ML20028B108
ML20028B108 | |
Person / Time | |
---|---|
Site: | Shoreham File:Long Island Lighting Company icon.png |
Issue date: | 11/23/1982 |
From: | James Smith LONG ISLAND LIGHTING CO. |
To: | Harold Denton Office of Nuclear Reactor Regulation |
References | |
SNRC-796, NUDOCS 8211290468 | |
Download: ML20028B108 (139) | |
Text
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LONG ISLAND LIGHTING COM PANY SHOREHAM NUCLEAR POWER STATION
" ' ~-
P.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792 November 23, 1982 SNRC-796 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Safety Evaluation Report Issue No. 8 Dynamic Qualification Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322
Reference:
(1) Letter NRC (A. Schwencer) to LILCO (M. S. Pollock) dated 11/10/82
Dear Mr. Denton:
In response to the reference (1) letter, enclosed please find ten (10) copies of Long Island Lighting Company's response to the concerns generated by the Seismic Qualification Review Team as a result of their plant site audit held from August 31 - September 3, 19E2. This information is being submitted in order to facili-tate the NRC staff's review and closeout of this SER item. Each concern is addressed separately with the concern restated and the response following. Any responses which require additional docu-mentation have this listed as an attachment.
In accordance with R. L. Tedesco's letter to LILCO, dated January 28, 1981, four copies of this submittal are being forwarded directly to Dr. Morris Reich at Brookhaven National Laboratory. As stated in the Reference 1 letter a response to the audit trip open items was anticipated to be made by LILCO within two weeks after receipt of Reference 1.
In view of this timely response, LILCO requests that the NRC staff review the enclosed information in a manner so as to facilitate final resolution of this SER item.
Very truly yours, () [
/ D
. L. Smith j jo Manager, Special Projects WVB:mp ( ,. g $
Enclosure cc: J. Higgins All parties 8211290468 821123 Dr. M. Reich (4) PDR ADOCK 05000322 E PDR
GENERIC ITEMS
- 1. Qualification documentation needs to be improved in the following areas:
- a. A " road map" should be provided to define the qualification process for BOP equipment.
- b. Complete test reports should be included in BOP SQRT package,
- c. Single spectra included in:62r:?qad. age should be identifed as limiting (worst case) spectra.
RESPONSE
- a. A summary report will be provided which will define the scope of the dynamic qualification program for BOP equipment. The report will describe the basis for including equipment in the program and the specific methodology applied for qualification of equipment. This report will be provided 30 days prior to fuel load.* "
- b. The vendor supplies qualification documents which normally include complete test reports which are included in the SQRT packages. In a few cases vendors may not have supplied a complete test report as part of their qualification documentation, e.g., for specific items 480V ,
Emergency Switchgear Bus 112 and 480V Motor Control Centers 1R24*MCC1120, in the NRC audit report. In these cases, complete test reports will be requested from the vendor.
If the vendor holds them proprietary, LILCO will take
. action similar to specific items 3 and 4. This effort will be completed by June, 1983.
- c. The single spectra included in the SQRT packages will be identified as limiting (worst case) spectra by fuel load.
- 2. The latest confirmatory load spectra should be included in all SQRT packages by the end of March 1983.
RESPONSE
The latest confirmatory load spectra will be included in all SQRT packages for floor-mounted equipment by the end of March 1983.
Clarification will be provided to the extent necessary to relate confirmatory load spectra to the qualification basis.
All replacement equipment (not in-kind) will be qualified to the confirmatory load spectra.
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Generic Items, Page 2
- 3. The latest confirmatory loads should be considered for the qualification of pipe mounted equipment, i.e., valves.
Phase I -
Prior to fuel load l
- a. Provide verbal description of 30 piping subsystems already analyzed.
b, Provide a list of pipe mounted equipment by Shoreham valve Mark Nos. in these subsystems,
- c. Demonstrate qualification to confirmatory load values for the valves listed.
Phase II -
Prior to operation above 5% power
- a. Identify all associated pipe mounted equipment for approximately 70 additional piping subsystems.
- b. Assess existing margin of safety for accommodating the upper bound of any load increase that could result ,from the confirmatory loads.
- c. Where adequate margins of safety are not evident, perform analysis to demonstrate equipment qualification utilizing confirmatory loads.
RESPONSE
LILCO has proposed the following program to evaluate the effect of the hydrodynamic LOCA loads discussed in NUREG 0808 on pipe mounted equipment:
Phase I t In the Shoreham Design Assessment Report (DAR), Rev. 5, Appendix L, LILCO has stated that a representative cross-section of primary and secondary piping was evaluated to the NUREG 0808 Confirmatory Load Definition. This cross-section consisted of thirty (30) piping subsystems (twenty-five (25) of which are attached to the primary containment at locations of high amplitude response spectra).
Attachment 1 is a listing of all the pipe mounted equipment on these thirty (30) piping subsystems by Shoreham Mark Number. LILCO has agreed to provide the SQRT qualification level and calculated acceleration for each item based on the NUREG 0808 Confirmatory Load Definition. Should any equipment acceleration levels be found to be above the present qualification levels, computer reanalysis of these pieces of equipment will be performed again, utilizing the NUREG 0808 Confirmatory Load Definition but eliminating simplifying assumptions that have been employed. This approach has been described in SNRC-755, dated 8/20/82 from J. L. Smith to H. R.
Denton, and agreed to by the NRC Mechanical Engineering Branch.
This analysis will be completed prior to fuel load.
_.. .~ __ _ _ _ _ _ _ . - _
Generic Items, Page 3 Phase 7.I In SNRC-755, referenced above, LILCO committed to perform a one-hundred (100) percent reevaluation to the final Mark II long term program load definition (NUREG 0808) of the piping attached to the primary containment at the three (3) additional locations of concern, i.e., 21 ft., 83 ft., and 106 ft. This reevaluation work is considered confirmatory and not required for fuel load and low power testing. During the SQRT audit from August 31 to September 3, 1982, LILCO also committed to the NRC SQRT evaluation team to identify all pipe mounted equipment on these additional piping systems (approximately 70 piping subsystems) and to evaluate that the existing margins of safety are sufficient to accommodate the upper bound of any load increase that could result from the confirmatory NUREG 0808 load definitions. For the set of equipment where adequate margins of safety are not evident, requalification will be performed utilizing the NUREG 0808 Confirmatory Load Definition. This approach is similar to the agreement reached with the NRC Mechanical Engineering Branch for these same additional piping systems. This analysis will be completed prior to exceeding five (5) percent power operation.
- 4. Commit to establish a maintenance and surveillance program to maintain equipment in qualification status throughout the plant life prior to fuel load.
Response
The Shoreham Nuclear Power Station has a surveillance and maintenance program which includes documented program plans, procedures, and results to ensure that the safety-related equipment identified in the dynamic qualification program is maintained in a state of readiness and operability so that it will perform its intended safety functions properly during and after the excitation imposed by the SSE or hydrodynamic loads associated with suppression pool discharges or a combination of the two. The Shoreham surveillance and maintenance program includes information supplied by equipment manufacturers and vendors regarding required equipment mainteaance actions and their frequency. The Shoreham dynamic qualification program has not imposed any additional surveillance and maintenance requirements on the equipment included in the program as a result of qualification. However, if any specific requirements were generated they would be incorporated into the existing surveillance and maintenance program.
- 5. Provide monthly status of equipment summary list and provide justification for the equipment which will be qualified after fuel load.
Response
The latest equipment summary lists including BOP and NSSS equipment is provided in Attachment 2. This list will be updated and provided on a monthly basis.
Generic Items, Page 4 Justification for interim operation for the equipment which will be qualified after fuel load will be provided before the end of December, 1982.
- 6. NSSS qualification documentation file should be located in Shoreham plant file system by June 1, 1983.
Response
At present, LILCO has on file at the Shoreham site NSSS Dynamic Qualification Summaries for the equipment qualified under the NSSS scope of supply. The summaries provide-.*he requirements, demonstrate equipment capability and provide a rationale for qualification certification along with the Qualification Summary of Equipment (SQRT) forms. However, in order to comply with this NRC concern, LILCO is generating the necessary purchase order agreement to obtain the backup qualification documentation. The detailed NSSS backup qualification documentation will be located in the SQRT documentation packages at the Shoreham site by June, 1983.
- 7. To satisfy requirements of IEEE 323-1974, provide a wri.tten statement that margin to cover uncertainty in manufacturing and test exist for equipment qualified by test.
Response
IEEE Standard 323-1974 states in section 6.3 that for vibration, a margin requirement should be included to account for variations in equipment and reasonable errors in defining satisfactory performance. This standard has been endorsed by the NRC in Regulatory Guide 1.89, " Qualification of Class 1E Equipment for Nuclear Power Plants", dated November 1974. The Shoreham FSAR in Appendix 3B states that Regulatory Guide 1.89 is not applicable to Shoreham since the Shoreham SER (dated February 20, 1970) preceded the implementation date given in Section D of Regulatory Guide 1.89. The FSAR Appendix section goes on to state that an attempt would be made to procure equipment to the standard referenced in RG 1.89. The Shoreham FSAR cites IEEE Standard 323-1971 as the applicable standard for equipment qualification for Shoreham. LILCO feels that conformance to IEEE 323-1971 in addition to the TRS enveloping the RRS and the inherent conservatism used in developing the RRS provides the adequate margin to cover uncertainty in manufacturing and errors for equipment qualified by test.
- 8. Cycling effects of hydrodynamic load should be addressed prior to fuel load, based on worst case consideration.
- a. For equipment qualified by analysis, cumulative fatigue usage factor should be demonstrated to be less than one.
The SQRT may decide to review the adequacy of the analytical model used.
- b. For equipment qualified by testing, the number of equivalent SRV cycle should be adequately defined.
Generic Items, Page 5
Response
- a. For BOP equipment qualified by analysis, a survey will be conducted to identify the most highly stressed equipment in several categories, i.e., pumps, valves, heat exchangers and tanks. Peak stress will be determined by applying a stress intensification factor applicable to the configuration. Cumulative fatigue usage factors will then be determined for each equipment category.
Vibration fatigue cycle effects for NSSS equipment designed to ASME code requirements was reviewed at GE by NRC consultants from Battelle Pacific Northwest Laboratories on October 7, 1980. The consultants stated satisfaction with the GE approach which encompasses OBE, SRV, thermal and pressure cycles.
Non-ASME code components qualified by analysis have not been required to address vibration cycle effects. An overall review of non-ASME code components showed that the effect of SRV cycling fatigue did not require further additional analysis. ,
- b. For equipment qualified by testing, the number of equivalent SRV cycles has been defined in the Design Assessment Report, Revision 5, pages 9-11 and 9-12.
- 9. Provide information of any field modification made to the already qualified and installed equipment prior to fuel load.
Response
Attachment 3 is the current status of field modifications to safety related BOP equipment since September 2, 1982.
As of November 12, 1982, GE records do not indicate any field changes being made to NSSS equipment since September 2, 1982 which would affect seismic qualification as documented in GE SQRT reports.
A revised list of BOP and NSSS equipment will be provided prior to fuel load.
4.
EQUIPMENT SPECIFIC ITEMS
- 1. Unit Cooler - 1T46*UC-022 Package No. SH1-276-5 A static deflection analysis was provided for the fan only. A clearance of .051" was noted between the fan and housing.
Provide upgraded calculations to also include the deflection of the housing.
RESPONSE
An analysis of the fan housing has demonstrated a maximum displacement of approximately 0.001 inches. The vendor qualification report provides a maximums static deflection of 0.00306 inches for the fan. A combined maximum displacement of 0.00406 inches for the fan and housing is well within the available clearance of 0.051 inches. is a copy of calculation 331-1-CZC which was prepared in response to this request. ,
- 2. Permanent Control Rod Storage Rack - 1F16*RAK-23 Package No. SH1-427-1
- a. The qualification loads report was not available in the SQRT file. Need clarification
- b. Provide evidence of verification for the non-linear analysis code used.
- c. Loads were not properly defined (i.e., a time history was used, but there was no description of what it represented).
Provide clarification.
RESPONSE
- a. The qualification loads report is now available in the SQRT file at the site.
- b. Verification of the non-linear code (RACKOE) used by the vendor to calculate rack loads was conducted by showing that the ANSYS code yields similar results for a test problem. Documentation is provided in Appendix E of the Seismic Analysis Report (Attachment 5) and is now included in the SQRT file at the site.
- c. The racks were subjected to horizontal time histories associated with SSE, SRV and LOCa. It was found that SSE was the dominant source of rack loads appearing at the corners where they are attached to the floor embedments.
Other loads were insignificant contributors. This is addressed in Appendix A, Section 125F21 of the vendor's loads report.
Equipment Specific Items, Page 2
- 3. .480 V Emergency Switchgear Bus 112 Package No. Sill-95-1
- a. The qualification report should be completed so that it includes a table of contents and sequentially numbered pages.
- b. The test reports from test labs should be reviewed as part of the qualification documentation package.
RESPONSE
- a. The pages have now been sequentially numbered and a table of contents included. It has been verified with the vendor i
that the qualification report is complete as filed.
i b. The vendor's test report had been reviewed in its entirety i prior to acceptance. It will be reviewed again for the l
purpose of identifying the substance of the test conducted.
For example, any test anomalies that may have occurred will i
be documented and included in the SQRT package on file at the site.
- 4. 480 V Motor Control Centers - 1R24*MCC 1120 j Package No. Sill-115-1
- a. Provide resolution to the concern regarding clearance problems between motor control centers McC1133 and MCC1125, and battery chargers BC-01 and BC-B1 respectively.
- b. The test reports from the test labs should be reviewed as part of the qualification package.
RESPONSE
- a. Review has indicated that the clearance between Motor 4
Control Centers 1125 and 1133 and the battery chargers is not sufficiently large to assure that these cabinets will not impact during a dynamic event. Accordingly, these cabinets will be rigidly tied to the respective battery chargers and implementation will be complete prior to fuel i load.
Tying the battery chargers to the MCCs increases the fundamental horizontal frequency of the MCC above the peak frequency of the Control Building spectra, thus reducing the scismic loading. Therefore, the seismic qualification of the MCCs is not affected.
- b. As in the case of 3(b) above, the entire vendor's test report will be reviewed again and anomalies and basis of
. disposition will be included in the SQRT package on file at the site, i
Equipment Specific Items, Page 3
- 5. Service Water Pumps - 1P41*P-003 Package No. SH1-51-1
- a. Provide information regarding the analysis to determine the pump's lowest natural frequency with consideration of the fluid mass.
- b. The analysis indicates that fundamental mode natural frequency is less than the pump rotary speed of 30 cps.
Provide assurance that no potential problem will arise if the frequencies of high modes are also within the pump speed,
- c. Provide justification of decoupling x and y dynamic -
degree-of-freedom in the frequency calculations.
RESPONSE
- a. The vendor qualification report indicated that the lowest natural frequency of the pump assembly is 22.286 Hz and included fluid mass effects at the pump bowl assembly. A review of the applicable seismic Amplified Response Spectra for this pump assembly indicates rigid range response applies above 10Hz in the horizontal direction and above 12 Hz in the vertical direction. It is concluded that the results of analysis of the pump assembly, including the effects of fluid mass, are representative and acceptably qualify the assembly for seismic response effects,
- b. The minimum pump assembly natural frequency (22.286 Hz) is about 14% above the pump rotary speed of 1170 RPM (19.5 Hz). Therefore, there are no natural frequencies of the pump assembly within the operating speed range and the assembly can, therefore, be considered rigid for operating purposes, as well as for seismic considerations as explained previously. Also, these pumps have been operated successfully, confirming that no resonances are excited.
- c. An independent multi-degree of freedom dynamic frequency analysis of the pump assembly for a coupled x and y dynamic model has confirmed the natural frequencies of the pump assembly provided by the vendor in his qualification report. Review of the independent analysis results also verifies the original choice of decoupling the x and y dynamic models of the pump assembly.
- 6. Main Steam Isolation Valve - 1B21*AOV-081
- a. Provide justification that the rapid closure of the valve which is not accounted for in qualification has negligible effects on the operability of the MSIV.
- b. Assure proper surveillance to insure adequate columns lubrication.
- Equipment Specific Items, Page 4
RESPONSE
- a. Stress Report 22A6416, (Revision 0, pages 1-4, 7-8, 143-150) provided in Attachment 6 shows all the load combinations considered in the evaluation. The MSIV does not close any faster during the dynamic event as compared to the normal situation. The closure time is controlled by a self-adjusting hydraulic control valve. The effect of the dynamic response of the extended mass of the MSIV actuator was analyzed as part of the piping analysis. The calculated forces and moments were than compared to the
. allowable and documented in Stress Report 22A6416, Revision O. Further, to assure each MSIV can withstand rapid closure, each MSIV was tested as part of the production testing sequence.
The stress in the MSIV seating area is not significantly affected by dynamic loadings. Attachment 7 shows the stress variation at the valve ends. At the seating area, the stress is even lower due to heavier wall thickness.
The MSIV is routinely stroke for checkout in order to assure the effects of closure have not overstressed the MSIV seating area. The effects of closure are determined by a leak test.
The impact force for MSIV closure under faulted conditions, with steam helping to close this valve, is not any greater than for the routine checkouts stated above. This is so because the stem and disc motions are controlled by a set of flow control valves and a hydraulic damper. Any excess closing force due to dynamic loads is absorbed by the .
hydraulic damper.
The stress at the disc has been analyzed and found to have a maximum stress of 14,550 psi vs. an allowable stress of 19,900 psi @ 575 F.
Based on the above, so-called " rapid closure" of the valve has a negligible effect on operability.
- b. GE does not believe special lubrication of the columns, over and above that recommended in the vendor's maintenance manual is required. This position is based on the fact that this MSIV actuator always closed properly during the seismic test, even though it exhibited some hesitation on opening. Closure of the MSIV is the safety mode, and is aided by the springs designed into the actuator. Opening of the MSIV occurs against the spring force, and accounts for the different behavior in closing vs. opening.
Stroking behavior of the MSIV is routinely checked to verify proper operation of the valve.
Equipment ^ Specific Items, Page 5
- 7. RCIC Turbine - lE51*TU-005
- a. The turbine in the plant (GS-1) is not the same as the one in the~ test report (GS-2). Establish dynamic similarity.
- b. Since the qualification is dependent on some modifications, report to the NRC when implementation of the modifications is completed.
RESPONSE
- a. Attachment 8 provides the General Electric memo which establishes dynamic similarity between the tested and installed turbines.
. b. Attachment 8 provides three Field Disposition Instructions (FDIs) which outlines the modifications required on the Shoreham turbine. These FDIs are scheduled for completion prior to fuel load and LILCO believes that these modifications will provide similarity between the tested and the in-plant turbine. Upon completion, the NRC will be notified. ,
- 8. Pressure Transmitter -
IC41*PT-002
- a. Field mounting configuration is different than that in the test. Provide assurance that the resulting response spectrum at the equipment mounting location would envelope the required response spectrum at the mounting location in the field.
- b. Documentation that justifies the similarity of the untested models to the tested units should be included in the over-all qualification documentation package.
RESPONSE
- a. Attachment 9 provides additional test data which verifies dynamic adequacy of the differential pressure transmitter.
- b. GE PPD numbers 145C3240, 163C1558, 163C1560, 163C1561, 163C1563 and 163C1564 all refer to Rosemount Model 1151 or 1152 differential pressure transmitters. An excerpt from the Rosemount test report 2758 (Attachment 10) states that models 1151 and 1152 are mechanically identical. Differ-ences are due to requirements of material traceability for pressure retaining parts for the 1152 model and the use of non-Teflon wire in the 1152 assembly. Neither of these differences would invalidate the applicability of the test results in the qualification test report to the untested model. Since the 1151 and 1152 models are identical in construction and dimension, LILCO concludes that the 1152 model test results are applicable to the 1151 model. This test report will be included in the SQRT package.
Equipment Specific Items, Page 6
- 9. 120 Volt Distribution Panel - 1R35*PNL-R2 Package No. SH1-124-1 Field mounting condition is different than that in the test.
Frovide justification that the qualification is valid from the viewpoint of dynamic similarity.
RESPONSE
The distribution panel was bolted by its four support ears to a fixture mounted to the test table during qualification testing.
The fixture consisted of two braced structural members with a full height support plate between them, simulating a typical plant wall.
The. field mounting of the panel assembly is by bolting through the four support cars to a wall mounted unistrut frame. The natural frequency of the support frame is well above the rigid range of the applicable required response spectra. It is, therefore, concluded that the field installation acceptability simulates the tested condition and will not alter the conclusions of adequacy.
By way of background, the original biaxial multifrequency qualification testing program resulted in test input levels that were generally 60% or more above the required level. The assembly was subsequently fragility tested to even higher levels, which assures the adequacy of these panel assemblies in a very conservative manner.
- 10. GENERAL The SORT disagreed with GE's use of single frequency / single axis testing method to qualify some shipped loose items. The Applicant was requested to provide the description of the items for which this qualification method was used.
RESPONSE
A list of Shoreham equipment qualified by use of single frequency / single axis testing is attached. Those items which are in iba category of GE shipped loose items are noted as such. 1 provides a listing of BOP equipment qualified by this method. 2 provides a listing of NSSS equipment qualified by single frequency / single axis testing. The attachment provides the following:
- 1. C&I devices on Local Panels See Table 2 from DRF A00.992, Rev. 1, Local Panels
- 2. C&I devices on Control Room Panels See Table 2 from DRF A00-992, Rev., 1, Control Room Panels i
Equipment Specific Items, Page 7
- 3. C&I Ship Loose Devices See table entitled, "Shoreham' Ship Loose Devices Qualified by. Single Axis / Single Frequency Testing" Note that several of the Local Panel and Ship Loose devices are the same device model, as identi-fled by GE PPD Number.
- 4. Mechanical. Equipment ,
B31-FO31 -Limitorque actuator on Recirc Discharge Valve E32-B001 MSIV LCS Heater P
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- IB21*MOV061 1E11*MOV037A 1E32*MOV022D IB21*MOV062 1E11*MOV037B IE41*MOV041 1521*MOV063 1E11*MOV038A 1E41*MOV042 1321*MOV064 1E11*MOV038B 1E41*MOV047
.1E11*MOV039A 1E41*MOV048 1B21*MOV068A 1521*MOV0683 1E11*MOV039B IE41*MOV049 1B21*MOV06CC IE11*MOV040A 1E51*MOV031 1B21*MOV068D 1E11*MOV040B 1E51*MOV032 1821*MOV083 1E11*MOV041A 1E51*MOV041 1E11*MOV042A 1E51*MOV042 IB21*MOVOS4 1B21*MOV085 1E11*MOV047 IE51*MOV047 1E11*MOV050 1E51*MOV04E 1E11*MOV031A 1E11*MOV053 IP41*MOV033A 1E11*MOV031C 1E11*MOV032A 1E11*MOV054 IP41*MOV033B 1E11*MOV032C 1E11*PCV003A IP41*MOV033C 1E32*MOV021A 1P41*MOV033D 1E11*MOV033A 1E32*MOV021B IP41*MOV042A 1E11*MOV034A 1E11*MOV035A , 1E32*MOV021C IP41*MOV0423 1E11*MOV036A 1E32*MOV021D
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5 F2 CS.HS N f 1744eUC-093 4AIIT C00LERS-295VS 274 PO SUFFALO FORGE SC000 YES 80H-t?781 SA 4
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SC154 YES 44540-1 SA/ SAT to FE CS M IT44eA00040 #8 REFUEL LVI. EXHAUST 319 CO P0HERS REGUL CO P0HERS REGUL SC112 YES 43812-1 SA/ SAT 24 FE CS.MS N 1T;4sA00091 RS POT CONTAM AREA EXil 319 i
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SBTsSIf8GLE FPEQUtilCY QUALIFICATI0tl HILEST0tlES I* CS aCOLO SitUT 00194 P : PIPE ffDUNTED A =RttVALUATI0tl ColtrLETE PC 2PRittART C0tlF. BIA%IAL TESTIllG D z0VCT II0tRittD B rRtqtitST FOR QttAL OR BID ISSUED tt0fEs 88UttntR Itt PL rPEDESTAL SC zSEC0tl0ARY Cotti. ' TYPE flTilG' COLUtti IS D2 s0YllAIIIC ArtALYSIS / rLocAftp Ott Coffr. C zS/H Rf Cofif tfilaATION TO LILCO )
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LILC3 00CHET 50-322 QUAL TYPE SAFE WUAL ! !
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SC000 YES 127514 IST 40+ F CS.HS H n 1C41eLT ete SUPP POOL 404 CD ROSEHOUNT 404 SC098 YES 127514 HBT 40+ F C3.HS H ;
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1293:TE 113 WVe9tFMJ DISOtARGE-tFT 494 CD ROSENDt#ff plt 8 pet F4 M B 4
1293sTE 132 RvettACL DISCttARCf-tFT med CD ROSEttCUNT PL28 teT Ft H S ;
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122VaTIS111R LCPI ATS 438 ED ASCD SC112 YES 19404 HDT 13 F CS.HS H CS ECOLD SHUT 00188 P PIPE ItOUNTED $8TrSINGLE FREQUEllCY OUALIFICATItti IIILEST0tlES REVISION 4 -HOVEleER 1982 )
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SPEC BIV. BLDS AVA!1. OUAL Suet. TYPE SAFE OUAt. (5 MARM i I SESCRIPTItRt H0. RESP VEteOR ELEV IttsP REPT HETH FREQ HTtG SHT9M ' STATUS g 14 Rett 319 CD FISHER CatT. 943 YES CD74-te SA 49 P4 CS.MS M j 1P41aTCV9G CImlL WM & #99VS HC-3 5
319 CD FISSIER CCHT. 943 YES CD74-29 SA 49 P4 CS.HS H fg
- 2P41 TCV949 - CNTRL WH & WSSVS HC-4 .
I ACU-19 C00 Lite 8 COTL 319 CD FISHER CCHT. 953 YES t-24451 SA 25 Pt CS 18 1 I M 17.TCV9t1 l
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ACU-7A COOLING 1RIIT 319 CD FISHER CONT, 971 YES t-24451 SA 25 Pt CS M ,
1N41 TCV921 319 CO COPES VIA. CAM 971 YES 19.3.115 SA 124 Pt CS.HS M 1MB9eA0V944 CHILLES NTW ISO BY 1H50eA0W949 CHILLES MTR ISO BY 319 CS COPES VULCAN 975 YES 19.3.115 SA 124 P2 CS.HS M , f 1950eLCV9tS CM SYSTEM A MANE 1F 319 CD COPES VULCAM 972 YES 19.3.115 SA 124 Pt CS.HS H {
FIRE DET SM STA 319 EO POHERS REG 944 YES 43912-1 teT 24 F3 C3.Ils M (
i 3He3 sets 991 43912-1 lef 24 F3 CS.Its H IM43eHS994 FIRE DEY SM STA 319 EO P0HERS REG 925 YES f{F 1MleFS 913 ACU-14 AIR FLOM 319 ED PCHERS RES 931 YES 43912-1 teT te Ft CS.HS H g f III41eFS 917 FM-29 AIR FLOM 319 EO P0HERS RES 944 YES 43912-1 HBT 24 Ft CS.HS M f;'
319 E9 POWERS REG 944 YES 43912-1 teT te Ft CS.llS M g
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EO P0HERS REG 999 YE3 43012-1 teT 24 F2 CS.HS M i DIl41sttTT921 ACU-14 COOLING CNTRL 319 943 YES 43912-1 MBT 24 Ft CS .HS M 1 M 1oltOO931 FW939 OUTD00ll AIR 319 EO Pf1HERS REG 319 EO P0HERS RES 944 YES 44549-1 teT 17 FE CS.HS M 1N4IntWO932 FW 939 ENHAUST AIR ,
EO P0HERS REG 944 YES 43912 1 HST 24 Ft CS.HS M ;
1X41stt00935 ACU-14A DISCHARGE AIR 319 319 En P0HERS RES 044 YES 43812 1 teT 24 Ft CS.HS M
, 1N41stee934 ON FAN FTI-29At a 319 ED P0HERS REG 937 YES 814057-1 Imf 21 F3 CS.IIS M
! IN41ollOO939 F W 72 OUTDOOR A!W 319 EO P0HERS REG 991 YES 44057-1 IST 21 F3 CS.HS M l IN41stID0999 FW 72 ENHAUST AIR EO P0HERS REG 035 YES 44057-1 HST 21 F3 CS.HS M IN41mit00041 FW 72 RETURN AIR 319 319 HD P0HERS REG 944 YES 44057-1 HBT 21 F2 CS.HS M
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, 5 LILC3 00CMET 50-3tt ACTIVE BOP QUALIFICATION LEVEL (220 litltS3 PAGE e tenart tgu!99kWT SPEC OIV. BLOG AVAIL OUAL 004t. TYPE SAFE GUA4.
IAAeER #ESCWIFTIERt NO. RESP WDOOR ELEV IttSP REPT 91ETH FREtt lifHG SHTOM STATUS f., {
319 EO PCHERS RES 823 YES 1901-4 SMSAT 24 F M M I m lerte.vC14 WENT CONTRtR. PAMEt.
319 EO POMOIS RES 925 YES 1901-4 SuSAT 24 F M M ,3 4 1 mlePlt.WCIT WEfff CONTWCL PANEL 1 m isPfe.VC10 WENT CONTWG. PANEL 319 EO PONEWS REG 025 YES 1001-4 SA/ SAT 24 F M M i[
t 319 EO POHERS RES 825 YES 1991-4 SA/ SAT 24 F CS.MS M q 3
13t41mPet.VC19 WEMT CONTROL PANEL I n teret.Wt*tt VENT CONTWOL PANEL 319 EO P0HERS RES 925 YES 1001-4 SA/ SAT 24 F CS.NS M (! t 319 EO POWERS RES 844 YES 1901-4 SA/ SAT 24 F CS.MS M 4 I mlarte.VC21 VDff CONTWOL PANEt.
111thTt 018 FM-Tt DAfFER CONTWG. 319 EO P0HERS RES 030 YES 43812-1 teT 24 F3 CS.HS M ( '
l 1R41:T19031 FM-39 CONTROL 319 EO PONERS RES 848 YES 43812-1 teT 24 Ft CS.MS M g i 1241:TT-801 RM TUF De 319 EO P0HERS REG 025 YES 43812-1 Inf 29 F2 ft M f{
i-RM TDP Itc 925 YES 43812 1 teT 24 Ft M M ,j
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y 1X41 TT-904 WM TU F Its 319 EO P0HERS REG 044 YES 43812-1 teT 24 F2 H H q R9t TEtr Ite 119 EO P0HERS REG 044 YES 43812-1 teT 24 F2 M M IX41:TT-803 In tsTT-See CMILLER EQUIP NW TDP 319 EO P0HERS RES est YES 43812-1 teT 24 F2 M M q .
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1X41177-007 3
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319 P0HERS REG 030 YES 44057-1 let 21 F3 CS M 1X40mIIO0031 FN-te OUT000R AIR EO '
3 1X49ett00032 FN-39 MOT DAFFER 319 EO P0HERS REO 630 YES 44057-1 teT 21 F3 CS M g 319 EO P0HERS P!G 038 YES 41057-1 IBT 21 F3 CS M 1X40mH00033 Fit-te RETURN AIR P0HERS REG 025 YES 1001-4 SA/ SAT 24 F CS.HS M 1X40 Pt4.VC13 VENT CONTROL PANEL 319 EO 025 YES 1001-4 SA/ SAT 24 F C3.HS M
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- ; }i LILC3 00CHti 30-3tt 80P CUALIFICATION LEVEL 8220 ITEttsi PAGE 9 l
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24RII9NWT SPEC BIV. SLDO AVAIL QUAI. QUAL TYPE SAFE QUAL MARM M4ett DESCRIPTIERt HO. RESP VEte0R ELEV IPCP REPT ttETH FREO HTIIG SitTON STATUS g IN40sPtLVC15 VENT C0tffect. PANE 1, 319 EO P0HERS RES DES YES 1001 4 SA/ SAT 24 F CS.NS M fi 1M41eA00937 ' OtTRL RH ISOL 319 ED POHERS RES 843 YES 44540-1 teT 27 F3 CS.HS H n f 1541eFS 011 F4tS OfTRL 319 ED PCHERS RES 043 YES 43812-1 teT 24 Ft C5.HS H j, ACU-7 AIR FLOM 319 to P0HERS RES 943 YES 43812-1 MBT 24 F3 CS.HS M q l IN41eFS 912 1R41 EMS 438 1M41e40V934 CONTRtL 319 to PCHERS REG 044 YES 43812-1 feT 24 FE CS.HS H l it ACU-7 OffRL 319 EO PCHERS RES 043 YES 43812-1 teT 24 F2 CS.HS M ,
IN41ol2-921 IN41oHOD933 F& tS DISol AIR 319 EO P0HERS RES 843 YES 44540-1 HE Y 27 F2 M N' {;
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I IIllePft Stt R958VS HOtt!TORING PANE 332 PD t#C 043 YES 45493-1 teT 13 F M N 4 ii 1111ertL-9tf Cotti R30H HOHITOR PtL 332 PO 99C 044 YES 45993-1 H5T 14 Ft M M 1911oPtt-924 C0ffT 900H HOHITOR Pet 332 PO MC 044 YES 45493-1 teT 14 Ft M M 1011ePIL-927 CCHT RM VEfff IIONIT PtL 332 PS MC 043 YES 45493-1 H8T 13 F M N lillePft-944 POST ACCOUNT HON 312 PO t9C 043 YES 45493-1 teT 14 F M M g j
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33S PO TOC 043 YES 45493-1 teT 14 F M M l' II11ertL-947 POST ACCOfff itDNITORS 943 YES 45493-1 lef 14 F M N t 1111mptE.-940 POST ACC0 TIT HOHITOIIS 332 PO telt
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332 PC tet 043 YES 45493-1 HDT 14 F M M 1011ePfil.049 POST ACCDHT tsaritTORS II11sPtt.-999 RAO ftOH PtL 332 PD IOC 043 YES 45493-1 HDT 4 F2 M N
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CR AfflIIOZZLt 332 PO teIC CB043 leT F CS.HS O/Z II11oRM-927 ED DELPHI Its 043 YES 1035-S SA/ SAT 29 Ft M M IT'8.RM-IS HYDRO REC 015 CONT CA81 344 HYDRO REcolm CONT CA81 344 EO DELPtC Tfe 043 YES 1935-S .SA/ SAT 29 FE N N
_ 1T484H-te P = PIPE 910UllTED SBT=SittCLE FREQUEHCY OUALIFICATION HILESTot4ES REVISICH 4 -NOVEllOER 1982 C3 SCOLD SItUT 00600 DA e5YIIAHIC AIIALYSIS e TEST ARTICLE STAXIAL TESTING A mREEVALUATIott CottrLETE F sFLOOR IIOUttf EO 8 rREQUEST FOR QUAL 09 DID ISSUED NOTE: flUtlatR Ill IIS mil 0T STArIDOY Op a QUALIFIED BY H etitITl8tR CS OR HS C sS/84 RttottittilnATI0tt TO LILCO ' TYPE liittG' COLUllH IS 83f etIULTI.F RE 00t flCY PIPIllG AttALYSIS 2 rPAsiiVE Ifrit O 209Al. DOC RECEIVED QUAf tTITY Ol' ITEttS.
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404 CD ROSEtIOUNT 847 YES 2747 SAT 35e Ft CS.HS M 1R41:TE 021 ACU C00 Lits CONT ISOL SYP V A0V48A.494 407 CD MAGitETRot. 043 YES 43235-1 IST 17 Ft HS M 3 1H50eLS 902 407 CD flAGttETRM. 043 YES 43235 1 IST 17 Ft itS M ,
Itt50mLS stb CM SYSTEM A IIANEUP 407 CD HAGNETROL ett YES 43235-1 SAT 17 F3 M M 1R43mLS ett FUEL OIL AtAt OAY TM 407 CO HAGNETROL 022 YES 43215-1 SAT 17 F3 M M 1943stS 907 FUEL OIL AUX OAY TM etS CO FISHER 971 YES C074-St SAT 23 Pt CS.MS 99 1940:A0V040 meSVS & CWAC 423 CD FISitER 971 YES C074-82 SAT 23 Pt CS.MS M IttSOIA0V043 R93VS & CRAC CD FISHER 625 YES C074-82 SA 23 P3 CS M 1P41:40V014 01ESEL MN t-134 OUTLEY 423 440 CO PERitUTIT C8072 YES telt 9 3-f te-CZC SA 40+ P2 CS F/Z
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L1LC3 00CHET 50 322 ACTIVE BOP QUALIFICATION LEVEL 1393 ITEllSI PAGE 1 { j i
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- 2 3 4 OPER LOAD.8'S OPERATOR 4 OUAL STATUS (*
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REVISI0tl 9 -HOVEltBER 1982
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I. , . _ O SMONTHf JOS HLS. LILCD 1 494 St !!t St LIST 3-SORT ACTIVE STCHC & HESSTER ENGINEi GEllETAL EttCT;IC COTE CORPOR". TION EQUIPittHT HSSS OUALIFICATIO*t LEVELt151 ITElfSI ItuH DATE 11/04/92 RUtt TIl3 14.14.C3 PAGE 1 O 4 , HARN ESUIPMENT St SLDO AVAIL QUAL QUAL TYPE SAFETY quel !. p t%stitR DESCRIPTICH NO. VttfSOR ELEV IHSP REPT HETH FRttl HTNG FUIC STATUS gj. {
?Dtle6-9 3 CERetMBEMB CMAPSER 921000t St SC000 YES DNF-A00T94-11 SA 49e P HS.CS S *{
t Ittis0-964 C0retMSitC CMafBERS R21D004 St SC000 YES DRF-A00194-11 SA 40+ Pt HS.CS S g 6 f g 18,tlet-995 CeretNSIMO CNAletRS 8210004 GE SC000 YES DWF-A00794-11 SA 40+ P14 HS.CS S IttleRV 992 Rft!EP WALVE St1F013 TARS ROCM PC099 YES VPF-5405-3-1 teT 40+ P11 CS S n 1stleA0V941 ISOLATIort VALVE-MS 821F0tt R0064 ELL SC002 YES HESE-24122-2 SA 8 P4 CS.HS S 13tlaatp*943 ISOLATION VALVE-HS 821F028 ROCHHELL SC002 YES HEDE-24122-2 SA 8 P9 CS.HS S ,3 IttleFE 90t FLOM tLttittti 821H005 PERHUTIT SC007 YES SA P4 H 8/Z ) 19t1311 043Y TitFERATUeTE ELEHttti 32170010 PYCO T002 YES DV14SC3094 SAT 40+ F4 M D g ; 1881:TE 099 fttPERATuft ELtiltitT Bt1Helt PYCO T059 YES DV195C3224 SAT 40+ F4 M D 13tleP3 Ott PRESSURE SMITCM 821tt015 BARMSOALE C5037 YES DV144C5359 SAT 33+ F4 M D 4
$ 'k ISttsTE 943X ftietRATURE ELEllEMT 821tt014 PYCO 7059 YES DV144C5359 SAT 40+ F4 H D rl 192121E 903 fttetWAftsit EttttElfT 821tt040 CROUSE-MI T003 YES Dvl59C4520 SAT 100 P M D e 4 !!11sP. 991 RECIIPC PUlr & HOTOR 831C001 BJ/GE PCOTO YES 204833C001-MS-1 SA . 400 Pt M S . . 1831 stew 931 RECIIPC SUCTION VALVE 831F023 ANCHOR , SC017 YES 305HA441 SA 41 Pt M S 1831mHOW932 RECIRC OISCHANGE VALVE 831F031 AtlCHOR SC014 YES SA/DA Pt M 8 ,
1031tF1 010 RECIRC FLOH Ettti 831H013 BIF SC000 YES SA P2 M 8/Z 1811s.YE 025 YtlPERATUtt EttHENT S3114023 CROUSE-MI PC045 Yt3 DV159C45te SAT 19 Pt M D i 1C11eHCU.91 CRO HYDRA CONT UNIT C110001 et SCOTS YES 303tlAS53 HST t 137 CS.MS S f l iC11sSOV044 ItCU SalttIDIO VALVE C11F009 ASCO SC043 P CS.MS 8 i ) C3 afortTROL WLOS P sFIPE IIOUtITFD SBTsS!!CLE FREQUttaCY 00ALIFICATION IIILEST0tlES REVISION 4 -HOVttBER 1992 )
"CS aCOLC sitUT 00Htt PC ePRIlfARY Cotif. BI ARI AL TESTitle A enttVALUATIOtt COIPLETE l D3 LOvtlAll!C AtlALYSIS PL sProtSTAL SC eSECottDAtty C0tif. S mREQUEST FfNt REQUAL OR 810 ISSUt0 Petta ##UtlOtti 1H F sFLOOR HOUtiTED QP sCUALIFIED BY /
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l%TelIULTI-FREQUtttCY RM ERA 0lfASTE Y altAlti Sitt. TUtstEL E stIARDHARE H00!FICATION REQ'O BIARIAL TESTitC SA sSTATIC AtlALYSIS H altt11titR CS OR 115 F QUAL CCC APVD A FItto i:STel1ULTI-f pt QUtilCY SATsSillGLE FREQUtf 8CY Z sPASSIVE ITill G sSQRT PAPER C0ftPLETE SillGLE AXI AL TEST!!C SIttGLE AXIAL TESTING ($'1RT PAPtit tiOT H rCOP1ES OF 00C 10 DISTRIDUTION } _ REQ'DI
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STOME & WESSTDI EMBINEE21tC CORPORITION RUpt BATE 11/94/02 O ^i! *! 3 JOB teseER 11409 3-SOR T G*HERAL ELECTRIC CATEGORY I EQUIPtIEHF RUM TIttt 14.14.43 g , LILCO 90CMtf SS-Stt ACTIVE HSSS OUALIFICATICtt LEVEtt151 ITEttSI Pact 2 i MARIt tWftPHEWT SE OLDS AVAIL QUAL qual TYPE SAFETY OUAL ) 4 ) ismett
- DESCRIPT!cM NO. Vtte0R ELEV ItfSP REPT HETH FRtt flits FUllC STATUS g ) j 3C11eAONG1 MCU DIAplWAWt VALVE C11F010 lett SCOTS YES SA P CSett$ B k l '
) IClasA0 Net MCU DIAPMRAEM VALVE C11F011 1994 SCPat YES SA P CS.MS S q 3C11eLS M9 LEVEL 3061708 C11M013 MAOMETROL SCOTe YES SHIP LOOSE S4T 396 F2 F -
- j. is ,
) IC11eLS 999 LEVEL SMITOt C11N013 MAGMETROL SCOTS YES DV159C9341 SAT 39* F4 M D q l( t IC91 TM-903 SLC STORAGE TAtet C41Aest LANCO SC113 YES RA54t/C41-Et SA $9 F M S i i IC91: Tit-130 SLC ACOAtuLATORS C91A003 NYDRA COM SC997 YES DRF C41-tt SA M/A Pt M S g ) IC91eP.Ott STUSY LI4 PtRP&HTR C91C991 tRtION PUH SC113 YES VPF-5517-t t 59T 40+ Ft M S ? y ld IC41sEV 919 tilPLOSIVE Val.Vt C91F9M CollAX SC112 TES VPF3394-34 2 S8T 350 Pt M S l ) q i .. t;. 3C91sTS8914 TD5' SMITOl C91H003 NEED INST SC112 SHIP LOOSE SAT 400 F D/E j i IC91ePT Set PRESSURE TRAMSittTTER C41 NOM ROSttIDIRtf SC112 YES DV143C1543 SAT S F M D ;( ) ,3 ii ICClePI Det PRESStAtt DWICATOR C91R993 ROBT SHAM SC11E YES DV143C1184 SAT 33e F M D .; ) ICS1sTIP-SM TIP VALVE eutDE Y C51J0M St SCOT 3 YES DRF-A00992-M SAT 400 F4 M D ,(( IC41sFT 991 DIFF PRESS 30fft C41M001 IPOSEMUtRtf SC000 YES DV143C1948 SAT Se F M D , IC41ePT 904 PRESS TRANS C41H004 SAILEY SC979 YES DV141C1184 SAT 33e P M D q ). 3C41eCE 014 Core TRAttSetITTtt C41tt000 SALLSOAUS SC030 YES DV143C1599 SAT 3 P M D t 3C41sPtt.-RSP RtiWTE Set? DM Pvt. C41P001 St SC043 YES SAI-Ot90A80PA-B lef 14 F M D q l ) 3CT1sPS 993 PetSSURE SetITCM CTitt003 BARMSOALE Cs931 YES DV149C5359 SAT 33+ F4 M D { It31tt-934 E118001 PERFtX CP SC004 YES DRF E11-1 DA 14 MS.CS 8 ) RMR NEAT titCHANGERS ft 9l It11eP-014 NHR Ptss's almTORS E11C002 SJ/GE SC006 YES DRF E11-11 D4 le F4 HS.CS S } C5 eCONTWG. BLOS P PIPE H0tRITED SBTzSINGLE FREQUENCY QUALIFICATION ff!LESTONES REVISION 4 -NovtteER 1992 S _ CS rCOLO SHUT 00000 PC :PRIttARY CONT. BIAXIAL TESTING A rREEVALUATION C0tFLETE ' 03 rCYt4Aff!C ANALYSIS PL :PE0ESTAL SC MSEC 0fl0ARY CollT. B mREQUEST FOR REQUAL OR BIO ISSUED HOIEt IIUt DER lit F sFLOOR 810UHTED QP sQUALIFIED BY / eLOCATED Ott Cotti. C *S/H REC 0fttErl0ATION TOLILCO ' TYPE HTNG' C0ttAIN IS ) MS SHOT STAfIDBY PIP 3tG AtlALYSIS HALL D = QUAL DOC RECEIVED QUAttTITY OF ITEttS. h 13T:IfUL T I-FREQUEt4CY RH tRA018ASTE T altA1H STit. TIR88EL E silARDitARE tt0DIFICATION REQ'O BIKKIAL TESTIfG SA
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1 c CS OF 07 01 62 f CURRttff DATE 11 13 82 ', SHeptMart ItJCLtedt POMtt STATION SHORCMAM CAft00RT I EQUIFittNT CHAtIG! RECORO Sfotit AtID ktnSTER tt#GIttttRIteG CCRPORATION l ; t EFFECT OM * ' [ DATE OF ISSUt EQUIP. EFFECTED NATURE OF CttAff5E SEI5? TIC QUAL. 90Ct#tttff 8 .................. ............. ADDITIONAL RELATS TO DE ADCED TO CAT.1 ItASS CF ADOCO ; F."tt15 99 00-02 1Htlertt. 040 - PAtttL REL ATS tit 0LIGIOtt HOMt r 1011ertt. 021 ATTACittttfliS TO SHIO / RAD. It0HITOR. STS. ItASS CF ATTACIGttttTS { F49926J 99-09 82 tt[CLIGIOLE-t:OttE : i 99-27-02 1tttleRM 40.41 CLEARAtlCE PRCO. FOR 02 DOTTLE RACMS tt00!FICATIO!I IttCCCPORAf t0 4 i P.3930ft It110 CALC'JLAT3CfI.ttotit t A00C0 ftASS OF LUISTRUT F4 tetS 09 30 82 1Z97pPit.ERI.4 ADDITIOHAL SUPPORT FOR tt00ULE CASES TO CCitr0Rf1 HITit TEST tt0UtfTIllG CotCIT10ftS. FPAt!E I41LL STIFFr!I PArttL l'- { }, I CAT. 1 PAfttL .itClit C F.3939L ItttleRM 40.41 SUPPORT OF 'HARAtlITE I' FIRE BARRIER SitALL PLATES ADDCD TO FRAHE 10 05-62
.t#0 IttPACT TO QUALIFICATI0tt . h *l)
D > 's MASS OF SODED C0tIDUlf (D et ATTACH!ttflT OF 1* DIAffETER CCtCUIT F.194818 10-07-02 1RZ9eHCC.1119 ifECLIGIDLE. f40!st .h'( oo :, ' 10 26-82 174TeUC.174.8 NOZZLE SUPPORT FOR UNIT COOLER APPROVE 0 Of CALCULATION F.43145 N : et ' 19 3 F.3945tt 11 09-82 1011erf t..tl.tt la DIAttETER C0tIDUIT ATTACitttttF TO FLEX C0tIDUIT USED Ctl B tt ; ALL COttitCT10ttS-t40!IE * ;i CAT. I PAtlELS
.O OATTERY CitAttGE/DISCtfARGE AtetETERS ADOt0 ;
F.~.289 7 IN PROGRESS 1H11sttC5-01
- TO ttAlta CotlTROL 00ARD ,1 i
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- I ePS-1053 IP50=PT-116A ePT-1160 f
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Attiachment 4 'Sp2cific Item No. 1 STONE & WEBSTER ENG'NEERING CORPORATION $ ~/// - A 7 5
,_ -. CALCULATION
SUMMARY
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l' O A CATEGORT / CODE CL ASS CLIEwt / PROJ ECT Lit ce / :nos Citm chit,- / / SUSJECT / TITLE / l, 6GfL.WC fice/ cP }/op:,'4G /d Unit Co*l.4ft T /T'/4 .x uc cat 4, B; oh. A, 8 fo rt. 'Qf:1~ sitsoir~ Ah 2 R*' A / ^! G C , Ertr<. B, / , C9JECTIVE OF C A L CI, L Aflo ts
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CALCULATION M ETH O D /A SSU M P flC N S L f/ w s c A u v u.e rto a : /~item ST,4ssbit,e b EA'C;WCirc-.vS *TTCT2* o ie - A /_' C usso 70 BCn~ot.m:^!C TWrk>usik6 bCFede-rtant,
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SOURCES OF D ATA / EQUATIONS
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'3 STONE G CEBSTER ENGINEERING CORPORATION ,
CALCULATION SHEET
- s wa m CALCUL ATION IDENTIFICATION NUMBER ^
J.O. O R W.O. NO. OlVISION 0 GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE E IIGO M 2 NMis) 33I-I C 2. c I
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>> E = 2 9x 10 ' n r ; r= +n 2'- 0. iso 4 x - < n. 02 ? .= iv "
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... . . .. . . : ~ a . : . . . . . . . - a . STONE & CEBSTER ENGINEERING CORPODATION rJ.- CALCULATION SHEET asco es CALCULATION IDENTIFICATION NUMBER J.O. O R W.O. NO. DIVISION & GROUP CALCUL ATION NO. l OPTIONAL TASK CODE PAGE If 600. 9 2 NM(y ) 33 l-( l CEC i
~
di e & P6
~
4 QA + W Hr= R.S [g - F9RM Fhc~~0 2- F% A Tliit/ 7 u.3 L%% R S ECT.' S// , hs = Ej h&P N 40 i.
,3 f0% THE SHEh DE Flee,9</ AS'umE Terra c>~'/CEN 2,2 53 Lpp 1//I ES ACTitJA AT THF J)lSThWCE S.H'l F ? St^ WE .Su?=?R' J= ~'5 ir HOUSING-is G ~6HER12 HODULus OF ELN Tic /TJI: G = 3= 5 = lS f?I.? '. .s. ** ~ 4xS$by$49 -5 en c[3 * /y,5xl.9' xI/36 = 0* I f 19 23 ** 4 9"'S144; Tb""L h t.s o L A C 5 MENT 0.C THE es 4=[/+[+[=/,2x/v'g I
a 8 v/O ~$ f, / <.- ') # ,
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-~-.~.y-..- _ _ . . . - .
w.- . Attachment 5
.>/* _ / . Specific Item No. 2 ~~
APPENDIX E 13. 2. b> _DESCRIPTICN AND VER!?ICATION OF THE NON-LINEAR IMPACT ANALYSIS E.1 OBJECTIVE AND OVERVIEW The purpose of this appendix is to describe and provide verification for a special purpose computer program (called RACKOE*) developed
- primarily to analyze fuel rack behavior resulting from seismic dis turb..s c es.
The fuel simple is considered support to rest in the rack at its center with a (hinge) between the two. With the seismic disturbance,
- the clearances between the fuel and the box walls lead to impacts thus making the analysis a non-linear one. ,
The space between the fuel and the rack wall is filled with water so that as the fuel and the box wall move relative to each other, hydrodynamic forces are set up due to the acceleration of the water . These forces are exerted on the fuel and rack structure . Methods described by Fritz (E1) and Dong (E2) are used to determine these hydrodynamic forces. Certain special features or options of RACKOE are discussed in attachments to this appendix. For example, calculation of the structural damping matrix is described in Attachment E-1. Friction ' with sliding behavior is another such option for fuel racks that are not tied-down to the ground (i.e. k pool floor) or for fuel that is allowed some translation within the confines of the box The valls. p formalism loss of generality.used allows RACKOE to treat multi-stick models witho The input preparation for the connection matrix, however, is more complicated for these models, so these multi-stick todels deserve special attention in the attachments The plastic . l olement option is also described separately. ' " The following sections describe the basic feature of RACKOE . l The input to the mcdel is an acceleration time history havingpoints i nt typical time intervals of 0.01 sec. The displacement and velocity n uRACKOE is an acronym for rack analys s considerin g kinetics of eartncuakes, e non-linea- #4a4 *e element program developed for Wachter Associates Prof. W. F. Stokey of Carnegie-Mellon University, Pittsburgh .
. ...- .~.------:- - ~- -- - - .__
2. i of the ground are found by integrating the acceleration curve twice, however, these two quantities are not needed for the determination of i the structural forces and displacements. A verification of the basic p one-stick fuel model with fluid coupling and fuel to rack clearances with contact springs is given. This verification consists of a comparison between ANSYS (Ref. E3) and RACKOE results using identical models and input. b E.2 MODEL DESCRIPTION For the sake of discussion, the 8 mass model used for ANSYS verification is described as an example. This model is illustrated in Figure E-1. The numbered and circled masses Q typically represent the following: Mass No. Parts .
~
1 1/7 rack mass, 1/7 fuel mass, base mass 2-4 2/7 rack mass 5-7 2/7 fuel mass 8 rotary inertia of the fuel . Some fluid or entrained water mass may be included in these masses, but here they are considered to be included in the hydrodynamic mass I matrix. The terms in this fluid mass matrix will be outlined assuming the above masses are " dry" masses. The numbered and lettered squares in Fig. E-1 refer to flexible elements.
~
The CTAC formulation is used to find the stiffness matrix for the
~
numbered elements. L. Flexibility Representation r-
' l-3 Bending and shear flexibility of the rack 4-6 Bending and shear flexibility of the fuel a-f Local flexibility of the rack and fuel elements where they meet. No forces are exerted on these ". springs" until the .
relative displacements of the masses ' exceeds the clearance distances.
- 7-9 Local support flexibilities E.3 THEORY The governing equations will be written explicitly for a two mass system and then extended to a general multi-mass system in matrix form: " M W eE** ^ HW '** .m <e.e.mm , w - etw a w ww * *<
.- ... - . .-..:.--..-. ~ - - -- ~ ~ - - - . '3. "l*1 "~ Nil *l-k12*2 + F,1 + F yyy+F12*2 x + Fyy"Z -Cyyiy-C y2 52 (E-1) l l
l m2 *2 =-k21*l-k22*2 + Fs2 + I21*1 + F22*2 + Fw2 <21*1<22 2 . (E-2) 1 1 where my = mass i xy = displacement of mass i ,
-kg3= the force exerted by the structure on mass i due to a unit displacement of mass j F g3= hydrodynamic force exerted on mass i due to a unit acceleration of mass j, described e.g. in ,
Fritz (loc. cit. ) . (F gg usually negative, others positive.) Fyy= fluid force extened on mass i due to a und 1 acceleration of the wall.
-C;.3= damping force exerted by the structure on mass i due to a unit velocity of mass j .
F,1= force exerted on mass i by the gap spring l
.- 2 = ground displacement l In matrix form equations (E-1) and (E-2) are ~ . "l~I ll -F 12 -kyy-k12 [*1\ ksi F ,1 -C yy -C l2 1 t .. = -k q K+J + ?+ 4. (E-2) ~ -F -k F '
21 "2-F 22 I
*2 21 22 *2 . s2 [F,2 -C21 -C22 *2 em -.7
.,l...... -- -- - - . - - - - - ~ . - - - - - . .
l
, 4. . l Solving for the accelerations yields: . Xy m -F yy -F K yy K E 12 12 l s1 wl 11 12 1 ~ =
[ h+ . 5+ [(E-4)
-F E F
- 2) 21 "2-F 22 ,*21 22, X)j fs2] w2j ,C21 C 22,
( 2h For a multi-mass system, the matrix form of this equation can be written as: I fX =(M-F)1((-K)fX + F, + F, 2
- (C $C (E-5) j s i
where f ) represents a column matrix with N entries, N being the
} number of masses, and ( ) represents an N x N square (and in these cases)
[ symmetric matrix. Inthefluidcouplingmatrix(-Fg3) , there are two effects considered; (1) fluid coupling between the fuel and the rack walls, and (2) coupling
. between the rack walls and the pool walls. In general, the fluid .. coupling matrix may be full; however, it is reasonable to assume that only the pairs (2,5), (3,6), and (4,7) , in the example given, will have non-zero off-diagonal entries. Following the guidelines laid down . by Fritz (Ref. El) and assuming that the pool walls move with the
, pool floor, the terms in the fluid mass matrix will be as follows:
-F yy =
1/7(MH + Mont ) ' f
-F +
22 = 2/7f MH + Mf + M[) F F =F (E-6) 22 = 33 44 F 25 = 2/7 + Mf ) F25 = FS2 = F36 = F63 = F47 = F74 F SS = 2/7 ) 55 = F66 = F77 m *- e =% =a , go e. s eus F g .*e to P 9 '*4N"#-b *" * ' ' '
. . . . _ . ~ . . _ . . . . . _ - - m. - _ - -- _m.._-_-_..__.._ - _. . 5.-
where rw is the total rack to wall hydrodynamic mass
~
MH is the total rack to fuel hydrodynamic mass is the water mass displaced by the fuel is the water mass contained within the rack in the absence 4 of the fuel (includes water or poison box water) Mont is the mass of the water entrained within the (inside boundaries of the) rack and the (outside boundaries of the) fuel (=d-Mf). The remaining fluid effects in F, are F,1 = 1/7 ( +
#w2 = Fw3 = F,4 = 2Fwl (E-7)
F = F,7 = C w5 " w6 where M[ is the mass of water displaced by (the outside boundaries of) the rack. Since the racks contain flow holes for coolant, no hydrodynamic mass effects are considered for mass 8. Expressions for M=H are 9iven in Appendix C for horizontal and vertical f j fluid flow. For MH , Dong (Ref. E2) recommends the "added mass" approach, Mf = C,Mf, where C, is of order unity for uncanned fuel assemblies. For the example considered, C , was chosen to be 2.75. For typical LWR fuel with pitch to diameter ratios - 1.3, a lower bound on C ,of 1.5 would be a reasonable estimate. With the close proximity of the box walls, the assumed value is probably more reasonable. For channeled - fuel assemblies, C ,would be quite high. In the limit C ,
- oo, the rack and fuel will move together and the analysis can be shown to degenerate into a linear one.
E.4 METHOD OF SOLUTION In the program RT.CKOE, equation (E-5) is solved in the following manner: i I
~ . ...-...nn.... - - ~ ~ . . . --- - .
_ _ ~~~_ _ _
. . . . . - - . _ . 1 6.
- 1. Using displacements and velocities from the n* time step, , i Ex and Ci are determined. (Determination of the C matrix is discussed in Attachment E-1.)
2. The spring forces F, are calculated for each clearance by first finding the difference between the deflections of the masses involved. If the difference is less than this clearance, the force is zero. Otherwise a non-zero K( Ax) is calculated for Fs*
- 3. These three structural forces are added together and ~*
premultiplied by the inverted mass-fluid matrix IM - F] {F ,) is multiplied by the
- 4. The constant vector [M - F]~
input (or interpolated) ground acceleration and added,to the previous result. are now known for each mass mi.
- 5. The absolute accelerations n k Although written in terms of the absolute displacements only require and velocities, the terms Kx and CA (and also Fs)and velocities (y = i - z)'
relative displacements (y = x - z) The relative accelerations are found by subtracting the ground acceleration I - - Zn Yn"Xn
~
- - The relative velocities are then updated n+1"Y n + IY n) ( At)
L I and these are used to find the relative displacements I - Y n+1*Y n + I n+1) ( At)
~ The calculational time step At is chosen small enough that x and its derivatives change very littletoover At/2the (forinterval.
example); .
- Accuracy can be checked by changing At ' d i
typically, a calculational time step 0.1 times the input groun acceleration time interval is sufficient for one-stick models.
- Thus, with ground accelerations specified every 0.01 sec, a calculational time step of 0.001 see is usually sufficient.
for multi-stick However, smaller time steps are often necessa:91 e.-- ,,m mt.e -
.--ms.,w em , , . , - ,y -
- s w &-^ *^*~.?- , - - - - - . , - - . - ,- ~ - . . , . -
~ ....-.~ ^ - - . . . - ~ - . . . . - . . . . 7 .-
models. It sho'uld be noted that using the updated velocity to find the displacement (instead of the velocity from the previcus time interval) improves the numerical stability.
- 6. Steps 1 through 5 are now repeated using the velocities, displacements, and ground accelerations for the n+1* time step.
E.5 VERIFICATION Figure E-1 shows the model used for checking RACKOE against the more general structural analysis program ANSYS (Ref. E3). To verify the essential feature of RACKOE everything except structural damping in eq. (E-5) , ANSYS was run only until and slightly after a fuel contact occurred. As input, both programs used the input ground acceleration shown in Fig. E-2. For completeness, the absolute ground displacement is shown. - In addition to the input ground acceleration, the following summarizes the relavent input data: My= 12,714 lbs. .
= 3,689 h s.
M2= M3 = M 4 M5" "6 "
"7 and 29,866,000 lb *m 2 g,3gc3 represents the m1 2 M =
8 rotary inertia of the fuel.) There were six gaps (3 to the left of the fuel, 3 to the right of the fuel), each with 0.3 inch initial clearance. Each gap spring is
~
assumed to have a stiffness K, = + + +.+ =Kg = 2.31 x 10 lb/in. (For the problem modeled, this stiffness would be representative 1y hight a good check on numerical stability probably results by assuming a stiff value here since a short duration fuel impact would be implied.) The non-zero fluid effect matrix terms were as follows:
-Fyy = 12,879 lbs.
I "
= -F = 38,121 lbs. -r22 = -F33 44 l 4,804 h s. -F5 5 = -F66 = -F77 = l F
25 = F52 = F36 = F63" 47" 74
= 6,560 lbs. *~ , e ,y .- , g, q e,- ...e. nee .** e- -'-memp, e p is m e gayie4%' ,_,= - , - - - . - -_---.,-_g. , -g-,._7 --, ,, ,,._, , , - , , - _ ,.
. . . . . . . . . . . . - . - . - . . -w. -
_ . . . . - ~ . . . .. I
- g, and for the wall coupling terms, F ,y = 17,392 lbs.
Fw2 = F,3 = F,4 = 34,784 lbs. The support springs were specified by 6 i K8= K 9
= 5.0 x 10 W in for the vertical ones, spaced 30 and ?O i.9ches, respectively, from the center of the rack.
For the horizontal spring 0 K = 2.041 x 10 lb/in. -
, 7 The flexible elements 1 thru 6 are " beams" with shear and bending degrees of freedom, specified by E (Young's modulus) , I (section inertia) ,
G (shear modulus) , A, (shear area), and J. (length) . For each element,
.. the values E = 27.76 x 10' psi, G = E/2.6, and A = 48.3 inches were assumed. Rack elements 1 thru 3 were taken to have A, = 176.6 in' and I = 117,351 in' . For fuel elements 4 thru 6, A, = 278.6 in* and I = 2 7 in + . (Realistically, E = 13 x 10' psi should be assumed for aircaloy, but EI as chosen corresponds to a fuel bundle natural frequency estimate of 3 cps.) Additionally, a shear factor (of 1.0)
I is specified for all elements. u r Input ground accelerations were given every 0.01 sec and the RACKOE L calculational time step was 0.001 sec. The equivalent ANSYS time step used was 0. 0025 sec. (NITTER = 4) . Apart from this difference, input preparation was essentially identical. Figures E-3 thru E-6 illustrate the significant results of the comparison runs. Fig. E-3 shows the fuel (top and middle) displacements relative to ground. Since the ground displacement is initially positive, the displacements are negative. The top of the fuel contacts at 0.44 see and remains in contact for approximately 0.01 sec. As top contact occurs, the middle fuel mass slows down. As shown in Fig. E-4, the top of the rack moves very little until the
' e.. , _ .. ..m.,-.w..-- -- - . - - + - + -
- . . . . . - . , . . . :. . :. . a . _ .- . . - . ..
\ . 9.
e 1 l impact occurs. The peak displacement predicted by ANSYS is slightly less than that predicted by RACKOE. This discrepancy is probably explained by RACKOE'S finer time step. The horizontal shear force at the bottom of the rack (proportional to the displacsiment) is shown in Fig. E-5. Note the small positive pulse at contact followed by a larger negative pulae due to fuel rebound. Again RACKOE picked-up the extreme not resolved by the longer time-step used in ANSYS. Finally, Fig. E-6 details the vertical support forces (or base moment). Again a contact-rebound effect is evident. Based on the RACKOE results, the peak horizontal force occurs 0.015 see before the peak vertical force. Considering the detailed agreement between ANSYS and RACKOE in this
~ - comparison run, the basic one stick fuel impact model is considered verified. Various options of RACKOE are discussed and justified in attachments to this appendix. ~
9 Der k e m ( e a m - .- =
- m e'e-e a s.._ -
. . , . - . - . ~ . - - - - . . . . - . . . - --- - - - . . . - - . - - - - - - - - - - - ,- , 10. / .. /
i k. v4 - Li Mu ew 13M M
'/ (3eb (ro) N3) a ? g g @
e-9
~ /
h@ (5)
/
I O O El 4 L
/ / m G D A f I A L -,- e a v-J // /r rr r/ -r r l =6 Fig. E-1 RACKOE Model used for ANSYS Comparison . l l
j l 9 an . =p .m g . . .ww . w -; es e
, *s-e e-+= = =y 3,.ww ,...,,mayw . . , - -,
- - - - - - eh...g'eM', ,,_...._._1---.=-"*^--
e 11. P Q
. W D O . . . . _ . -- .-- C. . _ :- ~~--- - i " ;~ii'-
F J
- - - _-_ :;, ; _ c;. - - _ , - -~ = . _ _ _ . - - - - - -
_ . - - . - , ~ -
. _ . .. _.,. ... . .y .e w ..12 p czet.LeWW. 9%D C2p .. . , ,..e. .._...=*-*=- . - - -. - - .- -.=--****'"",. .. ..
u
._ -. e- _ . . _ . ..s Q -- ,- 7- - _ ..,_g_ g _ _g -- -
g;. .44;_ O h
. _-f----~
F ; _ _. :#, - -: s ..___- . H~.-.:-- w - ---_-. - - --.: . _ . _ .
-E g .
g _ . - -_ . - * --S.__,_, n
-f -
__w -e ~ p r y __p
- _. M *f.-- C fg..M.w-**- .. _ e4 ~
g. [ -
-o- s . a f.f3 --- g -
m Ez' -
,' 'N _ - } --}-- -
e b
-g ;- -s 1 o % -- u r . -\- -n - -A - e-- 1 "M_ ; u a
e-
-g-1 1 .1 ---__ . _ _ p W
E ._ .. . **'4
\, ,
s ei.e
\ ~~ - - P- %- x- ; -- E ~
1 A~ 4 h-g u --
^ ,_^ ~ _ Q x.x _.- w_- m r- - -_. _.
m __ _ g _gr-O
-- - - .. O, '- ;e ._ ^-
m _ ~ _ y 1 ' m Cf.
- m h
M-
'O L. -- -A_-m C.,
xw-_ -w_ . . _ o y
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-s ,
m g
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(
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C o s N __ ,,4 P __ W O Was 9
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- h-.=__-
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- s.. . ..u.-s,._s .--- ;------*._._..gs._
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e
- l
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. =.
ut
%ene.4 m 3 t f - ?_: . : .4. t. * : [. 4. . 7: . .=.. . .2.7:1 .;J.9 Fuel f*m ea h ' a g
1~*1 " ~ I- -
~ , _ ;, yy.p---
7 "'S S ~~~-N!*"-l?' d@:C ~_ f .* - ' k- J- [ IN-55
._.._.....g.. . __ y .:- ::r . _= : ~: a ._ .--:[...:. . n.,=. 4::.g ~.g..- . ~; ? - * - 4 -- - - ; :.:=....
- -::-)l ,;
pg4 na3 g .,: t . *. .. : : u - \ Q -* =.u;..--
\
(- n ~2~~b*~h~~ .= ' se ~_~ : bhPug1 C) N:E'M f kh!.W W f:-:
- .bi=4_[
i- ~ _ _ _~'i : h::=~&.
- 5_- Q ' Q:.35f.t:;-
- :- c .. _ =. W4 ww/ e 9%:?.ti-a s'c0 i J=-h==~=f-7= =#/ M2isfi'
_ 3- _" _g = ! _
~~-
_=;.. i=.=.=l A -n; A ..:= 81
.A '- ** -emen u=xce+=y-a m:a =w =: 1-::(r q d ^ * * ==- + ..=.;--.1 . _;. : _ . ; i
_ --J.-'=- ... - . . . . . . . - - - . - - . .
-i... -~. :* L: : ) ~~ [.:** - .,.*. 2 "-*.. . ~ = .: . ; 17.-
T .! 1 . :.T !. ' . --* . - J.~.L.: :C. . ;% :. "
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F 80 .tif L :-h5 -l-}-' 5Ei:E =k ~-- %-d' 3-2 :' *i L-Sri.= -b jd
- 3:- _-: - ~ 2 E-N =
- = .u
-- -c =.r=-iiE~-9-d:=E"il-45
- -. _ . -a-
_.-.===a=.=------_------: ==N_~55- _---F ~~~ ' .: "-- :i-[M/- MT 55
- / =:. J . =.--- - - -- - - - =.=.
___..____-_ -_. - .:-- = _ _ _ _ _- - - : 5 =
=---
- ---o ..-
- = :- --s - - - -
,i _= .g_ ,_ .-. _ .,;_ - .__-._._._.. 2 _.f _ == -- - ._. _ _ _ _ , =
EEiU = = . , .-- a_ _.__ _. _ . .. _-- 1 =_E:.-
= :w -
_=___._..- - _ _ _ _ _ _ _ _ . . _ _ - _ . r . ._ - :-
. =. . ~ .a ~ . ~- .-_=.=_= _ . _ _ --- .. . . . . --._.-_._..._.=_..-.:=.:....._.c.._.=.__.=.=_ . _ _ . _ . ... ..J... =
- j. =.. -
- .=.a..:-.-L=-.... --=.--- -
_. - = -===:
. - - = = : - =.n : - =- = 6 5. . =- - _-- - - - - - - - -..-..-_.._.-=:-
- . ..j
=--c - - . _ . _ _ .=.-._._=.._.=_.-=-.==.----_.-.,_._-.__/:.f...v.i.---
_ . . . = = _ -...
~ _ _.
L=:;g ~~_._-.2.---=:=__=_:=====.-,=.: _. . ___ . _l--V. . _ . . _a====---=.=--= r.
=_ : e p =:u -OdC ;...,=.. _ -- - -==;--- _- - - _=-
_ s.; , _ _ . . _ _ _ ___ __ , . -.,
...t ; - . :1 ,/ .== : ._...- :-===---- =.m -: :-----_=-- . - - - . = = = -.
_=._=._-_..==._-_--==_-=..-^l/==_--.:,.._____,
.;---- - -i_-- -=_ -- . q=. Q ,- _-. .
_ :-- :=--- / f -- - =------ ---=
==c ;-__- ..:=.c---- _ : --=:- - --- _=-_._--t#==._-.---- -- 2 L r : :q .--- - = _ 2._._._. _--- = -- . .- .. =____ ., .._._. -_ -_ __ _- _. -_ __ .--_ . _._._._ _. _- _ --- ____ __ _.=.
_ . .e . ___ ._ __. _. __ ._- -- -__ -. .__ _ . _ . __ .___ _ _ . _ . .
- =.,_..__. _.-.
.-_.=._ =.:.e , _;.-. -=--m-;-------=- .:._:__.:-=.----_ ____.:.= =: w -- - ._=.=.~_;_==-::=---------1 : = m -- - - - - - - - _ _ = . = = = - -. == m _:_--- ._ : t_ _ _ __ /. r = - - .=- ;-- = ==a -- ; ?. ..._.-_.=__-r==::=- _ - - . _ . = = ---__=_--.!.=*--d.......=:.-.--- .. -
_ 4 - - .
".-"".",.Se C ::.:* =. ..J".-' _ = -"* r- - N 3 .--r .:._. ;_
_ - = ~.J. . .=- -
-_. .=====:=__ -
3 :.=---- . = . - - - - - - =-=== = _. f: < =:: .: ::=- ===: _. - .==: =.= ==-=:==.===_.=_.=.--
= .. : = =:= : -
- _ ==.==_._._-=-_.=____:===._==:--
=.- ? _:= : _==_ =---.=:.._. = = = . .: __ : - -.=~.---:=---.--__.--.== ;f , T=5=_=21-~-^= f^_ .g.=. =- _=C==Q === ~5 i = :.: =g =.:= ; _ .=.a= 5 -E=_. '.i_ .
s-; ? [ -~ To . ._ :,n,1 :P := mad'.2 = "" _ : O . 3
~
_1 ".iPO . 4 ..i= M - 2:3.3 E~~-I'
= = = . :..- = _ -;=_- -== . _ ._ -_ -= -. --=- -= = = _ . = . - -==-.-:.__--.;-----==------- ._..:--.-=:....;=.=--- --- : -L'". .""~:..------.="~.'-"-:...D.~~.--*~~~$p.--*---.1=---~~"_"'=~_. ^^~ - ~=---- * . * ' * *: : -- i=----' .__?.=. !"ap -** TT)d3 - .* =* __ :-L .: _ _._.._--*" .. :. : 1.:.
- 1' . . ! * . J ! _= . . : J = L. .=2*.*--L="-~_.:-'~ --*----.;=.-
- - -. . . - --.-v._._....._=.-=-:.-:.,.. . . .. . . . . - - = = - = -
Fig. E-3 Comparison of Fuel Motions Predicted by ANSYS and RACKOE. The initial fuel to box wall gap = 0.2 inch. O
- e e-e -e ew=g=--*w.g**. *-ge*-**s-.--8-~ * ~
. _ ., m- w..-.._. , , -- - -" w ..s . ..w.-.4~...
W e 13. e
.g ee - ..y. , , . . ..e. .
y . _ . . - _ g f f 4 . _ . . . L.3 . g ,._ . . 4 . 8. ;_
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_-g_ . . ...;.. _ . . _ ... _
.,. A. . .; .. . . . . .] }
V
- WO'~
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, - 9 _: , ? .-- .j..__ _
1
.' I .. . . . . . ,. .i - . .- .
l .. . ... - - . . ...:_. e-1:. _, y .7
. .. . . ._ ._.._:I4:~__.=_~.~_2=.._..;.;._.
1 -- -, _ g g- L- , .' . : ;. _ _ . =..j- - . = == i 9__;_ _ _. . . _;_ y g; ; --==-
;- ' i .=: % _:.- .-- li d. 24E:.:455' JE=f:: -*:=- =.=-.- _a: - a w -r - ; .-+= .- : - _=:. :--- n -- - _ _ = = =
a m :: .:.. , =- - . : . . , :=:--- l
..y tx. .--assys .-- - ::.
2
._. _ . r_i :: c .:_i =: a.T :=E pt_==i:-.-k.._j __:!:Fa=: _ .--';- ::i.I= = :jr.i-i-Zi; 73: p.E=5= E:: _ ;. . .a. - .
_ _ . . . .- - - - ..=_,._:--=
- . RACKor . _:e ._. =
.. . . - a u.= : . =. =_; - _ : . .- == . = =_r t .-_=- = -= = 2 - == = -:=;== n = = =-- ~ - 2 ' ' - 2~
I 'N *'- 4 +.2 4"_I_". ': r 7 5.__~_-' L 2 2r:.23:55.#* =-f-E.#: _ F:E.4!_3.-- 2: =.re 8 i .
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_ , . . . . .. . ;_ 4.. _ -.._m. ._. a,a.__ . . .
.;;_-v.u w . w , .. . . . . ._.3-.... . . ,_.
x __. _
.;__..,_:... _ . _m. _, . 2, , _ ; .j _. _ _ ..v.; ::_ . . - = _ _ - - __=.a..
s
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l-
,._.,.i. -- . ,-, :. .:_-=: r_:_- - a. . :.: _ _ . ._... : _ a _ ._
_. : -~= = --==r_.=_---:--=_:- _u_.. . _ a. . -. _
, ..at. .r.__-..._ _ -...t__.;-{n..=.J--=.r=_.=.-:=_:...;:.._-._._.a.=__:.=_._=____- ._ _ __r=.=__=.r a .
_.---u.a-.=--==.::___=..==_:..=.:=_-.__.4--;_:=.-.==:.-___._:
=
e.: - 1 - - _= = .__._. -=- . . _ = . = _ - _ , _ . _ . . .:---- .- - uu r .- - --+2------ _ _ _ _ ._. _ _. ._:..__ ..___. _ _ . . . . . _ _ -
..u..= ==.==. ,_;a===.--------------- - -- - --
e ,.._ * '* O :*-*-**.-*-- ---**='-.*=1..**?----*2.::---- . _.
. _ _ _ *1..-*:.=-__ .I_ _:r, ----:-. , ._ -}.._._-_ .=_: .o _ _ _ . _ . _ . . . . . . . _ _ _ _ _ . _ _ _ - _ _ _ _ . _
_'__._.m_._ _
; -f-- - :- 2 ..--1*. -'*>1 -*--*.-"- _. _ - - .:--- _- r : - - : :- -- _.. _ ---= _ _ _ . . . - _ _ _ . ,T-- .-W_-
r ::-__~r-_._._=---___..__--.__. . _ _ _ . _ _ ._ _ _ = =-- - . - . _ . _ _
.-=d- _ . _ _ . . = - . .*
- M A W~_'.*-.=;=;;=.. = :-- - ~ *, . _ - _ . - - - - . - -- --
- = ;
, *-*. 9Q ?.** L
- ;---"_'.:. ,:.-'.._ ,_ .V.-------*---r__=~*-2--- . - - - -
.._.-,.,y.____._. ., _- -_" .- __ __, ' _ * * ._ c . _ _ _ . . _ .._._ ._ .. _ _ . . .- *' ; 5 j . :"' .j =_ _ j: :. : ' _ * .J : *. . '. 7.: ' . ] , . -[ *. _;; r .=[ _ ,
f b. .g =_-s .: .- .=_.=: .=~_.: -
- - - = _== r - - _ - - - - --- - -- =-- r . --tr :.--: = :r-- . _ _ _ . .. _ _L---- _ -- n . _ . . _ . .. - . _..._-_-..":-._=.4._.4..
h"..* ..;". .* __.=.=l_= .._.._=_=.=.-".._=':*__".&-".=.*.__,.
.Q . .. .
m.-' --- - _...._....u=.=_. __--:-;=_:==.2===2==-.-_-=_-----
- r. r__ ===t = _ :: -
. = . . f, .= : _r: :. .a . . -
- .=. * --
. = - - . .-- . . : ' * - *.,- . ; = : =._r.' - - -- 2 :.- ~~ ';;"';;- ' -':: -* ~;=23i'-- . '.-. "--._-. - ~ . _-": ~~ . _ . -
0
. 7.'
- AD - = ; :--'- . . . _ _ .. .. ..:.-_
!;. : e r -- :-- _ -- --
_ . _ . . .- - - _ _ _ . - = . = - = _ _ -_ . .
.r . _ . . . . . _ _ . _ _ _ _ _ . . _ _ _ . .,=.=.,o,,, :_. . .:.:- . _ _.. . . -.___ __ . . . . ..-._._.: ._ . . . _..:..=_ ..._ . _ _ __..___ . . . . . . . =_. ... .=- :.:= ._ _ . ,,___
p
.-.-.;.. :: : --r...- ...I_... ..._._:..:-..;.__.:__.:_.
a . _: _. _==u=.--=:----=.-.;.=-.=r-__..-
--_.._._.=::==.:-------_~. = - - - - - . x=--
L t-i _ Ea - ___ = > = : - r= =gf e====~ =- - -- 2 0 = r_ :. .g=:' _:_: = =__ =. _ _ _. _ . . _ _ _ = t-
-2 ? .-4*
- w
=:__--_. -
__.: : = :. = u. = _: .; ;;=..__._ . C_ :. _. _=2-. - '- --
--.=_=.c=------- - . _."_ -= : =-- - t - _ _ . _ .
I, h_ . 4 . r_ r, .. . . ."*.=._-__r..__..._._-_..:_=_-=_:=.=..._:._=_..:_::-._:-.=~:.=:-.r_~__
,- ..._k .=.:==. ::.=---..=.:;;~:...--_._-_..--- - .= :.~.::- - - .= ~ ---
a.-
~~" : n =- - : == _ .: :: . _ _. -- * == =- - -:.-_=u.-=.--_;==.=:------ 1;.------ .: ;' f _,u..=__ : .:=. ; = r .;. e J.= : .- .:._ . r : __. ':. :. _= _: '= :.:.=_r- _ _ :._=._s_- _= ._2.; ==_- -=~ =-- nt - : ..:.:..._._.:;_.. =- .= - --- - - . - - = . .z .- -;_. .5.._
- g. -
- __ .
. .=_ _r:+- .-e . _----:_....=.=._.._._._.-.N_ . ...gi ...-. _ . . ..__ ._:r . - . _ +
_ . =_ _ _. : =_= *. _ _. ....e_. . . __, .--- _ - - {.-' -_ # - i f
- =.=-"_--*: =.1.=%: : .._ _. =.;"-*~~ ----.-.: - -*-- - . . . = _ . . . _ J W & V4 4 ktE CT.-. .- $-_-:
r.---.==--=;r-*:--.._.__---;-_.=r- . . : = =;: - _ .- u r=. .=. =. =_ =. =.: r ; . _:_=___=.._===_=.__-.,_==.=__-._.__==-----.a=_,_=u=-----
. . _ _. . _ _ - __ 2.___. _ _ __ s ._ - ==:- _ =_M
- t. . ._ -.: . a= _ :. _ . .=u :. :. u- r:= .;: =.= : :.; = - = = .:.:_ . . ._ . -- - . . _-_. ':
L "::v;- - . ::: . ._: : :.; _ :r--- _2 --_.r :r.== -- = _. . . ~ = - .y - -:
. . . . . , . -*..;2.. ._.4.__ ..._
T_ " ~.z .;.J: : ._ 2. Y w - - ' ' ' .; ;== .J
- :.--*.. :_.=_- *-----_.'.:,s.w . _. . _: -- - - - ' :.=_ . ;:- - 1'- _. : = :r : ._ e _ . . . . _. . =: . _. {L*T . . ; i.~ T. ._= ry .:::]-;.: - Q -----*-* _ . = . .
w 0.1
,. _D . 3
- -0. 4 = .a _ :E .a
, .. - 0.2
- _. . ..~ _ . . , .
. . . . . p......._.._._. --- - . ._G - .:.=:r .. = :
v- -
- ' h _ seconds : --
a . ._ . . ..=_._._;;:.=.... Fig. E-4 Displaccinent of the Top of the Fucl Rack as Predicted l by ANSYS and RACKOE.
.w..- .._e -.em. ._e w ...y..ygi . - * * - - * - - - - -
t
._ . _ . . . -.. ~ .. _ - ~._. . - - - - - - _ . . _ . . _ . - . . . . -
O e
. 14.
e
.. 4 : ...1_=.~.=.... ~ -i ;9 ; .,:- r - =; --- -
r--- .3 7. = ' : :-- . ::-- - ::.. _
! =-
- r. n ! '. . ~- . i. . .;
- 4. .- !. ._q ; *
- i. g ._ ; .
; . ..u....... ; x. . ._-
u.
- -a- :_ . _. ~.: :-13 ..:._ . :.__=-~ !~ . i j . l ; . 4. - . .i: : ilj : : . . ::_ T
- 2. :. _ . . . : . t-- - - 3. ._.
. . . ._..1 . . . . ._ .. .._._.. .. _ _ .,:...,, . __; . . - . 7 _. . . . ; _.=. .j . _.=m _ .. _... . __3 q . > -.-- 3'_ Ii'.r Mi~i~_2;:=. . +- -!S : '.9 7 5 i--:~~5 . i--55 _L 8 ' o
- f U-- = t72 dr% 0.)' ' - le D.ME) a !U .~5 5--
q .~ ". %:Y. .. . ; . T _N _ _ q.:: . ...._ .' - . .f .
. _u--.. .....:_ c_:.; --=._=-
- =.- - _: .== : : r- '
_~
. g_ - - -- _ .=.:== . =g .2 : :
- .a _9 t = -n::W :~:[d = : i _
-13' ._~.__j ~!4.:d. .' . ._ . ;.! : ._3" 3- ('pt. . , Q: P" -
_.. . . .u,.,. . r
. = 9 .r.. . . . . p___ : - =.: =. ,: =_=:. =.=. . _=; : . ...r .
- r. ; . . . 1. . _._ a.
. =. ._. == _:: =m _ _ . :, g = _7 w
_4 -i..._.;:===,...-- .. a . _r
= :
- . _4 . . _. a g- .: 1_ . . . . ..:_..___.=_;
._.:- : = :__= __ . _: _, ==1--=~ . . : __ :. = . . .
1= = .s-.u .
.g .: . .._- _a. c e. _._.ra, c.;=._ : :.; .; _ a. ; ___; _ - _ = _=:... ::: :r. _.. :.=_ :.q - r .=. =_. _. j_- _ u. . = . _a._ .. . _. : - . . . _ .c . .- _ ....=_ *iic '- I:4:SMhM - f ~ i U . ~_ .- , ";-T~~" ~5 5 ~_:~:.J-d** i=~~" . . .. g .. ... : _, s;.. ._. . ... ,. .+_._ _. . . . p. . . _ . . s _ ; . _- . . .. . , . s . . -. _. . .r _ : =.:. . _=.7 _ = . _ = _ . ._...'. m.: .r c. : ..=: n . _= _:. -._ :;;;-=ry. . . : ; . . _.=. . _ .:_ _.n. .: . . .: :
w_ _ .. : .::=_. __:.::- =2_=p
= . . :..=_< __ . . . _ .. - : _ :, _: __._ :2 =:=Tr+-
- = -- ..- .- ---;=._
;. ~ :- .: A e q- .." c.m . . : . . - . . _,2 :- .:_ - :- =- _= c . -
- th ;-.---.
= - : : =r :-r -= . .; . .- :: - _ _:= :.- --- "_ .=-- = = - _ ._
- -l
.-- r - - -
- q:= .,. , .: == :=. .=-r =. ::__ _._ . _. _4_ r- r4. : = =_ v .: w.;
..:...-__.r.2_-
w w . 4 - = - - - --
.:=_=- --: -- = = = . _ -___. -.=.r_ .;==_:;=_=_=_=.=_*--'_._-=r=:___=w.2___.
- .--: -. __ _ =::::= .___ - _ . --- -
- . . . . =: ._ ____ _:::: .=-- =t . _ _ . . _ . . . . _ _ _ _ . _ . _ _ _ _ _ . _ _ . . . .._ -j
- i. -
.-o;- .===.___..__ -
- t. =.- 1 --
._ . _ _ _ - _ - - - " = _ = . - . = . . . 1_ = - = . . _ - _ _ -
_=,' _=. . _=_. - = . = - - - - _ _ . _
. =_ __. ..;. _ ..
- ._e-- , -
- .=.._
._=..=.=._=.__~: - . - . . _ . . . . _ _ .
__.._.__::_=_=......-_._.___
= . =9 .u .:=
L =n =:=_=_-.=
- m :=-= : : -- : c . .-.-- -- -- :. _ = --~- ~
- _-:.-=:.- . -. ;~: v= .12,=_:__.:_..__.-_ 'd -i_E: :: 5 .i:hy E
_ __. _ _;._ _ -_ -- W'Qii'. ~.- = :.=r::_'.y._.___ . .__.j. -(:n _ __. JJE
; _~$ - 5=u-m -i=:'.~_^_.. _._1,:~====-_=--==___.__. . _ = - _:: ^ ._ . _i_==--~
A : .= - - - - -
= .c - ,=u=_-__.1====u..:.__=.r.=.=--.r__==.7._==-;.=__._==_.=:-:.___.._ == _= -: _.--- - -:==- .--=__.
- =. n _ = .
- _ ~ _ :. : ==...._u._
- ..__; . : ._: _;: ::- . ;=-.- a m . ___ - - - - . - - r_ .._:==_ ..-._. =___ - = - - - - - - - - - - - - - . = . - - _ _ _ _ . - = + - - - -
u
- s
= = 5: .
_a u u . ._ =
- _:.=._; ;-
=27.
_-:==------=_
.==::==___ -.1.====_ =. = : .: - _ :_ _ : == _ =.: :_:_. - u = :.___. .=-c. ..___=_=:._: . :. .:: . :. _ : :- =_: .=.- - - = == =, - .r--_= ..=-=.-.__.----__._=_=._..___e._. -- -o -- -- _ _-_._.a__==-.___ ;; - ._=.:.= .==_. .:== - =. := : . == = u. _ = :.=c - : _ ::___. --.=- - . . .w
__.-t. 7 = - .: :x :_ . - := .==-.--.:z.._:.--_.--:_ --_=-_=s.- -.= = ii:::S: .'__: =If 20 ir r I-- Y ".-~~" " 9 - O : E =552 -_ it i @ .i ri.; i ---
^
L _ . . _ . _ _ _ _ _ _ . . . . _ _
--- N n 2" " ~_ .
_ _ _ = - - - .2 : : =.: c= - -- , =_ ._u. _.- = - = ===5 __..___._.._. _::_=_=.==_----
. %_ _L__,.._.=m
_;.. - _ _ _ ==._: .:. .
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=.._::. q . t ...
6 . r. . Fig. E-6 Ccur.parison of ANSYS and RACKCE for Vertical Support Forces and Base Moments
, . e .
e
,,. .~.
16. E.6 REFERENCES
. El. Fritz, R. J., "The Effects of Liquids on the Dynamic Motions of Immersed Solids," ASME Trans., Journal of Engineering for Industry, February 1972, p. 167.
E2. Dong, R. G., " Effective Mass and Damping of Submerged Structures," UCRL-52342, L.L.L., April 1978. E3. ANSYS Runs and Restarts
'. a. AQEUQSR - main run containing time history accelerations and . model input data. Output includes . l. UX11, UYll " corner of rack" displacements
- 2. UX6 " middle of fuel" displacement
- 3. UX7 " top of fuel" displacement
- 4. UX4 " top of rack" displacement
' ~
- 5. UX12 " ground" displacement
~
- b. AQEVC4R - element forces on bottom elements of fuel and rack
- c. AQERLEF - element stiffness matricles e d. AQE3N43
- 1. UX1 thru 4 " rack" displacements
- 2. UY1 and 14 bottom of rack and fuel (no relative vert. motion)
These runs were made possible by P. H. Titus of Stone and Webster 8" Engineering Corporation, Boston (noted 1/7/80 and 1/9/80) . Wachter N Associates acknowledges Stone and Webster's disclaimer stated in their
;- March 24, 1980 letter (LIL-R-231 - transmitting AQEUQSR and AQEVC4R) and L restated in their August 3,1981 letter (LIL-R-269 - transmitting - microfiche for all ANSYS runs and post-process runs listed above) .
e, Sus I ei. hee
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I = ,. ,
* . ATTACHMENT 6 ' t.. . . . . . . . . ~ . _ . .
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SPECIFIC ITEM NO. 6
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* *' * * "3*"
22A6416 GENERAL @ ELECTRIC so 1 cu v e.a s-t e r ? NUCl.EARENERGY DIVistON PIP!NG. MtHJ STE;u p. ros: t c.,n er.qyo..e.,7 9.), ,, 00CUVint Tif t.t Tver SiRESS REPOR' Osticificarios O cnAwino doTHin pur NUGE AR B0!LER SYSTEM 3 upt gg !!/A g0 CR CE$tR?PTION GF GROUPS afvistous ._
) e. l tbh 0 CM3-1983 760C l
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w'e . 22As416 so. ~3. 2 GEN ER AL h E!ECTRIC , NUCLEAR ENEf4GTUlVIS10N nev. 0 STRESS REPORT If!TEP. FACE Atl3 EQUIPME!!T LOADS MAlfiSTEA!! Pl.*!!i3 VOLUME 6 . SHOREHNi *;L*; LEAR PONE _R PLAti! one L.I, 12. M79 PREPARED SY: , 44, '!'
- A5'hi.4LEKAR, P.6.
. I A! ICE BY: / -
f.T tiiEHyP.E. VE'liFIED BY: /?44 H stERZOG () f ,. APPRCMD SY: o.c ^ 70)(n6:95C.i. Acting Manager - Piping Stress Analysis 80lLI1G ~4ATER REACTOR SYSTEM.S E!;Gl:lEERI:iG DUAR!:JE!;T MECHAfi! CAL EQUIP:'E IT DESIG!! SECTI'0:1 PIPIT;3 CESIG:4 SUSSECTIO:1
. l . ..?
1 ( .
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221,s416 see. 3 GENERAL @2'il E.LE CT R I C NUCt. EAR ENERGY DIVislON
- u v. 0 TABLE OF CONTENTS -.
Subject Sheet. Nurber_
- 1. Introduction 5
- 2. Sumary 5
- 3. Descriptien of the System 5
- 4. Coordinates. ETement, and flode Diagram 6 5 Structural and Pressure Vessel Interface 6
- 6. Safety Relief Valve (SRV) Equipment Interface 6,
- 7. ~ Main 5 teen Isolation Valve Eculpment 'nterface 6
- 8. HPCI !solatiert Valve Equipment Interface 6
- 9. Suspension and Structural Attacheents 6
- 10. Pipe Branch Connection In'erface 7 l'
- 11. Terminology for Load Designation 7
- 12. References 8 0
4
. I s' - , ;/m .
27A5416 sa ao. 4 G E N E R A L h. E LE CTRIC NtlCLEAR ENERGY DIV1slON nev. 0 APDittDICES Sheet !!urber_ A. " Element and Node Diagrams . 9 4 Reactor Pressure Vessel Interface 18 C. Safe:ty Relief Valve (SRV) Eqaip.ent !.iterface , 36 D. Main Stem Isulation Valve Equiptent Interface 142 E. P.PCI Isolation Valve'Equipmer.t Interf ace 211 F. Suspensicn and Structural Attachments 218 G. Pige Branch Connectie interface 734 4 e e 4 s e e 6 9 e
\= 5 . .* % . s . .
.c.. ..... -- - . . . . . . . . - . . . .. . . . .. . .
- r. .-
a 22A6416 G E N ER AI. @ ELE CTRIC ss. ~o. 7 NUCt. EAR ENckCA:DIVisl&N ncv. 0
- 10. P!,PO BFANCH CONNECT! 1 INTEliFACE (APPENDIX G) 50.1 Therm 11 expansion deflections at drain lines and for elbcx taas are givan in this avendix. No tynanic inforr:stion is provided for drains and elbow taps, as it is assu' red the piping is sufficiently supported at the.e points to limit the dyrramic loads applied at the branch cennections.
- 11. TERMINOLOGY F0F. LOAD DES! GNAT 10N 11.1 The folicwim) designation is used in all appendices to describe the types -
of loads.
=
AP g Annulus Pressurizatio'n Loads (inertia Ef'fect)' AP O
= Annulus Pressurizatio'n Loads (Anchor DNplac'eceit Loads) -
CHUG;
= Chugging Load (!nertia Effect)
CHUG = Chugging Load (Anchor Displacemer.t Loads) D COND;
=
Condensation Oscillation (Inertia Effect) COND D
-= Condensation Oscillation (Anchor Displacercnt loads)
- OBE g = Operating Basis Earthquake (Inertia Effect)
OBE D
= Operating Basis Earthquake (Anchor Displacectnt loads)
P O
= Operating Pressure
. P D
= Design Pmssure Pp = Peak Pressure RV1 = Safety Relief Valve Opening Loads (Acoustic Wave)
RV2 g D' = Safety Relief Valve Basecat Acceleratic.) Loads (Inertia Effect) afety ReMef Vahe Basemat Acceleration Lo'.ds (Anchor Diviacement RV2 = D Loads) RV2 g D = Safety Relief Valve Basemat Acceleration Duc to ,%tornatic Capressort-zation System *(ADS) Vaive (Inertia Effect) ADS RV2 g = Safety 8telief Valve. Basemat Acceleration Due to Automatic Cepressuri-zation System (ADS) (Anchor Displacerent Loads) , D 4 *
.- \. ,. - l
22A6416 sw.s.o. 8 GEN E.9 AL h ELECTHIC NUC1.E AR ENERGY DIVtslON nev. 0 11,1 (Conti..aed) SSE g = Safe Shutdown Earthquake (Inertia Effect) SSE = D SafeShutdownEarthquake(AnchorDisplacementLoadg) TE = Themal Expansion TSVC = Turbine Stop Valve Closure Loads VLC g = Vent Line Clearing Loads (Inertia Effect) VLC = Vent Lir.e Clearing Loads (Anchor Displacement Loads) D W = Dead Weight 11.2 For piping analysis ar. orthogonal coordinate system is used. This system consists of primary and auxiliary subsystems as follows:
- a. The primary coordinate systen (global) identifies "X", "Y" and "Z" oi:ections -
42 showr. on the stress analysis diagrams where: .
"X"' is horizontal, positive in the 0* direction , ")"' is vertical (also called " elevation"). positive is up from the reactor -
pressure vessel invert.
"Z" is horizontal, positive in the 90' direction Moments about above axes are positive in the directions shown. -[
- b. The auxiliary :cerd:nate system (normalized) identifies "A", "B" and "C" directier.s at nozzles as sncen on the stress analysis diagrams. "A" is always ax'al along the direction of a pipe run. Where the nozzle is horizontal on inclines, the dircction of the "B" axis lies in the planc containing the "Y" axis such that the pejEction on the "Y" 8xi' is positive. Uhere the no:Zie is vertical, the directicr. of the "A" axis is p .rallel to the "Y" axis and the "B" axis is set parallel to the "Z" axis.
- 12. REFERENCES 12.1 See Volut.e 1. Section 5 for all referer.ces cited.
._) - ^
- j ..
' \l ~, . - l% lf . . .N ..~ . . . 1
- 1
$5' t
s t- TABLr Di PIPE MOUNTED EQUIPftCNT - MS!Y ll!GIIEST LOAD / STRESS Stir?ARY , RAII0 G6VERNING('I')
~
IbENTIFICATIONOF .m SEisVICE ITEf1 CALCULATED ALLOWABLE [ACTt!AL) GENERIC LOAD EQUIPf!ENT WITH
', LEVEL EVALUATED VALUES VALUE ~
(ALLO'J/ C0f tB I!:ATION ll!G11EST VALUES lC e m m
- D Axial 6.111 psi 0.455 1 Inner MSIV Inlet P S 2= '
ror ti.s.0. r--
, E 1 l ,
13.431 psi Inner MSIV inlet
=
5 cen< ting I,ll2 psi 0.033 1 P g 4. .- I for flin. E = r-G Torsion 605 psi 0.0450 1 Inner Msly inlet N N for 71.5.D. J Q "'". g,
- U Sm Axial 6,510 psi 0.181f! Inner f tSIV Outlet N "O 0 4' f o r f4. s . n . C E* - T 11 liending 2,'>4 5 ps i 35,816 psi 0.0822 7 Outer MSiv Outlet T 3 i C for it.S.D. ! O - . R lorsion 732 psi 0.0204 4 Inner MSiv Inlet 0 ' for fl.S.D. N S 'i' ' D Axial G,454 lb 10,200 lb 0.53 1 Inner MSIV - M.S.B.
E S Bending 307,101 in-lb 678.700 in-lb 0.45 1 Inner MSiv - M.S.B. B f I 0.06 Inner MSIV - M.S.B. G Torsion 44,100 in-lb 678,700 in-lb 1 O k' . N N N I f 0 Axial 5,434 alb 10,200 lb 0.53 8 Inner MSiv - M.S.B. E $ fi T T I .. Il Hending 547,662 in-lb 678,700 in-lb 0.01 8 inner MSIV - M.S.B. o m
! ' .E W N'
R Torsion 64,306 in-lb 678,700 in-lb 0.10 8 inner MSIV - H.S.B. T [' S M E (1) Load Combinations of 1 through 9 are evaluated. - g
- Weight force is taken out of this combination.
' 5 , s .
4 ,
~ .- . s. ..i. .. . . , ., ; ._ _. m 22A6416 sa ao.144 G EN E R AL h E LE CTRIC.
NUCLEAR ENERGY DIVISION 0 NOTES ON TABLE D1 LOAD COMBitlATION AND ACCEPTANCE CRITERIA FOR NSSS PIPING AND PIPE HOUNTED EQUIPMENT
~ ' '
NO. LOAD C08INAT10?!S SERVICE LE i/ELS Normal Operating and Operating Basis Earthquake Design Condition 1 7 2 Normal Operating, Operating Basis Earthquake, Operatieg Transients A and B 3 Normal Operating and Operating Transients and - Operating Basis Earthqt,ake C 4 Normal Operatino and Small Break Less-of-Coolant ' Accident and Associated Operating Transients C , 5 Normal Operating and Infrequent Operating Transient C 6 Normal Operating and Operating Transients and Safe Shutdown Earthquake D 7 Normal Operatine and large Break Loss-of-Coolant Acciden: and Safe Shutdown Earthquale D 8 f.'ormal Operating and Interrediate loss-of-Coolant ~ Accident and Associated Operating Transients and Safe Shutdown Earthquake D , 9 Normal Operating and Large Break Loss-of-Coolant Accident D
- e
.g . :.i j, .- . , , , f
... . . . , . - ... .. . .. ..w n.- .= ~ . . . . - . . . ~ . .. . .---
GENER AL @ ELECTRIC 22A6416 suo.145 NUC1. EAR ENERGY DIV12 ION ntv. 0
- TABLE D2 MSW ItiLET A7iD OUTLET CONNECTIONS - LOAD CRITERIA -
~ - ~ ~ ~ '
SERVICi LEVEL NO. LOAD C0".BINAT10N ACCEPTANCE CRITERIA A 1 TE + W 0.75 Sn B 1 TE +'W + CSEg + OBE D ) + (TSVC) 2 TE + W + II2 OBEg + OBE D ) + (RV1) _ 0 3 TE + W + OBEj + OBED +( 2 3 ,
+ RV2 0 All)2- ~
C 1 TE + W + CHUGg + CWGD )
+(RVI)y1/2 2.0 S, 2 TE + W + (CONDg +DCO.*1D ) +(RV1)g1/2 --
3 TE + W + (CHUGg + CHUG D ) + (RV2 g .
~
II2 *
, gyp ADS-)2 O _
4 TE + W + CONDj + COND O ) +(RV2 g
~ + RV2,#US)2 . )
i . g. l
\ . ..Y . ~
y Y *-
i 22A6416 sa. uo.146 I GEN ER ALh ELECTRIC
- a NUCLEAR ENERGY DIVISIOT nev. O .
y i TABLE D2 (Con.tinued) i SERVICE LEVEL NO. lDAD COMBINATI0?4 2.... . ACCEPTANCE CRITERIA b T - . 2/2 D 1 TE + W + ISE; + SSED ) + (TSVC)2 2.0 Sm N 2 TE + W + SSE g + SSE El p )2 + (RV2 3 ALL 27 /2 1
+ RV2 D If r- ~
3 TE + W + {5SE;+SSE)D + (CHUG 3 + CHUGD 1/2
+ (RV2g ADS + RV2 0 ^ $) .
4 TE + W + SSEg + SS D) +(C0!iDg + CONDD }
+ (RV27 ADS + RV2 0 ^) .
1/2 i S TE + W + SSEj + SSE D ) + (VLCg + VLC g )2 } 6 TE + W + SSEg + SSE D ) + (CHUG. + CHUGD } N .
+ (RVI)2 7 TE + W + SSEg + SSED + (C0!!Dg + C0f:DD I ~ + (RVI) x 1/2 8 TE + W + AP g + APD )g + (SSEg + SSE I D
l e
)
l
- . '. \/ v -
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22A6416 GEN ER A L () E LECTRIC sw. wo. 147 y NUCLEAT ENERGY DIVIs!OM REY. 0 TABLE D2 (Corttinued) LOAD CRITERIA CRITERIA FOR PIPE.(S pp;., MSIV CRITERIA
+Se rec.gn. ) -
M Service level A A p 1.0.75S,(Torsion) LeakageLimitl ' P P 2,g 2
. C 1 0 7S S,(Bending) 7 P
FA+PA 3 1 0.75 S, (h ial) P H 3'{I{,L[efs 2 1 2.05,(Torsion) Op ity M B
+N C y 1 2.05,(Bending)
P * +
- FA + P^
3 1 2.0S,(Axial) P
. O e 'e ~ , s ! , \. .
I
22As416 soo. 248 G EN ERA L h.E EE CTRIC NUCL EAR ENERGY DJVisl0*d ' stv. 0 :- TAB,LE D2 (Continued) ,-j NOTAh!ON. Fg Axial loading due to pipe reactions . . Hg Torsion load about A exis M B Bending load about B axis ,'. Bending load about C axis , H C ) Combined levels as shu,m values infor various this table. t Z Section medulus of pipe P , . Pg Axial load due to pipe's internal pressure - A p Pipe retal cross-sectione' area j S pg3g Primary stresses S Secondary stresses SECOND 5, ASME Code value for carbon steel pipe at design temperature
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- GENER ALOa ELECTRIC 22A6416 sw. wo. 149 .
NUCLEAP. ENERGY DivisJON ~ sa y. O TABLE 03 MSIV. BONtitT FLANGE - LOAD CRITERIA f SERVICE ~ LEVEL NO. LOAD Cotsit:ATION ACCEPTANCE CRITERIA
~~'
8 (OBE)g+(TSVC)g372 kg . 1 g EE '. I _ gw 0 (RV1)y1/2 5-i 2 (OBE g )2 "U ge . 1/2 wm a 3 (OBE I )2 + (RV2 1 ALL)2 fso l.'c
.J N -1/2 a-d f.
C 1 (CHUG;)2 + (RVI)2 5~- 1/2 v . . s> 2 (C0 tid)2+(RVI)f g Ex 172 m2
.s m " i 3 (CHUG)2+(R"2 g ADS)2 g
E'N . 8 s 4 (C0fD g )2 + (RV2 g ADS)21/2 J .f 7 g
~
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. 6 l .
t
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l - 22As416 so. uo. 150 GEN ER A L h ELECIRIC , NLELEAR ENERGY DW1310N arv. 0
- TABLE D3 (Continued)
SERVICE ! . LEVEL NO. LOAD COMBIfiAT10!1 ACCEPTAfiCE CRITERIA
~
1/2 o D 1 g, -
'(SSE I )2 + (TSVC)2 -
eM
~ ~ -
1/2 EE (SSE g ,, I )2 + (RV2 I ALL)2 2 g3 1/2 =E 3 (SSE g )2 + (CHUG g )2 + (RV2 3 ~ ADS)2 , g$ , W5 no
- 1/2 4 (SSE g )2 + (C0tlD g )2 + (RV2; ADS)2 ,
- - u .-. ~
3/2 Ym - 5 (SSE y )2 + (CHUG y )2 + (RVI)b 8 ,3 ,
- e '
1/2 5 ' 6 SSE g )2 + (C0:i0 g )2 + (RVI) 3,2 7 (SSEI )2 + (VLC I )2 8 ~~~
- - g ~ ~
1/2 R e
-(AP)2+(SSE)2 S
3 3
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t ..
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i
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i TABLE 16-B FSAR MSIV INLET /0UTLET - 'U ' '; :';, ' e. .
- HIGHEST STP.ESS SLtWARY -
f.$.i . 3 SHORE EM - MAIN STEMI LINE B .1-LOAD COMBINATIONS , I i L 1 Governing Identification of Equir 3 - ment with Highest Lond:' l I Highest - Allowable Load (1) Limits Ratio l .;I
! Calculated Comb. No.
Item Evaluated Load ( Node 97 f ]. 15375 .396 1 LEVEL A 6086 2 Node 103 il
.150 a
LEVEL B 6120 41000 l. !j STRESS DUE 4 Node 103 TO AXIAL 41000 .15 j 6172 _ LEVEL C Node 103 J .15 8 a 6198 41000 1 LEVEL D il I t ' 1 Node 97 F 15375 .076 t LEVEL A 1155 5 l 2 Node 97 41000 .034 . LEVEL B 1396 STRESS DUE 4 Node 121 L TO BENDING 41000 .035 , LEVEL C 1417 : M0 MENT 8 Node 121 41000 .045 : LEVEL D 1845 i k i a;> n- g -
~ g .- Ee& . 4 ,' ,
m 6 s .
TABLE 16CFSARMIIVINLET/0UTLET . N - HIGliEST STRESS SIM1ARY -
, lg , [ ', ' 'l SHOREHAM - MAIN STEAM LINE C gj i s L
Governing i Highest Allowable Load (1) Identification of Equip! Item Evaluated Calculated Limits Ratio Comb. No. ment with Highest Leadsi ' Load a, , I LEVEL A 6036 15375 .393 1 Node 91 & 85 ; STRESS DUE LEVEL B 6172 41000 .15 2 Node 91 a TO AXIAL LEVEL C 6720 41000 .16 4 Node 91 i I LEVEL D 6864 41000 .17 8 Node 91 H [ N LEVEL A 543 15375 .035 1 Node 107 911 41000 . 62 2 2 Node 107 STRESS DUE LEVEL 8 TO BENDING 1339 41000 .033 4 Node 107 F10 MENT LEVEL C 1542 41000 .038 8 Node 107 LEVEL 0 4 i e e l i b
i NUCLEliR POWER ' STEMS ENGINEERING DErRTMENT MEM3 . G.I. Samstad R.W. Hardy Attachnent' 8 DATE: August 27, 1982
.' t[ R.L. Lebre . ~
Specific Item No. 7 REQUIRED RESPONSE J.C. Kelso/E. Intrator DATE: rnou: ,
. FOR: ACT,10N O SUB>t CT: SHOREHAM RCIC TURBINE SEISMIC SIMILARITY DEcis10N O ANALYSIS INFORMATiord - Q
~ PWA 2613XS Rev. OC requested, for the SQRT progran, a similarity analysis between the Shoreham RCIC turbine and the turbines that were dynamically tested. This ' letter presents the results of this analysis. In order to prop'erly support the similarity claim, submitted drawings and other cesign information were extensively reviewed for identifying the differences between the Shorehan RCIC turbine and the turbines which were tested. Also, during several visits to the turbine vendor's facility, detailed " bills of material" and other proprietary manufacturing drawings were reviewed. The results of these reviews confirm that many areas of the turbir.es are identical in design. There are, however, specific differences between the turbines, sone totally insignificant, such as changes in the oil well cover plate design, while others receire engineering judgcent or analytical efforts to justify the claim for similarity. These latter areas are sner.ifically identified below, with justification offered for similarity claim or recommendations for corrective action. Base Plate Desien (Refer Turbine Outline Drawing 65818E
- Yersus Eb53E, a' lid the Proprietary Base Plate Drawing 65983C Versus 675170)
The coupling end pedestal for the Shoreham P,CIC turbine consists of two square columns, whereas the tested turbines had a solid rectangular section for the coupling end pedestal. An analysis of the Shoreham type base plate by Science Applications Incorporated (Marvin Cohn, dated August 28,1980) confirmed its capability of with-standing the required dynamic loads. There are other differences in the respective base plate designs which do not affect dynamic capability, such as grout hole locations, oil filter orientation, and a minor change in the location of the anchor bolts. The SA1 analysis also concludes that the #8 taper pins used for coupling end align-ment are adequate, but marginal. The first qualification test program was conducted on a turbine using (8 taper pins, one of which failed after 31 tests and an accumulated test time of almost 15 minutes (refer VPF 3622-79(1)-2, Tab 2, response to N0D-7 for more infornition). The turbine used in the second test program used (9 taper pins and lock plates for the pedestal bolting. No problems were encountered, but it should be noted that total test time was only 6.5 minutes (refer VPF 3622-527-1 , for more information).. ACTION: Consideration should be given to the modification to install #9 pins an'd pedestal bolt lock plates. FD1 114-88524 will be issued to define this installation.
~
cc: C.W. Dillmann, J.S. Mokri, M.P. Patel 88E DG 917 (RE V 7/79)
1 f Oht.
. 8-27-82 .Page 2 .
pwer Half Turbine Case The Shorcham lower half turbine case is essentially the same as those used on the test turbines. There have been minor changes in machining for improved productivity. These changes are judged to have no effect on dynamic characteristics, ifpper Half Turbine Case The GS1 RCIC turbine has lower half steam admission only. As such, the upper half turbine case does not have a high pressure steam ring (refer section drawing 77322E vs. 99019E). The casing is rigid, but with less mass, resulting in less dynamic loading on the support pedestals. j Turbine Shaft I l The machining of the Shoreham turbine shaft outboard of the governor end bearing has minor differences from that on the test turbines due to different overspeed trip designs (refer section drawing 77322E vs. 99019E). These differences do not affect the dynamic characteristics of the trbine shaft. Overspeed Trip Desion The Shoreham turbine uses a " disc type" mechanical overspeed trip design whereas the test turbines used a " pin type" design (refer drawing 65638B vs. 98501D). Externally, the trip assembly components are essentially the same, with minor differences in the stem length on the tappet-ball holder, the connecting rod length, and the bracket design for the limit switch attachment. The major difference is internal, i.e., the trip actuating device -- disc versus pin. As is evident from the referenced drawings, the trip devices are spring loaded, small mass components which are judged to be insensitive to external dynamic loads. l In the unlikely event that an overspeed transient occurred simultaneously with a l seismic (or other dynamic loading) phenomena, it is possible that the actual trip [ speed would be lower than design. However, this possibility would probably occur with both trip devices. ACTION: No action is deemed necessary. However, if the customer is i concerned, th'e turbine shaft could be modified to accept conversion to the " pin type" trip device. _ Governor Valve The governor valve on the Shoreham RCIC turbine is smaller than the valves used 3 cn the test turbines. The valve internal design is also different (refer j drawing 77336D vs.101180D). 1 The steam forces associated uth governor valve operation are judged to be sub-
.stantially greater than the forces related to external dynamic loads, thereby
)l rendering the external loads as insignificant. The operability of both valve j designs has been demonstrated by test and by actual operating experience. L l l
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J- . j'. * .DJst. \* 8-27-82
- r
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I Finally, with the smaller, but rigid valve body, the forces associated with external dynamic loads are inherently less at the valve / turbine inter. face.
~
Trip and Throttle (T&T) Valve , The Shoreham RCIC turbine uses a 3" - 900f Schutte and Koerting T&T valve, with overal'1 dimensions (inlet centerline to top) of 40-1/4" and face to face (inlet to outlet) dimension of 15-1/2". The test turbines used a 4" - 900# Gimpel T&T valve, with comparable dimensions of 41-3/8" and 17-7/8", respectively (refer drawing 69-XE-41 vs. 89621E). s.a i Review of the referenced drawings substantiates the claim for similarity between the two valves. The only major (but judged to be inconsequential) difference is that the Shoreham valve uses a G.E. trip solenoid -- push to trip, whereas the test turbines use a Thrombetta trip solenoid -- pull to trip. The actual trip nechanism is essentially identical on both valves. One $rea which could not be verified in the record search was the stiffness of the spring used on the trip latch assembly on the S&r, valve. During the first cual , test program, we found it necessary to increase spring stiffness to 25#/ inch . in order to prevent trip latch separation during the resonance search tests (refer, to YPT 3622-79(1)-2. Tab 2, response to NOD-2 for detailed information). ACTION: Verify stiffness of the trip latch spring used on the S&K valve. If necessary, replace with a spring having a stiffness coefficient of 25#/ inch FDI 114-88524 will be issued to define this irispection activity. - Turbine Electronic Controls The electronic and electrical / hydraulic controls used on the test turbines included: Power supply (dropping resistor) - W8270-281 Ramp generator / signal converter - W8271-083 and W 8271-590 EGM Control Box - W827i-236 Hydraulic Actuator - W8250-133 Hydraulic Servo - WW8250-190 Dur records indicate that the following comparable equipment was originally installed on the Shoreham RCIC turbine: Power supply (dropping resistor) - W8270-281 Ramp generator / signal converter - W 8271-083 EGM Control Box '
.WW8270-849 -
Hydraulic Actuator' - WAS250-133 - Hydraulic Servo . W8250-190 The only difference between the controls of the Shoreham turbine and the tested turbines is the EGM Control Box. Purchase Order 205-YC852 has been issued to
. replace the Shoreham EGM Control Box by Model 8271-236. In addition, this P.O. .also provides replacement of the RGSC by Models 9903-091 or 8271-590, both qualified.
F01 1)3 88524 has been prepared to define the installation of the new components. ACTION: Already taken.
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Dist' 8 27-82 Page 4
- i Turbine Oil Piping . ,
The turbine oil piping is the most difficult area to define design similarity. Unfortunately, the RCIC turbine oil piping was installed via a flow diagram only, without the use of an arrangement drawing. As a result, each RCIC turbine has a , more or less unique piping arrangement. However, each arrangement presumably has adequate support to satisfy the minimum criteria defined in the seismic analysis (refer VPF 2757-35-1). However, with the criteria for new load evaluation moving the frequency range of interest up to 60 Hz and beyond, additional piping review is recommended. ACTION: FDI 121-88524 has been ' issued to define the required piping review and the addition of piping supports. The above information completes the required response to PWA 2613KS, Revision OC, Task 6. Support information will be maintained in Design Record File #E51-88.
%$ w/$/y/ .C. Kelso Reactor Assembly & Plant Equipment Qualification MC-750, X51819 -
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0 r I MEVistoN FIE LD DisPOslTION INSTRUCTIO R.W. HARDY ,,,,7 1 o, h D g 'g g E D$ o 8S Pn NEc7 Shoreham j HPCI and RCIC Turbine Control Electronics N EcumwEwr m
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w o uo. E41-C002 and E51-C002 KS-01-1042 ,, DisCRWTioNOFTAsK Purpose of Instruction The project has cormitted to upgrading critical electrical / electronic components to the qualification standards of Class 1E equipment. It is therefore necessary to replace existing electronic control components on the HPCI and RCIC turbine with new equipment, equivalent to that qualified by test. This new equipment has internal design improvements which enhance overall operability; externally the new equipment will be a "one for one" replacement with the existing equipment, except for terminal designations. Required Documents HPCI Turbine Instruction Manual, at site RCIC Turbine Instruction Manual, at site Woodward Plant System Wiring Diagram 9976-717(VPF3622-25-2), included Material Required The new electronic control components include: Woodward Governor EGM Control Box for the HPCI Turbine, Model #9903-109 (Terry Corp. Piece #890004A04) Woodward Governor EGM Control Box for the RCIC Turbine. Model #8271-235 (Terry Corp. Piece #075850A03) Woodward Governor Ramp Generator / Signal Converter Model #9903-091 or 8271-590 (Terry Corp. Piece #890005A02 or 075925A02) This material has been requested via MR #YC852, with delivery direct to site. 6 APPHoVALS oATE APPROVALS DATE 7.as to riputut is sarriv acLaito [T)<cs 0 o
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IS / sartiv rumetee= es arrtetto E vts Q FIELo WORK O6oER No. E.W. Ziebe 1[N?c [ deT3
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__ .- -.-.~ .-...... . - - - . ~ J.' M6. i:'. . - 7 ' ' Fo No. 113-88524 1, . REVIStoN 0 O DisPO Tion INsMUCTION SHEET 2 oF - Of5Cr.PfloN oF ,ASK -
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Procedure _ Caution: Verify proper terminal identification on wiring prior , to its removal. HPCI Turbine Control Component Upgrade l Reference the mounting panel drawing 95414C (Section 15-M-17 of the Turbine t Instruction Manual), remove the existing EG-M control box and the ramp generator / ) signal converter module from the turbine control panel. Note: The original equipment may be returned to Woodward Governor Co. . for upgrading. i Install the new, upgraded EGM control box (Model #9903-109) and ramp generator / signal converter module (Model #9903-091 or 8271-590) onto the existing turbine l control panel. The equipment interfaces (new versus original) are identical, and no panel modifications are required.
- The external terminal designations on the new equipment are the same as those on 1 ECM Control Box Model f8270-811 and ramp generator / signal converter module Model 3 #8271-083. Therefore, install interconnecting wiring in accordance with the Woodward Plant Wiring Diagram 9976-705, contained in Section 8 of the Turbine Instruction Manual.
1 1 RCIC Turbine Control Component Upgrade ] Reference mounting panel drawing 95517C (Section 14-M-13 of the Turbine Instruction Panual), remove the existing EG-M control box and the ramp generator / signal converter module from the turbine control panel. Note: 1) The original equipment supplied may have included an EGM Control Box Model #8271-236. If so, do not remove, as this is the required upgraded unit.
- 2) Removed equipment may be returned to Woodward Governor Co. for upgrading.
[ ! Install the new upgraded EGM control box (Model #8271-236) and ramp generator / signal panel. converter (Model f 9903-091 or 8271-590) onto the existing turbine control - The equipment interfaces (new versus original) are identical, and no panel modifications are required.
- Install interco$ecting wiring in accordance with the Woodward Plant System Wiring Diagram 9976-717 (included with FDI). Note changes in terminal designation, compared with existing diagrams in Section 8 of the Turbine Instruction Manual.
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Quality Control Requirements ~ Site Quality Control personnel shall inspect final equipment installation, and - shall verify " terminal to terminal" wiring in accordance with the applicable plant system wiring diagram. Equipment Calibration The new electronic. control modules shall be calibrated in accordance with the procedures contained in Section 8 of the Turbine Instruction Manual and Service Information Letter (SIL) #351. Schedule for Implementation This FDI should be implemented as soon as the replacement equipment is available on site, and definitely prior to plant / system startup testing. NOTE:
- 1) This FDI defines installation of upgraded electronic control equipment, while maintaining the existing 4 to 20 mA signal input from the system flow controller. Due to a potential " ground loop" problem associated with the Bailly flow controller and the turbine control system, a separate FDI will be issued by C&IE, defining conversion from the existing 4 to 20 mA flow controller output signal to a 1 to 5 VDC signal. The impact on the installation of the new ramp generator /
signal converter module will be to remove the external jumper across terminals 9 and 10, and to move the existing wire on terminal 6 to terminal 10. This effort must be coordinated with the implementation of the C&IE FDI.
- 2) The turbine specification (s) will be revised to identify the con-version from the existing 4 to 20 mA control signal to the new 1 to 5 VDC control signal, in accordance with ECA 800801-1, Revision 1.
Appropriate MR/PO revisions will then be issued, requesting required changes to the applicable vendor control system wiring diagrams.
- 3) Inplementation approved FDDR KS-01-1042.
of this FDI shall result in superseding previously a
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7 OF gw HARDY SHEET __ FIE LD DisPostTION INsTRUCTIO { DATE DF ISSUE 1 ISSUED Bf PD & AC . Shorsham UNIT DATE$~0 N non cT - . guy RCIC Turbine.1EEE Uccrede ESi~C002 - YA W8/s//2 m setud _ [E5CruPTION OF TASK Purpose of Instruction Two qualification test programs have been conducted on the GS-2N RCIC tur assembly provided by Terry Corporation. with test results and report cation test in accordance with IEEE-344-1975, The second progran was retrievable from Vendor Print File (VPF) #3622-79(1)-2.a complete e test results and report retrievable from VPF #3622-527-1. The first program identified several areas where design changes were ' required in order to positively assure that the turbine assembly The adequacy coulddesign of these withstandchanges thewas con-servctive seismic test requirenents. successfully demonstrated during the second test program. The purpose of this FDI is to specifically address each area of potential concern, The and define the necessary inspection and possible corrective action required. items identified in this FDI do not affect GE documents, and ECA/ECN's are not applicable. . Required Documents RCIC Turbine Instruction Manual, at site Vendor Drawing 111904C, Lockplate Assembly, enclosed Paterial Requirements The material required for this instruction is specifically identified in the follow-The material can be obtained locally by site ing procedures for each task. personnel, purchased directly from Terry Corporation, or ordered through the General Electric Company. DATE t.cs touwtm, is sne ti v atta,ao Pges O=c APPROVALS DATE APPROVALS sat tTv r v=.cTio= is m'a t c1to hvts p ~~ jg FIELO WORK ORDER NO. j, gy',',C,,* ,C "g, roc ; YES % NO O g ,, b_@ M W W e/nb= DISTRsBUTION CODE FDi TASK COMPLE TED D AT E fg ? g INTERNAL EXTERNAL
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l' A nevnsson _ O rino oispos: TION INSTRUCTION ogscwrios or TAsx SHtti 2 OF 1_ Procedure . Detailed information follows, defining each area of potential concern, the required inspection,.and the necessary corrective action, if applicable. There are no ,, special tools or handling equipment required in implementing these instructions. If vendor assistance is desired, arrangenents for a service representative can be made through the Project Manager, or directly with: Terry Corporation P.O. Box 555 Windsor, CT 06095 Attn: Robert Theroux, Service Panager Tel. (203) 688-6211 Item 1 - RCIC Turbine - Trip and Throttle Valve Latch Spring (Refer Drawing 69-XE-41 in Section 14-M-10 in the Turbine Instruction Manual) During the first (seismic qualification) test program, the initial test activity resulted in inadvertent, unacceptable closure of the trip and throttle valve. The attached photograph identifies the partial separation of the latching lever assembly at the completion of one of the seismic tests. The coefficient.original latching spring was replaced with one having a higher spring The operability of the solenoid trip mechanism and the mechanical overspeed trip mechanism were verified aYter the installation of the stiffer latch spring, and proved to be acceptable. The seismic qualification test program was then successfully comleted. The second (environmental qualification) test program, including dynamic testing, was also successfully completed. Corrective Action
- Remove the latch spring from the trip and throttle valve assembly, and measure its spring constant, which should be 25 lb/ inch,1 10%.
i not satisfy this value, it must be replaced. If the installed spring does I is Terry piece number The appropriate replacenent spring l of 2.75 inches. 105594A10, a 0.845 inch diameter spring with a free length body and the washer Theininstalled th spring, resting against the " jam nut" on the valve adjustment is necessary. e latch lever, will have the proper compression. No - 32.5 pounds,f, The spring " load" in the valve latched position is i
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_a ety,sson { FIE LD DisPOslTloN INSTRUCTION SHEET 3 or D1sCRIPTioN oF TASK _ Item 2 - RCIC Turbine - Coupling End Pedestal Assembly - During the first (seismic qualification) test program, the entire turbine assembly. was subjected to a total of 33 tests with an accumulated test time of 905 seconds. Approximately one-third of the way through the test program, turbine structural bolting began to loosen. The test facility did not have adequate tools to properly retorque the turbine bolting. Finally, after 31 tests with an accumulated test time of 875 seconds, one of the alignrent dowel pins in the coupling end bearing pedestal failed, and the second pin had an offset distortion of approximately 1/16 inch. Both conditions were attributed to bending loads on the dowel pins due to loosened pedestal bolting. The design of subsequent turbines was modified to use #9 tapered dowel pins in Ifeu of the original #8 pins for alignment control, and to use a positive
" lock tab" for the pedestal bolting. The second (environmental qualification) test program, utilizing these design improvements, was successfully completed.
Corrective Action
. With reference to vendor drawing 111904C, attached, inspect the turbine assembly for installation of the #9 taper pins and use of the positive lock tabs on the coupling end bearing pedestal holddown bolts. If not in compliance, the follow-ing corrective action is required:
Material: Flat washer, 2 each, Terry Piece f75778A07 Locking Plate, 2 each, Terry Piece #111903B
- Threaded Taper Pin, 2 each Terry Piece #111284B Taper Pin Nut, 2 each, Terry Piece #75238A05 Note: (a) To avoid possible disturbance of the turbine alignment, the following procedure is to be carried out on one side of the coupling end bearing pedestal at a tirre.
(b) Should it be necessary to realign the turbine, this should be accomplished before fitting the new dowel pins. (Refer to Section 4 of the Turbine Instruction Manual for alignment definition.) (c) Numbers in ( ) are the item numbers identified on t assembly drawing 111904C. '
- Caution:' This is a special 17-4PH stainless steel pin -
DO NOT SUBSTITUTE' I
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- 1. Remove the existing tapered dowel pin (3). If this pin is smaller
. than #9, drill 1/2 inch diameter pilot hole and ream for fitting the , .
required #9 pin.
- 2. Remove the pedestal holddown bolt (5).
- 3. Locate flat spacer washer (1) on the machined spot facing around the pedestal holddown bolt hole. The washer must sit flat with full face-to-face contact. Any rocking or interference must be eliminated.
- 4. Place locking plate (2) on top of the flat washer (1), and align holes for the dowel pin (3) and the holddown bolt (5). It may be necessary to enlarge the holes in the locking plate to assure no interference with the dowel pin or the holddown bolt.
- 5. With the holes in the locking plate aligned, install the #9 tapered dowel pin (3) fimly in position. Assure that the pin extracting nut (4) is threaded back sufficiently to allow the pin to seat fully into its hole. The shoulder of the installed tapered dowel pin should be approximately 1/16 inch below the edge of its reamed hole (referDwg. 111904C).
- 6. Apply Fel-Pro "Hi-Temp" C5-A lubricant (or equivalent) to the threads of the pedestal holddown bolt (5), install, and torque to 310 to 340 ft-lbs, such that one flat of the bolt head is aligned to facilitate lock plate bending (refer to Section A-A of Drawing 111904C and the attached photo for acceptable orientation).
- 7. Using a blunt-ended tool (brass or wood), bend the end of the locking plate (2) against the flat of the pedestal holddown bolt (5). The bending line should have a small radius, as opposed to a square edge which could result in cracking.
Quality Control Requirements Standard site quality control procedures shall be used in implementing this FDI. Particular emphasis shall be used in assuring that adequate procedures are used - in conducting the inspections defined above, and assuring proper completion of the defined correcf,ive actions. . Schedule for Implementation This FDI should be completed prior to the startup test activity on the RCIC system. NOTE: FDI 12l defines the required additional supports for the lube oil piping.
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FIG.1. LOCKING PLATE IN POSITION ON COUPLING END PEDESTAL FOOT BEFORE LOCKING
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4'V 121-88524 R. i.f}.hM. S[?N.? Eh~N.; 3.T3 i; * , M~iX a_- -"r- _ _ _ J i --- 3 REVl5loN FIE LD DISPOSITION INSTRUCTIONp/ SEP 291982 3 3 SHEET oF R.W. HARDY 3 oATE oF I,5$uE SHOREHAM" paoncT , univ ISSUED BY PD & HC - RCIC TURBINE DATE k U~
'O # M EcNiiniooRip ooR E51-C002 w'L No- . . N/A ,.
OtsCMWisONoFTASK This FDI supercedes Rev. O. The purpose of this FDI is to improve the load carr.ying capability required for confirmatory loads of the lube oil piping assembly by adding supports to the existing pipe assembly. 1.0 Required Documents
~GE document 213A8273, Rev. 1.
2.0 Paterial Required / . The material required in this instruction is a 2x2x3/8 angle (A-36), Plate (A-36) and U bolts as identified in the attached sketches for each support. The material shall be obtained by site personnel. 3.0 Procedure 1.ocate and install lube cil pipe supports in accordance with the attached document. 4.0 Quality Control Requirements . Standard site quality control procedures shall be used in implementing this FDI, including site QC verification of above work. a APPR OV A LS ;' oATE APPROVAL.5 cATE ve*s t.wis=tast is s.e n v a t La,a o D es O: MP PATEL c M 8 4/9 /;./r; **'"""'e"'^"'"' D " " O *': is o..c.. ..o, FIELD WORK 98oER NO. Q "g ' C,,",'
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Attachment 9 -lf
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Specific Item No. 8 E 4 S. E ORE HAM NUC _IA7 .
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POWER STATION c --
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1 UNIT 1 - L ' q 1 +
. SEISMIC QUAllFICATION REEVALUATION , 'l CLASS 1E EQUIPMENT .
i; DIFFERENTIAL PRESSURE TRANS;i!TTER C O M P O N ENT N A M E;5,163c1560,163c15ci, 145C3240,163Cin ( i PP D. NO.: menn. mcisu - _ .Mi s ll MPL
REFERENCE:
C41-nc04 : p
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I . GE DRF A00-992, VOLUME 3 i I ' SUPPLEl1 Erit 1 . 2 THE SE!SMIC CUAtlMCATION REPORT (S) IDENT1AED MERE 1N HAVE DEEN EVALUATED ,1 AND REQUALIRED WHEAE NECESSARY TO SHOW THAT THE ABOVE. MENTIONED
' i 4
3 ; COMPONENT IS CAP ABLE OF MEETING THE NUCLEAR AEGULATORY COMMISSION i SEISMIC QUAORCATION REVIEW TEAM (SQRT) REQUIREMENTS.
; )
q l 1 PREPARED BY3 N*C' Db DATE , e i .' I onciniz,7,on: GENERAL ELECTRIC CO., CONTROL ROOM DESIGN ENGINEE: TING l .1 i I j l REVIEWED BY: DATE N - SQRT PROGRAM MANA *ER / I s
;E .
l APPROVED BY: DATL- b Mb ,
;. QUALIFICATION ENGINEERING MGR. t 9 I t
G E N E R A'l h) E L E CT R I C . j
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s QUALIFICATION
SUMMARY
- 1. Component Name: DIFFERENTIAL PRESSURE TRANSMITTER
- 2. MPL or EDL Item No.: C41-N004, (CE Identification Numberc; 163C1558, 163C1560, 163C1561,163C1563,163C1564 & 145C3240)
- 3.
- Qualification Documentation A. Qualification summary of equipment (SQRT form) including required response spectra.
Attached B. Reference Documents Reference Document Revision or Number Identification Date Title / Subject
- 1.
- GE DRF A00-1084-101 1981 Seismic Test of Rosemount 1151.
- 2. S&W J.O. No. 116.00.02 9/2/82 Required Accele-File No. 930., GEA-2815 rations for Stand Hounted Equipment,
- SNPS-1
- 3. GE DRF A00-794-10 1980 Seismic Test of Ceneric H22 Local Panels.
C. Additional Supporting Documents
- 1. As - Built Reviews of Equipment
- 2. Shipping Group MPL References -
- 4. Requirements This device is required to maintain its structual integrity and operate when subjected to the seismic and hydrodynamic loads as specified in reference 2 and shown on each Shipping Group MPL Reference Sheet.
- 5. Demonstrated capability
- 1. Sin 21 e axis, single frequency vibration tests with a frequency scan of 4 to 70 hertz and a 2g input were run in all three axes. .
Output voltage was monitored during each 30 minute test. Resonant dwells of 30 seconds each were held at the resonant frequencies. Thoughout each test the output was continuously monitored on a strip chart recorder. Output voltage showed no deviation. See A00-1084-101, K for a detailed description of the test.
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,' 2. Another single axis, single frequency test sequence in three axes was performed from 1 to 30 hertz with a 3g input. The cycling I time was 30 minutes per axis, and 30 seconds of dwell at each l resonant frequency was performed. There were no electrical shifts observed or mechanical failures noted. See A00-1084-101, L for ~
test details.
- 3. A multi-axis, multi-frequency vibration test was conducted as shown e in reference 3. The test input 2PA was 7.0g's over a frequency range of 1 to 260 bz. Although the device was mounted on a local rack, the test indicates that the unit can operate satisfactorily during a multi-frequency, multi-axis seismic test.
- 6. Rationale for Qualification Since the maximum expected acceleration for this device at the Shoreham site is less than the tested capability of 2g's over the 70 hertz range, the device is qualified to SQRT criteria. The dual axis test noted in Reference 3 further supports the qualification for mult-axis affects.
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- 145C3240, 163C15580 163C1560, Qualification Summary of Equipment 163C1561, 163C1563 163C1564 s .
(GE PPD Number) I. Plant Name: Shoreham Type:
- 1. Utility: Long Island Lighting Co. PWR
- 2. NSSS: GE 3. A/E: Stone & Webster BWR- 4 Mk II II. Component Name Differential Pressure Transmitter 145C3240;1
- 1. Scope: [X] NSSS [ ] BOP 163C1558;1 163C1560;3 163C1561;1 163C1563;1
- 2. Model Number: Rosemount 1151 Quantity: 163C1564;1
- 3. Vendor: Rosemount
- 4. If the component is a cabinet or panel, name and model No. of the devices included: N/A
- 5. Physical Description a. Appearance Electronics housing attached to pressure sensor.
- b. Dimensions 4.5" diameter x 9" high
- c. Weight Approx. 11 LB
- 6. Location: Building: See attached "As Built Review of Equipment", line III.1.
Elevation: See attached "As Built Review of Equipment", line 111.1.
- 7. Field Mounting Conditions [ ] Bolt (No. , Size )
[ ] Weld (Length )
, [x] See attached "As Built Review of Equipment", line III.3.
- 8. a. System in which located: See device list for system in which each device is located,
- b. Functional
Description:
Instruments perform 1E function in the system indicated on device lists
- c. Is the equipment required for [ ] Not Standby [ ] Cold Shutdown -
See device list for each system. [ ] Both [ ] Neither
- 9. Pertinent Reference Design Specifications: PPD # 145C3240, 163C1558 163C1560, 163C1561, 163C1563 163C15654.
NOTE: 163C1558, 163C1560, 163C1561, 163C1563, and 163C1564 are qualified by similarity to the tested 145C3240.. 12/80 L. - -. . - _ - ' -
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145C3240, 163C1558, 163C1560, 163C1561, 163C1563 163C1564 (GE PPD Number)
~2-III. Is Equipment Available for Inspection in the Plant: [x] Yes [ ] No IV. Equipment Qualification Method:
f [x] Test [ ] Analysis [ ] Combination of Test and Analysis Qualification Report *: CE DRF A00-1084-101,K (No., Title and Date) Seismic Test of Rosemount Model 1151, 9/11/72 Company that Prepared Report: Rosemount Company that Reviewed Report: GE V. Vibration Input:
- 1. Loads considered: a. [ ] Seismic only
. b. [ ] Hydrodynamic only
- c. [x] Combination of (a) and (b)
- 2. Method of Combining RRS: [ ] Absolute Sum [x] SRSS []
(other, specify)
- 3. Required Response Spectra (attach the graphs): Attached
- 4. Damping Corresponding to RRS: OBE N/A SSE 4%
- 5. Required Acceleration in Each Direction: [ ] ZPA [x] Other At location (specify)
OBE S/S = N/A F/B = N/A V= N/A SSE S/S = ** F/B = ** V= **
- 6. Vere fatigue effects or other vibration loads considered?
[ ] Yes [x] No If yes, describe loads considered and how they were treated in overall qualification program: N/A
- NOTE: If more than one report complete items IV thru VII for each report.
12/80
**See device list for individual component required accelerations. Required ac-celerations were provided by Stone and Webster. [
Reference:
Stone and Webster J.O. No. 11600.02, File No. 930, CEA-2815 dated 9/2/82.
.-s %. g ev .,w = g.e , w -e-6m-s.m==w.--e..y.gmw,.q- . - w- , . , -- e
_. . . . . . . . .. .... m.. . . _ _ . . . . _ . . . .. \ .. 145C3240, 163C1558, 163C1560, 163C1561, 163C1563 163C1564 (GE PPD Number) yI. If Qualification by Test, then Complete *:
- 3. [X) Single Frequency [ } random
* [ ] Multi-Frequency [ } sine beat
[X) resonance search
- 2. [X) Single Axis
[ ] Multi-Axis 3. No. search of Qualification (2g, 4-70 bz) Tests: OBE _ N/A _limit and malfunction SSE _ N/A _ Other (specify) Resonance test (3g, 1-30 Hz). Device was A00-794-10. See subjected to 5 OBE's and 1 SSE while mounted on a GE local rack.
- 4. Frequency Range: 4-70 Hz 5.
Natural Frequencies in Each Direction (Side / Side Front /Back, Vertical): S/S = 62 Hz T/B = _7_ _ (minor),50,68, Hz V = 70 Hz 6. Method of Determining Natural Frequencies [x] Lab Test [ } In-Situ Test [ } Analysis 7. TRS enveloping RRS using Multi-Frequency Test 2 g. accel is greater than the ZPA of the RRS [x} No[ ] Yes (Attach TRS & RRS graphs) S. Input g-level Test: OBE S/S = _N/A F/B = _N/A V = _N/A SSE S/S = _N/A F/B = _N/A V= N/A OTHER(specify) S/S = 2 a 's F/B = 2 e's V = 2 z's Also an input of 3 g's @ 1-30 Hz was applied during a subsequent test see GE DRF A00-1084-101 for 2g and 3g tests.
- 9. Laboratory Mounting:
i
- 1. [ } Bolt (No. . Size ) [ ] Weld (Length Transmitter was mounted to a pipe which was clamped to )[] the table (
resonance test) 10 Functional operability verified: Transmitter was mounted on a local rack fo . [x] Yes [ ] No [ ] Not Applicable 11. Test Results including modifications made: Test results were ' _s a t i s f a cto ry. . 12. Other test performed (such as aging or fragility test , including results): _N/A - L
- Note:
If qualification Iten VII. by a combination of test and analysis also ecomplet
, _,,.y.. e.e a "' ' " *
~~._-..u-_- . - ... ... , l ' l
. .4 . 145C3240, 163C1558, 163C1560,' ! 1 163C1561 163C1563 163C1564
. (CE PPD Number) 5/A VII. If Qualification by Analysis, then complete:
- 1. Method of Analysis:
s [ ] Equivalent Static Analysis [ ] Static Analysis [ ] Dynam'ic Analysis: [ ] Time-History [ ] Response Spectrum
- 2. Natural Frequencies in Each Direction (Side / Side, Front /Back, Vertical):
S/S = F/B = V=
- 3. Model Type: [ ] 3D [ ] 2D [ ] ID
[ ] Finite Element [ ] Beam [ ] Closed Form Solution
- 4. [ ] Computer Codes:
Frequency Ronge and No. of modes considered: { . [ ] Hand Calculations -
- 5. Method of Combining Dynamic Responses: [ ] Absolute Sum [ ] SRSS
[ ] Other: (specify)
- 6. Damping: OBE SSE Basis for the damping used:
- 7. Support considerations in the model:
- 8. Critical Structural Elements:
Governing Load or Reponse Seismic Total Stress A. Identification Location Combination Stress Stress Allowable Maximum Allowable Deflection B. Max. Critical to Assure. Functional Opera-Deflection Location bility k i 12/80 S
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SEISMIC OUALIFICATION REEVALUATION OF NUCLE.1R' SAFETY RELATED EQUIPMENT : 1 : SH GP MPL
REFERENCE:
C41-5110 TITLE: STDBY LIO CON LCL INSTR : PL 028X153TFC001 : , i : REQUIRED FOR: ( ) HOT STANDBY, ( ) COLD SHUTDOWN, ( )BOTil, (X)NEITHER : REV 1 : l 's- - - - - - - IIESC RIPT ION ------- :E:SFISMIC CAPABil.ITY/ : MAXIMUM EXPECTED : NATURAL FREQ. : l EQUIPMENT NAME : IDENTIFICATION :C: MALFUNCTION l.IMIT : ACCEL.ERATION AT LOC.: (Hz) : I
- s
- : : : : : : : : : I 6
MPL NUMPER : : : F-B : S-S : V : F-D : S-S : V : MTG. INSTR; i
- _____________________'____: :_:-_____: _____: :______:______.______:____________.:.. l.
i :1EMPEAATURE SWITCH :157C4629P901 :P: ---- : ---- : ---- : ---- : ---- : ---- : ----------- : 1 l : U.11 !!993 : : : S.A. : S.A. : S.A. : : : : : INDICATOR, PRES 50RE :163C1184P017 : : ---- : ---- : : .:
- P:
( l' '
- .41 R903 : : : 15.0 : 15.0 : 15.0 : 1.0 : 1.0 : 1.0 : 6 100+ :
.I : T P At4SM I T TER , ~ GAGE PRESS :163C1563P917203 :P: ---- : ---- : ---- : ---- : ---- : ---- : ----------- :
l _1>:C41' t:094 : : : 03.0 : 03.0 : 03.0 : 1.0 : 1.0 : 1.0 : 6 50 : j : : : : ___. : ____ : ____ : ____ : ____ : ____ : __________. . t i
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AS-3CII.T RE*!!!"J OF ECUI?MCTI'
- . Plz : Mr=e: Sh:::hn= tree: Zi.?. 4 .'C: II
- 1. Utility: ' :* C0
'2. NSSS: E 3. A/E: Stone and Webster II. Ecui:=e:: Iden:1fics: ten (to be completed before field inspection)
Scope: BCP.
- 1. Name: ?rcssure
- 2nstitter
- 2. Vendor (manufacturer if different) and model nucher:
Reusenount. Mede; 1151
- 3. S&W Mark number: ICf. *?T002
- 4. Drawing nu=ber: 7.62-133J (Vendor or S&W file)
- 5. Location given by S&W records:
, S&W Dwg.
( Elevation 112 f t 4 Building sc Source 11600.02-FK-1H III. Installation Reviev (to be completed during field inspection)
- 1. Actual location: 31dg SC Elev 112 f t Col. No. 9
- 2. If not installed: .
Reason: N/A Present location
- 3. Mounting: N) Floor [ ] Pipe * [ ] Other (See Section VI. Supplenental Re= arks) (Describc) -
. - - - - .- -- De scribe- the weldin g. 4 r holcin g.. for: --- - ----- .- - --- - - - -- - - - - - - . . ,
Drawing (4) 1/4 in, dia bolts (SH1-3'43, Sketch K-25;-2) Field (4) 1/4 in. dia bolts . If different, gise E&DCR No. and date N/A - (attach copy)
- to valve bonnet for operators
- 4. Equipment matches the drawing [X).
If not, describe differences N/A l e
. . . . , . . , , , a. - .*-*=e*.--*em--****-****e**.****""*b * "' '*- * ' * * ' " * " * ~
. ~ . x _w . .a- e a 2 =a.,__.--....... /. . .. s. *C ..
Cil::0 % D .
- 5. 3ase.;rnfigurati:n
^
Wedge Anchers(O 1/2 in. 0.0. ezch baseplate E= bed =ents e Supple =en:ary Steel Descrip:1cn: IV. Namer 12:e Ec de - (:: be cr=,,leted during field inspection)
- 1. l.ocati:n en equip =en: Too
- 2. Type IX ) .Me:a1 plate bended or riveted to equip =en
( ) If not, describe
- 3. Na=eplate contains the following inforr.ation:
[X ] Equipnent Name Pressure Trans=itter [X ) S&W Mark Nu=ber 1C41*PT002
/ Rose = cunt
( [X ) Na=e of Vendor (=anufacturer if different) [ X ) Vendor Model No. 1151 V. _P_hotocraehic Record Take photoBraphs of the =ounting. If the equip =ent is =ounted on a support structure such as a duct or instru=ent stand, take photographs of :he support structure and the equipment together. On the back of all prints, s:a=p with your "noted" sta p (approxi-mate date photo was taken) and shew the equipment = ark au=ber. VI. _Sucole= ental Remarks
- - - - - - -- - - - -(A s-Bu i-i t -Lo ad s ). . - .Ye s- X. -- Ko. - - - - - - - - - - - -- - - -- - - - -- -- - - - - -
Instru=ent =ounted on double les floor stand. (SH1-343) Reviewers Sta=p: NIO NAS 2 O bb2 C.03 " Initials < . . Distributi.on: -- Original to the As-Buil: Record
- Copy to the Seis=ic File Photos in the Equipment Albu= (pasted)
Central File Package (at site)
~ *
, ' ' " ' 'C4E~ _,. ,_ .".Y.. ~ - ' . eE '
' *R9 ? *
. e Attachment 10 in C *. . Spacific Item No. 8 k . ,
t I p-me A
. t i yd..na ,vmcd ~
l Twx: sto-57s si 3. TELEX 39 0123 I
*i SEISMIC QUALIFICATION TEST FOR 1151/1152 PF.ESStlFI TRANSMITTER WITH STAINLESS STEEL .
- ELECTRCHIC HOUSING s ,-
RMT F4 port 2758 i . I
. Israil Isra11 . 2,W~. .~ ., . , . . ~ . . . . -
y?'. . ,~ . : s- >. . Vf SEI.SHIC QUALIFICATION TEST l
- FOR 1 151/1152 PRESSURE TRANSMITTER WITH STAINLESS STEEL ELECTRmIC HOUSING
- RHT Report 2758
- 1. SC0k AND SUM $. RY '
This report covers a seismic test en a Rosencunt Pressure Transmitter model 1151/115 with stainless steel (SST) electronic hcusing. The test was perferned at E viren Laboratories, 9725 Girard Avenue South, Minneapolis, m 55431. Two configurat ons were tested, namely solid rount and with panel neunt mot.nting bracket (RMT Nh. 01151-0035-0004). The data obtaired shows minimal effec the given seishic vibratien input en the transnitter perfomances. A fragility limit of 3 9 was established for the bracket asse bly and in excess of 4 g's for solid rount.
- 2. TESTkNG 2.1 Gene'r al The seis ,ic qualifications of Resercunt mocel 1151/1152* is intended to demcnstrate thy e:;u.pnent's ability to perfctm its function and within its specified accuracy during and after the time it is subjected tc the forces resulting fren a prespecified s{isni: spectrun. The transnitter is subjected to the seismic tests while simulatijg tne operating conditicns as proof testing and to detemine the transmitter (w{th SST housing) capabilities during such test, p ___ _
, 'Nodel 1151 is; mechanically identical to nadel 1152. Model 1152 has the re- }
d quiments of $aterial traceability o'f pressure retaining parts and the use of non Teflon wird in its assembly. f
< _ _ _ _ __=. - - - ._ - ._ . m - . a - ~
- a. - -- - ~ _ _ _ . = . . . . -- . _
Attaclunant 11 -
. Sp cific Ittm No. 10 SHORElIAM EQUIPMENT QUALIFIED BY SINGLE FREQUENCY / SINGLE AXIS TEST Equipment No. Spec Equipment No.
Spec Items Item Description Item Item Description 310-2 Mtr Operated Cntrl 20 39-1 4.16 kV Metal-Clad 3 Switchgear Valves (Act'uator) 54-1 Fire Dampers 38 310-3 Mtr Operated Cntrl 12 Valves (Actuator) 318-1 A0V - (Solenoid) 2 89-1 Aux Skid & Accessor. 24 318-2 A0V (Solenoid) 2 89-2 Gen & Exctr Control 3 Panel 318-3 A0V (Solenoid) 2 Engine Control Panel 3 (Limit Switch) 2 89-4 Diesel Engine 3 318-4 A0V (Solenoid) 2 89-5 (Limit Switch) 2 89-6 Starting Air Rec'ver 12 318-5 A0V (Solenoid) 17 89-7 Starting Air 6 (Limit Switch) 17 Compressor 318-6 A0V (Solenoid) 6 105-1 Cont. Rm. AC Filter 2 (Limit Switch) 6 Trains (El Comp Only) 318-7 A0V (Solenoid) 4 RBSVS Filter Trains 2 (Limit Switch) 4 105-2 (Elec Comp Only) 319-3 Cntrl Pal (Pal Only) 9 111-1 A0V (Limit Switch) 6 (Solenoid) 6 348-1 Press - Temp Switch 4 111-3 A0V (Solenoid) 4 348-2 Press - Temp Switch 15 (Limit Switch) 4 406-1 Resist. Temp. Detector 18 I 118A-1 125 V Static Battery 3 14 l Chargers 423-1 Chilled & Service Wtr A0V (Solenoid) 7 120-1 B.O.P. Main Control 1 (Limit Switch) 7 Board (Elec Comp Only) 423-2 Temp control Valve 124-2 Dist Panel Board 12 (Solenoid) 2 (Limit Switch) 2 134-1 Reactor Cont. 10 Elec. Penetration 423-3 Temp Control Valve , (Solenoid) 2
- 172-1 A0V (Limit Switch) 8 (Limit Switch) 2 (Solenoid) 8 GRP-1 Limitorque Oprtors 165 310-1 Mtr Operated Control 4 Valves (Actuator) CRP-2 Limitorque Oprtors 54 CRP-3 Limitorque Oprtors 4 GRP-4 Limitorque Oprtors 12 B3-11600.02-MS95
i - Attachment 12 s 1
*g .. .
Specific Item No. 10
',----t- t ygw. ;. a .= = c . .mx - - r ; : n-7 u ' v ' :- " S2 :D ? M - = l * ~2 .7.r - ~ - --- -.m c ._ - --
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. jp .j .- SHOREHAM SORT DRF# A00-992 .
1 [ t i Rev. 1 l s/5/81 1 S HOREHAM NUCLEAR } i t POWER STATION '
'I<
r UNIT 1 - . i 1. u
.I ti f i E. BEISMIC OUAl.lFICATION REEVALUATION j Ii E
CLASS IE EQUIPMENT ' f fl LOCAL PANELS
.1 i
J il 1 SAI f 029-QA-80-PA Rev.2 - [ h h 2 0
.~{ l }
Prepared by: E S. RAMADAS A k0/ l :2
; April 3,1981 ./ -
- j i
[ Date: f ! l i j Orgon!20 tion: SCIENCE APPLICATIONS, INC. l s: 1, I 5 Polo Alto Scuore, Suite 200 )4 J 5 Polo Alto, Collfornio 94304 ,{
; I l t ,
t 1 i 1 j
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f i f- 4 i it } i
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3 . 5 l . , 2 8 \
l- ) J : t I i GENERAL h, ELECTRIC !
-- =- . _ . _ m _ ,.. __ r s ; . r, Uy W R 7 r OU'37'TFf E_ "4,71* *-**," ".7 ?? 'l-g g ;. q. -- y a ,*ag.g* 'F**"*'.
.... .:: : n . w ._- ._ ~~ =
- s
,a a e I, Table 2 ,' - SHOREHtM NUCLEAR PO'a*ER STATION t
I .- N555 CLASS 1E LOCAL PANEL DEVICES WITH SItiGLE AXIS ,
/ MAXIMUM EXPECTED ACCELERAT10'4 AT MOUNTING. LOCATION. -
f - MAX. EXPECTED ACC. AT ANY IEEE 344-71 CAPABILITY LOCATION O'l MP1 # GE PPD DWG# (MAX.ACCN ON TESTED PANELS) SHOREHAM PA'iEL5 s-s y f-b s_s v f-b - i
' 1.41 15.0 3.0 5.4 15.0 ! 15.0 .!.
145C3008 Ol$'d!![ej ' 2 ^ i s ' 1,41 821.h06.N09.%021;t31.ND19- ' 11.0 ' 11.0 3.0 8 6.8 e
* :22;t21.sca.m:5.tst.a:1. 145C3009 11.0 ; ; ;
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.-- .i - , s' " . . . * ' 1ABLE - 2 Shoreham Nuclear Power Station toistrol Room Panels Class 1E Devices Qualified With Single Axis Malfunction Limits at u / Least 1.5 Times Expected Acceleration at Mounting Location. l Maximum Expected Acen 1EEE-344-1971 "
GE PPD Dwg # Tested Malfunction Limits Sho ha s
~ MPL s-s y f-b s-s y f-b 8 5
8 l * ' c 5218 5. E31A-5. 25 25 3.0 2.0 l 1.0 272A8270 25 Li'"***$~,[.[41A-5. , 8 i 25 1.0 l 1.2 ! 1.3 141A 5 272AB272 25 ! 25 l I I I i
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2.5 2.0 l 1.6 tu A s. tria.s.141 A-5. ts1A-5 272AB274 . 10 , 10 l*10
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E*'I 272A8275 . f. . e s . 2.5 2.0 2.0 (41A-s 272A9052 25 l. 25 ~l . 25
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The malfunction limits shown are for a chatter detector timing of 10 milisecs.
"The max malfunction limit in f-b is the acen this device was subjected to on tested panc) RPS Division B1 & B2' Logic Vertical Board, Lasalle H13-P611.
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I p i SEISMIC QU IELIFICATION . EQUIPMENT REEVALUATIO i t
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i Shoreham Nuclear Power Station Control Room Panels Class 1E
* .. Devices Qualified With Single Axis Malfunction Limits at /
Least 1.5 Times Expected Acceleration at Mounting Location.
/
- Maximum Expected Accn IEEE-344-1971 at any locaticn on
- MPL GE PPD Dwg # Tested Malfunction Limits Shoreham Panels.
f-b s-s v f-b s-5 v I i e s21t E s21w.r. C71A K , ,
, ti1A.K. [21A.E. [218.K. 13683137 8.4 e 11 l 7.5 5 '. 6.5 0.8^
E414.r. [51A-E g , . . ? s ; ; ' I 8 e s (211 5.921C.s.521A.5 3 2.7 8.8 5.0 145C3040 20 20 20 , e ] . e21H.5.t51A.s , e
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[41.is03 E51.x603 145C3027 15 15 ! 10 1.6 l 1.0 ! 1.0 5211.F. 521C.K. B21h K. l .
- l 011.r. EllA.K. [51A.x 145C3035 ~25 8 25 ; 25 5 . 6.5 ; 0.8
.' l DIA.K 145C3209 12 12 l 12 5 ! 1.2 I 0.8 . ; . i
' UIA-5 159C4282 10 ! 10 I 10 3 ! 3.2 ! 3.2 E32.h!!D. hif1. h655 k
- h656 nsss.nssi 159C4660 13 l 13 l 13 1.6 ; 1.0 l 1.0
! I i s21 s.z ! 8.0 3.0 ! 2.2
- 0.6 163C1285 8.5 e 9.0 !. :
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a a ., [32 8651. Rt52. R65 . , atie 164C5288 8 l 18 l 7 3.0 1 2.0 1.0
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111A 5. (I1A 5 [41A.5 I ! I 234A9327 25 ' 25 ; 25 2.5 ; 8.8 ; 5.0 l l : .
'#I*'5' U IA-5 234A9329 25 l 25 l 25 3.0 l 2.0 l 1.6 ! I s2in.s ! l i l.
234A9337 25 l 25 ; 25 3.0 ; 2.0 ; 2.0 trix.5 e ; 2 262A6023 25 i 25 s. 25 1.2 i 1.0 ' 1.3 i e ts1A.s 262A6824 25 25 25 1.0 l 1.2 l I 1.3 T I t tila.s 272A8268 25 25 l 25 1.0 ! 1.2 1.3
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.s SHOREHAM SHIP LOOSE DEVICES QUALIFIE0 BY SINGLE AXIS / SINGLE FREQUENCY TESTING p REMARMS ;;
c.EIStitC C APADII.ITY / 11ALFUtlCT10tl Lit 11T (GE REFERENCES) i itAlfE V i I DEllT IFIC AT r ott F-B S-S m ! A00-1684-91 t 95.0 05.0 05.0 l I TEMPER ATI. IRE El EMET lT 145C32 4 03.0 03.0 03.0 A001084101W - 145C 3249 DIFF PRESS TRAt!SMITTER
, \ \ 1-t ??.0 29.0 ?.9 . 0 .A001084-141 PPESSUPE StilTCH 03.0 02.0 e's 101084-150 l i 159C4606 03.0 l 's . II - II .;- 11, TD17 16 3C1107 Ft.0tl METER 15.H 15.0 g I!!DIC ATOR , PPESSURE lic.t - 12, T r: 7 163C1134 tS.O 15.0 1 S . li t Stl! TCH , PPESS ItllitCATIllG t 0.14 10.0 10 . t:' f.Il010P 4 - 16?. j t.'3C1185 TP AllStil T TEP, PRESSifGE 03'.0 A001084101W i S 3C 1164 93.0 03.0 ?
TR AtlSit! T T ER e DIFF PRESS 0 3. tl 03.0 03.11 A001084101W I 1 3C 154 s:1 TP Atistil T T EP , CAGE PRESS 15.0 A001004-215 163C157 3 15.0 15.0
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164C5359 St!! T C H . PPESSUPE 03.0 03.0 A001084101W TRAtlSitITTER, ABS PRESS 03.0 A001084101W 163C1558 03.0 03.0 03.0 TRAflSHITTER, DIFF PRESS 03.0 03.0 A001084101W 163C1561 TRANSMITTER, GAGE PRESS 03.0 163C1564 e 1 SHEET tilitIDER
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