ML19323G124
| ML19323G124 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/02/1980 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-79-14, NUDOCS 8005300423 | |
| Download: ML19323G124 (38) | |
Text
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Metropolitan Edison Company Post Office Box 480 a
g 73 Middletown, Pennsytvania 17057 717 944-4041 Writer's Direct Dial Number May 2, 1980 TLL 192 Office of Inspection and Enforcement Attn:
B. H. Grier, Director U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pa.
19406
Dear Sir:
Three Mile Island Nuclear Station, Unit.t (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 IE Bulletin 79-14 Series Enclosed please find an interim report based on the inspection program which was performed to investigate the adequacy of the Seismic Class I piping systems as required by the subject bulletin. This report provides a list of discrepancies and a tentative reanalysis schedule.
It is still anticipated that the final report, which will describe the reanalysis and resolution of discrepancies to design requirements, will be issued by September 30, 1980.
Sincerely, s
J. G. Herbein Vice President TMI-I l
JGH:LWH: hah Enclosure cc:
J. T. Collins l
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b Metropohtan Ed: son Company is a Member of the General Public Ut.ht es System
o USNRC IE BULLETIN NO. 79-14 LNTERIM REPORT Metropolitan Edison Co.
Three Mile Island Nuclear Station, Unit 1
TABLE OF CONTENTS Section Title Page 1
General Introduction 1-1 2
Site Inspection 2-1 l
3 Inspection Procedure 3-1 4
Summary Report 4-1 ATTACHMENTS:
I Design Document Reference List II Procedure 79-14 III Seismic Category I Significant Discrepancy & Reanalysis Schedule
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SECTION 1 GENERAL INFORMATION This report is the response of Metropolitan Edison Company to USNRC IE Bulletin No. 79-14, dated July 2, 1979, including Revision 1 dated July 18, 1979, Supplement I dated August 15, 1979 and Supplement 2 dated September 7, 1979 for Three Mile Island Nuclear Station, Unit 1, Docket No. 50-289.
An inspection program was performed to investigate the adequacy of the Seismic Class I piping systems. The inspection verified if types and location of hangers and supports, attachments, valve and valve operator location and weights, and pipe geometry are as designed and as inputted into the seismic analysis.
In conjunction with the inspection program, engineering evaluations are being performed on systems with deviations to determine whether the as-built conditions meet design requirements. This interim report deals with the findings of the inspection program and provides a list of nonconformances and a schedule for reanalysis. A final report that will describe results of the reanalysis and resolution of nonconformances to the design requirements will be issued by September 30, 1980.
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SECTION 2 SITE INSPECTION This section describes the site inspection program including methods of inspection, reporting of deficier.cies, and evaluations.
A.
Methods of Inspection The inspection procedure covered in this report in Section 3 establishes inspection requirements for 2-1/2 inch and larger piping and pipe support assemblies.
It was used by the inspectors as a general guide, however the inspectors were not limited by the procedure and were encouraged to report as deficiencies anything they believed could effect system analysis.
The two principle documents used by the inspectors for comparison were the following:
1.
Piping Analysis Isometric Drawings These drawings were prepared as input documents for the original dynamic analysis of seismic class systems and represent the pipe geometry, support locations and function, valve location and orientation, pipe size and other elements effecting analysis.
2.
Pipe Support Drauings These are support detail drawings showing the configuration required i
to satisfy analysis function.
I Additional reference drawings used are outlined in Attachment I and include physical piping arrangement drawings, flow diagrams and vendor drawings.
The revision of all drawings being used is the revision current on the date l
of inspection. Reconciliation of inspected document revision and the t
i revision used in the original analysis will be addressed in the final l
l report.
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The inspectors worked in teams and divide the piping systems into work packages including an analysis isometric and related support assembly drawings. Discrepancies determined by comparison of the physical installation with the inspection package information were red lined on applicabla drawings and noted on data sheets. Thesa data sheets were compiled for each isometric and support detail. Copies of the data sheets are included with Attachment II.
In those cases where thermal insulation prevents the inspection of critical support elements (such as pipe attachments), the insulation is removed for inspection of 10% of the obstructed pipe supports for both normally accessible and inaccessible systems.
B.
Reporting Deficiencies A unique number was assigned to each inspection report by the inspectors.
This number was used as a tracking method to insure resolution of each deficiency. For supports, the support number was used and for piping systems, the system analysis number (ME number) was used. These reports were then submitted for evaluation and further analysis, as required.
C.
Evaluations Each inspection package is being reviewed for deficiencies. Those which I
would not cause a significant change in the analysis are signed off on the 1
inspection data sheet. Those requiring minor repair work but not affecting the analysis (loose nuts and bolts, missing washers, etc.), are reported for repair. Deficiencies potentially causing significant effect to system analysis such as missing supports, are evaluated.
In the evaluation, valve weights and centers of gravity as used in the original analysis are also checked against the valve manufacturers drawings, which represent the installed valve *.
Pipe material, diameter and wall thickness as used in
- Where this information is unavailable from manufacturing drawings, proven conservative estimates shall be used.
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the original analysis are also checked against the fabricators spool sheets.
If the results of the evaluation are favcrable, i.e., pipe and support stresses within code allowable, the system is acceptable as-built and drawings revised to reflect the as-built condition.
If the evaluation indicates that further analysis is required, the as-built condition is computer analyzed. The decision to rerun an analysis is basad on the magnitude of change and the margin between the original stress level and the code allowable stress level. Section 4 provides a summary of the results of the evaluations performed to date.
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SECTION 3 II.SPECTION PROCED,U_RE The following is a summary of the procedure developed for use by inspectors at the plant site in checking the geometry of piping and configuratio of pipe support assemblies. The detailed inspection procedure is given in Actachment II.
1.0 General A support assembly was defined as a fixed hanger or support, variable and constant support, seismic restraint, rupture restraint, and snubber. The complete support, incuding support attachment or bracing steel up to but not including embedment depth or building steel was inspected.
2.0 Inspection Tolerances 2.1 Pipe support assemblies were inspected against an acceptable tolerance which depended upon the pipe diameter. Refer to Attachment II.
If this tolerance was not met, the actual location was recorded.
2.2 Pipe geometry nar inspected against a tolerance of one pipe diameter in any direction.
It C ds tolerance was not met, the actual locaticg dimensions are recorded.
2.3 Valve and valve operators were inspected against an axial and radial tolerance. Deviations are recorded.
2.4 Support / restraint structural attachment orientation in relation to the pipe attachment were inspected against a tolerance of plus or minus seven (7) degrees in any direction. Deviations are recorded.
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2.5 Hydraulic snubbers were inspected for size, installation, and setting.
Deviations are recorded.
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_ _ _ _ _, _ ~. _, _ _. _ _ _. _. -. _ _ _... _. _ _ _
3.0 Inspection Elements 3.1 Support assemblies were inspected for the following:
Type (rigid rod, spring, U-bolt, etc.)
Quantity and size of pipe attachments Size of spring cans Correct bore and stroke on hydraulic snubbers Weld size, length and type Hex nut engagement Assembly component size and quantity 3.2 Clearance were recorded at four 90 locations for all wall penetrations, pipe box restraints or other possible interferences to pipe expansion or seismic action.
3.3 Material cubstitution was recorded for evaluation.
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a SECTION 4
SUMMARY
REPORT Section 2 of this report describes the work done as part of the site inspection.
As of the date of this report, 171 Piping Inspection Reports (PIR) have been submitted for evaluation. Of these, 68 do not require re-analysis as the original analysis performed applies to the actual configuration of the piping systems. Thirty-one (31) are being evaluated to determine their status and 72 require a re-run of the analysis. A re-analysis was required due to one or more of the following discrepancies:
a.
Dimension changes of valve or support location, b.
Orientation of valve or support.
c.
Support type deviation.
d.
New supports (not shown on drawings).
e.
Missing supports.
f.
Pipe geometry.
g.
Other discrepancies as noted in Attachment III.
Attachment III to this report is a schedule for completing the reanalysis as required by Item 4B(i) of Bulletin 79-14.
Included in the schedule are descriptions of the nonconformances found in those analysis packages requiring
, rework.
When it is determined from the reanalysis results what field changes need to be l
made, drawings shall be updated to reflect the as-built condition of the piping and supports as required by Item 4D of the bulletin. The progress of updating
(
as-built drawings shall be described in the final report.
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l The final report responding to all IE Bulletin 79-14 items, detailing the l
l results of the completed inspection, evaluation and re-analysis efforts, and outlining any required redesign / remedial action will be submitted by September 30, 1980.
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ATTAO?T.~iI DESIGN DOCUMENT REFERENCE LIST The following design documents were used as input to the seismic analysis.
SEISMIC ANALYSIS INPUT DOCUMENTS DOCUMENT SEISMIC ANALYSIS INPUT 1)
Pipe Specification for Piping materials, fittings, and wall Plant Piping (SP-5544) thickness, design pressures and temperatures 2)
Building Seismic Response Building seismic response spectra by Curves elevation and building seismic movements 3)
Insulation Specification Insulation types and thicknesses - used to SP-5546 determine weights of piping
,4)
Manufacturer's Valve Drawings Valve weights, c.g.'s and lengths 5)
Piping Isometrics Pipe routings, fittings in a format for use (PI-305-Drawings) with computer analyses.
(Derived from physical drawings) 6)
Physical Piping Drawings Pipe routings, fittings, valve locations (P-304-Drawings) 7)
Flow Diagrams Line specifications, operating l
(FD-302-Drawings temperatures Page 1 of 2
ATTACHMENT I DOCUMENT SEISMIC ANALYSIS INPUT 8)
Pipe Support Drawings See Note 1.
9)
Spool Sheets Pipe material, diameter and wall thickness - as fabricated The document type 5 drawings listed on the following pages cover all safety-related piping analyzed as seismic class I in accordance with the FSAR. Also listed for reference are system identifiers and the code number for the analysis.
System identifiers are coded as follows:
Code System Title AS Auxiliary Steam MS Main Steam FW Feed Water EEW Emergency Feed Water SW Nuclear Services Closed Cycle Cooling Water DC Decay Heat Closed Cycle Cooling MU Makeup and Purification SF Spent Fuel Cooling WD Waste Disposal CO Condensate.
RC Reactor Coolant LR Leak Rate CF Core Flooding DH Decay Heat Removal BS Building Spray RW River Water Monitoring Post Accident Purge Note 1:
The pipe support drawings were drawn using load information that is part of the computer analysis output and therefore do not qualify as l
input to the seismic computer analysis. The pipe support sheets, I
however, were used as part of inspection on documents.
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6 ATTACHMENT II 1.0 GENERAL PROCEDURE 1.1 Inspection of supports and piping geometry of Seismic Category 1 systems shall be as specified herein.
1.2 Piping supports to be inspected are fixed hangers and supports, variable and constant-support hangers and supports, seismic rest.ra.ints and hydraulic snubbers. They shall be termed supports for this procedure.
1.3 Piping geometry shall be inspected for arrangement and location of supports and valves in comparison to the mechanical isometrics and piping arrangement drawings.
1.4 Nonconformances and significant deviations shall be evaluated within the requirements of the plant tech-specs to determine their effect, if any, on the ability of the system to function.
1.5 Deviations which decrease the function of load capacity of a support shall be indicated on an ACTION ITEM REPORT. An engineering evaluation shall made to determine the support's capability and the systems ability to function.
If the support's capability is determined l
to be insufficient and/or the system function is disabled, then the l
Manager TMI-1 Engineering or the TMI-1 Lead Mechanical Engineer shall be promptly notified in accordance with the requirements of IEB 79-14 including Supplement 2.
1.6 Damaged supports shall be indicated on an ACTION ITEM REPORT and submitted for Engineering Evaluation.
1.7 Where a support deviates from the drawing, sufficient and detailed information shall be provided (on a separate sheet if necessary) to allow an Engineering Evaluation and to allow drawing changes to be l
made.
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ATTACHMENT II 1.8 Data which has been obtained by way of visual estimation in lieu of measurement will be identified in the final report prepared by GAI for GPU/ Met-Ed.
1.9 Thermal insulation may be removed, if required by IE Bulletin 79-14, Supplement 2.
Mirror insulation removal and reinstallation shall be perMaintenanceProcedure1410-T7.
1.10 Inspections requiring access which are impractical even with the reactor shutdown (and consequently are not performed) will be evaluated in GAI's final report on a case basis.
1.11 Observe Radiation Work Permit (RWP) requirements for all radiation / contamination areas.
2.0 PIPING INSPECTION 2.1 PIPING INSPECTION REPORT A PIPING INSPECTION REPORT shall be completed for each piping isometric.
If a portion of a system appears on more than one isometric, the isometric on which that system portion was inspected shall be referenced on the other isometric's system evaluation data sheet.
2.2 PIPE SUPPORT ATTACHMENT 1
l 2.2.1 Location of pipe support attachment to pipe shall be inspected and compared to the piping isometric.
2.2.2 The following axial tolerances are allowable:
PIPE SIZE TOLERANCE To 6" 14" 8" to 18" 8"
12" 20" to 36" l
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ATTACHMENT II 2.2.3 Support attachment locations not within tolerance shall be recorded on the piping isometrics for actual dimensions.
The support shall be identified on the PIPING INSPECTION REPORT.
2.2.4 Supports not shown on the piping isometrics shall be located on the drawings. A sketch showing function and attachment shall be attached to and referenced on the PIPING INSPECTION REPORT.
2.2.5 The piping shall be checked for unspecified interferences which ILuit the thermal movement of the pipe. These shall be located on the piping isometric and referenced on the PIPING INSPECTION REPORT.
2.3 VALVES 2.3.1 Valves shall be located within tolerances specified in Item 2.2.2 of dimension shown on piping isometric.
2.3.2 Valve operator rotation from piping axis shall be within 15 of that shown on drawing or to next bolt of valve bonnet if flanged bonnet valve.
2.3.3 Valves or valve operators not within tolerance shall have actual j
dimensions / angular rotation recorde'. on the piping isometric and 1
referenced on the PIPING INSPECTION REPORT.
2.4 SUPPORT ORIENTATION 2.4.1 Support str24 ural attachment orientation with the pipe attachment shall be within 7 of specified orientation.
2.4.2 Beam brackets or the equivalent may be rotated 90 for rigid rod hanger supports.
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ATTACIDfENT II 2.4.3 Beam brackets used with sway braces shall be oriented so as not to hinder axial movement, unless otherwise specified on the drawing.
2.4.4 Restraints designed to act in pairs shall provide the same function as the designed supports.
2.5 PIPE GE0tfETRY Pipe geometry shall be as shown on the isometric drawings. Where geometry deviates by more than one pipe diameter it shall be recorded on the isometric and referenced on the PIPING INSPECTION REPORT.
3.0 SUPPORT INSPECTION 3.1 SUPPORT INSPECTION REPORT 3.1.1 A SUPPORT INSPECTION REPORT shall be completed for each support inspected.
.3.1.2 The support including attachment to plant structure shall be as shown on the support drawing. Deviations not allowed within this procedure shall be recorded on the SUPPORT INSPECTION REPORT and evaluated by Engineering.
3.2 SUPPORT STRUCTURAL ATTACIDfENT 3.2.1 Support attachment to concrete shall be as shown on the drawing.
Where concrete expansion anchors are shown, the number and size only shall be recorded. Loose anchors shall be identified.
3.2.2 Supports attached by Unistrut shall have the number and size of bolts in Unistrut recorded.
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ATTACHMENT II 3.2.3 Embedments shall have dimensions and location of support attachment as shown on the drawings. Deviations greater than 1" shall be recorded.
3.2.4 Base plates shall be checked for the following (record deviations greater than 10% of measured quantity) 1.
Plate thickness, dimensions, orientation 2.
Anchor location, size, and quantity 3.
Edge distance from center of anchor to plate edge (if less than 2 X diameter of bolt, record) 4.
Location of support attachment 3.2.5 Anchors for other supports within 8 in. center-to-center shall be shown on support drawing.
3.2.6 Edge distance of anchor center-line to edge of concrete shall be shown if less than 6".
3.2.7 Floor and wall penetrations shall have clearance as specified on i
drawing. Check at four locations 90 apr, ct.
If no clearances specified, measure and record.
3.3 SUPPORk' TYPE 3.3.1 Support chall be that shown on drawing except as noted herein.
3.3.2 Rigid Rod Hangers 1.
Single rigid rod hangers may be interchanged with double-rod trapeze hangers provided new support is adequate to carry load.
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ATTACHMENT II 2.
Double-rod trapeze hangers may be interchanged with single rigid rod hangers provided single rod diameteris 1-1/2 times or greater than double-rod diameter.
3.3.3 Spring Hangers 1.
Types "A", "B" AND "C" spring hangers may be interchanged.
2.
The elevation of a Type "A", "B" or "C" spring may be different.
3.3.4 Hydraulic Snubbers 1.
A large bore snubber may be substituted for a smaller bore snubber.
2.
The fluid reservoir may be reversed from the drawing provided the vent hole is on the 'high' side of the snubber.
3.
Threaded end of the snubber shall be on the support structural attachment (building) side.
4.
Snubber shall be > 1/4" from full extension or full compression.
3.4 WELDED ATTACHMENTS 3.4.1 Welded attachments to pipe shall be as shown on drawing.
3.4.2 Record any crscked welds, or missing attachments.
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ATTACHMENT II 3.5 SUPPORT COMPONENTS 2
3.5.1 Support components shall be equal to or heavier than that specified on drawing or bill of material.
3.5.2 All components shall be installed. Missing components shall be identified.
3.5.3 Two steel plates may be substituted for a beam bracket. Record dimensions of plates.
3.5.4 Attachment plates with forged clevises may be interchanged with beam brackets with welded eyerods if equal to or heavier size than shown on drawing.
3.5.5 Weldless eyenuts with threaded rod may be interchanged with welded eyerods if equal to or heavier than shown on drawing.
3.5.6 Field fabricated pipe insulation saddles may be substituted for manufactured pipe insulation saddles. Record dimensions.
3.6 SUPPORT LOAD ATTACHMENT 3.6.1 Location of support load attachment to structural members shall be within 1" of specified location.
l 3.6.2 If location not specified, record location from point of structural attachment to building. Record distance between structural attachment points.
(e.g., rigid rod hanger on angle held by two anchor bolts.)
3.6.3 Lengths of structural shapes used to form a support bracket (e.g.,
knee brace) shall be as shown on drawing.
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ATTACIDfENT II 3.7 WELDING 3.7.1 WELDING - Symbol Shown Welding shall be in accordance with symbol shown or develop the strength of the weaker member.
3.7.2 WELDING - Symbol Not Shown l
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Welding shall be 1/4" fillet all-around or develop the strength of l
the weaker member.
3.7.3 Cracked or damaged welds shall be recorded.
l 3.8 THREADED IfEEERS i
l 3.8.1 LOCKNUTS 1.
Locknuts shall be tight and in accordance with the drawings l
except as specified herein.
2.
Only one locknut is required at turnbuckles on rigid rod hangers that have eyerods at the structural and pipe attachment points. The locknut may be either on the top or bottom of the turnbuckle.
3.
Two locknuts are required on any hanger that has a rod threaded at both ends and is between a clevis or eyenut and turnbuckle.
One locknut may be at the clevis /eyenut end, or at the i
turnbuckle end of the rod threaded at both ends. The other locknut shall be on the other rod at the turnbuckle.
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ATTACHMENT II 3.8.2 U-BOLTS U-bolts shall be installed to the tight or loose condition as specified on the drawing. All nuts shall be installed as shown.
3.8.3 THREAD ENGAGEMENT 1.
Nuts shall have full thread engagement (one. full thread exposed through the nut).
2.
Clevis / turnbuckles shall have full thread engagement (one full thread exposed).
3.
Less than full thread engagement shall be recorded.
Indicate diameter and depth not engaged in nut / clevis / turnbuckle.
3.9 MAINTENANCE ITEM REPORT 3.9.1 Items found during inspection which do not affect the function or load capacity of a support shall be identified on a MAINTENANCE ITEM REPORT for action by the Plant Staff as necessary.
3.9.2 Examples are:
1 1.
Loose nuts with full thread engagement (except on tight U-bolts).
2.
Loose pipe clamps.
l 3.
Loose bolts when used in shear only.
3.10 ACCEPTANCE l
l 3.10.1 Supports which are in accordance with the drawing or have deviations which do not affect the load capacity in accordance with this procedure are acceptable.
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ATTACHMENT II 3.10.2 Supports which do not meet the drawing requirements and b2ve deviations which reduce the load capacity shall be identified on an ACTION ITEM REPORT and submitted for Engineering Evaluation.
3.10.3 Data package is complete including all Inspection Report data sheets and marked up isometric drawings.
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FQ-R101 ATTACHMENT NO. 1 PIPING INSPECTION REPORT PIR-System Recommended Disposition ME Yes/No - Comp.
Dwg.
Rev.
Acceptable Reference Dwg.
Analysis Required Drawing Revision Req'd Within INSPECTION Tolerance 1.
Support Location 2.
Support Orientation 3.
Valve Location 4.
Valve Operator Orientation 5.
Pipe Geometry Date Engineer / Inspector DEVIATIONS
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ANALYSIS l
l Date Engineer / Analyst
FQ-R101 ATTACHMENT NO. 1 SUPPORT INSPECTION REPORT SIR-Support No.
Recommended Dispostion Drawing No.
Rev.
Acceptable Drawing Rev. Req'd Repair / Rework Req'd INSPECTION Yes/No 1.
Structural Attachment Per Dwg.
2.
Concrete Expansion Anchor Bolts Used No/ Size
/
3.
Unistrut Attachment Bolts Used No/ Size
/
4.
Support Type Per Dwg.
5.
Spring / Snubber Correct Size 6.
Structural Components per Dwg.
7.
Welding per Dwg.
8.
Locknuts Installed per Dwg.
AIR 9.
Full Thread Engagement MIR Date Inspector DEVIATIONS i
i DISPOSITION l
Date Engineer / Designer
)
FQ-R101 ATTACIDfENT NO. I b
MAINTENANCE ITEM REPORT ffIR-Support No.
Drawing No.
Rev.
DESCRIPTION OF PROBIE.M Date Inspector MAINTENANCE ACTION Date l
DISPOSITION l
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FQ-R101 ATTACHMENT NO. 1 ACTION ITEM REPORT
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ME No.
Drawing No.
Rev.
i DESCRIPTION OF FINDING e
RESPONSE
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4-8-80 Rev. O Sheet 1 of 11 ATTACHMENT III SEISMIC CATEGORY 1 SIGNIFICANT DISCREPANCY
& REANALYSIS SCHEDULE METROPOLITAN EDISON COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 Discrep-Descriptive Title Start PIR()
Priority ancy of Analysis Package Analysis Complete ME-219 1A 1,2,3,7 Cooling Water from 2/19 3/14 RC-P-1B to ME-218 ME-179 1A 1,2,3,4,7 N.S. Cooling Water from 2/19 3/14 RC-P-IC & ME-218 to ME-204 ME-214 1A 1,2,3,4,5, N.S. Cooling Water from 2/19 3/14 6,7,10 ME-213 to RC-P-1A &
ME-215 ME-215 1A 1,3,5,7 N.S. Cooling Water from 2/26 3/21 ME-214 to RC-P-1B ME-218 1A 1,2,4,5,7 Cooling Water from RC-P-1A 2/25 3/21
& ME-219 to ME-179 l
l ME-205 1A 1,3,4,7,10 RC-P-1D to Pen. #346 2/25 3/21 F
ME-044 1A 1,2,6 M.S. from Steam Generator 3/3 3/28 B to Header at 297'-0" ME-062 1A 2,3,7,8 E.F. Pump "A" Discharge 3/3 3/28 to Header i
4-8-80 Rev. O Sheet 2 of 11 Discrep-Descriptive Title Start PIR#
Priority
_ ancy of Analysis Package Analysis Complete ME-065 IA 1,7,8 E.F. from Header to 3/3 3/28 R.B. Wall ME-066 1A 6,8 E.F. from Header to 3/3 3/28 R.B. Wall ME-084 1B 1,2,3,4,5, R.B. Spray Vtr. Piping 3/3 3/28 10 from Pen. #308 to Header D at El. 417'-6" ME-089 IB 1,3,7 6" Pressure Relief from 3/3 3/28 Secondary Shield Wall to Drain Tank ME-051 IB 1,2,5,8,11 12" D.C. Piping from 3/3 3/28 Secondary Shield Wall to 36" R.C. Pipe
' ME-074 IB 1,11 D.H. from Reactor (Between 3/3 3/28 Shield Wall & R.B.)
ME-164 IB 1,3,4,5,6 From Letdown Coolers to 3/10 4/4 R.B. Wall Pen. #309 ME-97A 1B 1,4,6 2-1/2" High Pressure 3/10 4/4 Injection Piping from Pea.
- 321 to B&W Conn. #17 ME-160 IB 1,2,3,5,11 Pressurizer Auxiliary Spray 3/10 4/4 KP.-060 IB 3,11 D.H. Removal 24" Borated 3/17 4/11 Water Tank Discharge l
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4-8-80 Rev. O Sheet 3 of 11 Discrep-Descriptive Title Start PIR#
Priority ancy of Analysis Package Analysis Complete ME-010 IB 1,2,7 D.H. Removal 6" Crossover 3/17 4/11 ME-073 IB 1,2,3,7,8 D.H. Cooler DH-C1B Outlet 3/17 4/11 to R.B.
ME-04A IB 6,11 12" D.H. Pump Suction 3/17 4/11 ME-096 1B 1,2,3,7, D.H. Removal Borsted Water 3/17 4/11 11,12 Tank Discharge ME-172 1B 11 Pen. #354 to R.B. Spray 3/24 4/18 Pump Suction ME-01A IB 2,7,11 D.H. Removal Pump "A" 3/24 4/18 Suction ME-173 IB 2,7,11 Pen. #352 to R.B. Spray 3/24 4/18 Pump ME-146 IB 1,2,3,6, MU & Purification to MU 3/31 4/25 7,11 Pumps MU-P-1A, IB & IC ME-169 1B 1,3,7,11 4" MU Pump Suction from 3/31 4/25 D.H. Removal Cooler DH-CIA ME-045 IB 1,11 R.B. Spray Fump Suction 3/31 4/25 (for both pumps)
ME-176 IB 7,11 10" Connection Piping Bldg.
3/31 4/25 Spray Pumps PIA-P1B ME-020 IB 7,11 R.B. Spray Pump Suction 4/7 5/2 (Pump B)
4-8-80 Rev. O Sheet 4 of 11 Discrep-Descriptive Title Start PIR#
Priority ancy of Analysis Package Analysis Comolete ME-213 1C 1,4,7,10 Cooling Water from ME-205 4/7 5/2 to RC-P-1C & ME-214 ME-113 1C 1,3,6 R.B. E.C. Water Supply 4/7 5/2 from Pen. #412 to A.N.
Unit AH-E-1C ME-204 1C 1,2,3,6,7 8" Line from Pen. #347 4/14 5/9 to RCP-1A, IB, IC & 1D ME-091 1C 1,2,3,7 6" Pressure Relief from 4/14 5/9 Wall to Drain Tank ME-085 IC 1,2,10 R.B. Spray Water Piping 4/14 5/9 from Pen. #301 to Header at El. 417'-6" ME-093 ID 1,4,7,10 4" Pressure Relief Line 4/14 5/9 from Shield Wall to Drain Tank l
ME-162 1D 1,3 Electromatic Relief to 4/21 5/16 Secondary Shield Wall ME-128 1D 1,5 S.F. Cooling Piping from 4/21 5/16 Pen. #304 to Fuel Canal ME-117 2A 1,2,3,4,7, N.S. Cooling Water Return 4/21 5/16 11 from Spent Fuel Coolers "A" & "B" to Anchor Points ME-144 2A 1,6,7,11 N.S. Cooling Water to Air 4/28 5/23 Condensers i
4
4-8-80 Rev. O Sheet 5 of 11 Discrep-Descriptive Title Start PIR//
Priority ancy of Analysis Package Analysis Complete ME-137 2A 1,4,6,7,9,11 S.F. Cooling from Borated 4/28 5/23 Water Recire. Pump ME-177*
2A B&W Recire. Pump to S.F.
4/28 5/23 Cooler, Pump Bypass S.F.
Cask Loading Pit ME-061 2A 1,3,6,11 D.H. Removal 8" Borated 4/28 5/23 Water Line Inlet Line ME-095 2A 1,2,4,6,11 N.S. Cooling Water 18" 5/5 5/30 Supply to Heat Exchsngers ME-125 2A 1,7,8,11 S.F. Cooling Water Piping 5/5 5/30 from Coolers SF-C-IA &
SF-C-1B ME-41 UL 1,2,5,7 M.S. Piping from R.B. to 5/5 5/30 Turbine Generators ME-156 2A 1,6,9 N.S. Cooling Water Supply 5/12 6/6
{
to AH-E-24A & 24B ME-116 2A 1,7,9 N.S. Cooling Water Pump 5/12 6/6 Disch. to Anchors ME-155**
2A N.S. Cooling Water Return 5/12 6/6 from AH-E-24A & 24B to Assume Anchor Point ME-199 2A 1,4,6 Fan Motor Coolers to 5/12 6/6 ME-155 & 131 I
~
4-8-80 Rev. O Sheet 6 of 11 Discrep-Descriptive Title Start PIR#
Priority ancy of Analysis Package Analysis Complete ME-167 2A 1,3,4,5,6 4" Pump Disch. Header 5/19 6/13 M.U. Pumps MU-PIA, PIB
& PIC ME-196 2A 3,6,7 ME-144 to Inlets of 3/7 4/11 Sample Coolers ME-135 2A 1,4,7,8,11 S.F. Cooling from SF-T-2A 5/19 6/13 ME-72A 2B 1,2,6,7,8 D.H. Cooler DH-CIA Outlet 5/19 6/13 to R.B.
ME-136 2B 1,2,5,6 S.F. Cooling from SF-T-2B 5/19 6/13 ME-171 2B 1,7 6" R.B. Spray Text Line to 5/19 6/13 Borated Water Recire. Pump ME-139A 2B 3,5 F.W. from 30" Header to 5/26 6/20 Pen. #227 ME-200 2B 4,5,6 ME-116 to Fan Motor 5/26 6/20 i
Cooler Inlets ME-210 2B 1,2,4,5 ME-167 to Pen. #321 5/26 6/20
& #322 ME-032 2B 1,2,4,6, R.B. Spray Pump Disch.
5/26 6/20 7,8 (Pump A) l l
ME-046 2B 1,2,4,6,7 R.B. Spray Pump Disch.
6/2 6/27 1
(Pump B)
I
4-8-80 JRev. O
~~
Sheet 7 of 11 Discrep-Descriptive Title Start PIR#
Priority ancy of Analysis Package Analysis Complete ME-138 2B 1,2,4,8 F.W. from 30" Header to 6/2 6/27 Pen. #103 f
ME-008 2C 1,4,7 M.U. & Purif. from Filters 6/2 6/27 MU-F4A & MU-F4B to Reactor Wall Pen. #337 ME-188 2C 1,2,6,11 Distillate Cooler "A" to 6/9 7/3 ME-142 ME-195 2C 1,2,6 N.S. Closed Cycle Cooling 6/9 7/3-Water Outlet of A.H. Units AH-E-15A & 15B to ME-95 ME-223 2C 1,4 Cooling Water ME-222 to 6/9 7/3 '
ME-56 & ME-57 ME-225 2C 3,4,6,7 NSCCC-MC-224 to ME-190 6/9 7/3 ME-141 2C 1,8,11 N.S. Cooling Water from 3/24 4/18 NSH-100 to':R.C. Waste Gas Evap. "B" ME-143 2C 1,8,11 N.S. Cooling Water from 3/24 4/18 Anchor to R.C. Waste.
Evap. "A" ME-36 2C 1,2,7 D.H. Service Cooling, 6/16 7/11 River Water ME-37 2C 1,4,7,8 D.H. Service Cooling 6/23 7/18 l
River Water l
l
4-8-80 Rev. O Sheet 8 of 11 Discrep-Descriptive Title Start PIR#
Priority aacy of Analysis Package Analysis Conolete ME-49 2C 1,4 Condensate from Storage 6/23 7/18 Tk. B to EFW Pumps (Inside Struc.)
ME-56 2C 7,11 D.H. Closed Cycle Cooling 6/23 7/18 Water from Cooler DHE-1A to Cooler DHC-2A ME-57 2C 7,11 D.H. Closed Cycle Cooling 6/23 7/18 Wtr. from Cooler DHC-1B to Cooler DHC-2B ME-58 2C 7
D.H. Closed Cycle Cooling 6/30 7/25 Wtr. from Pump DH-RIA to Cooler DH-CIA ME-59 2C 1,4,7 D.H. Closed Cycle Cooling 6/30 7/25 Wtr. from Pump DH-1B to Cooler DH-CIB
'ME-67 2C 7,8 E.W. Pump Disch. to Header 6/30 7/25 ME-68 2C 2,4,7 E.W. Pump "A" Suction 7/7 g/l ME-87 2C 4
D.H. Closed Service 7/7 8/1 Cooling Wtr. from Cooler DC-C2B to Pump DC-PIA ME-42 2C 1,2,3,4,7,9 M.S. from Steam Generator 7/7 8/1 A to EF Pump Turbine ME-43 2C 2,3,4,7,8 M.S. from Steam Generator 7/7 8/1 B to Header at El. 297'-0"
4-8-80 Rev. O Sheet 9 of 11 Discrep-Descriptive Title Start PIR#
Priority ancy of Analysis Package Analysis Complete ME-64 2C 1
Turbine Driven Emer.
7/14 8/8 F.W. Pump Disch.
ME-70 2C 1,2 E.F. Water Suction Anchor 7/14 8/8 to Anchor ME-119 2C 1,6,7,8,11 S.I. Cooling Piping from 7/14 8/8.
Anchor SFH-116 & SFH-117 to 4" Conn. to D.H. Piping ME-120 2C 1,7,8.
S.F. Cooling Piping from 7/21 8/15 Base Supp. 5HF-117 to Retain. Ring in Wall ME-158 2C 2,3 16" R.B. Emerg. C1g. Wtr.
7/21 8/15 Pump Disch. from Pump RR-PIA
' ME-159 2C 1,3,4 N.S. Cooling Inside Pump 7/21 8/15 House ME-165 2C 7
12" Bypass for D.H. Cooler 7/21 8/15 DH-CIA ME-166 2C 1,7,8 12" Bypass for D.H. Cooler 7/28 8/22 DH-CIB ME-174 2C 1,7 4" Sodium Hydroxide to 7/28 8/22 Anchor on ME-96 & ME-119 ME-201 2C 4,8 KE-53 to ME-70 7/28 8/22
O 4-8-80 Rev. O Sheet 10 of 11 Discrep-Descriptive Title Start PIR#
Priority ancy of Analysis Package Analysis Complete ME-206 2C 1,3,8,9 4" Line frem Condensate 8/4 8/29 Tank "B" ME-230 2C 2,7,8 M.S. Pump Line to 8/4 8/29 Intermediate Bldg. Wall.
ME-132 2C 7,8 S.F. Cooling from S.F.
8/4 8/29 Pools SFT-2A & 2B ME-63 2C 1,2,6 E.F. Pump "B" Disch. to 8/4 8/29 Header ME-124 2C 1,6,7,.8,11 S.F. Cooling Wtr. Piping 8/11 9/5 to Borated Wtr. Recire.
Pump & S.F. Pumps SF-P-1A & SF-P-1B ME-145 2C 1,3,6,7, N.S. Cooling Water from 8/11 9/5 8,11 AH-C-4A & 4B ME-007 3
1,4 M.U. & Purif. 4" Line 6/16 7/11 MU-V89A to Filters l
MU-F4A & 4B i
ME-190 3
1,5,6 ME-16 to M.U. Purif.
6/16 7/11 Pump Suction ME-191 3
1,6,9 Inlet S.F. Pit Pump Room 6/16 7/11 Cooler IA, 1B from ME-116 l
ME-192 3
1,9 Inlet S.F. Pit Pump Room 6/23 7/18 i
Cioler IA, 1B to ME-131 I
l t
o 4-8-80 Rev. O Sheet 11 of 11 Discrep-Descriptive Title Start PIR#
Priority ancy of Analysis Package Analysis Complete ME-211 3
1,3,4,6,8 M.U. Pump Disch. Header 6/23 7/18 to Pen. #338 ME-212 3
1,3,4,6 M.U. Pump Disch. Header 6/23 7/18 to. Pen. #339 ME-224 3
1,3 Cooling Water ME-116 to 6/23 7/18 ME-58 & ME-59 ME-226 3
1,3 4" Thiosulfate to R.B.
6/30 7/25 Spray Pump Suction Th. to Anchor at Aux. Bldg. &
ME-175 R.B. bpray ME-228 3
4,5 DHCCC-3" Line R.B. Spray 8/25 9/19 Pump to 16" Line DHR Cooler
- To be voided. Covered by ME-137.
- To be voided.
Incorporated with ME-199.
DISCREPANCY CODE 1.
Dimension changes of valve ar support location 2.
Orientation of valve or support 3.
Support type deviation i
4.
New support (not shown on drawings) 5.
Missing supports 6.
Pipe geometry 7.
Required for correct support loadings with other ME's 8.
Valve weights or center of gravity changed or missing 9.
Seismic spacing criteria 10.
Incorrect response curve used l
11.
Generic anchor problem 12.
Valve missing from analysis l
... L -
4-8-80 Rsv. O PRIORITIES FOR NRC IE BULLETIN 79-14 REV. 1 SUPPLEMENT 1 AND 2 ANALYSIS / REANALYSIS METROPOLITAN EDISON COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 PRIORITY DESCRIPTION 1A Analyze piping inside containment to support 79-02 redesign effort.
1B Generic Anchors - all anchors identified inside containment plus the original 7.
IB Reanalysis inside containment.
Category 1 - Analyses with flagrant violations.
IC Reanalysis inside containment.
Category 2 - Analyses required to confirm judgement of unacceptable conditions.
1D Reanalysis inside containment. Category
- Analyses required to conform judgement of possible accepta e conditions.
2A Analyze piping outside containment to support 79-02 F.S.
< 2 redesign effort. Including balance of generic anchors.
2B Reanalysis outside containment.
Category 1 - Analyses with flagrant violations.
2B Reanalysis outsf.de containment with S.F.<5 but greater than 2.
Category 2 - Analyses required to confirm judgement of unacceptable conditions.
2C Reanalysia satside containuent. Category 2 - Analyses required to confirm. judgement of unacceptable conditions.
l 3
Reanalysis outside containment. Category 3 - Analyses required t
to confirm judgement of possible acceptable conditions.
i i
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