ML20249B446
| ML20249B446 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 01/04/1996 |
| From: | Dyckman J, White T BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20249B442 | List: |
| References | |
| C15.0.3273, C15.0.3273-R, C15.0.3273-R00, NUDOCS 9806230124 | |
| Download: ML20249B446 (65) | |
Text
_ _ _ . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _
& Boston Edicon CALCULATION COVER SilEET h
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PILGRIM NUCLEAR POWER STATION lSh I of p2,sf l REV.O FILE NO . SR @ R TYPE CALC No C15 0 3273 NSR O >
Subject Residual Heat Removal Heat Exchancer E207 A & E207B GIP Evaluation Preliminary Calc. O :
Finalization {
Discipline Division Manager: I{h-6 Due Date:
Approval /s/: . -w &, y- i 12 y
. Date: /, j fh Final Calc. @
independent Reviewer: CHAE) M T P TT6 /Shd WbMShtmhd @
Agreed 7 By J G hvhnum Date Ch'k'd/d. diar </4 Date Page(s) 0
/S/ A iM Ar_1 /S/ b . _ _ _
~~ I N ~I Table of Contents' f 10 Problem Statement l 23 Sununary of Results 1.0 Method of Solution 40 References 50 Calculation General Arrangement Resolve Nozzle Forces and Moments Compute D)Tiamic Response Characteristics Compute Seismic Inertia Forces From Vessel Combine VesselInertia & Nozzle Forces Compute Support Stresses Conclusion Attachments:
A. MSED 94-46 NEDORANDOM with E207 nozzle reactions (3 sheets)
B Preliminary Evaluation Checklist (2 sheets)
C. Independent Evaluation Checklist (3 sheets) l l This design analysis DOES O, DOES NOT @ require revision to design documents.
Affected Design Documents:
5 PDC 15 0.IS NOT @ Required.
A Safety Evaluations O,IS NOT @ Required.
This design analysis DOES O, DOES NOT @ affect the piping analysis index (PAI). If the pal is affected, initiate a
re sion to Calculation M561.
Minor revisions made on pages of this calculation. See next revision.
Replaces Calc No.:
Voided by Calc No.: O Or Attached Memo NESD 3.05 Res.19 JGDMM335 9806230124 980615" PDR ADGCK 05000293 P PDR
CALCULATION SHEET Calculation #: C15.0 3273 Resision: 0 Date; 10/30/95 Prepared by: 10 Dvekman Sheet 2 of 24 Checked by: W. Diordievic SR @ NSR O 1.0 PROBLEM STATEMENT A seismic adequacy evaluation is required for the Residual Heat Removal (RHR) Heat Exchangers E207 A & B to address Unresolved Safety Issue (USI) A-46 concerns.
2.0
SUMMARY
OF RESULTS The configuration of the RHR Heat Exchangers do not permit them to be evaluated using the specific methods of Sections 7.3 or 7.4 of the Generic implementation Procedure (GIP). As permitted by the GIP, an alternate method is used to evaluate the critical features of the vessels and their supports for seismic adequacy. The results show that these components and their supports meet design requirements.
'l 0 METHOD OF SOLUTION The RHR Heat Exchanger is venically supported by four heasy plate saddles approximately one third of the way down from the top The vessel is treated as a rigid body, transmitting piping nozzle reactions ind inertia forces through its suppon saddles to the structural steel frame. Tube and shcIl side fluid is under system prewure and flow, and is assumed to respond as part of the mass of the rigid body.
The response frequency of the supporting structural steel frame is computed by using single degree of freedom and an uncoupled two-degree system approximations. Resulting frequencies are varied 120% when used to obtain accelerations from in-structure response spectra to compute vessel inertia forces.
Structural analysis evaluates stresses in load path elements including the saddles, saddle bolting, and support beams. The vessel shell is 11/16" A515 Gr 70 steel andjudged to be adequately rugged to transmit nozzle and vessel inertia forces to the saddles. The suppon beam embedment was also judged adequate to develop beam capacities.
4.0 REFERENCES
- 1. Drawings C-60, C-91,2521-13-4,2521-5-4,2521-9-1 and 2521-16-1 2 Generic implementation Procedure, Rev. 2 '
Specification C-114
- 4. SEWS for E207 A and 207B NESD 3.05 Rev.19 JGD/hv95335
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dk%AMcd k t/9~ 4 NS" C\%c.n M l NEDORANDUM . MSED 94-46 From ,_JP Gerety/GJ Bechen Date 5/31/94 j To W.R. Kline .. l l
Subject:
Nozzle Loads for Heat Exchangers requiring A46 Analysis: E206 A&B, E207 A&B l E122 A&B, and E216 A&B f209 A&B,V l RIplies to: CSD 93-151 R1ferences: . CSD 93-151 (Copy attached) ;
\
Heat Exchanger Nozzle Load Sumrinary Sheets R: ply Requested: No i R: quested Date: NA Massage: (Use attached sheets if required) The attar! M Nozzle Load Summary Sheets provide the requested loads. All loads ie arted are based on analyses using 1/2 % damping for both the OBE and SSE conditions. All significant piping loads are reported with the exception that piping attached to the following nozzles is non-safety-related and loads are not available. Non-Regenerative Heat Exchanger Nozzles E206 A N1 Outlet [ E206 A N2 Inlet E206 B N1 Inlet E206 B N2 Outlet Distribution: CC G Bechen O Nuclear Engineering Manager O Nuclear Engineering Deputy Manager gM id[g O Field Engineering section Manager O Design section Manager O Ar.alysis Section Manager I
Ht Exchanger E 207A Nozzle Loads AMuce A ClgA 3 2 ;<3 g i ! E 207 A D* Nozzle Leeds Forces Ob) Moments (ftIbs) 12" Dettet
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- see equip dwg markup N
#ef, Piping Calc + x-east + y -up + z-south 821 rev 6 Lead Case Fx Fy Fr Mx My Mz pf*f/h/f t}g6 ES 4 Owt 75 315 76 -57 602 258 4684 192 8228 271 9475 SSf- V2/4 Thermal 895 OBE 153 57 412 1954 2726 573 Node 5 SSE 287 107 773 3664 5111 1074 QN l
'E 2078 C* Nozzle Loads Forces (Ib). Moments (ftIbs) Ek hk V 12" Outlet + a-into the nozzle
- see equip dwg markup
#ef. Piping Calc + b-up yQ 622 rev I I Lead + c-normalto the nozzle Case Fh Fc Ma M6 Mc AfM/?A/f Fa o.9 6 E A 'A Dwt 26 687 17 119 54 194[
Et fp*4 Thermal 1874 524 1524 1231 5747 3021 l' OBE 13 6 36 43 201 56 24 11 68 81 377 105 Node 75 SSE E 2078 8* Nozzleloada Forces (Ib) . Moments (ftlbs) 16" Outlet
- see equip dwg markup
#e/. Piping Calc + x-east +y-up + z-south N i
664 665 rev 6 Lead 8AMA/A/6 Case Fx Fy Fz Mr My Mz M Dwt 446 -4060 217 3515 -215 -3217 ) ! d Thermal 471 4067 1185 18 1843 63 g{ l 228 942 OBE 3952 9243 652 7807 Node 525 SSE 7410 17330 1222 14638 428 1766. M\ Qg E-2078 A* Nozzle Loads. Forces (lb) Moments (ft lbs)
~
- see equip dwg markup
/ 16" Inlet
+ x-east + y-up + r-south N3
#e/, Piping Ca/c 664 665 rev 6 Load cass Fx Fy Fz Mx My Mr l A9A18/An 28 77 46 946
! d6E. Ya % Dwt 6 -402 3919 -8611 7703 566 b % Thermal 1995 1178 566 678 699 1259 5743 3109 1290 1 OBE 4 1272 1311 2360 10769 5829 2420 Node ; 735 SSE l t Pagel L--_______________--______ . . _ _ i
Calculation C15 0 3273 Attachment B
. Page .l. of 2 _
RTYPE A9.02 PRELIMINARY EVALUATION CHECKLIST
- 1. IDENTIFICATION: Document Number: C15.0.3273 Revision 0 Residual Heat Removal Heat Exchanaer E207A & E2078 GIP Evaluation
- 2. CLASSIFICATION:
@ Yes No a. Does the proposed change involve Q listed equipment?
O Yes O No b. For a new procedure, Temporary Procedure, or major revision; does the Procedure contain procedural steps or requirements in the ItSAR? If yes, identify FSAR sections. N/A O Yes O No c. Is this a new procedure or Temporary Procedure that is Fire Protection Program related or a major revision that makes an existing procedure Fire Protection Program related? N/A
- 3. PRELIMINARY EVALUATION:
0 Yes @ No a. Would this modify plant characteristics or procedural steps described in the FSAR? If yes, identify section: ! O Yes @ No b. Does this affect the der.ign of systems, structures or components described in the FSAR? O Yes @ No c. Doe this affect the function of systems, structures or components described in the FSAR? 0 Yes @ No d. Does this affect the method of performing the function of systems, l structures or components described in the FSAR? l 0 Yes @ No e. Does this indirectly affect the capability of safety related systems, structures or components described in the FSAR to perform their functions? O Yes @ No f. Does this create a new test not described in the FSAR that could affect plant safety? l l I Exhibit 4 NOP83E5 Rev. 7 Joo w95ns ) l l _______-_____.a
Calculation CIS 01271 Attachment B. Page ,2. of 2_ PRELIMINARY EVALUATION CHECKLIST (Continued) O Yes @ No g. Would this change modify assumptions used in the accident analyses described in FSAR Chapter 147 If yes, identify sections: 0 Yes @ No h. Does this change affect the ability of a system required to achieve and maintain safe shutdown in an event of a fire? O Yes @ Ne i. Does this change affect a requirement of, or major commitment to, 10CFR50 Appendix R7 , O Yes @ No J. Does this change affect a requirement of IE Circular 80-18 (for l Radioactive Waste Systems)? O Yes @ No k. Could this affect the function of systems or components required for compliance with the Limiting Conditions for Operation in the Technical Specifications? O Yes @ No 1. In the judgment of tfie evaluator, is a Safety Evaluation required? if the answer to any questions in Part 3 is "Yes", then a Safety Evaluation is required prior to implementation. Check the appropriate block and provide any explanatory comments below:
- 4. @ No SAFETY EVALUATION RFgUIRED? O Yes
- 5. PREPARED BY: At / Principal Enoineer DATE: 9/7/95
- '/ ~ Title APPROVED BY: w_A h 4 Civil DM DATE: //9/96
(/ Title i l l Exhibit 4 NOP83E5 Rev. 7 l Jonhtss335
Calculation CI5 o 1m Attachment C Page .l. of 3_ INDEPENDENT DESIGN VERIFICATION RECORD (IDVR) -
- 1. Instructions to independent personnel Design Documents C15.0.3273 Q Residua 1 Heat Removal Heat Exchanter E207A & E207B GIP Evaluation (Document No.) (Rev.) (Document Title)
Design verification should be done in accordance with ANSI N45.2.11, Section 6, as amended by Reg. Guide 1.64, Rev.1. Verification Methods to be used; Document (s)"Q" Level:
@ Design review B Q O Altemate or simplified calculations O FP-Q O QualificationTesting O Non-Q Special Instructions:
( .I l> N T/Vr '
- Div. Manager
{ Date '
- 11. Verification Documentation:
Methods Used: E Design review (attach any documentation) E Altemate or simplified calculations (attach calculations) O Qualification Testing (attach Test Report) Design Document Acceptable: YES M NO O If not acceptable, give reasons or provide comments on Exhibit 3.06-B: 31;;"'c2""*""f "" T"'W iahsIec Date Independent Reviewer Acknowledgement of verification: b V
/ ! V f [2 Division Manager Date III. Resolution of comments:
Comments resolved (See Exhibit 3. ~ :
/bLognirAnt'[ngineer 12 2A 95 Date Action taken makes design doc ent acceptable o I- l2!2dhf Independent Reviewer Date Exhibit 3.06-A Rev. 7 l
JGD hk 'sS 2135 l
l Cdculation _C15 0 3m Attachment C Page 2 of 3_
$ Boston Edison DESIGN REVIEW CHECKLIST YES NO N/A
- 1. Where design inputs cerTectly selected and incorporated E O O into the design document?
- 2. Are assumptions necessary to perform the design adequately B O dewribed and reasonable? Where necessary, are the assumptions identified for subsequent re-verifications when the detailed design activities are completed?
- 3. Are the appropriate quality assurance requirements specified? E O
- 4. Are the applicable codes, standards and regulatory E D r requirements including issues and addenda properly identified and are their design requirements met?
- 5. Has applicable construction and operating experience been considered?
- 6. Has design interface with other functional units g requirements been utilized?
- 7. Was an appropriate design method used? E O
- 8. Is the design document reasonable compared to the design input?
- 9. Are the specified parts, equipment and processes suitable O E for the required application?
- 10. Are the specified materials compatible with each other and O E l the design environmental conditions to which the material will be exposed?
- 11. Have adequate maintenance features and requirements been O E 3pecified? 4
- 12. Are accessibility and other design provisions adequate O O 3 for performance of needed maintenance and repair?
- 13. Has adequate accessibility been provided to perform the -@
in-service inspection expected to be required during plant lifetime?
- 14. Has the design properly considered radiation exposure to @
the public and plant personnel? Have ALARA considerations been addressed? 1 S. Are the acceptance criteria incorporated in the design E D D documents sufficient to allcw verification that design requirements have been satisfactorily accomplished?
- 16. Have sufficient installation details and/or instructions, O Q including specification of applicable special processes, been included in the design output?
Exhibit 3.06-B Rev. 7 JGD tA95335
Calculauon CIS o 1271_ Attachment C Page ), of 1_
$ Boston Edison DESIGN REVIEW CHECKLIST (Continued)
YES NO N/A j
- 17. Have adequate pre-operational and subsequent periodic test requirements specified (including ist)?
O O E
- 18. Are adequate handling, storage, cleaning and shipping requirements specified?
O O g
- 19. Are adequate identification requirements specified? O O N
- 20. Are requirements for record preparation review, approval, retention, etc. adequately spect6ed?
E O O
- 21. Have all of the potentially applicable design considerations @ O O been correctly evaluated for applicability to the specific case and have the a 3plicable considerations been conectly and completely deat with?
- 22. Have the problems with this design, known from prior R O O applications, been considered and resolved?
- 23. Have relevant design basis documents such as Design Specifications, FSAR, Tech. Specs., and the Fire Protection E O O Review Report been researched and referenced in the design inputs and safety evaluation?
- 24. For modifications to existing components, check that the original manufacturers estimated impact on the existing O O $
components that will be modified is included, or a statement indicating why the information could not be obtained, or was not necessary to be obtained.
- 25. Are the Section XI Repair / Replacement Plant Requirements specified (refer to NOP 83El, Nuclear Engineering O O $
Department Work Instruction 409, or Exhibit 3.02-BB). COMMENTS RESOLUTION MN06 Cert 4 rA(N15 t} AVL Sf)N Pvterth?ATt-O (Nre '/PDUdb CALL 66&T)6NS f' Submitted O bE /2!29fv)[ Date Resolved
//
iV ' ! 2- 2/l Date 5 V Exhibit 3.06-B Rev. 7 JGD hk.95335
Boston Edizon C mp:ny - Pilgrim Nu;leir Power Stati:n GlP R:V 2 Corrected,2/14/92 St tus:Yes SCREENING EVALUATION WORK SHEET (SEWS) Shret 1.of 6 10 : T151 A (Rev. 0) l Class : 21 - Tanks and Heat Exchangers - Description : DG A Turt>o Air Receiver Building : DG A l Floor El. : 23.00 l Room, Row / Col: DG A Manufacturer, Model, Etc. - BASIS : Horizontal TANK analysis
- 1. The buckling capacity of the shell of a large, flat-bottom, vertical tank is equal to or greater N/A than the demand.
- 2. The capacity of the anchor bolts and their embedments is equal to or greater than the Yes*
' demand.
- 3. The capacity of connections between the anchor bolts and the tank shell is equal to or Yes greater than the demand.
- 4. Attached piping has adequate flexibility to accommodate the motion of a large, flat-bottom, N/A vsrtical tank.
- 5. A ring-type foundation is not used to support a large, flat bottom, vertical tank. N/A IS EQUIPMENT SEISMICAll_Y ADEQUATE? Yes COMMENTS
SRTs are W.R. Kline, C.T. Pitts and W. Djordjevic 1/21/93 REF: Drwg # C198 and C103, Detail 6. Horizontal Tank Analysis: T151 A is a horizontal starting air tank, supported by 2 saddles spaced 48" apart, on concrete piers which are approximately 6" high. There are 4 3/4" threaded rods per saddle,2 per bolt location, which pass thru the piers into Phillips shells which are installed in the floor slab below the piers. All anchors were checked for tightness on 11/2/93, and are OK. The piers do not require detailed load path evaluation based on the light loads, the short height and engineering judgement. The tensile load passes thru the pier in the threaded rods and into the stab. The shear load per pier is 909/2 = 405# (S&A Calc # 01C2672 - C - 022) . This load is judged acceptable. The piers are therefore adcquate. The tank dimensions are: 120" length by 48" outside diameter. The tank's CG is 32" above the top of the concrete piers. The tank saddle overhang exceeds S/2 but this is judged acceptable because of the large design margin and the fact that the overhang and saddle spacing are small physical dimensions.
- The shallow height at midpoint of saddle from TOC is 6". The total width of each saddle is 6", and the plates aie l 1/2" thick.
TM computed weight density of the tank under pressure is 32.5 pcf. less than the lower bound of the GlP parameter range (60 pcf - 75 pcf). The TANK analysis conservatively uses 60 pcf as the weight density. See S&A Calculation # 91C2672-C-022 for the development of TANK input and saddle stress analyses for T151 A and T1518.
l Boston Edison C::mp ny - Pilgrim Nucle r Power Station GlP Rav 2, Corrected,2/14/92 i st tus:Yes SCREENING EVALUATION WORK SHEET (SEWS) Shett 2 of 6 i l ID : T151 A (Rev. 0) l Class : 21 - Tanks and Heat Exchangers . ! Description : DG A Turbo Air Receiver l Building : DG A l Floor El. : 23.00 l Room, Row / Col : DG A Manufacturer, Model, Etc. :/ . Ev11uated by: ~
.h> ,
hli}lI/M Date: 63/ @[ vv7 hkW9!' i l
Attachment:
Pictures
Attachment:
TANK Analysis esults , i 1 f i i 1 l l l l i
Betton Edizen Camp:ny - Pilgrim Nuciser Powsr Stati:n GIP Rev 2, Corrected,2/14/92 Status: Yes SCREENING EVALUATION WORK SHEET (SEWS) Sheet 3 of 6 ID : T151 A (Rev. 0) l Cl ass : 21 - Tanks and Heat Exchangers - D scription : DG A Turbo Air Receiver ; Building : DG A l Floor El. : 23.00 l Room, Row / Col: DG A Manufacturer, Model, Etc. - { PICTURES
; o c
d k T151 A ' - i l l l'
Boston Edison C:mp:ny - Pilgrim Nu:le:r P wer Stati:n GIP R:V 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS) Stitus: Yes Shut 4 of 6 10 : T151 A (Rev. 0) l Class : 21 - Tanks and Heat Exchangers . Description : DG A Turtx) Air Receiver Building : DG A l Floor El. : 23.00 l Room, Row / Col : DG A M'nutacturer, Model, Etc. - - TANK Analysis Results Ctip 1 -Input Data
/ a) Assumptions
- 1. Tcnk is cylindrical, horizontally oriented and supported on saddles. Yes 2 Tank and saddles are made of carbon steel. t> Yes
- 3. Saddles are uniformly spaced. Yes
- 4. Saddles overhang is less than spacing / 2. Yes
- 5. BIse plates have slotted anchor bolt holes for thermal growth except for the base plate Yes under the fixed saddle.
- 6. Imposed nozzle loads are not significant. Yes
- 7. The tank foundation is adequate. Yes
- 8. Anchor bolts are cast in place or expansion type. Yes b) Materials Wright of Tank + Fluid ~-
4.08 kips Wright Density of Tank + F- 60 lbs/ft^3 S ddle Elastic Modulus 29000.0 ksi Saddle Shear Modulus 11500.0 ksi _ Brse Plate Yield Strength 30.0 ksi Anchor Type 3/4 in Expansion Bolts a c) Dimensions Tank Diameter, D 4.0 ft Tank Length, L 10.0 ft Tank Thickness, t 0.625 in Height of Tank + Fluid C.G., Hcg 2.67 ft Number of Saddles 2 Saddle Spacing, S 4.0 ft Saddle Height, h 6.0 in Saddle Shear cross-sectional area 14.75 in^2 Saddle Weak Axis Moment of Interia 18.0 in^4 Number of Bolt Locations / Saddle 2 Number of Bolts / Botting Location 2 Extreme Bolt Spacing, D' 3.0 ft Anchor Bolt Eccentricity, e 2.0 in Weld Thickness 0.125 in Base Plate Thickness 0.5 in
Bo:t:n Edirn Company - Pilgrim Nucle:r P:wer Station GlCRev 2, C:rrected,2/14/92 Status: Y:s SCREENING EVALUATION WORK SHEET (SEWS) ShYet 5 of 6 ID : T151 A (Rev. 0) l Class : 21 - Tanks and Heat Exchangers Description : DG A Turbo Air Receiver Building : DG A
- l Floor El. : 23.00 l Room, Row / Col: DG A M~ nufacturer, Model, Etc. :
/ ) dAnchor Bolts Type = Expansion Anchor Diameter = 3/4 in Manufacturer = Phillips Self Drilling (S) Product Name =
Pullout Shear Nominal Capacity 4.69 kips 5.48 kips l C*ncrete Compression Strength, fc' = 3000.0 psi l Reduction Parameters Capacity Reduction Factor Label Check Condition Pullout Shear
- 1. Type of Anchorage Yes 1.0 1.0
- 2. Installation Adequacy Yes Installation is adequate 1.0 1.0
- 3. Embedment Length Yes Embedment Length = 3.25 1.0 1.0 in
- 4. Gap at Threaded Anchors Yes Gap size = 0.0 in 1.0 1.0
- 5. Spacing between Anchorages Yes 0.53 1.0
- 6. Edge Distance Yes Edge Distance = 5.0 in 0.67 0.54 1 Concrete Strength and Condition Yes W 0.75 0.95
- 8. Concrete Crack Location and Size Yes Crack Size = 0.0 in 1.0 1.0
- 9. Essential Relays in Cabinets Yes Essential reays are not 1.0 1.0 present
- 10. Base Stiffness and Prying Action Yes 1.0 1.0
- 11. Equipment Base Strength and Yes Base strength and load path 1.0 1.0 Structural Load Path are O.K.
- 12. Embedment Steel and Pads Yes installation is O.K. 1.0 1.0 Does the tank satisfy all the assumptions and is within the applicable range of parameters? Yes St:p 2 -The allowable bolt loads
- Allowable Tension Load, Pu' 1.251 kips Allowable Shear Load, Vu' 2.834 kips St:p 3 - Determine base plate bending strength reduction factor l RB l 1.9989 l St;p 4 - Determine base plate weld strength reduction factor ' l RW l 8.6504 l St:p 5 - Determine the anchorage tension and shear allowable loads Allowable Anchorage Tension Load, Pu 1.251 kips "' Allowable Anchorage Shear Load, Vu 2.834 kips l
B:tt n Edicen Ccmp:ny - Pilgrim Nucinr Pcw:r Stati n GlP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 2 of 8 PLANT AREA
SUMMARY
SHEET ID : MGSETCTCON (Rev. 0) Equipment Description : MG Set Room B_uilding : RW Floor El. : 23.00 l Room. Row / Col: i Evaluated by: Date: V.
^
0E l2lK/93 M /W kMn l
Attachment:
Pictures MBShment: LAR 008. 2 Tier Conduit Raceway Sygiem Machment: LAR 009. Sinale Tier Trav_ Sv_ stem i lj l' i .. 5.J unnua
~!
..)
T a J l LJ e, b
.. j M
Bost:n Edizen Crmprny - Pilgrim Nu:le:r P:wer Stati:n GIP Rsv 2, C:rrected,2/14/92 Status: Yes SCREENING EVALUATION WORK SHEET (SEWS) Sheet 6 of 6 ID : T151 A (Rev. 0) l Class : 21 - Tanks and Heat Exchangers . Description : DG A Turbo Air Receiver Building : DG A l Floor El. : 23.00 l Room, Row / Col: DG A Manufacturer, Model, Etc. - Ctep 6 - Calculate the ratios and values rIpha (PuNu) 0.44 ' Wb 0.51 kips / bolt Vu / Wb 5.56 hod / D' O.89 Hco / S 0.668 F1 2.236 F2 2.323
-' , 8.:
St;p 7 - Determine the acceleration capacity of the tank anchorage lambda 1 2.485 G limbda_u 1.206 G Anchor Acceleration capacity, lambda 1.206 G / Ctep 8 - Determine the maximum saddle spacing for tran'sverse and vertical rigid frequency response l Mrximum Saddle Spacing, Sc l 19.37 ft l Ctep 9 - Compute the resonant frequency of *he tank in the longitudinal direction Saddle Stiffness, Ks 5770.235 kips /in R:sonant Frequency of Tank in Longitudinal Direction 117.59 Hz - St:p 10 - Determine the seismic demand acceleration l ZPA - l 0.15 G l 7 Tank is rigid in all three directions. Tank anchorage is adequate because anchorage acceleration capacity is greater than ZPA
~
St:p 11 - Check the saddle stresses The program does not check the saddle stresses Check the saddle stresses by an independent calculation Summary IS EQtflPMENT SEISMICALLY ADEQUATE? The tank anchorage is adequate.
ea Bo: ton Edison Company - Pilgrim Nuclear Power Stati n GIP R:v 2, C rrected 2/14/92 Sheet 1 cf 2 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ID : T151 A (Rev. 0) l Class : 21. Tanks and Heat Exchangers Description : DG A Turbo Air Receiver _uB ilding : DG A l Floor El. : 23.00 l Room, Row / Col: DG A
- 1. OUTLIER ISSUE DEFINillON - Tanks and Heat Exchanoers
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Shell Buckling Anchor Bolts and Embedment Anchorage Connections Flexibility of Attached Piping Other -; X
- b. Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolve e, then the signatories would consider this item of equipment to be verified for seismic adequacy).
%e tank overhang beyond the end supports exceeds the GIP Table 7-6 assumption of S/2. In addition this tank performs an air storage function and has a fluid density of 2.0 pcf which is below the parameter range of Table 7.6.
2 PROPOSED METHOD OF OUTLIER RESOLUTION f0ptionaj
- a. Defined proposed method (s) for resolving outlier.
Demonstrate large design margins. He tank was evaluated per the GIP with a tank plus fluid density of 60 pcf I and has a very large design margin. The saddles were evaluated manually for the actual tank plus fluid density of 32.5 pcf and also have a very large design margin.
- b. Provide information needed to implement proposed method (s) for resolving outlier (e.g., est! mate of fundamental frequency).
He large design margins and the fact that the actual frequency of the tank in the longitudinal direction is higher than the calculated frequency (because the actual mass is smaller than the mass value used) demonstrate that i T151 A meets the intent of the GIP requirements. No further action is required. His outlier is resolved.
- 3. COMMENTS >
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy: ; I
Bost:n Edi3:n C:mpany - Pilgrim Nucle:r Power Stati:n GIP R:v 2, C:rrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) Shzt 2 cf 2 ID : T151 A (Riv. 0) - l Class : 21. Tanks and Heat Exchangers Description : DG A Turbo Air Receiver ~ Building : DG A l Floor El. : 23.00 l Room, Row / Col : CG A l f a O*. to &ng - I l i I f t J
Boston Ediron Company - Pilgrim Nucisar Power Station GlP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS) Status: Yes Sheet 1 of 1 ID : T151B (Rev. 0) l Class : 21 - Tanks and Heat Exchangers Description : DG B Turbo Air Receiver Building : DG B l Floor El. : 23.00 l Room, Row / Col: DG B Manufacturer, Model, Etc. - BASIS : Horizontal TANK analysis
- 1. The buckling capacity of the shell of a large, fiat-bottom, vertical tank is equal to or greater N/A than the demand.
- 2. The capacity of the anchor bolts and their embedments is equal to or greater than the Yes*
demand.
- 3. The capacity of connections between the anchor bolts and the tank shell is equal to or Yes greater than the demand.
- 4. Attached piping has adequate flexibility to accommodate the motion of a large, flat-bottom, N/A vertical tank.
- 5. A ring-typa foundation is not used to support a large, flat-bottom, vertical tank. N/A IS EQUIPMENT SEISMICALLY ADEQUATE? Yes COMMENTS SRTs are W.R. Kline, C.T. Pitts and W. Djordjevic 1/21/93 For horizontal tank analysis see T151 A.
Evaluated by: ., WMU ' Date: hk
& lull %
q i (~ t
EA Bsst:n Edi3cn C:mp:ny - Pilgrim Nuclear Pow;r St'.tinn GlP Rev 2. Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) Sheet 1 of 2 ID : T1518 (Rev. 0) l Class : 21. Tanks and Heat Exchangers Description : DG B Turbo Air Receiver Building : DG B l Floor El. : 23.00 l Room. Row / Col : DG B
- 1. OUTLIER ISSUE DEFINITION - Tanks and Heat Exchancers
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Shell Buckling Anchor Bolts and Embedment Anchorage Connections Flexibility of Attached Piping Other X
- b. Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the dgnatories would consider this item of equipment to be verified for seismic adequacy).
He tank overhang beyond the end supports exceeds the GIP Table 7-6 assumption of S/2. In addition this tank performs an air storage function and has a fluid density of 2.0 pcf which is below the parameter range of Table 7-6. 2 PROPOSED METHOD OF OUTLIER RESOLUTION (Optionall '
- a. Defined proposed method (s) for resolving outlier. ,
Demonstrate large design margin. The tank was evaluated per the GIP with a tank plus fluid density of 60 pcf and has a very large design margin. He saddles were evaluated manually for the actual tank plus fluid density of 32.5 pcf and also have a very large design margin. ( b. Provide information needed to implement proposed method (s) for resolving outlier (e.g., estimate of l fundamental frequency). He large design margins and the fact that the actual frequency of the tank in the longitudinal direction is higher than the calculated frequency (because the actual mass is smaller than the mass value used) demonstrate that T151B meets the intent of the GIP requirements. No further action is required. This outlier is resolved.
- 3. COMMENTS i
- 4. CERTIFICATION:
l l T'.e information on this OSVS is, to the best of our knowledge and belief, correct a'nd accuiate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
[ i, l B:st:n Edison C::mp:ny - Pilgrim Nucl::r Pcwer St:tian GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS) Shzet 2 of 2 ID : T1518 (Rev. 0) I Class : 21. Tanks and Heat Exchangers Description : DG B Turbo Air Receiver Building : DG B l Floor El. : 23.00 l Room, Row / Col: DG B Approved by:
. Date:
[@[ C l r l t I ! l I l I
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON UNRESOLVED SAFETY ISSUE (USI) A-46. PILGRIM NUCLEAR POWER STATION (TAC NO. M69471) ' ATTACHMENT B ATTACHMENT TO RESPONSE #10 PASS ID AUXBAYGROUND (with LAR 015 & 023 sketches) Location: Aux Bay- Ground level El 23'-0" PASS ID RWTBCORR (with LAR 012 & 013 sketches) Location: Radwaste/ Turbine Bldg'- Corridor El 23'-0" PASS ID MGSETCTCON (with LAR 008 & 009 sketches) Location: MG Set Room El 23'-0" PA,SS ID UPSWGRCT (with LAR 006 & 007 sketches) Location: Upper Switchgear Room Cable Tray El 37'-0" Calculation for LAR 005 Location: Turbine Bldg El 37'-0" Calculation for LAR 017 Location: Reactor Bldg El 23'-0" Calculation for LAR 016 Location: Reactor Sidg El 23'-0" Calculation for LAR 024 Location: Aux Bay Bldg El 3'-0" i a _ -- -- _ _ - - - - _ - - _ _ _ - - _ - - _ _ _ - _ _ - _ _ - - _ _ - - _ _ _ -
I Best:n Edi3cn Comp:ny - Pilgrim Nucl:;rr Pcw:r Stati:n GlP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 1 of 6 PLANT AREA
SUMMARY
SHEET ID : AUXBAYGROUND (Rev. 0) Equipment Description : Aux Bay - Ground Level
, Building : AB Floor El. : 23.00 l Room, Row / Col:
Check List inclusion Rule Review Acceptance _
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
~
- 3. Tie Downs Yes
- 4. Channel Nuts Yes
, 5. Rigid Boots N/A
- 6. Beam Clamps Yes
- 7. Cast Iron Inserts N/A l Other Seismic Performance Concem Review Acceptance
- 1. Anchorage, Yes
_2. Welded Connections Yes l 3. Concrete Cotidition Yes 1
- 4. Corrosion Yes
- 5. Sagging Raceways Yes
- 6. Broken or Missing Components and Sharp Edges Yes
- 7. Restraint of Caoles Yes
- 8. Cable Fill / Ties Yes
- 9. Aging of Plastic Ties Yes
- 10. System Hardspots Yes
- 11. Short Rods N/A Seismic Interaction Review Acceptance
'l 1. Proximate Features Yes
- 2. Falling Hazards Yes
- 3. Differential Displacement Yes
- 4. Isolated Outliers Yes Limited AnalyllcalReviews
, LAR No. Document Name 015 A 3 tier P1000 Trapeze Support Raceway System.
023 Cantilever Conduit Support System
'I COMMENTS J
Single and two tier tray systems, lightly loaded. Some conduits of small diameter. i!
,j LAR 23 chosen is a cantilever conduit support. See markup of S&A 1989 report sketch.
LAR 15 chosen is a tall, 3 tier P1000 trapeze support with approximately 20 conduits. The remaining raceways in this area are enveloped by those in the Reactor Building, El. 23'. I SRTs are Djordjevic and Pitts - 6/1/93. M
>O b___________._____________
B:N;tsn Edizen CompIny - Pilgrim Nucisar Powar Station GIP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 2 of 6 PLANT AREA
SUMMARY
SHEET ID : AUXBAYGROUND (Rev. 0) Equipment Description : Aux Bay - Ground Level Building : AB Floor El. : 23.00 l Room, Row / Col: Evaluated by: Date: vw
/'
Th , [ !- 3 h r
Attachment:
Pictures
Attachment:
LAR 015, A 3 tier P1000 Trapeze Support Raceway System. {
Attachment:
LAR 023, Cantilever Conduit Support System. i e 4 J f e 6 f
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Boston Edison Company - Pilgrim Nuclear Power Station GIP Rev 2, Corrected,2/14/92 CABLE AND CONDUIT RACEWAY REVIEW Sheet 3 of 6 PLANT AREA
SUMMARY
SHEET ID : AUXBAYGROUND (Rev. 0) Equipment Description : Aux Bay - Ground Level . Building : AB Floor El. : 23.00 l Room, Row / Col: PICTURES i I O. _
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i I B ston Edi2cn Camp 2ny - Pilgrim Nuclear Powsr Station GIP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 4 of 6 {* PLANT AREA
SUMMARY
SHEET ID : AUXBAYGROUND (Rev. 0) Equipment Desenption : Aux Bay - Ground Level Building : AB Floor El. : 23.00 l Room, Row / Col: 2 l LAR 015. A 3 tier P1000 TraperfLS.upp. ort Raceway System. r-( l1 [" Beam Clamp (2) "A 5" /- (Typ)
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l Boston Edison Company - Pilgrim Nuclear Power Station GIP Rev 2. Corrected, 2/14/92 l CABLE AND CONDUlT RACEWAY REVIEW Sheet 5 of 6 } PLANT AREA
SUMMARY
SHEET {' ID : AUXBAYGROUND (Rev. 0) Equipment Desenpt.on : Aux Bay . Ground Level { r, Bui! ding: AB Floor El. : 23.00 l Room, Row / Col: ! LAELQ23Jan111cver condulLSupport systein, 1 4 n-O 00) s h V I ~ i JEC-fto sj @ f rib.lerg h 7 N dC '
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r i Boston Edison Company - Pilgrim Nuclear Power Station GIP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 6 of 6 l PLANT AREA
SUMMARY
SHEET ID : AUXBAYGROUND (Rev. 0) Equipment Description : Aux Bay - Ground Level 7., Building : AB Floor El. : 23.00 l Room, Row / Col:
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, *N, . 3"i \ P1001 3". 4" O Conduit and 3" $ Pipe = 4' Note: @ & @ are 2" and 3" $ Pipe, resp.
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B=t:n Edi3:n Ccmpany - Pilgrim Nuclxr Pcwer Stati n GIP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 1 of 6 PLANT AREA
SUMMARY
SHEET ID : RWTBCORR (Rev. 0) Equipment Description : RW/TB Building - Corridor Building : RW Floor El. : 23.00 l Room, Row / Col: Check ' List inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
- 3. Tie Downs Yes
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps Yes
- 7. Cast iron Inserts N/A i
Other Seismic Performance Concem Review Acceptance
- 1 1. Anchorage Yes
- 2. Welded Connections Yes
- 3. Concrete Condition Yes
, 4. Corrosion Yes
- 5. Sagging Raceways Yes
- 6. Broken or Missing Components and Sharp Edges Yes 7
. 7. Restraint of Cables Yes l 8. Cable Fill / Ties Yes ' 9. Aging of Plastic Ties Yes
- 10. System Hardspots Yes
- 11. Short Rods N/A J
Seismic Interaction Review Acceptance
~
- 1. Proximate Features Yes
- _ 2. Falling Hazards Yes
~
- 3. Differential Displacement Yes 1 4. Isolated Outliers Yes Limited Arnalytical RayJiews
( LAR No. Document Name
) -
012 Support No.12 013 , Support No.13 C.QMMENTS u 2-3 tier strut trapeze hangers. Two tiers generally of cable tray less than 50% full and one tier of conduits varing in size from 1"-3" nominal size. Hangers are attached to structural steel beams through a P1000 strut mounted to m beam by clamps and possibly welding although welding was not seen due to fireproofing surface treatment. Single conduits on wall also were observed, but were not deemed significant. Trapeze hangers were also attached to block wall on one side which is a safety related IE80-11 block wall and to a R/C wall on other side generally by 2 - 3/8" anchors. Hanger posts and cross-members are generally P1001 and fitiings are gusseted or ninety degree 2-hole fittings. Some fittings are welded to struts in addition to or in lieu of _l botting. The hangers have a good load path, a E
f l Borton Edison Ccmp:ny - Pilgrim Nucisir Pcwsr Station GIP Rev 2, Corrected,2/14/92 l CABLE AND CONDUlT RACEWAY REVIEW Sheet 2 of 6 ! PLANT AREA
SUMMARY
SHEET l ID : RWTBCORR (Rev. 0) Equipment Description : RW/TB Building - Corridor ! Butiding : RW Floor El. : 23.00 l Room, Row / Col: 2 LARs chosen currently identified as Support Nos.12 (figure 1) and Support No.13 (figure 2). Support No.12 is located outside Door 89 and Support No.13 is a worst case composite of 2-3 supports also located outside Door 89. SRTs are Djordjevic and Pitts - 5/6/93. Evaluated by: Date: l' d t dG izhs.le IS', f n/u/v i .
Attachment:
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LAR 012 r'
Attachment:
LAR 013 i, i ?I l ! Ia l m
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Boston Edison Company - Pilgrim Nuclear Power Station GlP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 3 of 6 PLANT AREA
SUMMARY
SHEET ID : RWTBCORR (Rev. 0) Equipment Description : RWITB Building - Corridor Building : RW Floor El. : 23.00 l Room, Row / Col: ELCTURES gd! " I. :
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I Bc ton Edizen Comp ny - Pilgrim Nuclxr Powzr Stttion GIP Rev 2, Corrected,2/14/92 I CABLE AND CONDUlT RACEWAY REVIEW Sheet 4 of 6 PLANT AREA
SUMMARY
SHEET ID : RWTBCORR (Rev. 0) Equipment Description : RW/TB Building - Comdor Building : RW Floor El. : 23.00 l Room, Row / Col: LAR 012
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Best:n Ediren C:mp:ny - Pilgrim Nucinr P w;r St ti:n GlP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 5 of 6 PLANT AREA
SUMMARY
SHEET ID : RWTBCORR (Rev. 0) Equipment Description : RW/TB Building - Corndor
,- Building : RW Floor El. : 23.00 l Room, Row / Col:
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B:stan Edi3:n Ccmp:ny - Pilgrim Nuclur Pow r Stati:n GIP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 6 of 6 PLANT AREA
SUMMARY
SHEET , ID : RWTBCOR51(Rev. 0) Equipment Description : RW/TB Building - Corridor i Building : RW Floor El. : 23.00 l Room, Row / Col: LAR 013 1 st t . ame te A,.al. ,a. y la.. . . . pie, up.),,i,a, f ^{ s+ eat bam couend w/M baad .a. e . I=. :: =_. =_ =_. ___ T _=. =. =_ I._ .= p lA- 7 p,,,,
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Bcctan Edisen Ccmp:ny - Pilgrim Nuciser PowIr Stati:ra GlP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 1 of 8 PLANT AREA
SUMMARY
SHEET ID : MGSETCTCON (Rev. 0) Equipment Desenption : MG Set Room
- Building ; RW Floor El. : 23.00 l Room, Row / Col:
Check List
,, inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes k' 2. Conduit Span Yes
- 3. Tie Downs Yes II 4. Channel Nuts Yes
[1 5. Rigid Boots N/A
- 6. Beam Clamps Yes
- 7. Cast Iron Inserts N/A Other Seismic Performance Concern Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections Yes
- 3. Concrete Condition Yes
, 4. Corrosion Yes i 5. Sagging Racewsys Yes
- 6. Broken or Missing Components and Sharp Edges Yes _
- 7. Restraint of Cables i Yes f, 8. Cable Fill / Ties Yes i2 9. Aging of Plastic Ties
~
Yes
- 10. System Hardspots Yes __
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features Yes
- 2. Falling Hazards Yes
- 3. Differential Displacement Yes _ l
'] 4. Isolated Outliers Yes l LimitedAnalyilcal Reviews LAR No. Document Name 008 2 Tier Conduit Raceway System 009 Single Tier Tray System 1 -
GQNIMENTS w Generally 1-2 tier tray and conduit raceways of same general construction as elsewhere in the Reactor Bldg. Trays are less than 50% loaded. l u l Two LARs chosen: LAR 008 (see picture in figure 1) is a 2 tier conduit raceway system with a longitudinal member which attaches it to wall. LAR 009 (see picture in figure 2) is a similar single tier system. l SRTs are Djordjevic and Pitts - 5/6/93.
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Boston Edison Company - Pilgrim Nuclear Power Station GIP Rev 2' Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 3 of C PLANT AREA
SUMMARY
SHEET ID : MGSETCTCON (Rev. 0) Equipment Description : MG Set Room Building : RW Floor El. : 23.00 l Room, Row / Col ; PICTURES
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Bact:n Edisen Ccmp:ny - Pilgrim Nuclier P w;r StatiUn GIP Rev 2, Corrscted,2/14/92 CABLE AND CONDUIT RACEWAY REVIEW Sheet 4 of 8 PLANT AREA
SUMMARY
SHEET ID : MGSETCTCON (Rev. 0) Equipment Description : MG Set Room Building : RW Floor El. : 23.00 l Room, Row / Col: 7 -. LAILQD8. 2 Tier Conduit Raceway System Decking Ribs N @ 12" c-c 1/8" x1-1/2" N
/"2 '
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118 \ 1 / 1/8"V1-1I2"
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\ x P2346 Concrete Wall p
2-114"h P2484(Typ) 7 (p 3/8"Shell Anchors
/ P2484
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1-II4"k 1-7/8"Q 1-1/2"0
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..s N / P2226 , ~ 2-114"O i
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Tributary Spans: P1377-jj: 2-114 " 9 East-West Conduit = S'-6" s 1-114"D ' b 2"6 North - South Conduit = T-0" j 2-114 " 4
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Bnst:n Edison Ocmprny - Pilgrim Nuclarr P:wIr Stati:n GIP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 5 of 8 PLANT AREA
SUMMARY
SHEET ID : MGSETCTCON (Rev. 0) Equipment Description : MG Set Room
. Building : RW Floor El. ; 23.00 l Room, Row / Col :
s l y 44" l' n 77 t f 72" i ' > 36" 6 I2" s 1-1/2"\r v < 6-1/2" j 4.j ga 4,j g.. I" Il-IE 23" I 4"llI ,jg,,g v l 3"l4"j 4"
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, 3.j q.' 2h 2-1/4" 1-114"p lLl t
i Looking North Looking West LAR 008 a 2/2 m 1 l 1 . - .
Bect:n Edi:on C mp ny - Pilgrim Nuclur Paw:r Stttien GIP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 6 of 8 PLANT AREA
SUMMARY
SHEET ID : MGSETCTCON .(Rev. 0) Equipment Description : MG Set Room
, Building : RW Floor El. : 23.00 l Room, Row / Col:
LARADJLSingle_Tler Tray system i k { , Ptococe s/c bolk I .4 i j F/oo/ jW
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SUMMARY
SHEET ID : MGSETCTCON (Rev. 0) Equipment Description : MG Set Room
, Building : RW Floor El. : 23.00 l Room. Row / Col :
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, PLANT AREA
SUMMARY
SHEET ID : MGSETCTCON (Rev. 0) Equipment Description : MG Set Room
, Building : RW Floor El. : 23.00 l Room, Row / Col :
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SUMMARY
SHEET ; ID : UPSWGRCT (Rev. 0) Equipment Description : Upper Switchgear Room Cable Tr j Building : TB Floor El. : 37.00 l Room, Row / Col:
)
Check List
)
inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes ,
- 3. Tie Downs Yes 1
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps Yes
- 7. Cast iron Inserts N/A Other Seismic Performance Concem Review Acceptance
; 1. Anchorage Yes
- 2. Welded Connections Yes
- 3. Concrete Condition Yes
- 4. Corrosion Yes
- 5. Sagging Raceways Yes
- 6. Broken or Missing Components and Sharp Edges Yes
- 7. Restraint of Cables Yes
- 8. Cable Fill / Ties Yes
- 9. Aging of Plastic Ties Yes
- 10. System Hardspots Yes
- 11. Short Rods N/A Seismic Interaction Review Acceptance
~
- 1. Proximate Features Yes j 2. Falling Hazards Yes 1
- 3. Differential Displacement Yes t 4. Isolated Outliers Yes Limlied Analytical Reviews
, p LAR No. Document Name 006 2 Tier System, Field Sketch 007 Single Rod Hanger Trapeze, Field Sketch
} COMMENTS J
One to two tier tray and conduit systems througt.out. One system is a 2 high x4 wide tray system which goes into j Battery Rm. and is a LAR 026 for Upper Battery Room. Otherwise construction similar to other areas with welded a and/or clamped anchorages. All Trays are generally 1/3 to 1/2 full. l l The two LARs chosen are: LAR 006 which is a 2 tier system with 24" trays (figure 1) and LAR 007 which is a rod hanger trapeze (figure 2). The remaining raceways in this area are enveloped by those in the Reactor Building, El. 23'.
] SRTs are Djordjevic and Pitts - 5/6/93.
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B:st:n Edizen Comp:ny - Pilgrim Nucisir Pcwir Statinn GIP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 2 of 9 PLANT AREA
SUMMARY
SHEET i ID : UFSWGRCT (Rev. 0) Equipment Description : Upper Switchgear Room Cable Tr j q Building : TB Floor El. : 37.00 l Room, Row / Col: Evaluated b(: Date: l$ l$
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Attachment:
Pictures r
Attachment:
LAR 006. 2 Tier Svatam. Field ketch
Attachment:
LAR 007.11Dgle Rod Hanger Trapeze. Field Sketch t I wJ 9 i wJ l a i f us l II a
Boston Edison Company - Pilgrim Nuclear Power Station GIP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 3 of 9 PLANT AREA
SUMMARY
SHEET '{ ID : UPSWdRCT (Rev. 0) Equipment Description : Upper Switchgear Room Cable Tr
._ Building : TB Floor El. : 37.00 l Room, Row / Col:
lii PICTURES i .,
)
l i L Figure 1 : LAR 006. Figure 2 : LAR 007. t l l L.. ) '. , 1 - i 5J
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l BC t:n Edi2:n Ccmp ny - Pilgrim Nucizr Power St:ti n GIP Rev 2, Corrected,2/14/92 CABLE AND CONDUlT RACEWAY REVIEW Sheet 4 of 9 l PLANT AREA
SUMMARY
SHEET ID : UPSWGRCT (Rev. 0) Equipment Description : Upper Switchgear Room Cable Tr Building : TB Floor El. : 37.00 l Room, Row / Col: l 1 i 1 l LAR 006. 2 Tier System. Field Sketch j i k I
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SUMMARY
SHEET ID : UPSWGRCT (Rev. 0) Equipment Description : Upper Switchgear Room Cable Tr Building : TB Floor El. : 37.00 l Room, Row / Col: U U L/~ (*
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SUMMARY
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SUMMARY
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SUMMARY
SHEET 10 : UPSWGRCT (Rev. 0) Equipment Description : Upper Switchgear Room Cable Tr Building : TB Floor El. : 37.00 l Room, Row / Col: LAR 007. Slagle Rod Hanger Trapeze. Field Sketch Jk +3 &
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SUMMARY
SHEET ID : UPSWGRCT (Rev. 0) Equipment Description : Upper Switchgear Room Cable Tr
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