ML20050B809
| ML20050B809 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/05/1982 |
| From: | GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML13323A262 | List: |
| References | |
| GA-C16708, GA-C16708-V03-B1, GA-C16708-V3-B1, NUDOCS 8204070439 | |
| Download: ML20050B809 (425) | |
Text
. - - _ _ - _ - _ . _ _ _ _ _ . __ - ._ . _ _ _ _ _ ___
GA-C16708
~o @
INDEPENDENT VERIFICATION OF SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 & 3 SEISMIC DESIGN AND QUALITY ASSURANCE PROGRAM EFFECTIVENESS VOLUME 3 O POTENTIAL FINDING REPORTS BOOK 1 REPORTS 0001 TO 0058 and REPORTS F001 TO F040 PREPARED FOR gE southern caittornia edison company GENERAL ATOMIC PROJECT 2408 APRIL 5,1982 A 510 CH C D DO O O 1 P PDR
fh N)
FOREWORD This report is presented in three volumes:
Volume 1 - Executive Summary Volume 2 - Program Results Volume 3 - Potential Finding Reports Volume 3 is a compilation of all Potential Finding Reports (PFR's) and Corrective Action Plans that were issued as part of this review. For
- convenience of handling, this volume has been divided into two books.
l Book I contains PFR's 0001 through 0058, which were the reports that were filed before the Interim Report was issued, and PFR's F001 through F040.
.s Book 2 contains the remaining FFR's, F041 through F112, and the Corrective Action Plans that were prepared by Southern California Edison in response to the seven Findings.
4 For assistance in locating a particular PFR, the PFR's have been grouped into sets of ten as indicated on the dividers. 1%rther, the first page of each PFR and Corrective Action Plan is printed on light green paper to aid in locating it within a grcuping.
Table 1-1 lists the PFR's in order by number and serves as an index to this volume. Table 1-2 is a list of the Corrective Action Plans.
I O
TABLE 1-1 LIST OF POTENTIAL FINDING REPORTS 2408-PFR Task Feature Contractor Subj ect Classification
-0001B C 6 Bechtel Omission in computer Observation mathematical model (P&ID 40112-10)
-0002A C 6 Bechtel Cantilevered line Invalid holding valve should be included in computer (related to dwg 1204-004-1, sht 50 PSG-82
-0003 C 6 Bechtel Input data for Observation seismic anchor move-ment (SAM) should be clearly specified in the calculation package. PSG-82.
-0004 C 7' Bechtel Stress intensifica- Invalid tion factor to be used PSG-245 for reducers
-0005 C 6 Bechtel Calculations should Invalid use latest design loads PSG-78
-0006 C 6 Bechtel Support analysis Observation should correspond to support used
-0007 C 6 Bechtel Seismic response Observation spectra used in analysis be for location to be analyzed PSG-78
-0008A C 3 Bechtel Design nozzle loads Observation listed in design spec s/b consistent with loads derived in piping analysis
O TABLE 1-1 2408-PFR Task Feature Contractor Subject Classification
-0009 C 20 Bechtel Design load for Finding structural member is greater than permissible load.
Tray hanger #37185
-0010 C 5 CE Nozzle loading Invalid analysis used for both units 2 & 3 CE cale. #S-PAC-010/6-24-81
-0011 C 4 CE Pump P016 low Observation pressure safety induction pump-vertical accelera-tion used in analysis appears to be low
-0012 C 4 Bechtel(a) Additional data Invalid needed from Bechtel to verify support structure stiffness and anchor bolt loads
-0013 C 1 Bechtel Discrepancies in Invalid computer input data for containment structure seismic model
-0014A C 8 Bechtel Piping stress analy- Observation sis pkg S cale.
! use latest design load
(* Original Design Organization response not required.
l l
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TABLE l-1 2408-PFR Task Feature Contractor Subject Classification
-0015 C 21 Bechtel Spec for control Observation room and field mounted panels
- 5023-502-5 fails to require internal panel wiring or connecting wiring be simulated or other-wise considered during seismic qual.
testing of panels
-0016 C 21 Bechtel Panel 2CR57 Spec Invalid S023-502-5 fails to requiru vendor to consider anchor details designed by Bechtel
-0017 C 21 Bechtel Panel 2CR57 spec Observation fails to require the vendor to consider dynamic interaction of cabinets arranged in specific manner
-0018 C 8 Bechtel PSG-78 Calc Invalid P450-1.109-9.100 sht I weld elec-trode not identified in calc.
-0019 C 8 Bechtel PSG-78 Allowable Invalid bending and weld shear allowable stresses not equal to basic requirement
-0020 C 8 Bechtel PSG 78 sheet 3 of Invalid cale. uses incorrect bending stress allowable
-0021 C 8 Bechtel PSG-78 Allowable Invalid stress on throat area 4
TABLE 1-1 2408-PFR Task Feature Contractor Subject Classification
-0022 C 8 Bechtel(a) PSG 78 Member forces Invalid for W6x25 column on sht 2 are inaccurate
-0023 C 6 Bechtel Value CG be Observation correctly modeled for computer input
-0024A C 6 Bechtel Input data for Observation seismic anchor movement (SAM)
! should be clearly 2
specified on the cale pkg (pkg #78)
-0025 C 8 Bechtel Note on sheet 1- Invalid margin of safety in as-built cales ade-quate to accommodate
' *O increased work loads not substantiated
-0026 C 8 Bechtel Cales and dwgs do Invalid not identify steel type nor weld elec-trode used. PSG-78.
-0027A C 10 CE ESFAS Aux relay Observation cabinet Lack of functional testing j during seismic excitation
-0028 C 10 CC ESFAS aux. relay Invalid cabinet No RRS given although RRS testing required
-0029 C 10 CE ESFAS aux. relay Invalid cabinet Requirement 1 for functional testing absent
(* Original Design Organization response not required.
(
5
TABLE 1-1 I 2408-PFR Task Feature Contractor Subject Classification
-0030 C 10 CE Vendor not required Invalid to account for anchor flexibility
-0031A C 11 Bechtel Seismic Category 1 Observation MCC Deficiencies in seismic testing requirements l 1
-0032 C 11 Bechtel Seismic Category 1 Invalid MCC Deficiencies in l component identifi-cation
-0033 C 6 Bechtel Valve weight not Invalid included in actual restraint cales
-0034 D --
SCE Inconsistency in Finding 10CFR50 App B criterion 18 reqmt and SCE procedure
- N18.04
-0035 C 6 Bechtel sesign change not Observation made
-0036 C 6 Bechtel Flow orifice and Observation node location not included in piping model
-0037 C 5 CE The moment of Observation inertia of the concrete slab in-correctly used
-0038 A --
CE Problem with inter- Finding face control O
6
1 1
(3
\- / TABLE 1-1 2408-PFR Task Feature Contractor Subj ect Classification
-00'9 C 19 Bechtel(a) Reference source for Invalid certain input values were missing in I&C equipment field mounting design calculation
- i
-0040A C 19 Bechtel Input acceleration Invalid ,
g level used in I&C equipment field mounting design I
structural analysis cannot be traceable
-0041 C 19 Bechtel(a) Reference sources Invalid were missing for I&C level transmitter (2LT-0312) weight and associate tubing, etc.
-0042A G --
Bechtel Several piping Observation supports were not installed per draw-ing. PSG-82. <
-0043A G --
Bechtel Installed piping Observation does not conform to stress isometric-PSG-82
-0044 C 11 Bechtel(a) Seismic Category I Invalid Switchgear errors in App. B when incor-porating response spectra
-0045A A --
CE Interface review Invalid requirement
-0046A A --
CE Design requirement - Out of scope externally designed component
- Original Design Organization response not required.
7
TABLE l-1 2408-PFR Task Feature Contractor Subject Classification
-0047 A -
CE Organizational Finding design review requirements
-0048 A -
CE Project office Out of scope responsibilities -
purchase orders
-0049 A -
CE Internal / external Observation design review consideration
-0050A A -
CE Design control of Out of scope spares
-0051 C 9 CE Seismic acceleration Observation specified in the CE specifica; ion for electric motor operated valves
-0052 A -
CE Project Design Finding Management - project responsibilities
-0053 C 11 Bechtel Seismic Category I Observation Svitchgear incorrect location information
-0054 C 6 Bechtel Need analytical Invalid justification supporting Unit 3 pipe configuration
-0055 C 6 Bechtel Need justification Invalid l for N/A treatment of seismic anchor move-l ment in PSG-57
-0056 C 6 Bechtel Inconsistency Observation i
between ISO sketch and computer model PSG-117 9
8
i
}
TABLE 1-1 ;
2408-PFR Task Feature Contractor Subj ect Classification
-0057 C 1 Bechtel Discrepancies in Observation computer input data for containment structure seismic model
-0058 C 1 Bechtel Discrepancies in Observation ;
computer input data for containment structure seismic model
-F001 C 6 Bechtel Piping design loads Invalid not conservative
-F002 C 6 Bechtel Anchor loads not Invalid I conservative
-F003A C 11 Bechtel Seismic Category I Observation ;
MCC - Deficiencies Od not accouting for base mount design
-F004 A --
CE Design control Observation j training l
-F005A B --
CE CEN-99(S) Seismic Invalid Evaluation of NSS ;
Supplied Instrum. t Equip.
-F006 B --
Bechtel Drawing in drawing Invalid log which required SEC approval not approved
-F007A B --
Bechtel Purchase spec did Invalid not stipulate special tool requirements
-F008 D --
Bechtel Inappropriate Invalid corrective action field generated drawing control I .
9
i TABLE 1-1 O
2408-PFR Task Feature Contractor Subject Classification
-F009 D --
Bechtel Inappropriate Invalid corrective action for instrument and control cards not showing Q and seismic class
-F010 B --
SCE Lack of design input Obse rvation requirements for spec #412055
-F011 B --
SCE Design document Observation reviewer comments not resolved in writing
-F012 B --
SCE Registered Observation Professional Engineers seal not stamped on spec 512055 calculation DC-339
-F013 B --
SCE Specification 412055 Observation distributed for use with missing page
-F014 B --
SCE Calculations added Observation to DC-339 subsequent to review and approval
-F015 B --
SCE No evidence of Finding computer program validation in calculation DC-339 Corrective Action Plan
-F016 B --
SCE Inconsistency in Observation review and approval requirements for calculations 9
10
TABLE 1-1 2408-PFR Task Feature Contractor Subject Classification
-F017 B --
SCE Quarterly listing of Observation new and revised standards not pre-pared and distributed
-F018 B --
Bechtel Purchase Spec SO 23- Observation 407-13, SCE 0447 5/15/75 - welding '
deviation
-F019 B --
Bechtel Computer code used Invalid for seismic analysis
( ASHSD) not vali-dated before use
-F020A B --
Bechtel Partial calculations Observation missing from PSG-78
-F021 B --
Bechtel Required information observation missing from PSG-82, O 57, 74, 117
-F022 B --
Bechtel PSG-78 Design Observation Approval Not signed by Chief Engineer
-F023 B --
Bechtel PSG-78, 82-57, 74, Observation 117 Chief Engineer did not sign for Quality I and II
- design
-F024A B --
Bechtel PSG-78, 82 Original Observation caleclations not in project file
-F025 B --
Bechtel PSG-74, Revisions Invalid not on title page
-F026 B --
Bechtel PSG-78, 82, 57, 74, Invalid 117, Page identifi-cation missing
! O
(,)
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TABLE 1-1 2408-PFR Task Feature Contractor Subject Classification
-F027A B --
Bechtel PSG-78, 57, 74, 117 Observation Page numbering irregularities
-F028 C 8 Bechtel Additional DCN's not Invalid included in calcula-tion P450-150-169
-F029 B --
Bechtel Unauthorized drawing Observation revision issued cable tray hangers
-F030A B --
Bechtel Inappropriate Invalid identification of procedure
-F031 B --
Bechtel Construction draw- Observation ing issued prior to calculation being performed
-F032 C 20 Bechtel Cable tray support Observation
- 37202 loading in calculation
-F033 C 20 Bechtel(a) Seismic Class I Invalid cable raceway support system allowables used in calculations
-F034 B --
Bec?.tel Procedural viola- Observation ticca - containment shell scismic analysis
-F035 B --
Bechtel Bechtel Design Observation Criteria Manual -
procedural violation
- Original Design Organization response not required.
0 l
12
O TABLE 1-1 2408-PFR Task Feature Subject Contractor Classification
-F036 B --
Bechtel Bechtel Containment Observation j Shell Analysis -
FINEL model proce-dural violation
-F037 D --
SCE CAR - F-194 proce- Observation I dural deficiency
-F038 D --
SCE Procedural Observation !
deficiency in ;
Correction Action Request (CAR) S-52 (site)
-F039A C 4 Bechtel Suction system for Invalid LPI of the safety integration system including the fuel water tank T006, suction pipeline air O
A-C-E portion
-F040 C 6 Bechtel PSC-117 - improper Observation simultion of fuel installation in model
-F041 C 6 Bechtel Incorrect calcula- Invalid tion of g-level -
valves
-F042 B --
Bechtel Procedural violation Observation on a specification change notice released without QA approval and signature
-F043A C 6 Bechtel Valve effective Observation 1
acceleration calcu- ,
lations inconsistent
-F044 B --
Bechtel Generic missing Observation design criteria and assumptions 1
13
I TABLE 1-1 O'
2408-PFR Task Feature Contractor Subject Classification
-F045 B --
Bechtel(a) PIPM Manual Vol. 1 Invalid rev. reqmts not inco rporated
-F046 D --
SCE Inadequate Observation corrective action regarding audit of BPC (USTC) procedures
-047 D --
Bechtel BPC relaxed FSAR Invalid concrete placement temperature without changing FSAR.
Audit 934
-F048 D --
Bechtel(a) Audit 975-Possible Invalid lack of inspections on seismic Class I and II equipment mountings
-F049 D --
Bechtel Failure to take Invalid action to correct incomplete requests for nondestructive testing
-F050 D --
Bechtel Treating a Invalid significant deficiency in engineering disposition on non-conformances as a minor deficiency
-F051 D --
Bechtel Audits 1476, 1555, Finding 1567 and 1855 audit findings not reported to manage-ment - a trend l
(a) Original Design Organization response not required. i l
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1 I
m TABLE 1-1 2408-PFR Task ,aature '
Contractor Subject Classification
-F052 D --
Bechtel Audits 914, FQA161, Observation 345, 601, 1072, 1104, 1555 and 1596.
Corrective action concerning field engineers inappro-priate or non-existent - a trend
-F053A D --
SCE(a) Field Change Notices Invalid
- vendor approval
-F054A D --
SEC Trend report- f>bservation document control -
-F055 B --
Bechtel(a) Pipe support cales. Invalid Rev. 2 not signed off O -F056 B --
Bechtel Pipe support FCN not properly approved Observation
-F057 C 10 Bechtel control Room relay Invalid panels 2L use of foundation anchorage flexibility
-F058A C 10 Bechtel Control room relay Invalid panel 2L speci-fication of repre-sentative equipment included in testing
-F059 C 10 Bechtel Control Room relay Invalid panel 2L determination of specific panel configuration to be tested
- Original Design Organization response not required.
~
15
TABLE 1-1 9
2408-PFR Task Feature Contractor Subject Classification
-F060 B --
SCE Spec addenda in use Observation but not released
-F061 B --
Bechtel Spec change notice Observation not incorporated within 120 days (Item 12)
-F062 B --
Bechtel SDDR not incorpor- Observation ated into spec within 120 days
-F063 B --
Bechtel Cal. dos not Invalid reference spec number as required
-F064 B --
Bechtel Dwg and spec were Invalid issued prior to cale being comt:.eted
-F065 C 8 Bechtel Applicability of Observation computer code used to analyze pipe frame
-F066 B --
Bechtel Uninitialed and un- Observation dated pipe support calculations
-F067A B --
Bechtel Pipe support cales Invalid were performed on wrong forms
-F068 B --
Bechtel Pipe support un- Invalid approved cales, Rev. 2
-F069 D --
SCE(a) Safety impect items Invalid not produced in accordance with Reg. Guide 1.29 (a)
Original Design Organization response not required.
16
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O TABLE 1-1 2408-PFR Task Feature Contractor Subj ect Classification
-F070 C 6 Bechtel PSG-117 - Incon- Invalid sistency in snubber orientation
-F071 C 3 Bechtel Refueling water. tank Observation T006 buckling criteria
-F072 C 10 Bechtel Splice box support Invalid
-F073 C 10 Bechtel Terminal Box support Invalid
-F074 C 6 Bechtel PSG-117 Incorrect Observation weight calculations
-F075 B --
Bechtel Specification not Observation revised to delete component seismic testing b)
(, -F076 B --
Bechtel Computer code not on computer code list Invalid
-F077 B --
Bechtel Unvalidated comp. Observation program for piping analysis
-F078 C 3 Bechtel Refueling water tank Observation (T0006) hydrodynamics
-F079 B --
CE Component specs Observation
-F080 B --
CE BOP design criteria Observation
-F081A B --
CE Proj Manager Observation provides design bases
-F082 C 8 Bechtel Pipe support cales. Observation
-F083 C 10 CE Load panels 2L123, Invalid ,
2L127, 2L147 i [
V}
17 i
TABLE l-1 2408-PFR Task Feature Cont ractor Subj ect Classification
-F084 C 10 CE Foxboro power supply Invalid 2 ARPS
-F085 C 10 CE Rosemount temp Invalid transmitters 442H-82A
-F086 B --
Bechtel Lack of SCE Observation -
authorization to proceed with design changes
-F087 B --
CE Reactor vessel Invalid support
-F088 B --
CE Quality record - Observation doc. distr./ approval form
-F089 B --
CE CE spec S-PEC-111, Observation Rev. 2 Method of Verification
-F090 B --
CE Reactor coolant pump Invalid snubbers stress report
-F091A C 8 Bechtel Rock bolt loading Observation criteria
-F092 C 8 Bechtel Pipe support PSG-82, Observation node 93 cales.
-093 C 8 Bechtel(a) Pipe support PSG-82, Invalid node 93
-F094 C 17 CE Charging inlet Invalid nozzle, rotating load coordinates
- Original Design Organization response not required.
till 18
4 TABLE 1-1 2408-PFR Task Feature Contractor Subject Classification
-F095 C 17 CE Charging inlet Observation nozzle, justification of peak stress intensity values
-F096 C 15 CE Reactor vessel inlet Observation nozzle
-F097 B --
Bechtel Incomplete Observation calculations
-F098A C 14 CE Hydraulic snubber Observation reactor
-F099 C 14 CE Reactor coolant pump Invalid DBE design loadings
-F100 C 22 Bechtel Containment interior Observation s tructure
-F101 H --
Bechtel No pressure safety Observation injection pump
-F102A C 14 CE Stress analysis of Observation reactor coolant devices
-F103 C 13 CE Reactor coolant pump Invalid support system
-F104 C 22 Bechtel Reactor coolant pump Observation support system i
-F105A C 1 Bechtel Containneent Observation l structure seismic analysis
-F106A C 2 SCE Aux. intke Observation structure, section D
-F107 C 2 SCE Aux. intake struc- Invalid ture, section F i
l O-19
TABLE 1-1 2408-PFR Task Feature Contractor Subject Classification
-F108 C 2 SCE Aux. intake struc- Observation ture, section C
-F109 C 15 CE Inlet nozzle of Invalid reactor vessel
-F110A C 15 CE Reactor vessel Invalid suport column
-F111 D -
SCE SCE quality trend Invalid report
-F112 D -
SCE Vendor approval of Invalid FCN affecting vendor originated document O
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_=- ..- -
_ ..- -.- . _. . .___ _ _ __- . _ _ _ __ _ ._ . . = . _ - . . _ . - - . . . . . _ - . _ . _ - . - _ _ _ _ - - . . -. . - .- _-... _ .
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TABLE 1-2 !
CORRECTIVE ACTION PLANS SCE Corrective Subject
- Action Request 2408-PFR i
i S023-S-485 -0009 l S023-C-158 -0034 S023-S-483 -0038 S023-S-486 -0047 I S023-S-484(a) -0052 S023-G-160 -F015 i
S023-S-527 -F051 4
1
}
i (a)This Corrective Action Request is combined with that of S023-S483.
21 i l 1
..__...m_ ._.. . _ . ___ ___,, _ _,- , _ . _ _ _ . _ _ _ . _ , . . _ , . _ . . . - _ , _ . _ , _ . _ _ _ _ . , . . _ . . _ _ _ _
PFR NO. 2408-PFR-0001 POTENTIAL FINDING REPORT REVISION B io' t SONGS 2&3 SEISMIC DESIGN VERIFICATION
%)
A. PREPARATION BY GA INITIATOR -
AFFECTED ITEMS: Safety Injection Line to Reactor Coolant Loop 1A Piping Stress Analysis Package PSG 82 REQUIREMENT REFERENCE DOCUMENTS:
P&I Diagram 40112-10 Computer runs Q45H25 and Q39H59 BASIC PEQuiREMENT:
Line 109-24"-C-LLO should be correctly identified la ISO Dwg. 1204-004-1 (Sh. 50 PSG 82) .
DESCRIPTION OF POTENTIAL FINDING:
Although the line 109-24"-C- LLO was correctly modeled in computer runs Q45H25 and Q391159, the ISO Dwg. 1204-004-1 (Sh. 50 PSG 82) incorrectly identified the line 109 as line No. 002-24"-C-LLO.
s
( I PREPARED BY: F. Lin OATE:1-18-82 _ ___
REJECTION OF GA TASK LEADER COMMENTS BY: DATE:
REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: DATE:
- 8. REVIEW BY GA TASK LEADER COMMENTS l 44 ,3 N (J.<.A Eu/d rT f' 0 l' b
,, pc; nyana tW^
f ,%k.
O AGREE PF IS VAll0 B W < fW DATE //n/8 v .
O REQUEST RE REVIEW BY DATE . -
O OlSAGREE BY DATE -. _ _
O REVIEW OF ORIGINAL DESIGN ORGS. COMMENTS BY: DATE:
PAGE 2 PFR NO. 2408-m-0001 REVISION 8 C. REVIEW BY ORIGINAL DESIGN ORGANIZATION COMMENTS q g O AGREE PF IS VALIO O OlSAGREE BY: DATE:
D. RECOMMENUATION BY FINDINGS REVIEW COMMITTEE DEFINITION ADEQUACY: 2 ADEQUATE O INADEQUATE VAllulTY: El VAll0 O INVAL10 CLASSIFICATION: E OBSERVATION O FINDING JUSTIFICATION:
CLASSIFICATION CRITER10N NO. RESULTING IN " FINDING"
] )
COMMENT ON "0BSERVATION" CLASSIFICATION
% kAsis Y N GA f # '
l BY:
. DATE: M. 20/72.
E. GA PROJECT MANAGER (T ACCEPT O REJECT
-d I BYV' //WF/" DATE: [ PL
' ..I.
'.. i POTENTIAL FINDING Rt: PORT 240s-Pre-000/
s I
SONGS 2&3 SEIST.11C DESIGN VERIFICATION PFR NO.
^ '
REVISION PREPAnATION SY GA INITIATOR .
AFFECTED ITEf.1S: '
Safety Injection Line to Reactor Coolant Loop 1A Piping Stress Analysis Package PSG 82 REQOIRE!.1ENT REFERENCE 00 cut.1ENTS:
PL1 Diagram 40112-10 -
4 BASIC REQUIRE?.1ENT:
Line 103-24" -C-LLQ should be included in the computer mathematical. model. g DESCRIPTION OF POTENTIAL FIN 0 LNG: Line 109-24"-C-LLO is shown in Stress ISO Dwg. 1204-109-1 (Sh. 58 PSG 82), but no nodal points have been designated. Consequently, the. runs
- Q451125 or Q39H59 do not pick up this line in the mathematical model. There may be a potential. error in Stress 150 Dwg. 1204-004-1 (Sh. 50 PSG 82) in interfacing with this lin:
- r. L n h *
'l-11-82 3
1 PREPARED BY: DATE:
REJECTION OF GA TASK LEADER COMt.1ENTS BY: DATE:
REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: 0 ATE:
B. REVIEW BY GA TASK LEADER COMMENTS
/[ l M g AG REE FF 15 VAL!O 3Y *-'a^- JATc / /<C 0 C.
l l C F'.EGUEST T$E REV!EW BY DATE ,_ l O DISAGREE BY DATE._ !
O REV!EW OC GRIGINAL DESIGN ORGS. CC,".'.*ENTS SY: _ D ATE: -
- .--~ .
A c, ,*:EViEc." CY ORIG!!!".L DESIGN O RG ANIZATION C O Mt.'.EliTS 00c/
Drewing 1204-109-1 is for Unit 2 and 3. The configuration as shown is for Unit 3; however, line 109 is mirror f:: age for Unit 2. tio node points were shown on this
. drawing since they were shown on 1204-004-1.; Line 109 is shown on 1204-004-1 be-
- en the check valve and node point 40 alttiough not identified. ' he computer runs
.cficct the configuration shown on 1204-004-1 and therefore include this line.
i O AGREE PF 15 VAUD g g O DISAGREE ,/MI# F BY W- - '? I L DATE: l~I M A D. REC 0f.".*Ef.0 ATIC N SY F;';D:N35 R EVIEW CD'.'MITTEE s
DEFINITION ADEQUACY: O ADEQUATE O INADEQUATE VALIDITY: O VALID D INVALID 10 CFR 21: O NOT APPLICABLE O APPLICABLE 10 CRF 50.E5(c): O NOT APPLICABLE O APPLICABLF. _
CLASSIFICATION: O OBSERVATION O FINDING
- .10STIFIC ATIO ft:
JLASS!FICATION CRITERION NO. RESULTING IN " FINDING" ._
4 l COMMENT ON "0BSERVATION" CLASSIFICATION BY: DATE:
E. TFT PROJECT MAf:AGER O ACCEPT D REJECT l l BY: - DATE:
h%Mgg gg O
IMPACT ASSESSMENT uwt PFR NO. 2408-PFR-04 s
- et eact r ant P 1A, Piping Package PSG 82 AFFECTEDITEM:
- 1. IS THERE THE POTENTIAL FOR REDUCING DESIGN MARGINS TO THE EXTENT DESIGN ALLOWABLES ARE EXCEEDED OR DESIGN REQUIREMENTS ARE NOT MET ?
No
No
- 3. COULD THE FAILURE OF THIS ITEM DURING AN SSE CREATE A SUBSTANTIAL SAFETY H AZARD ?
No f
- 4. COULD THE PROCEDURAL VIOLATION CPEATE A SUBSTANTIAL SAFETY HAZARD ?
No
- 5. ARE OTHER SIMILAR DEVIATIONS LIKELY TD EXIST ?
I cannot make judgment based on this one case.
l l 6. OTHER COMMENTS:
Per discussion with Bechtel on January 11, 1982, Bechtel was aware of the incorrect identification of the line 109 on ISO Dwg. 1204-004-01.
PREPARED BY: F. Lin d @ '
D ATE:1-18-82
/
COMMENTS:
hygg ugy/f 7.k n'2 w / r n s c f C /b'Ifu &
g! , ,, /sPc} "7 r-u1 1 /6" ~
chfp h , %u' 1
1 1
(Lk BY: DATE:
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ru n cmi mt rmumu nerun 4 ,
._ SONGS 2&3 SEISMIC DESIGN VERIFICATION PFR =7 NO. 4 p y g i '
A D z%98 - pff - cos REVI3 ION 2.
A PREPARAT10N'BY GA INITIATOR , , .
I I AFFECTEDITEMS:
, .Tafety. Injection Line to Reactor Coolant koop 1A i Piping Stress Analyses Packhge PSG 82 NEQUIREMENT REFEAENCE DOCUM, ENTS:
~
1
. i P&I Diagram 40112-10 i
. BASIC REQUIREMENT:
, ~ The esotilevered line holding valve 3/4 "x 114 x C-376, which branches out of cai.
tun 002-24 "- C-LIA. should be included iniche computer run mathematical model.
~ '
- O J . - -
+. '
., ~. .-
I
' DESCRIPTION OF PDTENTIAL FINDING:
Computer runs QU"25 or q39uS9 do not deplet this line in the mathematical model, although Otrasd ISO 1204 . %-1 (Sh. 50 PSG 82) identifies it as a dashed line at nodal point -s.
l I
Qg*g - -
l .IIEPARED BY: DATE:i-11 2 -
REJEl: TION OF GA TASK LEADER COMMENTS SY: - DATE:
REJECTION OF 0.a!S!NA!.0ESIGN ORG. COMMENTS SY:- - - - DATE:
- 5. REVIEW SY G A TASK LEADER COMMENTS
- / . ,
(
~
t -
I b AGREE PF IS VALIO SY _
DATE b8-N I
l M REQUEST RE REVIEW . EY DATE -
DISAGREE ,
BY DATE- -
O REVIEW OF ORIGINAL DESIGN ORGS. COMMENTS SY: -
__ OATE:-
l r
Ufos-ff R-oco'L REVISION
>!3 /e 2-e C. . REVIEW BY ORIGINAL DESIGN ORG ANIZATION COMMENTS 2'/08 - 88d'~4 ## Z-V ry small piping attached to large main headers are not censidered as significant in the dynamic analysis of the main line.
' This is a case cf a 3/4" line attached to a
. 24" line. The cantilevered line holding valve 3/4"-114-C-376 is a vent line. Vents ad drains fall within the scope of our small bore design guide specification, CS-P206. ( )
e
/igure 7 from that document is attached which shows the requirements. For the line of interest (single valve, 3/4"), the requirecint is that the overall length be kept balow I'-4". This particular vent is l'-3 1/2" and, therefcre, meets the requirement.
I b GRIE Nifv$N$ } h 806'I'f 'eismic, lo4Js en this cotilever vent
' line hu been checkel per atached calculdions.
G DISAGREE pg O n conforms 4. +e requiremed of BPc', es.trzo6, 6@ Therefore , BPe/s reponse is decePi ed ^"d I'
BY: [- o ." IN/ A DATE: 1 - / Pd 27Wa 1Nu.
I D. RE C0f.".*E'.0aTIC N E>Y F;'JD!fGS REVIEW C07.'t.tiTT EE G, cue - ['Fis umk /,
s .
DEFINITION ADEQUACY: E ADEQUATE D INADEQUATE ) p//62.-
q VALIDITY: O VALID E INVALID 1 10$FA-26 -- n NOT APPLICABLE n # esi in n, e
' ~ - -
i i 10.CAF-50;55(e): - D-NOT-APPHC4 F O-APPttSASif jgg g3/r t.
CL.ASSIFICATION: O OBSERVATION O FINDING t
] %)USTIFICATION:
3 l I
) CLASSIFICATION CRITERION NO. RESULTING IN " FINDING" -
1
! COMMENT ON "0BSERVATION" CLASSIFICATION 5
3 i
BY: -
l)
DATE: Y 1
1 E. TFT PROJECT MANAGER l .
O ACCEPT -
[ O REJECT p
l l
I h
BY: / 4 dO #
- DATE:
N;vemb0r 4, 1980 44Ue-rrn-uuuz
)yoV- Pf A -0 #I-PIPE TYPE SIZE '- y./3/8 @& e
(.
.] h NO VA'l'/E 1/2" 2'-2" W U
l 3/4" 2'-5" \\
I " ~
pgp L (TYP) j- ,
3
/
j~ 2'-8" g NOTES:
/
- 1. MAXIMUM "L" DIMENSIONS APPLICABLE TO SEISMIC CAT-L EGORY I VENTS, DRAINS AND Il2,, I ,-2.,
j- -
UTILITY STATIONS ONLY.
] X 3 IF "L"IS EXCEEDED, PIPE SUPPORTS FOR THE VENT 3/4" 1'-4"
, L AND DRAIN PIPING MUST BE
' PROVIDED.
I g 2. TABLE BASED ON FOLLOWING ASSUMPTIONS:
LS-
- 1/2",3/4" & 1" VALVES WEIGH 6,12 & 18 LBS RESPECTIVELY
- 1/2",3/4" & 1" CAPS WEIGH 0.18 .
a 0.3.0.5 LBS RESPECTIVELY
- NATURAL FREQUENCY OF O)
%d K7 L
1" 1'-7" 33 CPS OR GREATER f 3. VALVES SHALL BE GATE OR h SINGLE 1" g , 5" L l-- - (
- 4. VENTS AND DRAINS MAY BE USED IN ANY POSITION.
j j 1/2" 0*-9" 5. BENOS OR FITTINGS MAY BE USED.
3 L g,, ,j,, 6. THIS INFORMATION TO BE USED WHEN
' DIA OF HEADER I
DI A OF VENT
]-- M OR DRAIN FOR h & h, AND > 3 FOR
,_ yi FCR SMALLER DIA RATIOS L = 12" (FOR h . SUPPORT REQUIRED FO i l
~ "
@a@>
- 7. APPLIES TO ALL PlPE SCHEDULES UNLESS OTHERWISE STATED.
DOUBLE OC VALVES g ..
(SCH 40)
/
C/ Figure 7 STANDARD VENT AND DRAIN PIPING 66
_. -- . ~
7
GENERAL ATOMIC COMPANY
'3 A 268 RE V. 6+73 CALCULATIONS FO A EQU;P. NO.
lPROJ.NO. CALC.NO. lPAGE l OP 1 PREPARED SY
'f DATE [ Q] =-$ ( REF. DOCUMENTS:
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. O A 230 REV. 6-79 GENERAL ATOMIC COMPANY CALCULATIONS FOR
, equip. NO.
lPROJ.NO. CALC.NO. lPAGE LOF b PREPARED BY j, DATE l Q]- $( REF. DOCUMENTS:
h REVIEWED BY I I DATE y - 9/R - C5 0 0 >
APPROVED BY DATE ,li/$//r1. b l l l l l l l l l l l l
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Mu fs 6'FK -coo z GENERAL ATOMIC COMPANY D
Frzm: Frede r sek Lin oate. January es, 92.
' To be ahchel 40 2406-PFR-ooo2 h TELEPHONE COMMUNICATION RECORD (Please hand letter legibly in black or red ink)
Call Initiated by: Frede rick Lif1 at G A Other Call Received by: Tavc CA pifo Beehic l atek Other Other
Participants:
Mon t.
Date l- 4.5- B2 Time i P.M. Program Name/No. Task or 189 No.
Subject:
PFR - ooo 2 As summary. I ( Fred Lin) did not have hon rGuile Tone. C$- P20(o af 4he 4twe n -
i of conversa%n with Thtoe Canik . I wa4 noi sure -bt if Clag '2. eroe<
l' (nd c 'Z A la meter neel woi -6 be an alu v_ed in t6, mrbmolte d undel l
winin -the main run. 6n 'I- ash) -thic aueshen 4n DAue hve's renlo -
i i a
__wa s ,. No.for t" anl under Cr- Gim. 'l 7;oex , theu, nsem e llu 4l leo 4e-Tedan 4ulle spec. . C5-P 2.0 6 -A c condruv%n . -therv4Coe if M not nereuen'lu as J fe be. IncludeJ in -the maMema3(ca0 whde} w'fk -+k r mai A run n ive < . 3avA
_ _ f uge sted mp_ -b read the blan Entile se ce.. <n est I woul A knew whu 14-wuld vid be reautreJ in er_ mA,1 a nolutec a4 fona a< 4e niuswere enc 4roctd l-
~
L f 1 I dete/ dias -6 CS-P2o6 . 'f <Aj/ I haop nny Petehrel 4Ac (see '.
~
Then h e.
J 4ad it had been Jelluecel to 4A lact Thurdio U-21-gz) . I (d I'll check."
)
T nltn tea rnp44P) n f T O M 's ani :nouA .u ane d SAM orwoaAer run et V ,g t i l P% A'2. . He 4ad He utill ehe& :nin :-F .,, i Action items: Date Reg'd Responsible O
Info ec: 'ile No.
GA 1615
GENERAL ATOMIC COMPANY O ook OA m REv.c.rs c2 /##-#88 2/67rz4cn: -
CALCULATIONS POR . 2~ $ '
EQUIP, NO. CALC.NO. OF lPROJ.NO. lPAGE l PREPARED BY [ DATE l 'l 9 .- St REF. DOCUMENTS:
,O. REviEweO By 7 ' ~ d' OATE APPROVED BY DATE I l I l l l l l I I i I !
Ii I i I ,
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! l l l ! l I l l l l l l t i i i i ! I i l i ! ! II
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+
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1 I i l l l I i ! I I I I 1
, . I i l i i
!i M i = *l LtJ..'s) [t'2.(.9,5) t'o.3 Gs,5) + tz._( i,%t I -)(is,5)[ =3f1 ur.
! i ! ! i i i : I i iii i I i i ; i j i !
i
! ! M = d(45Rf3189# -
=r l, 0 0 's in-th , ' l i !
! I l l l
...i.
, l , i l i - .___
! t._. 4!
! ! ! e I_
' I i i i i ..f I
- . i i c = i1 o_p-i_Z =Ttt's = TC (o.@5)"(o,t13') = o, o n_4 in, I
I i i ! I i l iil i i ! l l i .
i i i i i l i! I i
. L L. (9) ' (e= erm f o,W ' ( - I i x i I
.i l 4 '
! ! ! ! 1l ll O [i.09) 'I 00 3 3
'iZ ^ b b f
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- i i i i i i i iii:,:i;
- m. . .J.a._ L ~;: e u -,. . %:.. .... . e.d.m., . # ' w..q. ,.MQ
, . .wr m .,_ m._. ..,_ ., . .
.' . l . - .
POTENTIAL FINDING REPORT 240s-ppa- coo 3 SONGS 2&3 SEISMIC DESIGN VERIFICATION PFR NO.
~
REVISION A. ..EPARATION BY G A INITI ATOR
! AFFECTED TTEMS:
Safety Injection Line to Reactor Coolant Loop 1A Piping Stress Analysis Package PSG 82 REQUIREMENT REFERENCE DOCUMENTS: i p ASME B&PV Code, 1974 Edition 1
1 l >
BASIC REQUIREMENT: "
Input data for Seismic Anchor Movement .(SAM) should be clearly specified in the
- ~
Calculation Package.
DESCRIPTION OF POTENTIAL FINDING:
- Sheet 39 of PSG 82 which identifies SAM data is not cleady documented and is not readily traceable. It needs more specific detailed description on the source and its validity of data and the application to mathe=atical model nodal points, uv b PREPARED BY:f. L o yi- .
( DATE: 1/11/82
[ HEJECTION OF GA TASK LEADER COMMENTS BY: DATE:
l REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: DATE:
- 8. REVIEW BY GA TASK LEADER COMMENTS c .
l
^
l t
i I -
)
GREE PF 13 VALID BY * *
- DATE /~//-EE M REQUEST RE REVIEW BY '
DATE -
O DISAGRSE ,
BY DATE
'O REVIEW OF ORIGINAL DESIGN ORGS. COMMENTS SY: DATE:
W -
C7 .
r au r. t **nv.-r'"
,U .
RE VISf C$
r MO3 AEVIEV.' CY O RIG:!! A L D E 5;C'4 0 F G ANIZ AT10N COMMENTS 3 / Seismic anchor covement data were developed through written 10:i's and codified through
["'bsequent verbal discussion and noted on appropriate calculation sheets.
/.
Ralative covenents between buildings are shown at the bottom of page 39 of 87. Three cc ,binations of relative but1 ding notions were modeled in the computer. The three con-binations are shown pictorially by the three sets of squares displaced relative to each other. Each of the conbir.ations represents a relative movement in three directions (X, Y, Z). Therefore. nine seisaic displacement computer runs were nade with novements shown by E PF IS VAUD the asterisk numbers on the right of page 39.
Q A$Gg/% \ Un O DISAGREE C SY: 9f&; 0 /R L L gg3g, f ~r G A D. R E C C ? "
- E '. 0 2. T i C ' E Y F . '; D"O S R E \ . EY.' C D '.' .'.' ;TT E E Mjwf,- 4, e e 26 : #
DEFINITION ADEOUACY: 00 ADEOUATE [D INADEQUATE <
- 1) Cit. W Ay VALIDITY: 55 VAll0 O INVALID 2on/aa~! M 10-Cin 21. " #
. u MATTL!C ' E LE O *?"L' CAD LE 10c. ..___n a.,. nr ie):
u auiArrth.es:. -u.
NA'*A8A
u arr u t, A :LE q VJ ' r) clui )
CLASS!FICATICN: S OBSERVATION D FINDING
,) A l Y=LL -
e a
{.. .,TIFIC ATIC N: Y ^ Y>h .
CLAS$!FICATION CRITERION NO. RESULTING IN " FINDING ~
COMMENT ON OESERVATION" CLASSlFICATION M a~< n i
& -a, & w & m & & . Enaxs~s.yeaswa p & A
- a /Vwstibb, k r y/4fy $ r=f f M &y J 3. " &
j BY: / DATE: 2- :
/ g w
E. T FT F R C .'E CT .'.' A ';; G E R ,
l JB( ACCE~T O REJECT s b I I EY: b LMMfft 40 OATE: z'/ VI
/ /
IMPACT ASSESSMENT 2408-Pra-003 PFR NO.
AFFECTEDITEM:
S.I.Line to Reactor Coolant Loop 1A, Piping Package PSG 82
- 1. IS THERE THE POTENTIAL FOR REDUCING DESIGN MARGINS TO THE EXTENT DESIGN ALLOWABLES ARE EXCEEDED OR DESIGN REQUIREMENTS ARE NOT MET ?
No. Based on stress summary table (Sh 40 of PSG 82), the design requirements were met for SAM loads given on sheet 39 of PSG 82.
No
- 3. COULO THE FAILURE OF THIS ITEM DURING AN SSE CREATE A SUBSTANTIAL SAFETY HAZARD ?
I do not know.
- 4. COULO THE PROCEDURAL VIOLATION CREATE A SUBSTANTIAL SAFETY HAZARD ?
No
- 5. ARE OTHER SIMILAR DEVIATIONS LIKELY TO EXIST ?
Icannot make judgement based on this one case.
- 6. OTHER COMMENTS:
Additional informationspertaining to this finding were obtained from BPC (GA Log 1348-9021 through 1348-9025 and 1348-9029) . From these informations the data shown on Sheet 39 of PSG 82 have been considered consenative. The application of the data to mathematical model was depicted in the SAM run computer input data sheet (GA Log 1348-9029).
F. Lin 2-2-82 PREPARED BY: DATE:
- qg 60/[
/ cu_ scN C/fdflM l
BY: - DATE:
/ / / '
i
Q@
- Enclosure (3)
._.,_,.,,... 3-****
p CALCULATION SHEET nffoyoe4-;A cq CALC NO
'- N DATE T-CGNATURr 9 " O D AT E"~ CHECKED
/'
D. p. .CT_< + ' e'~-" ~ ' -- " b ,
aon no. " ? - ' E SUEJCCT * * ' ~ ! /"' # # #*" *~ ' 2 N # 8 # "~ -SHEET M OF U SHEETS 1=4E.'b .
a . ~. . -+ .7 - 22 E LECTP)L Cy A LLL EFN(
.wuw am xu7g .
3 =. 70N NE-L (Pi p l N .@)
. y && lT hNY BLD-E7 0
4- ,
- 1 ml
- N..j N,I
, i 0 =
1 unck(.m?)
y
=
. .... . + i =. 2s .
.. y r-- , .
,. A 2 = - 25
$ 5 =. 2. s
= .
1
- 2. .
u a .t.4 __ v g.
n;m. s .. y.3 -
.4 s= S7
(. T" s
3
- M. 4/ 4.g= .72 ~ $
. t. w 17 .. ..
. + B = . 0 6 65,-
~~
1
- J 2 ' - -- f~3 '
.M ' I65~
ai 1.
,a .
t t- ;w -
5 .
1 .
c' f&jfRpaek .' 5:l.g, ii n 5..:;g~h.:. .. -
n . : :n :: -
P-E L A -flV E. OCN E. t\ E'NT .. .
. .. ; , t q
, . $ . c[ ?3 1 3 $
=
T d @'2*5 ,,., k1 '
') ( ' -
.. ~ 1.\ g =. . cf g = ~ .5" l ' M=\59C a N =
- 28, { 33Ag= ,37 % A 1C OSO6 ;
AE
- d E..I 0 2 5' A, 3 = 472 Is5
- .
- k c ~
p,.: Q[ ,.
'i' d, ,'h g
, W l'"
- 1349-903.L ..
Enclocure (1) d/h A b D /_ BX- f -f Q CLARIFICATION OF SEISMIC DISPLACEMENT USED IN PSG NO. 82 m
V
Reference:
PFR No. 0003 The differential seismic displacements between the Tank Building and the Piping \
Tunnel, and between the Electrical and Piping Gallery and the Piping Tunnel were six pag 17, 1977, At- %
transmitted tachment (A)fromhereof.C/S Astostated Pipe in Stress t [he IOM,)e by IOM dated [0ctoberthe reported k '
M cognized to be Monservative, meaning that the high numerical values given repre-sented an upper bound to be used for initial design purposed subject to reduc-tion by refined calculations if necessary.
Subsequently, through technical discussion between the C/S and the Stress Design Engineers, the displacements were re-evaluated to obtain more realistic and lower displacement values. These displacement values were those stated between (2) &
(3) and (3) & (4) in sheet 39 of Calculation No. M1204-002-2, Attachment (B) hereof. The reduction in displacement values was based on the recognition that ,
the Piping Tunnel is a light (relative to displaced mass of soil), unconnected structure embedded 14 feet below grade, so that under seismic event the tunnels seismic response would track the surrounding soil. Therefore the required dif-ferential displacements amount simply to the displacement of the Tank Building or the Electrical & Piping Gallery with respect to the soil in which the Piping Tunnel is effectively anchored by embedment.
The corresponding calculation for numerical demonstration that the re-evaluation of differential displacements yields lower values is enclosed as Attachment (C)
(Calculation No. C-280-J, sheets 97, 98, 99, 99A through 9911). The pertinent N displacement values, which are calcualted to be lower than those used in the pip-ing analysis per sheet 39 of Calculation No. M1204-002-2, are shown in sheets 99F & 9911. ,
Differential displacements between the Safety Equipment Building and the Electrical and Piping Callery AX = AY = AZ = 0.25 for buildings (1) & (2), as shown in At-tachment (B), are conservative. The corresponding calculated displacements were transmitted from C/S to Stress Group by IOM dated July 31, 1980, Attachment (D) hereof.
e 6 e w) ,
1349- 9M/
' /)ll.2.'!; e i; ' b Enclosure (2) '3
.l . .- > : 5 . ' -- 4 h
L ,-o- . .L.: 2 hhGi G;W W $ sn.O,4rF*'$2L4.' !
Aki512:::a:,- .6 W r,D,&,M %CW K ?2 %@2 i Cd i2.t .? &M&""
hb;.~1, ,5,e O ' @'# ' f,,, '
M@ MWN ( )W g ,$s%fi'y;;
, .,e ~-
9 j k h2.d' or,,c. Memorencum k%s
- s. e. ems
. m %, 802 2OO-A 450-C ,
.mo ,
" saa onofre trait s 2& 3 o. October 17, 1977 sechtel Job 10079 - e Seiscie Anchor Move =ents Fn,m 1. Eersh i%
or Civil / Structural
%,,, o R. Kosiba (
R. Chu m LAPD, B-45 s,s.
M. Campbell R. Ellis -
n - l ' "" d t
(.4 f pl 3$y y)
The Storage Tank Building and the Piping Tunnel are not included i f
in the "POSI" co=puter program used to evaluate seis=1c displacement response.
I Tank Building and the Piping Tunnel',iand_between the Electrical -Co
& Piping Galleries and the Piping Tunnellcan be set equal to the '
seismic response displace =ents between,the Storage Tank Building; and theanalyses.
element Electrical 6 Piping Gallerier as derived from their finite j '!
I.l The values for differential displacements between' structures, applicable to the three cases stated above, are as follows:
5' D.B.E._
6, B . E. = D. B.E. (0.55) I,,
U
- - g AN-S = 1.19 in. c' AN-S = 0.65 in. .
A oE-V = 1.20 in. s1 AE-V = 0.66 in.
overt = 1.32 rads ;n.
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- snteroffice ' Memorandum
- s. Mohamed c., 3023-200-h50-c
. July 31, 1980 $, 1 n I a ,,,,, san onofre Units 2 & 3 [j Bechtel Job 10079 From A. 14Paz '
Seismic Anchor Movements k, or Civil / Structural Engineering 5 LAPD, 3471 g ,,, 364 I L. Hersh m ce ,. i. H. Nugent ~ ,[6/u J[ "d ) > . /bc.ra,s -> l The seismic anchor movement case numbers 109, 110, 111 and 112 are f given on the folleving pages. gg The maximum relative displace:nents between buildings are as follows: ' ON-S , '_h-V Overt ,, Buildings 1.65 1.-27 1.99 Containment - Auxiliary .92 Containment - Safety Equip. .91 1.09 - 1.04 .92 1.46 Containment - Storage Tank 3.48 Containment - Fuel Handling 1.71 1.74
)
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-( Turbine - Safety Equip. .25 .17 .22
.11 .12 .06 Turbine - Intake Structure -
Il Safety Equip. - Elect. & Piping , I# ' Callerv .18 .05 .18 1.53 ' -
' [%c'7f 1 Safety Equip. - Storage Tank 1 1.41 1.00 5 *, I '-
2.82 c.f.n 1.99 v.M3 3.06 2.%7 0" C>
'rT] Storage Tank - Elect. Tunnel [S. y
]iiStorage Tank - Piping Tunne1 1.79 0 'M 1.80 4 " A 1.98 Diesel Generator - Piping 1.06 1.53 Tunnel 1.12
. s i
t' The ad-C The above relative displacements are ' conservative valuesl jacent buildings and plant coordinates will be required if relative . displace =ents are needed at specific locations.
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Bechtel Power Corporation
^
- g Interoffice Memorandum S. Mohamed 5023-200-A. 450-C 3 T.
San Onofre Units 2 4 3 pa, %, July 31, 1980
\( ,
%.e. ,,,, f*
3echte1 Job 10079 Seismic Anchor _Movenients n.,,, d .' Lopes os Civil / Structural Engineering
- c. L. Hersh m IAFD, 3471 g ,,. 364 H. Nugent The seismic anchor movement case numbers 109, 110, 111 and 112 are given on the follow:ing pages.
, The maximum relative displacements between buildings are as fo11cust Buildings ON-s AE-w Avert _
Containment - Auxil:iary 1.65 1.27 1.99 Containment - Safsty Equip. .91 1.09 .92 Containment - Storag6 Tank 1.04 .92 1.46 Containment - Fuel Handling 1.71 1.74 3.48 Containment - tiect,, & Piping callery .90 .65 .96 Auxiliary - Safety Equip. 1.58 .76 2.89 Auxili.:ry - Tuel Handling 1.03 2.03 2.35 Turbine - Safety Equip. .25 .17 .22 Turbine - Intake Structure .11 .12 .46
@ Safety Equip. - Elect. & Piping W 1 Callery .18 .05 .18 8 Safety Equip. - Storage Tank 8 1.41 1.00 1.53 L*r- N'I T . BT5torage Tank - Elect. Tunnel i 2.82 1.99 3.06 g] Storage Tank - Fiping Tunnel cg3 1.79 1.80 1.98 - ,tm % y 4 (.y r:ei $.
I , Disael Generator - Piping l Tunnel 1.12 1.06 1.53 I The above relative displacements are conservative values. The ad-jacent buildings and plant coordinates will be required if relative f displacements are needed at specific locations. O. +% TT jjb l u . ... ina .. . .. . . n.
9, cal'.CUCATION SHEET cat.c. NO
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Interoffice Memorandum Fue No. 8023-23-200-A, 450-C ( To R. Ellis Detober 26, 1979 saw.s San Onofre Units 2 & 3 o,, k, Bechtal Job 10079 A. Lopes Fran Seismic Anchor Hovemen_t_s S l or Civil / Structural l As 'Los Angeiss st. 4322 , cw as Power Division l M. Strang u3:, ,
@ $13 3 The seismic anchor movement, case number '107,is given on the following N
pages. i The relative displacements between the containment shall and interior structure (case number 108) are as follows: Elev. 30'-0" Horizontal vertical 0.03"]l 0.10" OBE. ltlev. 62'-9" Borisontal 0.08" O, Vertical 0.11" 4 A. Zap TTale ,. G I i
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. _..._ __ __. For Cas e (b.107
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4wei Copo 424 Kan p.so 15.1, na f7 -n 18 19 30 21 22 ' D 24 29 M . 11 29 29 N . 31 u 0 M
'1 Bechtei Fower Corporation interoffice Memorandum
' y, 8. Sethi FNs No. 5023-200-A, 450-C
% san onofre Unita 2 & 3 a, Detober 17, 1977 %
Bechtel Job 10079 Seismic Anchor _ Movement _s re L. Hersh a Civil / Structural
% ,, R. Kosiba m L&PD, B-45 sas. S
- 2. S __
M. Campbell R. Ellis The Storage Tank Building and the Piping Tunnel are not included in the " POST" computer program used to evaluate seismic displacement response. Conservatively, the displacanents between the Storage Tank Building and the Piping Tunnel, and between the Electrical
& Piping Ca11eries and the Piping Tunnel can be set equal to the seismic response ddeplacements between the Storage Tank Building and the Electrical & Piping ca11eries ald erived from their finite element analyses.
The values for differential displacements between structures, c 3, applicable to the three cases stated above, are as follows: D.B.E. f. B.E. = D.S.E. (0.55) s@ AN-S = 1.19 :in. AN-8 = 0.65 in. AE-W = 1.20 :in. AE-W = 0.66 in. overt = 1.32 'in. - Avert = 0.73 tu.- 4N-S = 0.028 rad. 4N-8 = 0.015 rad. E-W = 0.024 rad. M-W = 0.013 rad.
+ ert = 0.016 rad. A art = 0.009 rad.
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7t. Ellis - Storage Tank Bu11 ding and Electrical Tunnel are not included in the " POST" computer program. The conservative displacassants between these'two structures are using tha parkna values of , seismic response displacements of Senrage Tank Building and
.__ Safety Equipment Building. ,
, The following values are the displacements: -
g D.R.E. -
._0BE_a D.B.E. (0.53) ,
45-5 = 1.87847 in. AN-5" = 1.03316 in. AR-V = 1.32681 in. AE-W = 4.72975 in. Avert = 2.03957 in. Avert = 1.12177 in. e M-S = 0.04379 RAD 95-8 = 0.02408 RAD GE-W. = 0.00794 RAD Gs.w . 0.00437 RAD 8 Vert = 0.00424 RAD BYart = 0.00233 RAD -
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k]o()e Date 2. 67 Time lj Nffl Program Name/No. Task or 189 No.
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GENERAL ATOMIC COMPANY From: Frede FIak Date: IPS t S, j (~ To be a%he) % ?FR-0003. TELEPHONE COMMUNICATION RECORD (Please hand letter legibly,in black or red ink) Ca!! Initiated by: Fred Lrt1 atGA Other Call Received by: kkhed lo ogL atGr fecdok Other
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Date 2.4 N Time $$ Program Name/No. Task or 189 No.
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GENERAL ATOMIC COMPANY From: krederTtK LEM Date: Fr} . to . 140L ( ~',) T o 6 duke) % 9 PR -ooo 3__ TELEPHONE COMMUNICATION RECORD (Please hand letter legibly in black or red ink) Call Initiated by: Yre] L 'n at GA Other Call Received by: A\[ reel b ogy, atfsA96thkA k Other t ( - Other
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Date 1"[0- 66 Time i AM Program Name/No. Task or 189 No. subject: PFR-ood, eachtel h% rehej bu GA wea Talex
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GENERAL ATOMIC COMPANY From: Frede n e k. LM oats: Feb, to, mbt (~ Yn he_ a$$ tina) % VW~OOOO TELEPHONE COMMUNICATION RECORD (Please hand letter legibly in black or red ink) Call Initiated by: A1freA Lopes- atfrt& 44 1 otner
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Date 2.-10-%/L Tima ll 0 M A Program Name/No. Task or 189 No.
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GENEFtAL ATOMIC COMPANY From: Fre d e t-Tek lin cate: Feb, t b , 14 6'2-T To be aikached 4n PPR-ooo3-TELEPHONE COMMUNICATION RECORD (Ptease hand letter legibly in black or red ink) Call Initiated by: Frred L. In s atGA Other Call Received by: A\fre j love 7- at44 Egchhel Other Other
Participants:
dono Date 1-\(o-6'2 Time l,')'l P,M. Program Name/tto. Task or 189 No. Subicett 6ecMel Loa Y,X-4441(6A tra t%B-Rott +ru 13%-fo26); k TelerfrmteMel (GA Leg IM6-43B'1)
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auestions [p,Llo) dnl aniders ( A.Loe.et) w/A ducIn, & converdinn . g Q C1). when was h inharated pnwer back on,lu, ' F iu.ipete<ra met, A(t) . 6. Al Wildines are noi en 4e same OnAAton. TL ' are <nnaclei as our<e
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GENERAL. ATOMIC COMPANY
' From: Fre_J artcle Lin oate:_rd 8 6, 1%2 l
(~ be a+FaeheA u PPR- oo o3 'vl Th TELEPHONE COMMUNICATION RECORD J (Please hand letter legibly in black or red ink) I Call Initiated by: Fred Lin at G A Other Call Received by: Alfred Lopee at GA 8eeltfel Other Other
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N00t* Date 1-1(,-Bt Time 1:0 l'd Program Name/No. Task or 189 No.
Subject:
Bechfel I o BY-(AM (6A tu nst-40114ru 13H-4o2d Viiler b Bedkl (6A La 148-43B1) Summary This h s conYInuah dra Tejeha' 6 unreah Remd cn J Q(4) Whic.h bu'lling hue vou analvve) -for inJAddual build:na finSe eleme,d- Junarnic J ' ' ) a rulutc klated wMk e naralw 'oio. rn4 < u<+e m ? i- i ; r A C+) neu) Ste %&hs Eeviament 1 i BihTO . Glect. &' Pcorna Aalleru TD
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eip.meni rv1pAsl A N r+ t,. emitea " st> Peg suis Action items: Date Req'd Responsible Info ec: File No. GA 1615
GENERAL ATOMIC COMPANY From: FreMericl< ln'O Date: Feb, 16, I % 2
- ~ To ba. anachoA % PFR -o o o 3 TELEPHONE COMMUNICATION RECORD (Please hand letter legibly in black or red ink)
Call Initiated by: F reJ Liri at G A Other Call Received by: A16e) at4* Bedfel Other Lops Other
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hj nM Date 7-l b-BIl TimeI:I"7Pti Program Name/No. Task or 189 No.
Subject:
Bechtel Log B)(-G@l[GA lo41%6 -9021 thru 13%-(025),1 TehX frews Bedfel [GA log IMB-43M Summary 'Thk Sh I t ocniin'utth' ' Ocm Telephse Cmmuntedlem. Remed O Q('7) How come are 4he ts+ien OBE +o ME. a re_ different -fo r- numerAr-anA denominder in Tdle r# SL,9 4 l\ of E'nclosure 4 (6A Loo IM-6-rom ) 7 For ens +ance m M- s en re eAi ot , I waterstor #[g' c = , d C = o.s.C while & - denomindoe p8 ". = 8[ [ = o d .l A('1) The sason is *t -the numerder t< -for se c.ce e-C fn+,ar de/ Lu ni Dou]et- block andlo4t f kw] on ,c_ ped paramete&ourne elemerd:c fumerdructure
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Action items: Date Reg'd Responsible W Info cc: File No. GA 1615
GENERAL ATOMIC COMPANY From: Fr ederick Lin _ oate: 1 e b. i'7 , 1T 81 (~; To be -fited in PFR-o0o3 _ L/ TELEPHONE COMMUNICATION RECORD (Please hand letter legibly in black or red ink) Call initiated by: Fred Lin atGA Other i Call Received by: kl(red LopeE at9A-8eekYel Other Other
Participants:
Mone o Date 1 ','l- 62. Time iO SAP 4 Program Name/No. Task or 189 No.
Subject:
PFR-ool set 6mic- Anal34ib Summary Name 4 +he e.omputer codes u4ed in Bechtel 6e be+h integrded potaer block analpis ond indivMual buil Ain4 finite eJ e m e nt an nlu, sis _ is ca \\e a " BSAP 7 l ( The. wedel usel in +he intenrated oower block an4lu sis is n,ade of iv lumped ,,c Pam rra tA me.ter modelsupers4ruchres u. 'nn ee.' edmesh enmmon ,g+heo-f -Rnihe ebe MenYs ch koI\* The teode! itsed in the Indididu Ak buikdina finite e{e med a ndlu,si.s k wsa of Gent 4a 4 rent sueerdruc4ure s i kn o ii on e-kd bus 5(MXe e 4p riha s ch GOI\ o . Action items: Date Reg'd Responsible Info ec: Fire no, GA 1615
i j - POTENTIAL FINDING REPORT .. ... 24ca-Prn-cco4 PFa No. l -C. ..... . ....- SONGS 2&3 SEISMIC DESIGN VERIFICATION REVISION
^
""o RATION BY G A INITIATOR
- l AFFECTE0 lTEMS: Safety Injection Line to Reactor Coolant Loop 1A ll Piping Stress Analysis Package PSG-245
. REQUIREMENT REFERENCE DOCUMENTS:
Unce's Manual ME 101 linear clastic analysis of piping systems. . . BASIC REQUIREMENT: . , ASME Section III NC-3673.2 requires that a stress intensification factor be used for reducers. r DESCRIPTION OF POTENTIAL FINDING: At node points 144 and 145 where the highehe DBE soisr.ic strcas occurs (7180 psi) the reducer is not specified in the input and there is no stress intensification factor applied at that location. The code requires a stress l inteneffication factor f?t reducers be used which would increase stresses. Gl b *N3 h ree h$ S* I <> n
" * ** h 1 82 PREFARED BY: t DATE:
REJECTION OF GA TASK LEADE A COMMENTS SY: DATE: REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: DATE: - j 3. REVIEW GY GA TASK LEADER ' COMMENT 3 A N + C O 09 Al g
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1 l ir AGREE PF IS VAll3 BY = DATE /~~// IID i> > 'i+++_l DATE i
-Q REGUEST RE REVIErl BY 0 O!SAGREE BY --
CATE O REVIEW OF ORIGINAL DESIGN ORGS. COMMENTS DY: DATE:1
l PAGE 2 PFR NO. 2408-Pre-E a l REVISION D'<Jn g r-
. REVIE'.'.' CY ORIGIN AL DESIGN ORG ANIZATION COMMENTS
. Per NC-3673.2, the stress intensification factor at the reducer is' calculated on
[ age 12 of calculation :t-1204-063-2 (PSG 245). The SIF for this reducer was determined to be one, and the re fo re , the SIF at t'his location is included in the analysis. See Summer 1976 Addenda to NC-3673-2 for corrected formula. O AGREE PF IS VALID CD DISAp E gQs A [ g C dy::- BY: < M - L1 DATE: /~/ f- M 8/ D. RECOM'.1END ATl0N BY FINDINGS REVIEW COMMITTEE DEFINITION ADEQUACY: E ADEQUATE O INADEQUATE . VALIDITY: O VALID Gil[ INVALID tocc" n O& O ArrucABLt. ,)/g //2ofr2' t0 @ r_gg55g. O NOT APPUCAStF O APFDU;tBLE _ CLASSIFICATION: O OBSERVATION O FINDING i l STIFit'ATION: CLASS!FICATION CRITERION NO. RESULTING IN " FINDING" COMMENT ON "0BSERVATION" CLASSIFICATION BY: DATE: ' 28!U (/ E. TFT PROJECT MANAGER
$ ACCEPT O REJECT l l
< p BY: / AMVW DATE: [/22 2_.
l 'i ,[, _. POTENTIAL FINDING REPORT 24ca-tra-coos
! SOfjGS 2&3 SEISMIC DESIGN VERIFICATl0ij PFH 49. _
REVISION -- f DREPAn ATION BY G A INITIATOR - . AFFECTED ITEMS: safety injection Line to Reactor Coolant Loop 1A Piping Stress Analysis Pack.nge PsG-78 HEQUIREMENT REFERENCE DDCUMENTS: Pipe Support Drg No. S2-SI-059-E-Oo6 BASIC REQUIREMENT: , Calculations use latest design loads. DESCRIPfl0N OF POTENTIAL FIN 0 LNG: support X-rigid at node 143 Drg. No. S2-Sl-039-H-Oo6 elevs design loads of (+29850 and -25100). Sheet 63 of PSC No. 78 is given as (+43510 and -39901) for the loading at that support. An unsubstantiated statement titst higher loads are still within the margin of s,fety was made.
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0' N. Marsh [*^
//ao/ra.. ] FREPARED BY: - - - DATE: 1/11/82 REJECTION OF GA TASK LEADER COMMENTS BY: --- DATE:
REJECTION OF DRIGINAL DESIGN ORG. COMMENTS BY: - DATE: . f S. HEVIEW BY GA TASK LEADER COMMENTS - ay_dd p % m M g &bt
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CATE ' ( :.EGUEST RE REVIEW BY DATE
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BY - _ _ DATU O REVIEW OF ORIGINAL DESIGN ORGS. COMMENTS BY: DATE:
- PAGE 2 PF R NO. 2408-PFR-0 ),c REVISION _
SEW CY ORIGINAL DESIGN ORGANIZATION COMMENTS
' ,parently, the actual physical configuration was not clear to the reviewer. l l
-St-05'l-!!-006 is only a bl6ck in compression. It was obvious to the design engineer that a load of 44 KIPS can be adequately transmitted through a 6" X 6" X 7/8" thick block of steel (o = 44/6 X 6 = 1.222 ksi vs. Allow of 31.9 ksi).
k f62.- Mt & ^. O AGREE PF IS VAUD D DIS AG R E E f4.jp
'Y 1
fik -2 l c20 g^o BY: ! Ib ' 21 R D ATE: /-' S'~ Y' D. RECO:."/E!.OATICN BY FI'?D:NGS REVIEW COMMITTEE l DEFINITION ADEQUACY: ID ADEQUATE O INADEQUATE VALIDIT(: O VAllD ElINVAllD 10 C F a 71- O NOT M 3LE D MFUCADLE , 14N 5n 55f@ O NCT Ae"L!C'"LE O
- e"L!C '3LC CLASSIFICATIO N: 0 OBSERVATION O FINDING
.T IFIC ATIO N:
CLASS!FICATION CRITERION NO. RESULTING IN " FINDING" COMMENT ON "0ESERVATION" CLASSIFICATION BY: DATE: 2 82 a - E. TFi PR OJE CT .'.1 A N A G E R
% ACCEPT O REJECT
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POTENTIAL FINDING REPORT 2408-ern-0006 SONGS 2&3 SEISMIC DESIGN VERIFICATION PFR NO.
~
{ l REVISION A. PREPARATION BY GA IfJITIATOR j AFFECTE0 lTEMS: Safety Injection Line to Reactor Coolant Loup 1A Piping Stress Analysis Package PSG-78 REQUIREMENT REFERENCE DOCUMENTS: Pipe Support Drg. No. S2-Sl-059-H-009; Computer Run Q22L27: ISO Drg No. 1204-059-1. BASIC REQUIREMENT: Support analyzed to correspond to support used. DESCRIPTION OF POTENTIAL FINDING: ISO Drg. No. 1204-059-1 and sheet 63 of PSG-78 call for a spring support at node 147. Computer run Q22L27 calls for a rigid support with spring constant of 1080 lbs/in. (spring). Where as Drg. No S2- S1-059-H-009 calls for Mech. Snubber at Node 147. This is inconsistant. l I PREPARED BY: N. Marsh Lt DATE: 1-11 -82 REJECTION OF GA TASK LEADER COMMENTS BY: DATE: REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: DATE: B. REVIEW BY G A TASK LEADER COMMENTS b REE PF IS VAll0 BY v3 - DATE /' N- 97.- l I I C REQUEST RE REVIEW 3Y DAfE O DISAGREE BY OATE C REVIEW OF ORIGINAL DESIGN ORGS. COMMENTS BY: DATE:
l AL, L z e e s e . is. . 2.4CX FHetCCt REVID0? .__
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- r. ;onstric du;;. 1204 -O','J - 1 Lim :p r i n;; in nhown locatc<l at nole point 147 anel the
, be:r (dyn.in f ra l l y rl;,1<!) a t orn!<: point 146. 11m cc,nputer run Q721.27 specilles these component; un i n;; the locations ";pecif led on the ison<:t r i c . l t
The no<!c point (147) callout on dw;;. no. S2-SI-059-ll-009 in incorrect. It r.hould read i j 146, Tlic location of the snuhber, an shown on the support d rauin;;, agrees with the loc.ition shown on the isonctric and used in the computer analysis. Therefore, the anal v il e, is correct. I O AG 'EE PF IS VAUD - Itine r inconsistency; correction would not change design. C, C-O DISAGREE t & " '/F ! gy:_ _. / 7/' E '. O /.R 1.0- DATE /'/ M R
- i. F E C 0'.".* E ' 0 !-Ti ~ 'i [,Y F .';*J fi' S :.E \'i E'// C D '.".'.;TT E E 8o m .'v ye p ,
ds DEFlfilTIOfi ADEQUACY: E ADEQUATE Q INADE QUATE d,, Aj ,fp'y,~.ro gg/p VALIDITY: (R VAllD D lil V A LI D M6 % M 10 CTil21. O NOT * "L!C,' 2 LE O A??uCA0tE b fL- #Y ##/0 ' !' ' f NX //17/&' 10tRF 50.55b): n unT ^?PUCAELE D situt.2LE g fh g& C' 'IFIC ATIO f?: E CDSERVATIO!i O FINDlllG ,jg a.
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IMPACT ASSESSMENT 2408-PFR-0006 PFR NO. AFFECTED ITEM: Piping Stress Package PSG-78
- 1. IS THERE THE POTENTIAL FOR REDUCING DESIGN MARGINS TO THE EXTENT DESIGN ALLOWABLES ARE EXCEE0E0 OR DESIGN REQUIREMENTS ARE NOT MET? No Tht, Dit$ses for* h Seh.S M $C SE M lCf cllCe habb-
- 2. IS THERE THE POTENTIAL THAT THE ITEM MIGHT Fall OR ENDANGER OTHER ITEMS DURING AN SSE ? No '!2[ 2
- 3. COULD THE FAILURE OF THIS ITEM DURING AN SSE CREATE A SUBSTANTIAL SAFETY HAZARD ? No
- 4. COULD THE PROCEDURAL VIOLATION CREATE A SUBSTANTIAL SAFETY HAZARD ? No l S. ARE OTHER SIMILAR DEVIATIONS LIKELY TO EXIST ?
Similar deviations may exist but none were found by this reviewer. { } 6. OTHER COMMENTS: This deviation is not a problem f rom a design aspect. The nodes were close enough together to have little or no effect on the c.nalysis. f .
"* #8 1 26/82 PREPARED BY: DATE:
COMMENTS: 0p N a$ I m l I BY: 2&MN DATE: / - 1 6 - 1 2.- 1
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llCOUl8ET.tEllT REFEREf!CE DOCU .tEilT3: - PJpinr, Streus Analysis Package PSG-78 CASIC REQUIREMElir: ' The ceisele responac spectra used in t.he analysis be for the ' location to be analy:cd. DESCalPT10ft OF FOTE!!TIAL FliCD11:0: Sheet 7 of Pachage PSC-78 referes to respon'se spectra for no::zle (1A) fro:: C. E. transctittal 900-D-52-0. The responce cpectra.used in the atuslysis is S 023-900-B-55--O witich ic for nozzle (2D), Sheets 33 through 33. There is no statement to the effect tuat the response spectra is the came for both nozzles.
/m (v)
PREPACEO CY: _17. Its rs h [ AL _ DATE: 1-11-82 UEJECTIOi! 0F GA TASi' LEADER CD*.~.'.tEtiTS ;Y:- n DATE: -- REJECT 10tl 0F ORIGit:AL DESIGil ORG. CGr.li.*EDTS "' GY: MNNM DATE:J /M/ 2.
~
. REVIEW CY GA TAsi' LEADEG COL'.r.tE!!TS
~
'IEE PF IS VAll0 "~
OY _ DATE [-'/4 "f l
. QUEST nG.REVIEV/ BY ---
0/.TE - - O DISAGHEE OY DATE- * [ RCVICW OF ORIGifJAL DESIGrl OHGS. C07.17.1ErJTS BY: b=' ._ OATE: __ l-22%
N##- ma H E V t'.,1 C :1 vg[ y, (,Y O h t Git:A t l'i. '_ Ib 'd O I;f> A N IZ Al!O ri C0 fm.LNT3. p,,.,. 7 of 91 of pSG-73 c'it ablinlu a tint "the ncinnic spectr.: ut:ed in the dynanic analynic i envellope of C/:; and C-P..nupplie.1 curven". Since the C-F. ;pectra for the four . ,... . . t y l a je e t ion uozz tos IA, 1 11 , 2A and 2:: are aino;t idsntteal, an envelope spictra of tin' four was developed and uned for all four lines. 'tho re f o re , the correct spectra v.in uned for the location analyzed. 1(efer to deutgn specification DS-1204 for cpectra of tlic four nor.zles. O AGREE PF 15 VAUD Q DISAGF[EE /'vd; ' bt; r ': ij ;= BY: '! ' ' - ' ! F I P- DATE: /-' 7 ~^~1 F I C D'."
- E '. 0 '.T I C '? E.Y F i'; D : N 3 5 R E Vi EV! C O '.".'.tB E E -
DEFINITION ADEOUACY: 5 ADEOUATE D INADEQUATE VALIDIT'Y: I!D VALID D INVALID 1MfR-2h O "0T "?L!C4&tE- O AFFliCAULE / 22.[g2_ 10sRM025Mm . -- O NOT AFFuCABLE D AFFUCABi.E CLASSIFICATICN: E OBSERVATION O FINDING .
.'(_ FIC ATIC N: j }
CLASSIFICATICN CRITERIO No. RESULTING IN." FINDING" COMMENT ON O ESERVATION" CLASS!FICATION D M YMf P '-
~
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EY: G/ DATE: 2/[F2
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(i in PROJECT mar:AGER E ACCEr~T D REJECT I I i Y: A- MrWm DATE: f/2Y PL . - - . _ . - __
IMPACT ASSESSMENT 2408-PFR-0007 PFR NO. Safety Injection Line to Reactor Coolant Loop 1A AFFECTEDITEM: Pinine Stress Annivsis Packane TSG-78
- 1. IS THERE THE POTENTIAL FOR REDUCING DESIGN MARGINS TO THE EXTENT DESIGN ALLOWABLES ARE EXCEEDED OR DESIGN REQUIREMENTS ARE NOT MET ? No N0
- 2. IS THERE THE POTENTIAL THATTHE ITEM MIGHT FAIL OR ENDANGER OTHER ITEMS DURING AN SSE ?
- 3. COULD THE FAILURE OF THIS ITEM DURING AN SSE CREATE A SUBSTANTIAL No SAFETY HAZARD ?
No
- 4. COULD THE PROCEDURAL VIOLATION CREATE A SUBSTANTIAL SAFETY HAZAliD ?
- 5. ARE OTHER SIMILAR DEVIATIONS LIKELY TO EXIST ?
Other reference deviations may exist. { } 6. OTHER COMMENTS: It is felt that the response spectra referenced in the package as the one used in the analysis, should be the one contained in the p akage, instead of one that is not referenced. Otherwise, I agree with the original c~aign organizations comments. b PREPARED BY:N. Mrsh D ATE: 1/20/82 COMMENTS: d , I \ l l gV
/
! f # If g;/Aim 4ci BY: , h DATE:
//h'[fL I
ppg gg,2408-PFR-008 POTENTIAL FINDING REPORT REVISION #A SONGS 2&3 SEISMIC DESIGN VERIFICATION jff
'M/a A. PREPARATION BY GA INITIATOR -
)
AFFECTED ITEMS: Refueling Water Tank S21203MT006 REQUIREMENT REFERENCE DOCUMENTS: (see original) BASIC REQUIREMENT: (see original) DESCRIFTION OF POTENTIAL FINDING: BPC supplied the vendor (Brown-Minneapolis Tank) with an addendum to the design specification aef. 1) that included design nozzle loads. Out s of the six loads given for the 24" Safety Injection Suction nozzle, two of them are not conservative. Ref. 1 Ref. 2 l I F b 4334 lbs 4754 lbs 4 2 ft-lbs 30 ft-lbs PREPARED BY: C. Dahms [/ef. I 7 4 DATE: 1-23-82 REJECTION OF GA TASK LEADER COMMENTS BY: DATE: REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: I[ DATE: /'#7'EE B. REVIEW BY GA TASK LEADER COMMENTS l l l REE PF IS VALIO BY L DATE O REGUEST RE REVIEW BY DATE O DISAGREE BY ^ DATE _ MREVIEW OF ORIGINAL DESIGN ORGS. COMMENTS e BY: DATE: A i s
PAGE 2 PFR NO.JW-FM- odo F REVISION X8 1/r C. REVIEW BY ORIGINAL DESIGN ORGANIZATION COMMENTS //V/f C AGREE PFiS VAll0 O OlFAGREE , BY: DATE: D. RECOMMENDATION BY FINDINGS REVIEW COMMITTEE DEFINITION ADEQUACY: E ADEQUATE O INADEGUATE VAll0ITY: R VAllo O INVALl0 CLASSIFICATION: E OBSERVATION O FINDING JUSTlFICATION: CLASSIFICATION CRITERION NO. RESULTING IN " FINDING" l I COMM ENT ON "0 BSERVATION" CLASSIFICATION h1 M m 2Nm ga & Ms wa y % . M Jh e 2 p)h@A %B BY: # ~ DATE: 2 Mgp__ l r1 ' v E. GA PROJECT MANAGER C!!! ACCEPT l C REJECT l t J > l sy: P M/ t&/sut#b OATE: ( l
[. ppg go,2408-PPR-Ooos i - POTENTIAL FINDING REPORT REVISION l SONGS 2&3 SEISMIC DESIGN VERIFICATION l t r l A. PRC. PAR ATION BY G A INITIATOR AFFECTED ITEMS: Refueling Water Tank S217.03MT006 REQUIREMENT REFERENCE DOCUMENTS: Ref. 1) BPC Design Specification S023-407-13, Addendum No. 7. Ref. 2) BPC Calculation No. M1204-002-2A (PSG 82) Ref. 3) Design Report for Refueling Water Tank BPC Log No. 407-13-110 (Brown-Minneapolis Tank) BASIC REQUIREMENT: The desi.;a nozzle loads listed in the design specification (Ref. 1) should be consistent with the loads derived in the piping analysis (Ref. 2). DESCRIFTION OF POTENTIAL FINDING: BPC supplied the initial design specification (Ref.1) to the vendor (Brown-Minneapolis Tank). The vendor then supplied maximum allowable nozzle loads to BPC (Ref. 2, Attachment 1). These allowables are not traceable to the vend.>r's analysis (Ref. 3). BPC used these allowables as guidelines in performing the piping analysis (Ref. 2) and calculated actual design nozzle loads (Attachment 2). BPC then supplied the vendor with an addendum to the design specification (Ref. 1, Attachment
- 3) specifying t'ie design nozzle loads. This design specification and the piping analysis, gbothBPCdocuments,arenotconsistentwithoneanother. (see Attachment 2 and 3)
PREPARED BY: C. F. Dahms [. '[ / L- DATE: 1-15-82 REJECTION OF GA TASK LEADER COMMENTS BY: DATE: REJECT!LN OF ORIGINAL DESIGN ORG. COMMENTS BY: DATE: B. REVIEW 3Y G A TASK LEADER COMMENTS
/
7/ O AGREE PF IS VAllD BY / ~( l'(L DATE ![/J/'m ' I 6 / l O REQUEST RE REVIEW BY DATE O DISAGREE BY DATE O REVIEW 0F ORIGINAL DESIGN ORGS. COMMENTS BY: DATE:
om
/. PTR NO 24DR-PFR-C ,
.j. : -
. PAGE 2 REVISION A
.ps REVIEW DY ORIGif At DESIGN ORriAfd%ATIDN COMMENTS F' et.ch=,nc (2) pro,1 des notti. loado which vere developed .c the ti=e the eateuiation va.
,erformed. These were calcul.oted and sect the requiremento of Attachment 1. i-
/. At these a later date, loads with more some refiaco marginnor:le loads were were autrsitted developed to the vendor in'from the co=puter Referenes analyses and
- 1. The co=puter
/ cnalyses are refe renced i s the calculation, Reference 2. I There is no require =ent for the design cpecification and the piping analysis to be identical with one another. % e loads in the dcoign specification =ust be concervative, D AGREE PF 13 VAUD (i.e., equal to or exceed).whpn co= pared with calculated Iceds. ' G DISAGREE h1b Note: A1.'l attnehments and references stated chove refer to these ' gg stated in part A of this PFR. , BY:
/
- DATE '!f4! W -
). REC 0r".*E!.0 ATION SY FirJD:NGS REVIEW COMMITTEE g g g a-,
DEFINITION ADEQUACY: D A0EDUATE ElifADEQUATE p VALIDITY: D VAUD D.lflWLib' 4
.. 10 CFR 21:
10 CRF $0.55(e): D EDT APPLICABLE D HOT APPLICAELE D APPLICABLE D APPLICASLE gE 7@Q e / b ASIFICATION: D DDSERVATION - D FIN 0lHG
- JtiSTIFICAT! Oft:
CLASSIFICATION CRITERION NO.JIESULTING IN "FINDlHG*
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IMPACT ASSESSMENT 2408gR-0008 p Rev E AFFECTEDITEM:
"'"* '"8 ^'*# "
- 1. IS THERE THE POTENTIAL FOR REDUCING DESIGN MARGINS TO THE EXTENT DESIGN ALLOWABLES ARE EXCEEDED OR DESIGN REQUIREMENTS ARE NOT MET ?
No, the error found in the design specification has .egli,gible effect on the stress analysis performed by the vendor (see attached memo).
- 2. IS THERE THE POTENTIAL THAT THE ITEM MIGHT Fall OR ENDANGER OTHER ITEMS DURING AN SSE ?
No
- 3. COULO THE FAILURE OF THIS ITEM DURING AN SSE CREATE A SUBSTANTIAL SAFETY HAZARD ?
NA
- 4. COULD THE PROCEDURAL VIOLATION CREATE A SUBSTANTIAL SAFETY HAZARD ?
No
- 5. ARE OTHER SIMILAR DEVIATIONS LIKELY TO EXIST ? Similar deviations may exist but cannot be judged on this case alone. However, the document control between the piping analysis and the vendor design specification is unclear and cannot be traced.
l l 6. OTHER COMMENTS: The design nozzle loads calculated in the piping analysis were pointed out as being incorrect (Attachment 4) and therefore explained for the two non-conservative loads in the design specification (see attached memo) . PREPARED BY: C. Dahms [. [- [ DATE: 2-2-82 COMMENTS: l
/ '
l
. INTERN AL CORRESPONDENCE CA 1076 IN REPLY / ROM C. F. Dahms M [ REFER TO 70 Review Findings Committee DATE l-27-82 SUBJECT Impact Assessment Rev. B for PFR-ad8 To clarify Impact Ass'essment 2408-PFR-008 Rev. B, the two higher loads (FB "" B)additional performing calculated in the piping analysis (Ref. 2, Attachment 2) were used in calcuR tions in the same manner as was done in the tank analysis (Ref. 3, Attachment 5).
F B
~
L a 4754 lbs V r = 19 in. = 127 psi
'if roT T = 5/8 in.
Total shear stress n 99 + 127 = 226 psi 40.6 Sp 10,000 psi The stresses caused by the momentB M = 2 ft-lbs were not even calculated by the vendor (Ref. 3) because in analyzing a 24" nozzle, 2 ft-lbs is practically zero. This is also the case with M = f- s nstead of 2 ft-hs. B If the piping analysis (Ref. 2, Attachment 2) was performed incorrectly end the loads were combined in a manner explained by BPC in the telephotie conversation (Attachment 4), the net design loads would be substantially lower and all the loads given in the tank design specification (Ref. 1, Attachment 3) would therefore be conse rvative. Looking at the piping analysis in more detail led to the conclusion that it was done correctly. When computing the design basis earthquake loads (Attachment 2), one must compare the dynamic seismic with a calculated static ceismic. Conservatism would require the usage of the larger of the two, then the loads would be combined in the following manner: Thermal Exp. + Dead Wt.+ k (DBE)2 + (seismic movement)2 According to the indepet dent calculations (Attachment 6), the piping analysis is correct and therefore does not explain for the error in the tank design specification. However, this error does not have any safety impact on the tank as l was shown above. l l o O
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f TANK S21204MT006 (UNIT Tk'O) COMBINED DESIGN LOADS N0ZZLE SIZE 1 24" Fa= 6531 lbs Ma= 1366 ft-1bs (Cross Tie) Fb= 3174 lbs Mb= 5722 ft-lbs Fe= 4515 lbs Mc=14756 ft-lbs 2 24" Fa= 8293 lbs Ma=11702 ft-lbs (Safety Inj. Fb= 4334 lbs Mb= 2 ft-lbs Suction) Fe= 8555 lbs Mc= 9946 ft-lbs 5 3" Fa= 133 lbs Ma= 18 fr-lbs (Drain) Fb= 123 lbs Mb= 30 ft-lbs Fe= 36 lbs Mc= 127 ft-lbs 8 6" Fa= 263 lbs Ma= 60 ft-lbs (Overflow) Fb= 345 lbs Mb= 220 ft-lbs Fe= 129 lbs Mc= 368 ft-lbs 16 4" Fa= 417 lbs Maw 113 ft-lbs
. (SFP Make-Up) Fb= 264 lbs Mb= 262 ft-lbs Fe= 198 lbs Mc= 311 ft-lbs 17 6" Fa= 500 lbs Ma= 126 ft-lbs (CVCS Gravity Fb= 72 lbs Mb= 107 ft-lbs Feed) Fe= 102 lbs Mc= 29 fr-lbs
, 3 3" ( 10 3" Instrument Connections - Luads Are Negligible 12 through 15 3" TANK S31204MT006 (UNIT THREE) l Same as Unit Two (above). 1 1 i i I I I I , R Revised and Redrawn lo79Fo F(,R J/W pf e - loc 4); - l , e No. R EV1$lONS DATE 04. I CHK. I E.C.S. I CHF. E. I P. C l QAE. BECHTEL POWER CORPORAT;ON N-l SAN ONOFRE NUCLEAR GENERATING STATION l l ENGINEERS & CONSTRUCTORS pig
# "" ** S023- TANK OZZLE LOADS - SHEET 3 me No. oATE arenovao 407-13 SOUTHERM C ALIFO R NI A EDISON C0lAPANY 10079 SCALE LOS ANGELES. CALIF.
.................- A S o 23- S X- M- S76-B
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GENERAL ATOMIC COMPANY cA narEv.c.n CALCULATIONS FOR e EQUlP. NO. lPROJ.NO. CALC.NO. lPAGE OF PREPARED BY O . E. i, ah.my CATE / / -p aa/ 2
- REF. DOCUMENTS:
/'- REveEWED BY JATE $
APPROVED SY DATE i ! .l i liI I I I I l l i l l ! !I I i i i I; I l l I i I l ! I I i I I I l l l l l l l l l i i i !I I I
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h 4. o ' (, o + f/shq6 % (vio @ s i+ (& r E '! l' I-I. l l ! 1 I l I, _ l l l l i I 1 l-I ! ! ii I I h I I 11% = ' / 7 % ! u i z 4 j(_cy,:do z c(fdog : = 1 e / / .,_ 6 2 C I i ! i I L I i I ,,l _ ! s i i i l- . e
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POTENTIAL Fli! DING REPORT R EVISIGN f SONGS 2&3 SE!SMIC DESIGrj VERIFICATION A. P'iEPARA.TiOU 3Y G A i JITIATOR . AFFECTED ITtMS: Seismic Class I Cable Tray Supports Tray Hanger No. 37185 Ref: Calculatiens No. C270-01-02 l Sheets 360 - 365 t REQUIRE */ENT REFERENCE 00CUMENTS: j
- 1. Globe Strut !
Catalog G-643/OSG/ncv. 12-80; Page 71 l
- 2. AISC Manual of Steel Construction 7th Ed. , Sec. 1.5.6 l l
B ASIC flEQUIREMENT: l i Allowable single-point pullout load for CI-3812 Series ! Inserts = 2474 Lb x 1.33 = 3290 lb. DESCRIPTION OF POTENTIAL FINDING: Axial load on lateral brace was calculated to be 3860 pounds (Sheat 361). Allowable pull-out load on braco connection is only 3290 pounds (Sheet 364) Therefore, the applied load, as calculated, exceeds the permissible lead. See Attachment 1. . t l/ h' e ----~
? m ucy H. S nchez PREPARED SY: DATE:
REJECTION OF GA TASK LEADER COMMENTS BY: , DATE: REJECTl0:4 05 0?iG'NAL DESIGN ORG. CO.'.1MENTS BY- e/b MdId
's et DATE: y e
- 8. REVIEV! 3Y G A TASP LEADER COMMENTS I
i
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., ., - , . , (
C AGi.EE F F !S V100 5't :; E i ,* ! O ilEQ' JEST ':E r:EVIE'.*. BY j DATE l
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O O!SAGREd BY A DATC_ E VIC'.'l 0F C R;CI:: Al i.ESIGN O RG3. COl.it.iE:: r3 gy: _ 1 - k D.\TE 1 ! l .- l . . _ _ .. _
g . rAutt rt h N U. .:4. 5-F FRQ
- - REVISION dA
- d. REVIEW CY ORIGINAL DESIGN OF.G A?aZATION COMMENT! W #"
The design engineer did not clearly indicate the basis for acceptance of the floor con-
, r ~ rion ti. rough a CISS12 inser't in the concrete floor. The acceptatce is established n co: paring the given perpendicular pull-out load capacity to the corresponding cos-ponent of the brace load, which is 3360(.707) = 2730#
thus: "3290# > 2730# OK" should have been stated in the calculation O AGREE PF 15 VAUD .. G DISAGREE 4 - ' ' S
]# DATE: IY D. RE C0!."*E?,0 ATiCN EY Fi!5:f;35 REVIEW CO'.'M:TTEE DEFINITION ADEQUACY: El ADEOUATE D INADEQUATE VALIDITY: If VAllD .D INVAllD 1MP 71- - n unT m ucAgtE O Art;,;cA3tE -
10 e"r 5155M- O unT m ucA3tE y urticAgts CLASSIFICAT'10N: O OBSERVATION RI FINDING
'. IFI'0ATIO N: -
t > CLASSIFICATION CRi~ ERION NO. RESULTit G IN " FINDING" I - s COMMENT ON "DESERVAT10N" CLASSIFICATION - PFR laa F & M dw L M w & 40-4, d ms;> , d M} 4) U[m & [b# ~
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- . TR FF.C.'E CT " A'; A G E R O ACCEn O REJECT I I
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BY: / / Afhw , DATE: O
, ~ . _ . _ . . _ _ . - . _ . . - .
IMPACT ASSESSMENT
.2 40f- PFR NO. 0009 AFFECTE0lTEM: SE/SM 8 C CLASS I C ABLE TRAY SUPPO RT 44'6718 6
- 1. IS THERE THE POTENTIAL FOR REQUCING DESIGN MARGINS TO THE EXTENT DESIGN ALLOWABLES ARE EXCEEDED OR DESIGN REQUIREMENTS ARE NOT MET ?
YE3
- 2. IS THERE THE POTENTIAL THAT THE ITEM MIGHT Fall OR ENDANGER OTHER ITEMS DURING AN SSE ?
'~
YES
- 3. COULD THE FAILURE OF THIS ITEM OURING AN SSE CREATE A SUBSTANTIAL SAFETY HAZARD ?
THE FAILURG OF THis ITEM c o V L C) A FF E CT T H E ope R AT io M OF THE S A FGTY IM IECTio N PuM P ( P-old A M D THE REA cTOR- RE F UELING WATE R T A N k OVfLET VALVE ( H V- 93o1)
- 4. COULO THE PROCEDURAL VIOLATION CREATE A SUBSTANTIAL SAFETY HAZARD ?
fV / A ,
- 5. ARE OTHER SIMILAR DEVIATIONS LIKELY TO EXIST ?
IT ns Poss l G L E
- 6. OTHER COMMENTS:
a.) THE Do cd t4E NTAT io W coMTA IM S ERRORS b) T HE DESIGW APPE ARS To SE IM A DEQU A TF. PREPARED BY: H.SAWCHE . DATE: L il COMMENTS: f-Ed L427 k b /C )$ L? C Jl'4 ff/O <'Y s l & a ac,10 jur,4~ ~r G ,% r u , w ,~ h < + u n e,c cn en-w h . /&c. owc w M 7~ /EK n - m 64 m w ap. /2~ a s er jf/ C7 laO %k (tM of Sdde [/uc f CsAI" aynge as \ vales ,c%7 ared p H-nt, N ,n c4
+tu woiw - ,fu m p,-4./
S y d 'cd R/k e n n ,.<.w f $ 7 G p, et c 4yM havi C 'c o c u< JC'v BY: M O. /. M DATE: 7/ O" _j. y 6 je + > i
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f INTERNAL CORRESPONDENCE i GA-1076 I IN REPLY FROM: H. W. Sanchez REFER TO: TO: G. L. Wessman DATE: Feb. 8, 1982
SUBJECT:
Project 2408 - Test Data for Globe-Strut Products Ref.: PFR No. 9 The following statement appears on page 2 of the test report submitted by U.S. Gypsum Co.. entitled ' Load Test Data for Globe-Strut Channel. Accessories and Concrete Inserts": The allowable load values contained herein are released for promotion in the sale of related GLOBE products.
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POTENTIAL FINDING REPORT 2408-PFR-0010 SONGS 2&3 SEISMIC DESIGN VERIFICATION PFR NO. s REVISION 1 A.' PREPARATION SY GA INITIATOR AFFECTED ITEMS: Safety Injection Tank T-008 (SONGS UNIT 2) REQUIREMENT REFERENC6 DOCUMENTS:
- 1. Evaluation of revised nozzle loads on the Safety Injection Tanks, C-E Calculation
#S-PAC-010, 6/24/81.
- 2. Bechtel letter No. BC-1617 dated May 4, 1981.
BASIC REQUIREMENT: The scope of Ref. 1 includes the design of nozzles on S.I. Tanks for both Units 2 and 3. The Ref. 2 letter states that the ' attached nozzle load tabless are for safety injection tanks in Unit 2. The nozzle load table for Tank 007 is marked applicable to Unit 2 while load tables for Tanks 008, 009, 010 are marked as applicable to both Unit 2 and 3. The validity of nozzle loads used by C-E for Tank 007 in Unit 3 are in question. DESCRifTl0N OF POTENTIAL FINDING: l t PREFARED BY: M- Kr4ahna (h/ DATE: 1-13-82 REJECTION OF GA TASK LEADER COMMENTS BY: DATE: REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: DATE: B. REVIEW BY GA TASK LEADER COMMENTS es d AGREE PFIS VAll0 BY DATE b l / / / O REQUEST RE REVIEW BY DATE O DISAGREE , BY OATE O REVIEW OF ORIGINAL DESIGN ORGS. COMMENTS BY: 1 DATE:
.~.,f . ,.. -. -
Ji
I PAGE 2 PFR NO 240&-PR-0010 l
~
l REVISION C. REVIEW BY ORIGINAL DESIGN ORGANIZATION COMMENTS Loads in Bechtel Letter BC-1617 were transmitted when Bechtel reali' zed th'ey had excee2 d, I the C-E allowable nozzle loads as given in C-E Spec.1370-PE-603. C-E then selected the' l maximum loads from this letter (from Tanks T-007 and T-009) to determine if these loads l were acceptable, in order to provide a bounding solution. Any loads less than or equal to the loads provided by Bechtel whether they are for Unit 2 or Unit 3 would be accept-able. In the event that higher loads are calculated for Unit ?, it is anticipated that Bechtel will once again notify C-E and ask for our concurrence to use these higher loads; O AGREE PF IS VALID It is our understanding that the Rechtel analysis for Unit 3 is not > yet complete. Note that C-E Letter S-CE-6756 dated July 31, 1981 0 DISAGREE to Bechtel relative to these~ loads does not reference a specific plant or tank, but refers to any tank on either Unit 2 or 3. Therefor 3 we do not bplieve that the question of the nozzle loads BY N b 5CTO 4 V6/A F DATE: //Z '/r ' - u' sed by C-E to be a valid concern. D. RECOMMENDATION BY FINDINGS REVIEW COMMITTEE NEN#N v e.as aw.5 *
- U" W
' heltomwy DEFINITION ADEQUACY: 5 ADEQUATE O INADEQUATE , g E) ble cgv ec. votN be.
.A %g 1, VALIDITY: O VALID E INVALID ha.Deup Oga*imh...
y eco 3,. n un, moo .ran,e n nooi.e.o.E 7 1 .55Mw O NO A i . L' a ^ i /* co w cK CLASSIFICATION: O OBSERVATION O FINDING ave (,Q Hu w & e. ], JUSTIFICATION: g, g), og CLASSIFICATION CRITERl0N NO. RESULTING IM " FINDING" ik 2. COMMENT ON "0BSERVATION" CLASSIFICATION H L hw % W
. ,F,ly BY: - '
DATE: ,- M,IL llui B> 9 E. TPT PROJECT MANAGER l r I B ACCEPT , l O REJECT ,
~
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' M I Mj /h**" i j /go/gp_ y p) .(
By: DATE: E 4 , 1 k s t ( ~*
3- , . 3 i y D INTERNAL CORRESPONDENCE
, GA-1076
- ATTACHMENT 1 IN REPLY FROM: M. Krishnan REFER TO:
TO: ~ Findings Review Committee DATE: 1/27/82
SUBJECT:
Safety Injection Tank T-008 n The following is an asplification of the description of Potential Finding on page 1 of PFR-0010. CZ initially issued a design specification whi:h specified the maximum nozzle loads the S.I. tank was designed for. Bechtel then checked the noszle loads obtained from their piping analysis against the maximum allowables supplied by CE Bechtel then informed CE of the actus1 loads obtained for each
,, tank (T-007. 008. 009 and 010) in Units 2 and 3 and this was greater than the e CE allowables. CE then re-evaluated the S.I. tank based on the higher nozzle
)' loads supplied by Bechtel and bounds the analysis by evaluating only the tanks with the highest loads (Tanks T-007 and 009). CE then stated that these Bechtel supplied nozzle loads were acceptable and could be valid for Units 2 and 3. The validity of nozzle load on tank 007 was in question since Bechtel's transmittal was not clear if the loads were applic ble to both Units 2 and 3.
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FROM: LOCATION: DATE: TO: LOCATION: DATE: i O- TELEPHONE COMMUNICATION RECORD 9 ( PLEASE HAND IEITER TrrmY IN BIACK OR RED INK) PFR - DolD CALL INITIATED BY: d/. /. A//A#S/4 AT GAC $ OTHER: CALL RECEIVED BY: D At/c C4 #/ To AT GAC C OTHER: SE2:urEL OTHER PARTICIPANTS: A//oe&n/ /6 pts /4A/4d (.2t3)946-/tt/ X593 i PROGRAM NAME PROGRAM NUMBER DATE: /* 75!f2. TIME: 9.30 m
/
$stsute [c//EO. 240f ,
SUB3ECT: fe2 " AfD22f K l DADS oAl SAFETV hk/[Cflod SkMk' TOOY
SUMMARY
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Date Person ACTION ITEMS: Required Responsible l l
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A ._>i DISTRIBUTION: E ODN . A/l. Er[Sk h I / File No.:
1 POTENTIAL FINDING REPORT SONGS 2&3 SEISMIC DESIGN VERIFICATION PFR Nh.4og_pya_ooit REVISION t .. A. PREPARATION BY GA INITIATOR AFFECTED ITEMS: LPSI Pump P-016 and Support Structura REQ'JiREMENT REFERENCE DOCUMENTS: San Onofre 2 & 3 FSAR, lig. 3.7A-95, DBE Vertical Acceleration Response Spectra at Elev. -]5'-6" of Safety Equipment Building (Safety Injection Area). BASIC REQU:REMENT: Building response spectra curves indicate vertical acceleration value
- of approxhnately 1.2g at 33 to 40 cps with 5% damping.
DESCRIPT10N OF POTENTIAL FINDING: Vertical acceleration specified by C.E. and used in pump vendor (Ingersoll-Rand Co.) static aaalysis is 1.0g (Ref. C.E. Spec.1370-PE-410, Rev. 07, and I-R Analysis Report EAS-TR-7625N), which is less than the FSAR criteria. l b, -
.. s . -
PREPARED BY: _ DATE: REJECTION OF GA TASK LEADER COMMENTS BY: DATE: REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: fN'I DATE: g2Ms2 B. REVIEW BY GA TASK LEADER COMMENTS i I' O AGREE PF IS VAll0 BY b DATE ' 1 l i l' O REQUEST RE REVIEWSY DATE O DISAGREE BY .-- 4 DATE O REVIEW OF ORIGINAL DESIGN ORGS. COMMENTS BY: l ' / C-DATE:
/
N _.,. _ . ._. _ . _ _ _ _ _ _ _ . - ____.L___._.. . __. _ - _ _ _ _ ._ _ 2 _ _ . _ . _ . _ .
_, .m -- PAGE 2 PFR NO.2408-PFR-00ll REVISION C. REVIEW BY ORIGINAL DESIGN ORGANIZATION COMMENTS Per Bechtel telecon (R. Rogers - BPC to J. M. Westhoven C-E) 4:15 'p.m. EST January 2Pd I The FSAR reproduction of the seismic response curve is difficult to read in the area of concern. The BPC project curve, which is clearer, indicates better that 1.09 is the appropriate value. It is noted that a seismic response curve is a smooth envelope of calculated accelerations vs frequency values and is conservative for this reason. The C-E project specification for the component was reviewed by BPC project personnel O AGREEPFISVAllD~ for proper interface and was provided status one (1) designation on 7/26/77. The specification appropriately identified 1.0g as B DISAGREE the seismic vertical requirement. BY: DATE: D. RECOMMENDATION BY FINDINGS REVIEW COMMITTEE DEFINITION ADEQUACY: O ADEQUATE O INADEQUATE VAllulTY: O VALID 0 INVAL10 - 10 CFR 21: O NOT APPLICABLE O APPLICABLE 10 CRF 50.55(e): O NOT APPLICABLE C APPLICABLE
. CLASSIFICATION: O OBSERVATION O FINDING JUSTIFICATION: I CLASSIFICATION CRITER10N NO. RESULTING IN " FINDING" COMMENT ON "0BSERVATION" CLASSIFICAT10ri
, BY: DATE: E. TFT PROJECT MANAGER O ACCEPT O REJECT - BY: DATE:
-- m._ _ . _ .
PAGE 2 . gg / PFR NO.2408-PFR-r REVISION .s , gvuin C. REVIEW BY ORIGINAL DESIGN ORGANIZATION COMMENTS Per Bechtel telecon (R. Rogers - BPC to J. M. Westhoven C-E) 4:15'p.m. EST January 21, if The FSAR reproduction of the seismic response curve is difficult to read in the area of 1 concern. The BPC project curve, which is clearer, indicates better that 1.0g is the appropriate value. It is noted that a seismic response curve is a smooth envelope of calculated accelerations vs frequency values and is conservative for this reason. 3 The C-E project specification for the component was reviewed by BPC project personnel . O AGREE PFIS VAll0 ~ for proper interface and was p.rovided status one (1) designation on 7/26/77. The specification appropriately identified 1.0g as 3 E DISAGREE the seismic vertical requirement. BY: , DATE: D. RECOMMENDATION BY FINulNGS REVIEW COMMITTEE i I DEFINITION ADEQUACY: E ADEQUATE O INADEQUATE . j VAll0lTY: B VALIO O INVALl0 - 14CFR-21: 0-tt0TAFFLiCABLE O APPLICABLE - sh f/W/9'L 10 C8p sn n5(s): Q-NQT-APPtiCABLC O-APPLICABLE-q . CLASSIFICATION: IN OBSERVATION O FIN 0 LNG JUSTIFICATION: CLASSIFICATION CRITERION NO. RESULTING IN " FIN 0 LNG"
' C0MMENT ON " OBSERVATION" CLASSIFICATION (Led 5
,6 L A~r'2 9' 4, A A.~/ ~ J4 K 6 b &&
- ga w a - y.nsa CAe7 PW'
{/ n / rz A fE BY:' # DATE: (/ l ( E. TPT PROJECT MANAGER f l 3 El ACCEPT O REJECT l
/
BY:. N DATE: O
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, FREQUENCY (cycles per second) 100 50 25 to 5 2 1 .5 a
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'. ,,. l f4ATERIAL : .ASME SA 193 GR .B~7 PS I , l DATA 1 dL) r yis t.p, s.y = 105.000 Pst gj b) ALLOWABl.E STRESS r:.neN5'E's, Sr == H8 y;
% 2.5 S oo0 00 w
, e n' m- s, ed,a ~
, g, g .yg C Bot.T DI A l
$i
' SECTION 1
- d) AREA 0F CROSS
=- 2 433 2
@ MINOR. DI A , Ac.s. -
* &m
. l
- REACTION S h MTG. . root 36 LT 1 F 7. SOLT l
RE ACT 0H S AT EACH M : t".. j S. 1 DAD CRITF.RI A
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. =
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' =
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- pu :
l' BOLT ST RESS ES * .
!. MAX. TEH$lt.E sTRCSS , F /A,,h .
.' 2 f f f f . 4-IN'.'
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. lY;7 9..L'S *
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- 1 Dit AA STRESS s MAR * !HC AR FCECf /Ac.3. ~~N4T~~l egg
' <
- 3.IlA1. .
. M
- 4. COMelNED sTRCCSE S
- l (* '$1')4 5"2 '
~
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- U.@f
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.. . .. .3 g3.1 STRUCTURA1. INTECRITt Ahkt.YSIS RTSht.T_S -
. .. s .
c, . e
.. er g, ' resultant stresses (Ibs.[in. ) due to combined totsi loading
- pr critical components. .
I
- Stress Stress' Category Calettlated A11ovabic t
Component Condition I (- , d 5588 15100 F Design Pn ~ Fump Casing & Cover 20 g f 22650-i De' sign' ' PgP, 3 bopCasing& Cover , 4530d 33274 tror=al' / Upset PgP 3+Q Pump Casing & Cover , 22902 . 24300 Mounting Toot Normal / ,,, Upset , . PgP* , MM 24300 Nor=al / . Upset Pg+P 3 Hounting Poot field , N m,00 Normal */ Upset Pg?3 . Coole'r Bracket ' 12 M Upset P +P3 MSS p Hotor Supporting Head Nor=al / Casing-Suction Noz=le Py +P3 % DC 210'44
- 4530'0 Intersection Norval / . Upset ,
~'
Casing-Discharge Noz:le Pg +P 36312 - *4'5300" 3 M DC
. Intersection Normal / Upset .
i Stress est
. 301.T STRESSES I .
, Calculated A11ovabic
. . Component Type of Stress .,
15172 - 25000 Cover Dolcs Normal
- .. 15000 Shear 7586 cover Bolts T '
23935 aR '
~25000-Mounting Foot Bolts
- Normal %
359 15000 Hounting Foot Bolen Shear /
.. 7000 Cooler Brachce Bolta Normal . 1469 .
< 4200 Cooler Bracket Dolts Shese - 908 14400 tot 1 told-down Dolta Nermal 8561 8600 - '
"*fI!old-Down Dolto Shear 5477
+7000 l, Nonnal 5350 "C Dbx Dolta
- --- - -- ' ~ ~ ~ ~ ' ^ ' ~ " ~ _
Tb: G, ldessm % 4SS-26S'/ ' D w ,: it). b. @nn ett C E. Responses to: 2408-PFR-0010
- Loads in Bechtel Letter BC-1617 were transmitted when Bechtel realized they had exceeded the C-E allowable nozzle loads as given in C-E 5pec. ,
i 1370-PE-603. C-E then selected the maximu:a loads from this letter (from : Tanks T-007 and T-009) to detemine if these loads were acceptable, in ! order to provide a bounding solution. Any loads lesc than or equal to the ' loads providad by Bechtel whether they are for Unit 2 or Unit 3 would be t acceptable. In the event that higher loads are calculated for Unit 3, it is anticipated that Bechtel will once again notify C-E and ask for our ' concurrence to use these higher loads. Note that C-E Letter S-CE-6755 i dated July 31, 1981 to Bechtel relative to these loads does not reference [ a specific plant or tank, but refers to any tank on either Unit 2 or 3. I
- Therefore we do not believe that the question of the nozzle loads used by .
; C-E to be a valid concern.
Responses to: 2408-P M w C-E has reviewed FSAR Figure 3.7A-93 (95 is e typo) and finds that the , 5% damping curve is on the 1.0 g line. C-E has reviewed the I-R Analysis Report EAS-TR-7625-N, dated 17 June 1976 and finds that the lowest natural frequer.cy of the pump / motor structure is calculated to be 39.66 Hz. At this frequency the spectral value from FSAR Figure 3.7A-93 is essentiaMy 1.0 g, the value given in the component .spacificction. ' C-E, therefore balieves that the acceleration used in the C-E -
/ ,
specification 1370-PE-410 to be acceptable, j)p}s t REs y ses Lu e* 0 (oc- % M V'>55 o' ss - m n =. . o
, s
____, . '~ ' ' ' x _ _ , _ _ _ m w
. _ ,-. - , , .- -- - - w- m
Z K L /e.1
~
racM: LOCATION: DATE: J/J/82 ~ To: A 6/e LocAT!ce:: oATE: pSCEPiW l T E L E P 110 il E C0MMUffICATI0fl RECO'Rd3 i ( PLET6E IND IIITER LEGIBLY Di EIACK OR RED HE) ,
~~~
ncuit.- - Call. IitITIATED BY: f 7,,,1/.I /~4n /es AT GAC h OT N . ~ .. -~~~' O Call. RECEIVED BY: 804Jewsi//JeJ'r uer/Aove .AT-GAC-6 OTHER: C4
- OTHER PARTICIPAftTS: E, To- ., [4 del .
/
I 3-PROGRAM ttAME PROGRAM flVMBER DATE: t/J/BJ TIME: 7!30 4H' roAin kirnic erview ' . osstoo
SUBJECT:
PfR - p o rt , I/er be' / 4 cce /es. h o'n 4 1 e 9;< Je'se',} b .lyrh of Ae-p P-ott
SUMMARY
- I' ~ r ll t 'a r I"Nnred /h/ GNC I"le</'r/r/ /1.e reiros.le n ep o n te rpee/<a ~ cme tG fl,e- %fefy' Eg.<ip e.4 ElJ, . </ e lev. -ls'-t fo t h rli b a /r a /erftba/ acce/en/isn r/iht. fly Ai hw /sr as fhe /, o y rp e e ,' g e'd J, ,
CZ e d ured ist /he p n.p vendor /Ge < </yr/r , luf thaf revola / /1.ex */vr5 Y4 ' /os),$gt uss'n o c/u.e / pthol4 no yf fe rea c/so'n r de /e/*wided $.7 /he EPC pops y .sc .stpes rah o< h.a ., fhe de rr}n /= *,/r areJ ly fi,e ,3u n p yes ,h i-s ' di k,< ft A no owr}<rts pro 1/emt. //e s/ 'd n ot d&* 9 <e e ulf>> /1,r'r i ' fe/p << /a ti? .
. Date Person ACTIO:t ' ITEMS: . Required Resconsible
,e B
^
File f;c.:
. = - = - - . - . . . . . . . . . . -
_. PFR NO. 2408-PFR-0012 POTENTIAL FINDING REPORT REVISION
~
. SONGS 2&3 SEISMIC DESIGN VERIFICATION W A. PREPARATION BY GA INITIATOR AFFECTED ITEMS: LPSI Pump P-016 and Support Structure REQUIREMENT REFERENCE DOCUMENTS:
- 1. San Onofre 2 & # FSAR, Fig. 3.7A-93, 3.7A-94 and 3.7A-95, Bldg. Response Spectra.
- 2. CE Spec. 1370-PE-410, Rev. 07
- 3. Vender (1-R) Pump General Arrangement and Installation Criteria Documents C-8 x 20 WDFB6 x 21, Rev. 01 and L.N. 8x20WDFB6x21, Rev. 01
- 4. Vendor Analysis Report EAS-TR-7625N BASIC REQUIREMENT:
Vendor used acceleration values of 1.0 G vertical and 1.5 g horizontal for static analysis of pump components, which assumes little if any amplification of building accelerations. DESCRIPTION OF POTENTIAL FINDING: Potential failure of pump support structure design to meet assumptions used in vendor analysis and potential overstress of pump mounting bolts. Check calculation indicates strength of mounting bolts specified by vendor may be marginal. Documents on design and analysis of pump support structure were noti available for this review. m -
~
* ' 7 PREPARED BY: DATE:
REJECTION OF GA TASK LEADER COMMENTS BY: DATE: REJECTION OF ORIGIN /.L DESIGN ORG. CDhlMENTS BY: DATE: B. REVIEW BY GA TASK LEADES COMMENTS k - r&u- em h[ r- a Y a n. 'fa i r A C'h k
- cf '
coleftb& tE
$~t rayoa*/ sfra.cluse dra v.- yr ud a tyrn vere c6/<ibed ho.u BPc a-d <wilved.
The nko'E/y offin r.iposf rte,*ctare un defer-oheJ fa 6e **'op u afr co<d < <e-eAo.ek of /4e no.< fdy 4o //r u r/Ay ted* * /oaJSyr coers'/e r ,f w,'fs /s,e eaf.a<a f Sey e,,a y J aelaa/ (/*wer) p*pdy *.eyyle wJ da prory ef fhe />a ,p/ rays t atreoui/p < /k < ,, fh e de erj., fuj .y i saa.4 ,.' lo e afin'yr !*~A Ea fed lg BPc pojo'.,, nae lyses r< fA r.- fhe ve,1) o < ca les*/a fr on i in A caftJ the r/v a <.,/4 o /;f s e to //r /s 6e a Ja,,,,,je,
' ' ' - ~ ~
h #O
~O AGREE PF IS VAll0 BY -
DATE QUEST RE REVIEW BY DATE
/ 8b 'g'idt-O DISAGREE BY DATE ** i O REVIEW OF ORIGINAL DESIGN ORGS. COMMENTS BY: DATE:
.. .~.
PAGE 2 PFR NO. M & N -d#l " REVISION N>E C. REVIEW BY ORIGINAL DESIGN ORGANIZATION COMMENTS -~
.)
O AGREE PF IS VAll0 0 O!SAGREE BY: DATE:
- 0. RECOMMENDATION BY FINDINGS REVIEW COMMITTEE DEFINITION ADEQUACY: 10 ADEQUATE O INADEQUATE VAllDITY: O VAll0 E INVALIO CLASSIFICATION: O OBSERVATION O FINDING JUSTIFICATION:
CLASSIFICATION CRITERIDN NO. RESULTING IN " FINDING" COMMENT ON "0BSERVATION" CLASSIFICATION s. n , , E. GA PROJECT MANAGER l S ACCEPT O REJECT a W a-6 BY: A d6WN DATE: PL
*
- PFR NO. 2408-PFR-0013
~
POTENTIAL FINDING REPORT REVISION SONGS 2&3 SEISMIC DESIGN VERIFICATION A. PREPARATION BY GA INITIATOR AFFECTED ITEMS: Containment Structure Seismic Analysis REQUIREMENT REFERENCE DOCUMENTS: Not Applicable BASIC REQUIREMENT: M: a.pplic2bleYA The mass value at a node for vertical translational degree of freedom should be theoretically the same as the mass value for horizontal translational degree of freedom. , DESCRIPTION OF POTENTIAL FINDING: Thia PFR documents a deviation noted in the computer input data to SMIS code. Detailed descriptions are given in the attached sheet. l b, a
\
PREPARED BY: T. H. Lee YSN DATE: 1-15-82 REJECTION OF GA TASK LEADER COMMENTS BY: DATE: REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: DATE: B. REVIEW BY GA TASK LEADER CO'4MENTS l s 1 l BY /'O DATE II f f.
/b . ,
{ } ' U AGREE PF IS VAll0 y i I O REQUEST RE REVIEW BY l' DATE O OlSAGREE BY DATE O REVIEW OF ORIGINAL DESIGN ORGS. COMMENTS BY: DATE:
'
- REVISION d'bfr -952- 001_ $
, C. REVIEW DY ORIGINAL DE51GS ORG ANIZATION COMM ENTS M3/42WCL ! Sea attached sheet. g p . D AGREE PF 15 VAUD -
% DISAGREE Y:
DATE: -@
!8b D. .R E C O ?.".* E '. 0 A TI C N E Y F .'!D' N 5 5 h E VIEW C 0 7.".'.iTT E E DEFINITION ADEQUACY: jE ADEQUATE D INADEQUATE VALIDITY: O VALID E INVALID 10 CFML D-NOT- AP?L! CAB LE D APPt4GAStL._ 2/SAz k 10fM 53.55(th D-NOT-APPi.iCABLt a APFLicASLt ^ f[2l/&f--
CLASSIFICATION: O OBSERVATION D FINDING (T
.,l 'TIFIC ATIO N: ,
l I CLASSIFICATION CRITERIC k NO. RESULTING IN " FINDING" COMMENT ON "0BSERVATiON" CLASSIFICATION Y$ BY: / DATE: [ E. TFT PROJECT MANAGER O ACCEPT D REJECT SY: / A f 4 V K 4 &' ggig. L 4
l y , FFR NO. 2h08-PFR-00 M
- REVISION
~
DESCRIPIION OF PCTIENTIAL FEID:2iG: This deviation concerns the use of different values of mass at the, same node for different directions of motion. This type of deviation was noted in the following documents. (a) " Final In-structure Response Spectra Ana3,ysis for the Containment and Interior Structure, SONGS 2 & ,3," Aug 1973. Chapter 3; Sec.E Calculation Sheet 10-E of 16-E Sheets.
- t. , ;; . ,
- i. .i 1 f.
'i(b) "SMIS Finite Element Model For Time-History Analysis of Containment With NSSS Equipment',' Sheet 1, Figure A l+.
Description of deviation , q; In document (a), the mass values are shown as follows for node 10. Node No. Hori (H) or Vert (V) Mass (K)
*10 '
y10 ' In document (b), the mass values are shown as follows for node 16.
,. ADDITIONAL LUMPED ETERTIA Node No. X-Dir (H) Y-Dir (V) 188 252 16 Note that the reviewer attempted to justify these direction-dependent mass values from the master-slave nodal relationship but still could not verify these values. Nor could the reviewer duplicate the same ratios of mass values by considering the fact that vertical input level is 2/3 & i of the horizontal input level. Theoretically, inertia values do not V depend upon directions of tranlational degree of freedom.
D
~
gh Attachsint to 2408-PFA-0013 wp/y p It is recognized that generally in a lumped parameter model the same mass value is assigned to all three translational degrees of freedom at a given nodal point. Theoretically, however, there is no basis to require equal mass values clong the three translational degrees of freedom. For mathe=atical modelling of complex structural systems it is warranted, consistent with fundamental theory, to incorporate different masses along each direction as necessary. In lumped parameter models the distribution of mass must be consistent with the directional characteristics of the structural system as governed by the direc-tion of inertial load paths available within the system and by the boundary conditions of subsystems attached to the main system. With respect to documents (a) and (b), as cited in PFR-0013, the pertinent clarifications are as follows: (numerical values, in units of weights, are weights of corresponding masses) o (a) The total mass along horizontal direction for node 10 - 11002 k, which includes the steam generator mass = 1893 k (refer to attached sheet 6-E). The steam generator mass along vertical direction was not assigned to node 10, but distributed to nodes 2 and 3 instead. This distribution of mass was used in recognition of the snubber-type supports of the steam generator. Therefore the mass along the vertical direction for node 10 Y = 2/3(11002-1893) = 6073 k as stated in the attached sheet 10-E. TQ0}/3factorwasintroducedtoscaledowntheinertialforcingfunction on the right hand side of the equation of motion, which in the calculation sheets is defined as the weighing array used to represent the vertical
- {s i
seismic input as 2/3 of the horizontal input: Enl III + Ec3 til + (x) fx1 - {n) ful l 2/3 factor applied to
. mass terms for vertical degrees of freedom.
The above mass values along the horizontal and the vertical directions are j also evident in the attached calculation sheet 6-E, where for node 10: Horiz. = 11,002 k vert. - 9,109 k, and (2/3) 9109 - 6073 k (b) The total mass along vertical direction for node 16 = 252 k, which includes the mass of snubbers = 32 k each. Along the horizontal direction the mass of the snubbers was subtracted from node 16 and transferred to nodes 26 and 27, as stated in attached sheet 6-F. The total mass along the horizontal direction at the level of nodes 16, 26 and 27 equals 252 k, as indicated in the attached sheet 15-F: Node No. H V 16 188 252
- 26 32 0 '-4 , 27 32 0 252 k 252 k
l
* *%' CALCULATION SHEET N#~ -*k (I":' ' * * * * " P. *?." .T " ^. !.' "
MOR w ALM. C A(IFOR N 6 4
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1 fjC[/ , CALCULATION SHEET a yor_ ev/c- ovia gs/n # SIGNATURE 16b bME%I DA CHECKED +' Sd DATE 4 73
% I5% JOB NO. OO!"YD
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SIGNATURE 9 1 E N ADA DATE -Il~ E CHECKEC E PROJECT MY'~ ,e T D JOB NO. DO 'l NC (
'BJECT (M A &d- m WN%h - W W"L MM': I SHEET N -M OF AE-'~- SHEETS '
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PFR NO.21408-PFR-0013 ; l i p INITIATOR'S RE-EVALUATION COMMENTS (AFTER THE PFR HAS BEEN REVIEWED BY BPC) The initiator has studied the review coments of BPC and full,y understands the technical basis for BPC to use mass values dependent upon directions of translational degree of freedom. The reason that the initiator could not duplicate the same values as given by BPC is that the initiator attempted to justify them through the use of one scale factor while the BPC terived at those values through the use of two factors, namely, (1) mass value for vertical degree of freedom is initially chosen to be different from that for horizontal degreeoffreedom,(ii) applying 2/3scalefactorforvertical-input analysis . Some additional questions generated during this re-evaluation have also been clarified by BPC through long distance phone call. Details of this verbal clarification.are given in the attached " Telephone Comunication Record". Since the deviation is not an error, the initiator suggests that the PF be invalidated. O) a,
%/
BY: T. H. Lee DATE: 2-3-82
& C w s- 7L:r PF d 6 wd/ .
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rg . . T. H. Les GA DATE; 2-3-82 LOCATIC44: Finding Review Committee l TO: LOCf.T!m. GA - pf g7g. l 2%&- p,@ 00/3 C TELEPHONE COMMUNICATION R E C O R D #>/2-M ( PIESE IW:D IrrH2 LEGIBLY DJ EIACK OR PED H K) CALL IfiITIATED BY: T. H. Lee AT GAC S OTHER: CALL RECEIVED BY: A W+ Tg,,, AT GAC C OTHER: BPC. Whittie OTHER PARTICIPANTS: None . . DATE: 2/3/82 TIME: 1:15 pm
SUBJECT:
- PFR No. 2408-PFR-0013
SUMMARY
- This phone call was made to obtaine further clarifications on BPC's review comments in regard to the subject PFR. The clarifications are itemized as follows:
l ' l (1) The initiator wanted to obtain confirmation from BPC that the use of different mass values for different directions of translational degree of freedom is due ( to (i) coordinate constraint and (ii) redistribution of mass amoung related
'a nodes. BPC has confirmed this point.
(2) The initiator wanted BPC to verify that in the equation given in their review sheet, the mass matrix [M ) on the right is different .from the [ M J on the left, therefore a different symbol should be used. BPC agreed that the symbol [,M] on.the right should be changed to a different one. (3) The initiator wanted to confirm with BPC on one point that it is not necessary l ' to scale down the mass values for seismic analy..s under vertical input because one can sinnly scale down the innut. l
- BPC agreed that it can be done in either way. Scaling down the mass values l was done for nurnose of convenience oniv
. Date Person ACTION' ITEMS: . Required Resconsible l;
DISTRIBUTION: . File No.:
PFR NO. 2408 PFR-0014 POTENTIAL FINDING REPORT REVISION 4 SONGS 2&3 SEISMIC DESIGN VERIFICATION A. PREPARATION BY GA INITIATOR AFFECTED ITEMS: Pipe Support for Node 116 of Safety Injection Line to Reactor Coolant Loop 1A. Calculation Tag S2-Sl-043-H-020. REQUIREMENT REFERENCE DOCUMENTS: Piping Analysis Package S-78, M1204-043-2B Cold Leg Safety Injection Line 1204-043 Class 1 Stress Report for S-78, Calc. No. M-DSC-050 p.274. BASIC REQUIREMENT: Drawings and calculations label nodes properly. DESCRIPTION OF POTENTIAL FINDING: Node 116 is mislabeled as node 117 on the pipe' assembly drawing and the pipe support calculation TAG:S2-S1-Qd3-H-020. Calculation Tag S2-Sl-043-H-020 is actually for node 116. 4 l f V2 5/97 f,,. g. So/na fcooy /* R. S avatcioglu PREPARED BY: DATE 1-23-82 REJECTION OF GA TASK LEADER COMMENTS BY: DATE: REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: ' Sob e >o c b OATE: 8- / - t 2. J B. REVIEW BY GA TASK LEADER COMMENTS I 1
, REE PF IS VAllu BY DATE V '
O REQUEST RE REVIEW BY
/ DATE
/ '
O DISAGREE BY ' DATE bEVIEW OF ORIGINAL DESIGN ORGS. COMMENTS BY:
/ /
-b OATE: N2M
//
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PAGE 2 PFR NO.2408-PFR-0014 L REVISION 4 C. REVIEW BY ORIGINAL DESIGN ORGANIZATION COMMENTS ,q g, O AGREE PF IS VAll0 0 OlSAGREE BY: DATE: D. RECOMMENDATION BY FINDINGS REVIEW COMMITTEE
, OEFINITION ADEQUACY: E ADEQUATE O INADEQUATE VAllulTY: E VALID O INVAL10 CLASSIFICATION: E OBSERVATION O FINDING JUSTIFICATION:
CLASSIFICAT10ll CRITERION NO. RESULTING IN " FINDING" _ _ J l COMMENT ON "0BSERVATION" CLASSIFICATION WW U A On BY: DATE: M 2 2 M 2-f) ' / E. GA PROJECT MANAGER 8 ACCEPT O REJECT
.q g BY: / d4MM OATE:
J
u-PFR NO. 2408-PFR-0014
~
POTENTIAL FINDING REPORT REVISION SONGS 2&3 SEISMIC DESIGN VERIFICATION A, PREPARATION BY GA INITIATOR AFFECTE0 lTEMS: Safety Injection Line to Reactor Coolant Loop 1A, Piping Stress Analysis Package PSG-78 Node 117, Calculation Tag S2-Sl-043-H-020 REQUIREMENT REFERENCE DOCUMENTS:
~
Piping Stress Analysis Package S-78, M1204-043-2B BASIC REQUIREMENT: Calculation use latest design load. DESCRIPTION OF POTENTIAL FINDING: The load used in design calcula': ion for pipe support at node 117 is (+69500/-69500).* Sheet 63 of S-78 gives a load for node 117 of (+18736/-38736) l , *per DCN 05 Y l PREPARED BY: R. Salavatcioglu [ $. DATE: 1/18/82 REJECTION OF GA TASK LEADER COMMENTS BY: DATE: REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: DATE: B. REVIEW BY GA TASK LEADER COMMENTS l
~
REE PF IS VAll0 BY DATE O REQUEST RE REVIEW BY DATE O DISAGREE BY DATE O REVIEW OF ORIGINAL DESIGN ORGS. COMMENTS BY: DATE:
f'.
~l ,
PAGE 2
-och
. PFR NO. 2408-NR-00 i
' REVisl0N
" REVIEW BY ORIGINAL. DESIGN ORGANIZATION COMMEliT3 Firot,
. pipe cupport drawing.the apparent inconsis t,ency ta because of an incorrect point no
. (117) on the Secondly, the higher load (69,500 lbs.) used in the pipe support c from a previous piping stress analysis. a on came lower value of 50,635 lbs. The final support analysis indicated a w:s conservative. Ita support calculation was not changed since the design O AGREE PFIS VAUD G
(SgREE BY: # tj DATE: - I D. RECOMMENDATION BY FINDINGS REVIEWCOMMITTLE
, g DEFINIT 10!! ADEQUACY: O ADEQUATE N INADEQUATE & //4 4 //7 VA1.10lTY:
O VAUD A, D INVALID ' 10 CFR 21: O NOT APPUCABLE O APPLICABLE { CRF 50.55(t): ( ) O NOT APPLICABLE O APPLICABLE CLASSIFICATION: O OBSERVATION O FINDING JUSTIFICATION: . r CLAS$1FICAT10N CRITERION NO. RESULTING IN " FINDING"- COMMENT DN "OUSERVATION" CLASSIFICATION , t e i BY: / 3 3 () _ DATE
/
E. TFT PROJECT MANAGER O ACCEPT O REJECT wi
. , _ - . . _ - . . _ -- -w--
l l l lMPACT ASSESSMENT 2408-PFR-0014 ;( PFR NO.
)
" ' #8 *
~
AFFECTEDITEM:
- 1. IS THERE THE POTENTIAL FOR REDUCING DESIGN MARGINS TO THE EXTENT :
DESIGN ALLOWABLES ARE EXCEEDED OR DESIGN REQUIREMENTS ARE NOT MET ? No
- 2. IS THERE THE POTENTIAL THAT THE ITEM MIGHT FAIL OR ENDANGER OTHER ITEMS DURING AN SSE ?
No
- 3. COULD THE FAILURE OF THIS ITEM DURING AN SSE CREATE A SUBSTANTIAL SAFETY HAZARD ?
NA
- 4. COULD THE PROCEDURAL VIOLATION CREATE A SUBSTANTIAL SAFETY HAZARD ?
No
- 5. ARE OTHER SIMILAR DEVIATIONS LIKELY TO EXIST ?
S Yes, This is the second mislabeled node we've had. l Ij6. OTHER COMMENTS:
, g, gg ude w7 h b3$
C R. Sa . accioglu PREPARED BY: D ATE: 1-23-82 COMMENTS: l 4 f j i i /
4 INTERNAL CORRESPONDENCE GA 1076 4 i IN REPLY FROM Rs Salavatcioglu (. @ a,( REFER TO TO Review Findings Committee DATE 1/27/82 SUBJECT PFR-0014 Revision A The node number on pipe support calculation TAG:S2:SI-043-H-020 is mislabeled as node 117. It is the calculation for node 116. The calculation for node 117 is TAG:S2:SI-0430H-021. We have verified that this is correct by comparing the elevation in the piping isometric and the calculation. l l l O g
--. . - - . . - - . . ~. ..- -- _ _ ---. - - . _ - . . - . . - FBOM: E baIAUAbiO4f4 a LoCATICd: 64 DATE: 2-1-31 {' To: Yem r>c_ tocArton: BecMel DATE: l T Z. g li%
/~T, TELEPil0NE COMMUNICATION RECORD I 'V'
( PLEASE 1mND IrfrER LEGIBLY IN BIACK OR RED DE) f CALL INITIATED BY: T. $ alAA/ A]2(o e lt4_ AT GAC @ OTHER: & 4 CALL RECEIVED BY: N emot. .AT GAC C OTHER: 8ce. Ale.] OTHER PARTICIPANTS: nm - -
?.4-tt - PROGRAM NAME PROGRAM NUM'lER I DATE: D TIME: T: %0AA4 $Cf 24og -- 4o O
SUBJECT:
TF R- 0 014
SUMMARY
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/i DISTRIBUTION:
File No.:
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PFR NO.7J.193-f L1'c._0015 POTENTIAL FINDING REPORT REVISION - {
\
( SONGS 2&3 SEISMIC DESIGN VERIFICATION A. PREPARATIOff BY GA INITIATOR AF FECTED ITEf.1S: The engineered safety features system control panel (panel 2CR57) of the ILC system. REQUIREMENT REFERENCE DOCUMENTS: The Bechtel Power Corporation Specification for - Control Room and Field Mounted Pancis, specification number 5023-502-5 with Addenda I, II and III. BASIC REQUIREMENT: That all natural frequencies be greater than 10 HZ horizoatally and 1511Z vertically ( Para. 4.6.5.3 of specification and Addendum 1). Acceleration response when subjected to the DBE control room floor response spectrum shall not exceed 3 "g" in any direction (para. 4.6.5.4 of Addendum 1) . DESCRIPTION OF POTENTIAL FINDING: The specification fails to require that the internal panel wiring or the connecting wiring be simulated, accounted for or otherwise considered during seismic qualification testing of panels. Inaccurate determination of mode shape, acceleration levels and natural frequency may have occurred if the wiring was not considered. l Y) s
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S. Rodkin 1-17-82 PREPARED BY: DATE: REJECTION OF GA TASK LEADER COMMENTS BY: DATE: REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: DATE: # Y~ @ A B. REVIEW BY GA TASK LEADER COMMENTS
& "A g wifb dlt/i W Inf E I "
wiri w a-2 "D 'B YZ i [ E AGREE PF IS VAllD BY DATE
~
l l O REQUEST RE REVIEW BY DATE O DISAGREE BY - E
/
dEVIEW OF ORIGINAL DESIGN,0RjS. _ C}}gENg DATE
PAGE 2 PFR NO 2408-PFR-0015 REVISION _ l
- ... REVIEW DY ORIGINAL DESIGN ORGANIZATION COMMENT 3 { )
t ( . , See attached sheet. l O AGREE PF 15 VAUD DI DISAGREE SW \
' r W -
DATE: h __
- 1. REC 01."?!?.DATICN BY FI';3'N35 REVIEW COMMITTEE _
DEFINITION ADEQUACY: E ADEQUATE D INADEQUATE VALIDITY: 5 VALID 0 INVALID 10 Cf". 21. - O NOT APPL lCA"LC u ArrLICA5i.E -
.,3MM 50.SSL U iiQi ArrLICABLt G AFFliCAllLE LASSIFICATION: 8 OBSERVATION O FINDING UJtI5TIFICATION:
CLASSIFICATION CRITERION NO. RESULTING IN " FINDING" COMMENT ON "0BSERVATION" Ct.ASSIFICATION
$ We- & W f
BY: '
- m/
DATE: __ / 8!8!f2-
/
I. TFT PROJECT MANAGER M ACCEPT O REJECT b- . . { }
.- - . . . - . . _ . . - - - - - - . - - . - - . . - . . - - - - : --- -- - . :m------- - -.
Q? Attachment to 2408-PFR-0015 Specification 8023-502-5 requires the vendor to consider the internal panel wiring and connecting wiring. The following paragraphs of the specification and addenda substantiate this statement: 4.6.5.6, 4.9.1.5, 4.9.4.24. 4.9.4.25. The requirements for consideration of wiring were understood by the vendor as evidenced by Wyle Test Procedure No. 3570 (Los No. 5023-502-5-12). page 8, article 4.4.1. In additton, in Wyle Test Report No. 54498 (IAg No. 5023-502 501) Photograph 8 " Dummy Weight Installations" is a photograph of the actual test installation and dussy wire bundles can be seen. In conclusion Wyle Test Report No. 58379 (Los No. S023-502-5-679) documents in-situ testing performed on control panel CR-57 installed at the San onofre nuclear Generating Station, with internal wiring and connecting wiring installed. The test results show the first mode of CR-57 to be 28 hs. i 0) l .I ,
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p - Attachment to
\ .. ./ 2408-PFR-0015 N
7F Specification 5023-502-5 requires the vendor to consider the internci panel v Ql wiring and connecting viring. Da following para:;raphs of tha cpecification and addenda substantiate this state =ent: 4. 6. 3. 6, 4. 9.1. 5, 4. 9.4. 24.'T.T. 4. 25 , D The requirenents for conoideration of viring vara undcr' stood by the vendoF'as~ ky s evidenced- by Vyle Tcat Procedur{ !b. 3570' (I[o'g]T.- 5023-502-3-12), page 8, - l article .:. 4. t'. -In addit ion, in Wyle Test F.cyort ::o. ., . . 3 (Los l's.r S023-502-3..
~ ~
{~g .Tf0'iT'Photograp'h Sj"Dunsy Weight Installations
- is ~alhocogYaph oTtih'E' Aclu'al "
- g. ' O
- test ~ installation and du::ny wire bundles can be seen.
8 ~ W . %4u Q., In conclusion Wyla Test Repor.tr h*o;* 5337'r'(Dig Td"S0'23:502:54679}, docu::ents in-situ testing perforned ou cen'c'rci psel"CT.-57" ins'ta116d 'at'the San Onofra Iluelear D Cenerating Station, with internal wirin.; and connecting viring installed. The Tk " test results show the first code of CR-57 to be 28 hs. ML46 i]aus 40r Gx inr, '/.G.S s* 6dys i'., hen 1 fniiT M P.<cMWA '
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_ _ _ . . .._ . _ - _ - - . _ - - - - =c-- --- - --
)~ Attachment to 2408-PFR-0015 Add Stan Rodkin's comments to page identified as above and beginning:
Specification S023-502-5 requires the vender to consider the internal panel wiring and connecting wiring. The following paragraphs of the PFR-0015 author's review comments on Bechtel's response to PFR-0015 cosunents written 1/24/82 - Stan Rodkin, 2/8/82 4.6.5.6 Does not exist, 4.6.5.5 says in part that the purchaser will determine which panel to test and will supply a representative sample of panel mounted equipment to be included in the panel test. 4.9.15 Is under 4.9 " Design and Construction Details", 4.9.15 says that panels shall be constructed and reinforced to comply with all spec requirements with all equipment installed and wired. It says nothing about the configuration of a test item, specifically whether or not the wiring shall be installed. 4.9.4.24 Again is under Design and Construction. It says a lot of good things of support brackets for wiring etc. but does not control test item configuration. 4.9.4.25 Again is.under Design and Construction. More good things about wireways etc but it does not control test item configuration. We need to see Wyle test procedure 3570 (log #SD23-502-5-12) and should request it from Bechtel. Photograph 88 is a poor reproduction of the original. It does show a roll of wire hanging in the lower right corner. This is inadequate proof that the internal panel wiring and the external connecting wiring were adequately considered during the seismic qualification testing. Wyle report 58379 In-Situ testing, looks only at first mode natural frequencies in panel 2CR57, fn = 28 HZ. No acceleration data is given. l m y . .%._, .,w,.e .--..ew&- - - -- ~ ~ - " " '
- e Attachm:nt to 2408-PFR-0015 Addendum 1
( Specification S023-502-5 requires the vendor to consider the internal panel wiring and connecting wiring. The follo'aing paragraphs of the specification and addenda substantiate this statement: 4.6.5.6, 4.9.1.5, 4.9.4.24, 4.9.4.25. The requirements for consideration of wiring were understood by the vendor as evidenced by Wyle Test Procedure No. 3570 (Leg No. S023-502-5-12), page 8, article 4.4.1. In addition, in Wyle Test Report No. 54498 (Log No. S023-502 501) Photograph 8 "Duany Weight Installations" is a photograph of the actual test installation and dummy wire bundles can be seen. Bechtel reviewed and approved the Wyle Test Procedure and Wyle Report No. 54498-2 (Log Nos. S023-502-5-12 and -501 respectively). In addition, Bechtel witnessed the actual test and inspected the test specimen including the installed dummy wiring. The dummy wiring was concluded to be representative of typical wiring installation as would be accomplished upon installation of the control panels at the jobsite. In addition, Wyle Test tteport No. 58379 (Log No. S023-502-5-629) documents in-situ testing performed on control panel CR-57 installed at the San Onofre Nuclear Generating Station, with internal wiring and connecting wiring installed. The test results show the first mode of CR-57 to be 28 hz.
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$ Specification SO23-502-S requires the vecdor to consider tha hter: 21 panel -
wirics c:d cc .neti: g vicin . 33 fc11ovi:; p.arsgraphs of tha ap<citice; ion g 3 and adde:da substancia:e :his state::en:: 4.6.5.6. i.9.1.5, 4.9.4.21, 4.9.4.25. P d Rg The requirc:ects i : ecasic::::to: of vi-ita vers u:12::ce:d 5-i :he ve:dar as kg evidenced by Vyle Test Procedure.5o. 3570 (Lc; :52 $013-502-5-12), ps p S, i o g garticle 4.4.1. In additic=, in Wyla Test Ecport No. 34493 ( og l'o. 5023-502 501) Thotograph 8 "Du==y Weight stallstiona* is a photes:aph og :ba ac:ual y s , test inscellstien and d::=y vire h :dles can be seen. 4h b Bechtel redeced and approved the Wyle Ta=: 7tc<:edura c d Wyle Repo;t 1*c. 54493-2 Q -A(Log Nos. 5023-502-5-12 med -301 raspectively). .In addities, 3e:htel vi: sssed W d. g the actual test r.:d insocc:cd the tes:'speci:en it.:1.,: din :he i=s::11ed d.::=t N $ 5viring. Tac de==7 . iring was ecceluded to ba rapresen:aciva of typie:1 virih; O g$atthe.jobsita.Insta11stics as vould be acce=p11thed upo: in:cs11stics of :n een rel psa Q LJud-In additics, Wyle Test Reper: No. 53379 (Los No. 5023 :,' 2-5-629) docc:sents in- -
- f-Nsitutes
g Lug perfo;;ed on ce= trol pinal CE-5'T ina:alled at tha Sc: 0:ofre Xuelcar
% k test resul:s show the first code of CF.-57 to be 23 hs. Genera:1cs S:stice, Tha vi:h intern .
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s ( ) Attachment to 2408-PFR-0015 Addendum 1 l (Additional Bechtel response based on request of 2/4/82 for more information, this response arrived on 2/5/82) Add Rodkin comments (2/8/82) to page beginning: Specification S023-502-5 requires the vendor to consider the internal panel wiring and connecting wiring. The etc.... The specification does not clearly require the wiring to be considered during seismic qualification as good engineering practics requires, however, evidence is presented in Wyle Test Procedure 3L?0 (Bechtel Log SO23-502-5-12) and in the second paragraph of Addendum I to Bechtel's response that the wiring was considered during the seismic qualification test program.
)
()
's, Attachment to PFR 2408-0015 This PFR is declared invalid.
The basis for this declaration is the information contained in Addendum 1 to Bechtel's response to this PFR; specifically, that information contained in paragraphs 2 and 3 which provide the author of this PFR with satisfactory evidence that the internal and connecting wiring were adequately considered during the test program. Stan Rodkin / % !b' * ' b $ 9 9
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IMPACT ASSESSMENT -pfe.- PFR NO. 2 flag 08 # I Ii O > C 4 Y)
~ AFFECTEDITEM: f/#C /O G 8/ M b A Q[l/MdC
- 1. ISTHERETHE POTENTIAL FOR REDUCING DESIGN MARGINSTO THE EXTENT DESIGN ALLOWABLES ARE EXCEEDED 08 DESIGN REQUIREMENTS ARE NOT MET ? . . .
1
- 2. ISTHERE THE POTENTIAL THATTHE ITEM MIGHT Fall OR ENDANGER OTHER M//9 ITEMS DURING AN SSE?
- 3. COULD THE FAILURE OF THIS ITEM DURING AN SSE CREATE A SUBSTANTIAL M '
SAFETY H,AZARD ?
- 4. COULD THE PROCEDURAL VIOLATION CREATE A SUBSTANTIAL SAFETY HAZARD ? //0
#O
- 5. ARE OTHER SIMILAR DEVIATIONS LIKELY TO EXIST ?
S. OTHER COMMENTS: M6W l l l i PREPARED BY- DATE: *d
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COMMENTS: _ I hi/A WE .
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l 1 PFR NO._.g4o347o_go y _ l POTENTIAL FINDING REPORT REVISION - l SONGS 2&3 SEISMIC DESIGN VERIFICATION 1 % l \ ' A. PREPARATION BY GA INITIATOR AFFECTED ITEMS: The engineered safety features system control panel (Panel 2CR57) of the 16C System. REQUIREMENT REFE'RENCE DOCUMENTS: The Bechtel Power Corporation Specification for control room and field mounted panels specification number S023-502-5 with Addenda I, II, and III. BASIC REQUIREMENT: That the acceleration level at device mounting points on the panel not exceed 3 "G" when the panel is exposed to the control room floor (30' elevation) DBE responue spectra (Section 4.6.5.4 of Addendum I to the specification). DESCRIPTION OF POTENTIAL FINDING: The specification fails to require the vendor to consider the anchorage details designed by Bechtel (the embedments ) in his analysis or his test of panels. Consideration of such details might result in natural frequencies and mode shapes which would cause the maximum specified "G" level at device mounting locations to be exceeded during seismic excitation. I b/ Stan Rodkin
$% /kN 1-17-82 PREPARED BY: DATE:
REJECTION OF GA TASK LEADER COMMENTS BY: DATE: REJECTION OF ORIGINAL DESIGN ORG. COMMENTS BY: DATE: B. REVIEW BY GA TASK LEADER COMMENTS 6 s g ' l AGREE PF IS VAll0BY "f/ L f0V DATE
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PAGE 2 Pf R NO. 2403-PFR-0016 REVISION AEVIEW BY ORIGINAL. DE5tGN ORG Ahl2AT10N COMMENT 3 (7oes- attached sheet. - l l ' 1 l 0 AGREE PF 13 VAUD DI DISAGREE 3Y >* W DATE: IbIbO -
- 3. P.EC0f.".'E'.D ATICN E,Y F ND!NC5 REY!EW COP.t!.uTTEE DEFINITION ADEQUACY: E ADEOUATE D INADEQUATE -
VALIDITY: O VALID E INVALID 1&WMi~ O "Pt icABf F-- 10 CR540istd: D-ft07%FFLiCABLE U NOT APPLICABLE O D A"LE
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;;JtlSTIFICATION: I CLASSIFICATION CalTERION NO. RESULTING IN " FINDING
- I COMMENT ON 0 BSERVATION" CLASSiflCATION BY:
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E. TPT PROJECT MANAGER S ACCEM i D REJECT
- 1 1 1 BY:/ NC% DATE:
Attactment to 2408-PFR-0016 i , specification $023-502-5 requires the vendor to consider the anchorage details ' designed by Bechtel. The following paragraphs of the specification and addenda substantiate this statement: 4.6.5.', 4.6.5.3, 4.9.4.22, 4.9.6.1, 4,9.6.2, 4.9.6.3. Conference. noten numbers 1466 and 1475 provide additional clarifica-tion of the anchorage requirements. _ Vendor compliance with the required anchorage is demonstrated in Wyle Test Procedure No. 3570 (143 No. S023-502-5-12), page 7, articia 4.1, and in Wyle Test Report No. 54498 (Los No. 3023-502-5-501), page 3, article 3.2. In conclusion, Wyle Test Report No. 5637) (143 No. S023-502-5-679) documents in-situ testing perfomed on control panel CR-57 installed at the San Onofre Nuclear Generating station. The test results show the first mode of CR-57 to be 28 hs. O
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O ADDENDUM TO POTENTIAL FINDINGS REPORT NO. 2408-PFR-0016 Prepared by: D.C.A. Koopman Date: 2/4/82 Concurrence by Initiator: S. Rodkin [8-The response to the PFR. in conjunction with the additional information supplied by Bechtel is satisfactory. This PFR is declared invalid on the basis of the following considerations:
- 1. In Specification S023-502-5. Addendum 1. par. 4.6.5.1 of Seismic Design states:
"The structural system for the panels. including the attachment interf ace of all panel mounted equipment and the base anchorage of the total system to the floor or wall. shall be designed and qualified to meet the requirements of Seismic Class I Equipment as specified herein l and in Appendix 4F".
(- -
- 2. Under " Design and Construction Details ~ par. 4.9.6.2 (Addendum 1) states:
"Means shall be provided in the structural bases so that panels can be welded to tne foundations of the panel base".
- 3. Par. 4.3.6.3 states:
~
....the Vendor shall submit for review and approval. drawings showing details of the basic anchoring method".
- 4. Conference Note 1475 (Ref. 0016-2) states:
~1. The main control room floor has been poured and inbeds installed to meet control panel layout previously provided to~ Jelco in I transmittals of CSE and Electrical floor plan drawings.
~2. The pr.nels will be welded to these inbeds."
l
- 5. Section A of Appendix 4F of S023-502-5 states:
**A complete qualification procedure and monitoring technique shall be presented by the Vendor to the Purchaser for review prior to the actual start of qualification work." Wyle Test Procedure No. 3570 (S023-502 ,5-12-2). is the procedure for testing the subject panels
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- 6. Para. 4.1 of this Test Procedure states in part:
" Mount the specimen. on the test machine uttitzing a 4 inch square tube interface fixture. Weld the control panel to the fixture in its normal mounting manner. Weld the fixture to the surtace of the test machine."
This is to simulate the in-service anchoring method. s
References:
0016-1 Test Procedure for Seismic Qualification Testing of Two Control Panels for San Onofre Nuclear Generating Station for JELCO Inc. Rev. B 6/8/76. Wyle Test Procedure No. 3570. Bechtel Log No. S023-502-5-12-2; SCE No. 0376. (TFT No. 1348-9196). 0016-2 ~ Conference Notes No. 1475." Bechtel. Wyle. JELCO. Feb. 6. 1976. (TPT No. 1348-9127). y
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- PFR NO. 21208-PCR-0017 I- .
POTENTIAL FINDING REPORT REVISION SONGS 2&3 SEISMIC DESIGN VERIFICATION (' pa. PREPARATION BY GA INITIATOR
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!. AFFECTED ITEMS: The engineered safety features system control panel (panel 2CR57) of the I&C System. ~
REQUIREMENT REFERENCE DOCUMENTS: The Bechtel Power Corporation spe'cification for control room and field mounted panels, specification number 8023-502-5 with Addenda I, II, and III. BASIC 5EQUIREMENT: That the acca.leration level at device mounting ^ points on the panel not exceed 3 "G" in any direction when the panel is exposed to the control room floor ,' (30' elevation) DBE response spectra (section 4.6.5.4 of Addendum 1'to the specification DESCRIPTION OF POTENTIAL FINDING: The specification fails to require the vendor to consider the dynamic interaction of cabinets arranged in the specific nanner of the
" San Onofre Control Room caoinets. Such dynamic interaction may produce mode shapes resulting in excessive g levels during seismic excitation, k
b' PRCPARED BY: DATE: REJECTION OF GA TASK LEADER COMMENTS BY: . - DATE: REJECTION OF OHIGINAL DESIGN ORG. COMMENTS BY: b b, , DATE: 3'/O N
- 8. REVIEW SY G A TASK LEADER COMMENTS
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- PAGE 2 PFR NO. 2408-PFR-0017
. s ., REVISION C. REVIEW DY ORIGINAL DESIGN ORGANIZATION COMMENTS f) j See attached sheet. ,
F 1 i 1 1 O AGREE PF 15 VAUD G DISAGREE 4 3 At#
]V DATE: 3 D. REC 0r".*Ef.0 ATICN SY FI'JDfNGS REVIEW COMMITTEE DEFINITION ADEQUACY: E ADEQUATE D IRADE'QUATE VALIDITY: R VALID D INVALID 10 Cin 2t C NOT ATEUCABLE C ATFULAttt -
?O Car 50 55M: C iv0i AFFUCABLE C ?SPt!CA9tE PLASSIFICATION: E OBSERVATION O FINDING
\-AISTIFICATION: l I CLASSIFICATION CRITERION NO. RESULTING IN " FINDING" COMMENT ON "0BSERVATION" CLASSIFICATION L Y . M r-.r e v4 , Y eJ& a ~ 9) W .
BY: - DATE: 6 /2.ML m E. TPT PROJECT MANAGER < O ACCErr ' i ! O REJECT S BY: h_ s D ATE: TE _ =_ _-
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Attachment to 2408-PFR-0017 O)T ( Specification S023-502-5 requires the vendor to consider the dynamic inter-action of cabinets arranged in the specific manner of the San Onofre control room cabinets. The following paragraphs of the specification and addenda substantiate this statement: 4.9.1.1 (drawing number 53000 included with specification) and Appendix 4F, section C.3.2. Conference notes numbers 1466 and 1475 provide additional clarification. Vendor understanding of this requirement is documented in the "Jelr Qualifi-cation Approach" attached to Wyle Test Procedure No. 3570 (Log No. 3023-502 12), and in Wyle Report No. 54498-2 (Log No. SO23-502-5-501), page 5, article 3.0; pages 6 through 9K; and page 15, Figure 1. l In conclusion, Wyle Test Report No. 58379 (Log No. S023-502-5-679) documents in-situ testing performed on control panel CR-57 installed at the San Onofre Nuclear Generating Station, bolted to the other control panels to form the j horseshoe configuration. The test results show the first mode of CR-57 to be 28 hz. .
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IMPACT ASSESSU dNT 2408-PFR-F0017
, PFR NO.
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- AFFECTEDITEM:
- 1. IS THERE THE POTENTIAL FOR REDUCING DESIGN MARGINS TO THE EXTENT DESIGN ALLOWABLES ARE EXCEEDED OR DESIGN REQUIREMENTS ARE NOT MET?
No
- 2. IS THERE THE POTENTIAL THAT THE ITEM MIGHT Fall OR ENDANGER OTHER ITEMS DURING AN SSE ?
No
- 3. COULD THE FAILURE OF THIS ITEM DURING AN SSE CREATE A SUBSTANTIAL SAFETY HAZARD ?
Yes
- 4. COULD THE PROCEDURAL VIOLATION CREATE A SUBSTANTIAL SAFETY HAZARD ?
No
- 5. ARE OTHER SIMILAR DEVIATIONS LIKELY TO EXIST ?
No I ) 6. OTHER COMMENTS: Itisfortuitousthatthecabinetdoesnotappeartohaveaproblem{ l bared upon subsequent analysis performed by BPC during their response to this PFR. Thus, thsre is no safety problem for the Engineered Safety Systems Control Cabinet CR-57. However, it is TPT's opinion that the PFR written against the design specification is valid because th2re are no instructions which lead the vendor to more specific requirements. It is TPT's opinion that the seismic qualification program performed by GELCO on this cabinet is of poor quality and may not meet industry standards. PREPARED BY:
- IM DATE: N~b ~
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INTERNAL CORRESPONDENCE i GA-1076 1 IN REPLY PRON: R. Vollman REFER TO: TO Potential Findings Committee DATE: March 24. 1982 4
SUBJECT:
PFR-0017 Impact Assessment on Seismic Qualification of Control Cabinet CR-57
SUMMARY
A time history analy sis of a 2 DOF model of the cabinet shows that l amplified subsystem response is less than the required 3g's. Thus, there is no , safety problem for the Engineered Safety Systems Control Cabinet CR-57. j However it is TFT's opinion that the PFR as written against the design spec is valid because there are no instructions in the specification which lead the
- vendor to more specific requirements. It is TPI's opinion that the seismic l l qualification progran performed by GELCO on this cabinet is of poor quality and 4
._ may not meet industry standards. The seismic qualification report was 4 ') incomplete and s'ifficult to follow and interpret.
L DISCUSSION l The description of the potential finding is repeated in what follows for ref erence purposes.
"The specification f ails to require the vendor to consider the dynamic j interaction of cabinets arranged in the specific manner of the San l Onofre Control Roon cabinets. Such dynamic interaction may produce mode shapes resulting in excessive g levels during seismic excitation."
Excessive g levels are greater than 3g's. The vendor who constructs these control cabinets is GELCO. formerly knova
- as Circle A-W Products. They certified that the control cabinet met all the l seismic requirements specified by Bechtel in the design specification based upon seismic testing performed at Wyle Labs under contract to GELCO.
The assertion of the PFR was based upon TPT's review of the design specification. BPC's response to this assertion is that it is their practice to write general design specifications for equipment and follow up later with s pecific instructions to the vendor relevant to the particular piece of equipment. In this case. BPC had two meetings with GELCO on January 6 and 28
) 1976 to discuss these and other details. These meetings are documented in 1
INTERNAL CORRESPONDENCE CA-1076 conference notes 1466 and 1475 which were supplied to IPT in BPC's response to this PFR. BPC claims that this practice constitutes a complete specification since it was stipulated in these conf erence notes. among other things. that the whole horseshoe arrangement must be seismically qualified (ieta 4.(6) of CN No. 1475). TPT disagrees with this assertion and feels that the specification does not lead to the conference notes. Thus, the thread of continuity is lacking. If the design specification stated that BPC must review and approve seismic qualification test plans and procedures. then the thread of continuity would exist. Thus, it is IPT's contention that the PFR is valid. The configurations tested were portions of the total assembly. specifically shipping unit 3 of the double horseshoe arrangement shown in Figure 1. Shipping unit 3 with dummy weights attached to simulate internel equipment and
. guages was attached to a dynamic shaker table in the same manner as the actual installation in the Reactor Auxiliary Building. The first structural mode (front to back vibration) natural frequency was found to be 10 Hz. Two
[ subsystems (Panels) modes were identified at 7.8 and 22.5 Hz. The maximum acceleration in the cabinet was found to be 2.2g's. It was argued that the 10 Hz natural frequency was high enough to be outside the amplified response regions of the floor response spectra where the control cabinet was located. In fact. it was stated that when the cabinet pieces were assembled into the horseshoe arrangement the frequency would most assuredly increase lending further confidence that there would be no masses being vibrated above 3g's. This, is the extent of GELCO's work to satisfy Item 4.(6) of CN 1475 in which BPC instructed them to qualify the total horseshoe panel configuration. The 22.5 Hz panel mode was not considered to be a problea because the frequency was to f ar into the near rigid zone of the floor response spectra. There does not appear to be any considertions of coupled vibration ef fects at the unknown higher installed frequencies. The seismic qualification of the whole double horseshoe cabinet was based on the test and evaluation described above. There does not appear to be an approval by BPC's technical staf f of this seismic qualification pro gr am. Acceptance appears to have been made at the project engineering level without staff reviews. - Later, af ter the cabinets were installed in the Auxiliary Building. BPC asked CELCO if additional equipment could be added to the cabinets without affecting the seismic qualification. The concern was that additional mass
; vould lower the 10 Hz natural frequency into the amplified response region.
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[ j . ! ? - l O I j INTERNAL CORRESPONDENCE GA-1076 i i t i GELCO maintained that an in-situ test would need to be performed to find out. The in-situ test showed that cabinet 3 had a 33 Hz first fundamental frequency in the forward and backward mode and the cabinet 1 (Figure 1) had a corresponding frequency of 28 Hz. This raised the question by the reviewer as to whether the 22.5 Hz panel could be aptified beyond what the response spectra indicated by coubling with thei 28 HZ structural mode assuming the same i panel existed in shipping unit No. 1. Initial estimates indicated that the 3g limit could be exceeded if the mass ratio of the submass to the structural mass i 1 was low enough (about .01). Estimated values ranged from ~ .055 to ~ .02. I It was not clear from the poorly executed seismic test progra and ! 4 evaluation if this was a problem. BPC's f eeling was that it is not a problem. l However, quantifiable evidence was not available. J In BPC's response to this PyR an analysis was performed to quantify the anount of added amplification the panels experienced during a seismic event due to coupling. A two-degree-of-freedom model was made with frequencies tuned to l 28 Hz and 22.5 Hz as shown in Figure 2. The acceleration time history used to ! i h generate the response spectra at the floor location nearest the cabinets was l input. The mass ratio was varied in 3 steps of .05. 005. and .0005 to bound ! all possibilities. The highest splified acceleration experienced by the small l mass was 1.35g's at the smallest mass ratio. The lowest was 1.13g's. Assuming l the cabinet was rigid and entering the response spectra at 22.5 Hz would have given a response of about 1.2g's. Thus some coupling is occuring. but it is small because the energy level of the components of the earthquake in the i neighborhood of 22.5 Hz at the floor of interest are low and do not excite the ! cabineto to a significant level. ' To illustrate that low frequency systems are amplified, the 22.5 and 28 Hz frequencies were divided by 10 to give 2.25 and 2.8 Hz. The highest amplified , ' response was 4.43g's from the time history analysis and 7.01g's using the floor ' response spectra. This shows the conservativeness generally found in the response spectra technique when compared with the more accurate time history results. CONCLUSIDE The PFR as written against the design specification is valid in TPT's , opinion. It is to be noted that during the review of this item it was judged by TPT that the seismic qualification program performed by GELCO is of poor quality and is probably not acceptable based on standards set by the industry.
] However, it is found by analysis that the cabinet subsystem response in quotion is below 3g's and meets the design specification requirements. Thus, there is no safety problem.
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,' . .Bechtel Power Corporation Engineers - Constructors
(' 12400 East Impenal Highway Norwalk. Cahfornia 90650 MAL ADORESS P o Box 60Mo . TE AWNAL ANN (X. LOS ANGELES. CALWOANLA 90000 TELfPHONE (213)e644011 February 5, 1982 Log BX-7017 - l'. 1 E C E I V .'t Mr. George Wessman G* L. WESSMiM Director of Torrey Pines Technology Post Office Box 81608 s 10 S U San Diego, California 92138 . -- F111
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Subject:
Southern California Edison Company " 0 PY San Onofre Nuclear Generating Station, Units 2 &.3 ~~~~~~~~~~ .... Bechtel Job 10079 TPT Independent Review of SONGS 2 & 3 Seismic Design File: S025-722-G -
Enclosure:
(1) Addendum 1 to Potential Finding Reports 2408-PFR-0015 and 2408-PFR-0017
Dear lir. Wessman:
The enclosures are Bechtel's response to your Potential Finding Reports. If you have any questions, please refer them through J. Hempe. l Very truly yours, l BECHTEL POWER CORPORATION 1 aM7dcu y H. F. McCluskey l Project Management ! Ios Angeles Power Division CEM:jv cc: Mr. J. J. Adrian, SCE b
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c 2/f// 9'82 Qq gg- 70/ 7 ) Specification S023-502-5 requires the vendor to consider the dynamic inter-action of cabinets arranged in the specific manner of the San Onofre control room cabinets. The following paragraphs of the specification and addenda substantiate this statement: 4.9.1.1 (drawing number 53000 included with specification) and Appendix 4F, section C.3.2. Conference notes numbers 1466 ( and 1475 provide additional clarification. 1 Vendor understanding of this requirement is documented in the " Jelco Qualifi- ! cation Approach" attached to Wyle Test Procedure No. 3570 (Iog No. S023-502 12), and in Wyle Report No. 54498-2 (I.og No. S023-502-5-501), page 5, article l j 3.0; pages 6 through 9K; and page 15, Figure 1. Bechtel reviewed and approved the Wyle Test Procedure including Jelco's Qual-ification Approach and the Wyle Report. A Bechtel comment on an earlier sub-mittal of the Test Report No. 54498-1 (Log No. S023-502-5-167 which is in-cluded in and superceeded by Log No. S023-502-5-501) addressed the particular concerns: "The seismic qualification of the complete set of cabinets attached together must be presented before approval of this document can be given." The final submittal of the Wyle Report No. 54498-2 addresses the dynamic in- i teraction of the control panels arranged in the specific arrangement of the San Onofre Control Room. This report was reviewed by Bechtel and the state- l ment that adjacent sections will add stiffness and tend to reduce the response of the cabinet was consistent with Bechtel's experience. Consequently the report was accepted. Wyle Test Report No. 58379 (Log No. S023-502-5-629) documents in-situ testing performed on control panel CR-57 installed at the San Onofre Nuclear Generating Station, bolted to the other control panels to form the horseshoe configuration. This in-situ testing was performed to provide assurance that the final as-built panels would remain acceptable following necessary field modifications and with the specific objective to determine panel first mode frequencies. This test program confirmed the previous Bechtel and Wyle experience that the earlier seismic testing of a single panel section was conservative. The test results show the first mode of CR-57 to be 28 hz.
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.e Supplementary Analysis in Response to PFR-0017 i
- 1. The floor response spectra (FRS) exhibit amplification (high energy content) i within the following frequency ranges I
a) 0.5 to 5 cps, horizontal FRS with ZPA = 1.0g b) 0.5 to 7.5 cps, vertical FRS with ZPA = 0.75g This indicates that the input motion to the control cabinets does not con-tain driving frequencies higher than about 10 cps (see attached sketches no. S023-SK-S-695 and 696). The discrete frequency content (.5 to 7.5 cps) of the floor acceleration response is derived from the " filtering effect" of the building response dominated by soil /struv ure interaction, and re-sults in motion with no driving energy at the high frequency range, i.e., f ,> 10 cps.
- 2. In-situ testing, Wyle Test Report No. 58379 (log No. S023-502-5-629), has demonstrated that the first mode frequency of the shipping section 1 is 28 Hz and that the first mode frequency of the shipping section 3 is 33 Ez.
This means that both shipping mections can be considered as rigid under seismic event, particularly for the seismic input defined above. Therefore, from the tested frequency characteristics and given input it can be con-cluded that the amplification of the floor acceleration input through the cabinet structural system interaction with the instrument panel subsystems i will be insignificant even when the subsystem / system high-valued frequen-l cies are closely spaced and the mass ratios are low. Considering the panel ! subsystem frequency of 22.5 Hz, the responses at instrument mounting loca-i (u } tions are predicated to be about lg horizont.1 and 0.75g vertical, and cer-tainly less than the stipulated 3g's.
- 3. A study was undertaken to demonstrate the foregoing assertions on insigni-ficant interaction amplifications for the cabinets in question. The modal time-history method of analysis was used because the alter' native response -
spectrum analysis is not adequate to recognize the phasing and algebraic sign of the modal responses which are relevant for this type of study. The model selected for the time-history analyses was a 2 DOF system with individual-mass frequencies of 22.5 and 28 cps representing the panel and the supporting structure, respectively. For the mass ratio a parametric evaluation was done utilizing values of 0.05, 0.005 and 0.0005. Table I gives the mass values and ratios derived from the components as described below: ( l a) Primary mass - Shipping sections 1, 2, 3, 4, 5 and half of shipping section 6 - 21509 Secondary mass = Panel and instruments of shipping section 3 - 1186 Ratio = 0.0551 l l b) Primary mass = Shipping sections 1, 2 and half of shipping section 3 ( = 10100 1 j Secondary mass = Panel of shipping section 3 = 551 Ratio = 0.0545 B8H72-Q
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! c) Primary mass - Same as b above = 10100 Secondary mass = Panel of shipping section 3 scaled by total front panel area = 551 (36/84) = 236 Ratio = 0.023 Therefore, the mass ratios of 0.05, 0.005 and 0.0005 as selected conserva-tively encompass the actual mass ratios.
The time-history input used was the Auxiliary Building Control Area at ele-vation 30 acceleration records in X and Y directions. Modal damping value was set at 2%. The results of the analysis are shown in Table II. As expected the maximum acceleration of secondary mass is about 1.3g < 3.0 for a mass ratio of 0.0005. This mass ratio is estimated to be considerably lower than the actual mass ratios within the cabinets. In addition to the above analysis utilizing actual frequencies that are characteri=ed as a rigid system, another analysis was performed utilizing system frequencies shifted towards the amplification range of the floor response spectra. This shift was introduced by dividing the frequencies j by ten. Table III gives the corresponding responses calculated for the same mass ratios considered before. Also given are the responses calcu-laced by response spectrum analyses. The results confirm that significant j
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amplification associated with system / subsystem interaction is relevant when 1 the closely spaced frequencies are within the driving or amplification fre-
; quency range of the input motion. Also, it is evident that for response spectrum analysis in this case the combination of modal responses by alge-braic summation rather than SRSS gives a more realistic evaluation.
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Weights i Shipping Weight of Instrument Weight of Weight of Mass Ratio Section Panel No. Instrument No. Structure No. (1) + (2) (1) (2) (3) (3) 1 719 659 4677 .29 2 454 643 3476 .32 3 551 635 3894 .30 4 442 578 3709 .28 5 698 828 4499 .34 6 703 459 7507 .46 From Wyle Test Report No. 54498-2 l l l l l
, ggy.jV/'-0013 l y a/n/n-TABLE II 3 Results of Time History Analysis
,) f - 22.5 cps, f = 28.0 cps 3 2 a) X direction (horizontal) floor acceleration time history, ZPA = 0.908g, input Subsystem (Secondary) Mass Response Mass Ratio Max. Acceleration (g) Amplification Ratio 0.05 1.029 1.13 0.005 1.179 1.30 0.0005 1.215 1.34 b) Y direction (horizontal) floor acceleration time history, ZFA = 0.943g, input
; Subsystem-(Secondary) Mass Response 1
- Mass Ratio j .,
Max. Acceleration (g) Amplification Ratio ' D O.05 1.107 1.17 0.005 1.226 1.30 0.0005 1.271 1.35 c) Vertical direction was not considered since the modal shapes of the closely
- spaced modes / frequencies do not suggest interaction in the vertical direction.
t b mg..m, %,~ .s, -..,.-,--e . L *4Mh +m- w.L s.a.4 - , - -e. - , - - - -.
' .2.A/o 6 - / V a - U
- O t:Ab ~3l) E---
TABLE III
- Results of Time History Analysis j
f - 2.25 cps, f = 2.80 cps l 2 a) Y direction (horizontal) floor acceleration time history, ZPA = 0.943g, input Subsystem (Secondary) Mass Response Mass Ratio Time History Analysis Response Spectrum Analysis (g) Max. Acceleration (g) Algebraic Summation SRSS 0.05 4.00 3.28 5.47 0.005 4.055 3.69 6.80 0.0005 4.175 493 3.74 7.01 6.0 approx. from FRS @ 2.5 cps (. l N
_ = - - - _- =
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FREQUENCY (eyeles per second) ' 300 to 25 10 5 2 1 .5 .2 i i i. ,.. O SW" N gIs ' ' ' ' i SECMTEL POWER CORPORATION
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FFR NO. 2408 Fit-0018 ._ i ' POTENTIAL FINDING REPORT REVl$ ION - i L. 1 SONGS 2&3 SEISMIC DESIGN VERIFICATION A PREPARATION BY GA INITIATOR , AFFECTEDITEMS:' Safety Injection Line to Reactor coolant Emop 1A Tiping Stress 1
- Analysia Package FSG-78, Mode 146 (Incorrectly shown as Noda 147, Ref. 2406-FFK-0006) Tag .
No. 52-51-059-H-009.
~'
REQUIREMENT REFERENCE DOCUMENTE: ..... .
- *7-.
- Specification 5023-409-2, Nucisar Servics Pipe Supports, Hansers and Accessories for ~ ~
~
San Onofra Nuclear Cenarating Station, Duits 2 and 3 Page 4F-9 (4/24/74). 1 8ASIC REQUIREMENT: Structural Steel Design Per AISC 5 pee. (Feb. 12,1969).
, . .e , , -
l
~ '
OEscalm04 0F POTENTIAL FINDING: "D - Revised Calculatina F450-1.109 - 9100. Sht.- 1 uses weld . allowable stress of 13.6 ISI,
'wtdch is the allowable in AISC Spec (1963) for E60K1 alectrode. The weld allowable stress
~
in AISC (1969) is 18 K3I for 360I1 alactroda.. Ibe. calculation uses weld allowable strasse i for 2 different electrodas trithout calling out ths.nlactrodas.
?* 7hn PM is unsid (
d . N Y S N S " " l
//23/I,E
^
A. Zimmer 1-18 42' l PREFARED SY: DATE: '
~
REJECT 10N OF GA TASK LEADER dk)MMENT5 8Y: -DATE: REJECTION OF ORIGINAL DESIGN ORG. COMMENTS SY: DATE: B. REVIEW RY GA TA3X LEADER
,',yp;]f,h,i".. - t0ggEgTS .
,. ~.; ; - .
- i. 22. -
l 7 Y [ .s/ AGREE PF 15 VAllo 8Y d JiA DATE
//s' /p. - -
O REQUEST RE. REVIEW SY
/ / DATE
/
D DISAGREE SY DATE O REVIEW OF ORIGINAL DESIGN O AGS. COMVENTS EY: nats-
I PAGE2 gogge pj6 V PFR NO.2408-PFR-00. 88-- O/d REVISION A& //1Y/rs C. REVIEW BY ORIGINAL DESIGN ORGANIZ ATION COMMENT 3 d The weld stress allowable of 13.6 ksi is not used in the referenced calculation. BPC g
-s esign methodology uses the lower allowable stress of the two electrodes used for pipe upport steel which are given 'in Specifications S023-206-18 and CSP 207.
The AISC Code allowable stress for seismic loads is 16.93 ksi in the leg of the weld (based on Fy = 31.9 ksi and E60XX electrodes and a 1/3 increase in allowable for seismic loading). The calculation is conservative because the weld allowables used are less than the AISC Code allowable for seismic loads. O AGREE PF 15 VAUD G DISAGREE BY J
# DATE:
/
D. R E C O'."
- E '. O A Tt C ',' B Y F.';3"i 3 5 R E Vi CW C D P.' MITT E E DEFINITION ADEQUACY: El ADEQUATE D INADEQUATE VALIDITY: O VALID E INVALID HFCF&20 -
0 NOT AT?ttCASLE D AF7tiCA5cE-IDJM ES E%1- 0 NOT AFFi.iCA5LE Nf" '/1Y/f' O ArruCASLE CLASSIFICATION: O OBSERVATION O FINDING ( STIFICATICN: CLASSIFICATION CRITERION NO. RESU1. TING IN FINCING" COMMENT ON OBSERVATION ** CLASSIFICATION SY:
- DATE: / ' '
b f/ E. TFT PROJECT MANAGER [] ACCEPT O REJECT l \ l
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BY A 4M/Mt'uf_ - g A;g. / L
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..-__..m. _ _ . _ _
wm wn _ =.-., n - - - - o , g , ,;,y, ,,,, GENERAL ATOMIC COMPANY
,. CALCULATIONS FOR EQUIP. NO. , l PROJ. NO. CALC.NO. lPAGE OF PREPARED BY [, [ p 4 my DATE REF. DOCUMENTS:
f, REVIEWED BY DATE / APPROVED BY DATE COl8,.gpef
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49 . . m a, 24ce-m.coS, I # D' .i PDTENTIAL FINDING REPORT Riv810N -
\ b -D ! ' SONGS!&3 SEISMIC DESIGN VERIFICATION 9 . . . .- . . - . . _ .
l A. PREPARATION 3Y E A INITIATQN , ,
' AFFECTED(Tears: ' Safety Injection time to tractor coolant 1a.91A. Tiping Ste:ess Analysia
> raaaa. rss-7s. =a. lu nocorr.etty sho .s d. . m. mar. 240s-era-coo 6).
IIIt5EENkiNDliddOCUMENT3- . .
.5pecification 8023-409-2. Nuclese Service Pipe 5apports, Bangers and Accessories for Saa Onofre Nuclear Generating Station, Unita 2 and 3. Pasa 4F-9 (4-24-74).
'8ASIC REQUIREMENT:
. : A11ovebte stress under DRE koadina for structural steel is 0.90 times the W=ue guaranteed yield stresses -listed in the AIsc Spac. Mb.. 52,1969).
4
-011CRIFTION OF POTENTIAL FINDING: Revised calculation P430-1.109 - 9.100 sht.1 ,
uses bending allowabia = 19.14 KSI (0.ETy z 4.9) and sold ebear allowable scrasses cf 13.6 ESI sad 21.0 ESI thich are not equal to- 0.9 s Fy per the basic requirumast. - . PFa is inya/al(See a'NocNbb . NhN. / .
.; 63/s2 PREPARED BY:
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DATE:
-e 82
.(
fg / REJECTION OF GA TASX LIADE A COMalENTS 3Y: DATE:
' REJECTION OF 0 AIGINAL DESIGN ORG. COMMENT 5 BY:
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