IR 05000320/1981005

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IE Insp Rept 50-320/81-05 on 810406-10.No Noncompliance Noted.Major Areas Inspected:Activities Associated W/ Submerged Demineralizer Sys & Interfacing Sys & Equipment
ML20004E882
Person / Time
Site: Crane Constellation icon.png
Issue date: 05/19/1981
From: Ebneter S, Sassani A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20004E881 List:
References
50-320-81-05, 50-320-81-5, NUDOCS 8106160051
Download: ML20004E882 (7)


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O U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-320/81-05 Docket No. 50-320 Category C

License No. DPR-73 Priority

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Licensee: Metropolitan Edison Company P.O. Box 480 Middletown, Pennsylvania 17057 Facility Name:

Three Mile Island Nuclear Station, Unit 2 inspection at:

Middletown, Pennsylvania Inspection conducted:

April 6-10,1981 Inspectors:

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(7 date signec A.D. Sassani, Jr., Reactor Inspector

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date signed cate signed Approved by:

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S.D. Ebneter, Chief, Plant Systems Secticn, Engineering Inspection Branch I

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Insoection Summary:

Inspection on Aoril 6-10, 1981 (Insoection Recort 50-320/81-05)

Areas Inspected: Special, unannounced inspection by a regional based inspector of work activities and documentation associated with Unit 2 Submerged Demineralizer System (SDS) and interfacing systems and equipment, including:

instrumentation and electrical installations and documentation.

The inspection involved 35 inspection hours on site by one NRC regional

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based inspector.

Resul ts: No item of noncompliance was identified.

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Region I Form 12

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81061600 51

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DETAILS 1.

Persons Contacted General Public Utilities Nuclear Corcoration (GPUNC)

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Bensel, System Support Engineering Supervisor J.

Brummer, Lead Instrument & Control Engineer G.

Derk, Lead QC Supervisor

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Devine, Manager, Recovery Engineering

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Elam, Plant Engineering Manager, Unit 2

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Hovey, Vice President and Director of TMI-2

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King, Operations Manager

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Newman, Licensing Supervisor

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Swartzwelder, Licensing Engineer R.

Warren, Lead Mechanical Engineer Burns & Roe Y.

Setton, Senior Mechanical Engineer E.

Sch'iefer, Site Civil Liason Engineer Babcock & Wilcox W.

Adams, Electrical Engineer R.

Skillman, Manager, Recovery Support Engineering U.S. Nuclear Reculatory Commission

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Earrett, Director, TMI Procram Officer

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Bellamy, TMI Program Office

  • denotes personnel present at exit interview 2.

Review of Documentation The inspector reviewed documentation relative to portions of the Sub-merged Demineralizer System to ascertain whether applicable requirements have been met.

Documentation reviewed fer this determint& tion include:

Unit 2 Recovery QA Plan, Revision 0

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Engineering Change Memorandur Procedure, EMP-008, Revision 8

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Technical Data Report, No. 201, Revision 0

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Technical Evaluation Report, SDS, April, 1980

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Technical Evaluation Report, SDS, Appendix 1, May 23, 1980

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System Design Description, SDS Feed and Monitor Tank No. 2-M74-

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SDS System Description, October 30, 1980 j

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Instrumentation and Control Equipment and Installation Specification,

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No. 2555-69A Electrical Design Criteria Specification, No. 13587-2-E01-100

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Local Control Station Specification, No. 13587-2-E-28

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HV & AC Equipment and Installation Specification, No. 2555-63,

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Revision October 24, 1975 480v Unit Substation One Line Diagram No. E-031

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Supoly Manifold Submerged Ion Exchanger, P&ID, 5270-A-5001,

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Revision 5 Contaninated Feed Water System, P&ID, 5270-A-5002, Revision 4

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Off Gas & '.f quid Separation System, P&ID, 527D-A-5004, Revision 6

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Ion Exchange Flow Sheet, 5270-A-5005, Revision 2

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General Layout Plan, Ion Exchange Equipment, 5270-A-5007, Re-

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vision 1 Filter Manifold Piping Plan and Elevation, 527D-L-5001, Revision 1

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Feed Manifold Piping Plan and Elevation 5270-1-5006, Revision 2

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SDS Feed & Monitor Tank, P&ID, 2-M74-SDS01, Revision 2

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SDS Instrumentation, Plan View, SK171-2, Revision 0

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Feed Pump Manifold Electrical (Instrumentation) Plan and Elevation,

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RW3501-082-06-2, Revision 2 Feed Pump Manifold Connection Diagram, E-818, Revision 0

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General Specification For Instrument Mounting and Piping, 527-J-

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5001, Revision 0 General Specification for Off Gas System 527-Y-2001, Revision 1

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General Specification for Elctrical-General Requirements, 527-P-

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5001, Revision 3

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General Specification for General Instrument Requir ements, 527-J-

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5002, Revision 1 505 Monitor Tank Transfer Pump (PIA) Schematic Diagram, No. 2-

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E76-50501, Revision 1

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SOS Grounding & Raceway Drawing, No. 2-ECR-6201, Revision 2

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Filter Air F em SOS to Existing Vent System, Plan and Section

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Drawing, No. 2232 SOS-MSA Off Gas System Duct, Elevation 347 feet, Fuel Handling

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Building, No. SM-001 Flow Diagram H&V, Fuel Handling Building, No. 2343, Revision 18]

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Fuel Handling Building Duct Layout, Elevation 347 feet, FF No.

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63-110052 Feed Shutdown System Relay Panel RP-1 Elementary Wiring Diagram,

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527-0-P-5015, Revision 1

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Ion Exchanger' Manifold Electrical (Instrumentation) Plan & Elevation,

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RW 3501-082-05-2, Revision 1 SOS Electrical Power Block Otagram, E-804, Revision 2

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SOS Electrical Power Block Diagram, E-805, Revision 6

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Radiation Monitor Panel RMP-1 Arrangement Orawing, E-833, Revision

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Radiation Monitor Panel RMP-1 Connection Diagram, E-840, Revision

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No item of noncompliance was identified.

3.

Engineering Change Memorandum (ECM)

The inspector reviewed documentation and records for portions of the Submerged Demineralizer System relative to Engineering Change Memorandums for instrumentation and electrical components to ascertain whether applicable requirements have been met.

Engineering Change Memorandums reviewed for this determination include:

ECM-648, Revision 0, 505 480v Power Feeder

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ECM-648, Revision 1, 505 MCC 2-329 Feeder Up-Grade

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ECM-648, Revision 4, SOS Power Feeders to Distribution Equipment

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E ECM-648 Revision 9, SDS Feed Pump Manifold Wiring and Power Connections

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ECM-648, Revision 11, SDS Exchanger Manifold, Relay Panel (RP-1)

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ECM-648, Revision 25, SDS Radiation Monitor, Panel RMP-1 Wiring

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ECM-740, Revisions 3 & 4, Monitoring Tank Electrical Installation

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ECM-5759, Revision 0 & 1, SOS MSA Off Gas System ECM-768, Revision 1, SDS Instrument Installations

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ECM-803, Reyision 0, Monitoring Tank Local Starter Modifications

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and Electrical Wiring.

No item of noncompliance was identified.

4.

Observation of Work & Work Activities The inspector examined work and work activities relative to portions of the Submerged Demineralizer System for instrumentation and electrical components to ascertian whether applicable requirements have been met in areas relating to system descriptions, specification, "as-built" drawings, and standard industry practices.

Areas examined for this determination include:

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MSA Off Gas System

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(1) Flow t idicator, FI-52.7-18, utilizes rubber hose between the pitot :Tatic flow element and the flow indicator, whereas specif, ation 527-J-5001 specifies instrument tubing.

Because the pitot static flow element is located upstream of the Off Gas filters, the potential exists for radioactive particulate accumulation in the sensing line.

Should the rubber hose break, particulate could become airborne around operating personnel. The inspector observed that several

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heavy objects were laying on top of the rubber hose, possibly causing material degradation.

The inspector indicated that the onsite NRC staff wil' review and evaluate the acceptability of this installation.

This item will be followed up by an NRC inspector on a subsequent inspection (81-05-01).

(2) The inspector observed that check valve, CN-V-VA-232, shown on drawing No. 527 D-A-5004, revision 6, was deleted from the system. The check valve was originally designed to be in line with butterfly valve, CN-V-VA-231 which is located upstream

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of the Off Gas blower and Particulate, Iodine, and Noble Gas (PING) radiation montioring system and is approximately four feet above the platform. Under normal operating conditions valve CN-V-VA-231 may be open or partially open, drawing air from atmosphere into the system onto the HV&AC stack.

With perturbations in the system (e.g., particulate slugs passing through during filter changes, off gas blower trips,.

etc...) the potential exists for radioactive particulate becoming airborne. The inspector concluded that undue risk to the health and safety of the operating personnel could exist with the present installation. The onsite NRC staff will review and evaluate the acceptabiltiy of this in-sta11ation.

This item will be followed up by an NRC inspector on a subsequent inspection. (81-05-02)

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Instrument Loops and pumo Motor The inspector examined the following instrumentation and electrical installations against system descriptions, specifications, "as-built" drawings and standard industry practice:

Radiation loop RE-527-11 through isolation-valve UV-527-08.

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Monitor tank pump motor (PIA) power and control circuits.

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Instrument loop FE-527-07.

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Areas examined for this determination include:

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B0P power supply interfaces to SDS distribution panels.

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Installation of conduit, cable, cable terminations, termination

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boxes, motor controllers, conduit and cable identifications, j

and grouading.

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Installation of panels, panel internal wiring, and hardware l

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referenced above.

Use of cable pull slips and termination slips.

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(1) The inspector observed miscellaneous instrument tubing was not secured properly and equipment not installed.

Examples are:

Monitoring tank level instrument tubing.

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Off gas valve CN-V-VA-231 instrument tubing.

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Off Gas & Separation tank level instrument tubing

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Ian exchanger isolation valve & instrument tubing to

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valve not installed.

The licensee representatives indicated that construction was not complete, design modifications were being incorporated, and testing was in progress. They indicated the instrument tubing and equipment would be in place and secured prior to system operation.

The inspector has no further questions at this time.

(2) The inspector observed that Radiation Monitoring Panel RMP-1 did not have name plates identifing monitoring instruments The licensee's representative indicated that the instruments have not been tested; at that time name platos would be attached to the panel.

The inspector has no further questions at this time.

5.

Exit Interview

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The inspector met with the licensee representative (doneted in para-graph 1) at the conclusion of the inspection on April 10, 1981.

In addition, NRC Program Office personnel (denoted in paragraph 1) attended the exit interview. The inspector sunmarized the purpose, scope, and findings of the inspection and discussed each.

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