'

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Primary Containment

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Secondary ~ Containment

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MSIV?s

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High' Pressure Service Water

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Emergency Service Water ~

- Main Steam Line Radiation Monitoring Containment _ Atmosphere Dilution System

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. Emergency Heat Sink

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Shutdown: Capability Outside the Control Room

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Fuel and Diesel' Oil System

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Temperature Control Diesel Engine Room, Emergency Switchgear & Battery Roomp and Intake Structure

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Refueling Interlocks

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1 SYSTEMS OR EQUIPMENT' INCLUDED'IN' REVIEW  ;

'THAT IS OUTSIDE THE STRICT DEFINITION OF SCOPE i s e

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-4 1.. Standby Gas Treatment . ,

'DPC-20479-l&2. maintain the Reactor Building and Refuel Floor negative.if SBGTS is initiated by; Reactor Building or. Refuel Floor-exhaust hi l radiatio Because they have sensing lines /that-  !

must respond'correctlyito. maintain a negative-

-pressure, they are' include >

, Ventilat' ion' Radiation. Monitoring System:

The VentLStack-and Main' Stack Radiation monitor I are used forLdetermination of Emergency Plan y'

Classification.- Because they have sample lines,

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.whether or not to manually initiate CAD, they are '

include . Refueling Interlocks This system is important because it. ensures protection-of the fuel claddin _ _ _ _ - _ _ _ -

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. Main Steam Line Flow Restrictors 3 [ 3.,

o No Instrumentation Control Rod Velocity Limiter F o No Instrumentation Control Rod Drive Housing Supports o No Instrumentation Standby Liquid Control System

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o Manual Initiation Only Control Rod Drive System

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o . Initiating Instruments are all in RPS, which is trented separately LNaclear System Pressure Relief o Automatic Initiation is from ADS which is treated separately Primary Containdient o Isolation of Primary Containment is covered in PCIS

! Secondary Containment o Isolation of Secondary Containment is covered in PCIS 1 MSIV's o No Instrumentation Unique to MSIV's o Isolation-of MSIV's is covered in PCIS 1 High Pressure, Service Water

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o Manual Initiation Only l 12. ' Shutdown Capability Outside the Control Room o Emergency Shutdown Pan 11 is put in service manualTy l o No Instrumentation unique to Emergency Shutdown l Panel 1 Fuel and Diesel Oil System o Only Instrumentation is Diesel Generatur Day Tank Level Switches, which are not needed to initiate the system 1 Temperature Control - Diesel Engine Foom, Emergency Switchgear and Battery Room, and Intake Structure

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o This equipment supports the operation of the system, but does not initiate the system

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PEACH BOTTOM UNIT'

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Has thi'y instrument initiated the system by correctly sensing the ' '

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