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Category:EXHIBITS (DOCKETING AND SERVICES BRANCH INFORMATION
MONTHYEARML20059D2431994-01-0707 January 1994 Package of Intervenor Exhibits Consisting of Related Correspondence Not Admitted Into Evidence.Related Correspondence ML20059M5291993-11-19019 November 1993 Applicant Exhibits A-21,A-22,A-24,A-25,A-26,A-29 & A-F1, Consisting of Related Correspondence Not Admitted Into Evidence.Related Correspondence IR 05000275/19910041993-08-24024 August 1993 Intervenor Exhibit I-MFP-70,consisting of Insp Rept,Re Rept Numbers 50-275/91-04 & 50-323/91-04,dtd 910304 IR 05000275/19930111993-08-24024 August 1993 Intervenor Exhibit I-MFP-26,consisting of Re Insp Repts 50-275/93-11 & 50-323/93-11 ML20059M7491993-08-24024 August 1993 Intervenor Exhibit I-MFP-T-2,consisting of 920422 Rev 4 to Procedure MP E-57.8 Temp Monitoring ML20059M7521993-08-24024 August 1993 Intervenor Exhibit I-MFP-T-3,consisting of 900227 Rept, Effects of Localized High Temps Upon EQ Components ML20059M7581993-08-24024 August 1993 Intervenor Exhibit I-MFP-T-3A,consisting of 900225 Table Re EQ Devices Affected by Localized High Temperatures ML20059M7601993-08-24024 August 1993 Intervenor Exhibit I-MFP-T-4,consisting of Rev O to MP E-57.8A, Temp Monitoring ML20059C7361993-08-24024 August 1993 Intervenor Exhibit I-MFP-88,consisting of NRC Insp of Diablo Canyon Units 1 & 2 ML20059D0841993-08-24024 August 1993 Intervenor Exhibit I-MFP-139,consisting of Insp Rept Re Dockets 50-275 & 50-323,dtd 920417 IR 05000275/19920131993-08-24024 August 1993 Intervenor Exhibit I-MFP-140,consisting of 920416,mgt Meeting Repts 50-275/92-13 & 50-323/92-13 ML20059D2241993-08-24024 August 1993 Intervenor Exhibit I-MFP-220,consisting of Protest of Util IR 05000275/19910061993-08-24024 August 1993 Intervenor Exhibit I-MFP-71,consisting of Rept of EC W/Util Mgt,Re Rept Numbers 50-275/91-06 & 50-323/91-06,dtd 910411 ML20059D2071993-08-24024 August 1993 Intervenor Exhibit I-MFP-193,consisting of Review of LER 1-90-015-00,re Docket 50-275,dtd 910118 ML20059M8621993-08-24024 August 1993 Intervenor Exhibit I-MFP-35,consisting of Rept, Self- Evaluation of Diablo Canyon Power Plant, Dtd Jul 1993 IR 05000275/19920161993-08-24024 August 1993 Intervenor Exhibit I-MFP-137,consisting of Insp Rept Re Dockets 50-275/92-16 & 50-323/92-16,dtd 920707 ML20059M5041993-08-24024 August 1993 Staff Exhibit S-2,consisting of Re Notice of Violation IR 05000275/19900291993-08-24024 August 1993 Intervenor Exhibit I-MFP-69,consisting of Insp Rept,Re Rept Numbers 50-275/90-29 & 50-323/90-29,dtd 910207 IR 05000275/19920171993-08-24024 August 1993 Intervenor Exhibit I-MFP-102,consisting of Insp Rept Re Dockets 50-275/92-17 & 50-323/92-17,dtd 920508 ML20059M1381993-08-24024 August 1993 Staff Exhibit S-1,consisting of Re 920519 Enforcement Conference IR 05000275/19920261993-08-24024 August 1993 Intervenor Exhibit I-MFP-118,consisting of Notice of Violation & Insp Rept Re Docket 50-275/92-26 & 50-323/93-26,dtd 921113 ML20059D2101993-08-23023 August 1993 Intervenor Exhibit I-MFP-196,consisting of Mgt Summary, DCO-91-MM-N067 D6, Asw Pump Vault Drain Check Valves, 910115 ML20059D1721993-08-23023 August 1993 Intervenor Exhibit I-MFP-168,consisting of Mgt Summary, Ncr DCO-91-EM-N009, FCV 495/496 Corrosion, ML20059D1841993-08-23023 August 1993 Intervenor Exhibit I-MFP-178,consisting of Mgt Summary, Ncr DCO-91-TR-N044, Maintenance Personnel Qualifications, ML20059D2031993-08-23023 August 1993 Intervenor Exhibit I-MFP-192,consisting of LER 1-90-015-01, Re Docket 50-275,dtd 910125 ML20059D1961993-08-23023 August 1993 Intervenor Exhibit I-MFP-191,consisting of Nonconformance Rept & Mgt summary,DCI-90-OP-N083, P-14 ESF Actuation Due to Valve Leakage, ML20059M5251993-08-23023 August 1993 Applicant Exhibit A-23,consisting of Rept DCO-93-TN-N006, DCM Maint & Testing Requirements ML20059M6071993-08-23023 August 1993 Applicant Exhibit A-28,consisting of Re LER 1-92-009-01 Involving Dose Limits Potentially Exceeded from Chemical & Vol Control Sys Valve Diaphragm Leakage Due to Thermally Induced Degradation ML20059D2181993-08-23023 August 1993 Intervenor Exhibit I-MFP-216,consisting of Nonconformance Rept & Mgt Summary DCO-90-SE N080,dtd 920128 ML20059D1871993-08-23023 August 1993 Intervenor Exhibit I-MFP-190,consisting of Mgt Summary, Ncr DC1-91-TN-N002, Backleakage Through Check Valve FW-1-531, ML20059D1821993-08-23023 August 1993 Intervenor Exhibit I-MFP-172,consisting of Mgt Summary, Rev 00,NCR DCO-91-MM-N049, Deg 1-3 Test Cock Valve, 911002 ML20059D2121993-08-23023 August 1993 Intervenor Exhibit I-MFP-210,consisting of Rept, SI-1-8805A, Failed to Cycle on Actuation Signal, ML20059C9651993-08-21021 August 1993 Intervenor Exhibit I-MFP-122,consisting of LER 2-91-007-00, Re Docket 50-323,dtd 911101 ML20059C9431993-08-21021 August 1993 Intervenor Exhibit I-MFP-117,consisting of LER 1-92-022-00, Re Docket 50-275,dtd 921030 ML20059C9571993-08-21021 August 1993 Intervenor Exhibit I-MFP-120,consisting of LER 1-92-013-00, ML20059D0701993-08-21021 August 1993 Intervenor Exhibit I-MFP-138,consisting of Nonconformance Rept, & Rev 00,NCR DC1-92-EM-N010,dtd 920729 ML20059C9871993-08-21021 August 1993 Intervenor Exhibit I-MFP-124,consisting of Technical Review Group Meeting Minutes Distribution, & 920124 DCI-91-TI-N047, Reactor Trip Due to Personnel Error & Safety Injection Due to Leaking Steam Dump Valves ML20059M5191993-08-21021 August 1993 Applicant Exhibit A-22,consisting of Responding to Violations Noted in Insp Repts 50-275/92-26 & 50-323/92-26 ML20059C9981993-08-21021 August 1993 Intervenor Exhibit I-MFP-127,consisting of LER 2-91-007-00, Re Docket 50-323,dtd 911101 ML20059C9901993-08-21021 August 1993 Intervenor Exhibit I-MFP-126,consisting of 911030, DC2-91-TI-N088 D2, Inadvertent SI Due to Personnel Error ML20059C9631993-08-21021 August 1993 Intervenor Exhibit I-MFP-121,consisting of 910503, Ncr DC1-OP-N038, Diesel Generator Start & Valve Actuation Due to Personnel Error, Mgt Summary ML20059C9841993-08-21021 August 1993 Intervenor Exhibit I-MFP-123,consisting of LER 1-91-009-00, Re Docket 50-275,dtd 910617 ML20059M5941993-08-21021 August 1993 Applicant Exhibit A-27,consisting of Responding to Violations Noted in Insp Repts 50-275/92-16 & 50-323/92-16 ML20059D0531993-08-21021 August 1993 Intervenor Exhibit I-MFP-136,consisting of Ncr DC1-MM-N028, Unit 1 Loss of Offsite Power - 910307, ML20059D1591993-08-21021 August 1993 Intervenor Exhibit I-MFP-154,consisting of LER 1-92-004-00, Re Docket 50-275,dtd 920520 ML20059D1301993-08-21021 August 1993 Intervenor Exhibit I-MFP-149,consisting of LER 1-91-006-00, Re Docket 50-275,dtd 910425 ML20059D0081993-08-21021 August 1993 Intervenor Exhibit I-MFP-129,consisting of LER 1-92-010-00, Re Dockets 50-275 & 50-323,dtd 921015 ML20059D1671993-08-21021 August 1993 Intervenor Exhibit I-MFP-155,consisting of LER 1-91-002-01, Re Docket 50-275,dtd 910517 ML20059D1461993-08-21021 August 1993 Intervenor Exhibit I-MFP-150A,consisting of Mgt Summary, Ncr DC1-90-WP-N093, Inadvertent Ground Causes CVI, ML20059D1421993-08-21021 August 1993 Intervenor Exhibit I-MFP-150,consisting of LER 1-90-019-00, Re Docket 50-275,dtd 910128 1994-01-07
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARDCL-99-123, Comment on Prs 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors & Draft NUREG-1022, Event Reporting Guidelines. Util Areas of Concern Includes ESF Actuations, Significantly Degraded Components & Historical Limitations1999-09-20020 September 1999 Comment on Prs 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors & Draft NUREG-1022, Event Reporting Guidelines. Util Areas of Concern Includes ESF Actuations, Significantly Degraded Components & Historical Limitations ML20205N4081999-04-14014 April 1999 Comments Opposing Proposed Rules 10CFR2,19 & 20 Re Proposed Repository at Yucca Mountain.Requests Information on How Much Radiation Being Released Now at Diablo & Hanford NPPs ML20205N4601999-03-21021 March 1999 Introduces K Schumann as Representative of Nuclear Waste Committee (Nuwic) of San Lius Obispo County.Informs That Nuwic & Nuclear Waste Management Committee Concerned with Transportation of Spent Nuclear Fuel Rods from Dcnpp ML20195E8841998-11-24024 November 1998 Petition for Mod to OLs to Require Plant Owner to Have Independent Contractor Evaluate Plant Safety Culture ML20236T3011998-07-24024 July 1998 Order Prohibiting Involvement in NRC Licensed Avtivities (Effective Immediately).Lh Brooks Prohibited for 5 Yrs from Date of Order from Engaging in NRC Licensed Activities ML20248C2261998-05-22022 May 1998 Comment Opposing Revised Proposed Rule 10CFR50 Re Protection & Safety Sys ML20129J4191996-10-18018 October 1996 Order Approving Application Re Corporate Restructuring of Pacific Gas & Electric Company by Establishment of Holding Company DCL-95-206, Comment Supporting Petition for Rulemaking PRM-50-61 Re Improving Fire Protection Regulations1995-10-0606 October 1995 Comment Supporting Petition for Rulemaking PRM-50-61 Re Improving Fire Protection Regulations ML20091P8721995-08-23023 August 1995 Comment Opposing Petition for Rulemaking PRM-50-61 Re Nuclear Energy Institute Proposed Amends on Fire Safety for All NPPs DCL-95-001, Comment on Proposed Changes to Reactor Pressure Vessel Integrity Rule 10CFR50.Endorses NEI Comments1995-01-0303 January 1995 Comment on Proposed Changes to Reactor Pressure Vessel Integrity Rule 10CFR50.Endorses NEI Comments ML20077M7521994-12-30030 December 1994 Comment Opposing Proposed Rule 10CFR50 Re Shutdown & Low Power Operation for Nuclear Power Reactors DCL-94-270, Comment on Proposed Rules 10CFR2,51 & 54 Re Rulemaking for NPP License Renewal.Endorses Comments & Changes Proposed by NEI 941208 Submittal1994-12-0808 December 1994 Comment on Proposed Rules 10CFR2,51 & 54 Re Rulemaking for NPP License Renewal.Endorses Comments & Changes Proposed by NEI 941208 Submittal ML20149H0851994-11-0404 November 1994 Initial Decision (Construction Period Recovery/Recapture).* Renewed Motion to Reopen Record 940808,denied.Served on 941104.W/Certificate of Svc ML20072L2651994-08-23023 August 1994 PG&E Opposition to San Luis Obispo Mothers for Peace Renewed Motion to Reopen Record.* Util Opposes San Luis Obispo for Peace Motion Based on Affidavit Stating No Evidence Found in Motion Re Flaw in Program.W/Certificate of Svc ML20072F0291994-08-12012 August 1994 Erratum to San Luis Obispo Mothers for Peace Motion to Reopen Record.* Intervenors Corrects Error in Renewed Motion to Reopen Record Re Application for License Amend to Extend Term of Operating License for Plant.W/Certificate of Svc ML20072B2651994-08-0909 August 1994 Comment Supporting Proposed Rule 10CFR26 Re FFD Requirements Concerning Random Drug Testing ML20072A5821994-08-0808 August 1994 San Luis Obispo Mothers for Peace Renewed Motion to Reopen Record Re PG&E Application for Amend to Extend Term of OL for Plant.* Motion to Reopen Record to Introduce Insp Rept Identifying Alleged Problems W/Plant.W/Certificate of Svc ML20071L2061994-07-26026 July 1994 Comment Supporting Proposed Rule 10CFR26 Re Changing Current Drug Testing Policies to Exclude All Personnel in nonsafety-related Positions ML20072B8481994-07-26026 July 1994 Comment Opposing Proposed Rule 10CFR26 Re Changes to FFD Requirements Concerning Random Drug Testing ML20071L1901994-07-20020 July 1994 Comments on Proposed Rule 10CFR26 Re Relaxing Rule on Drug Testing of Employees Working at NPP DCL-94-134, Comment Supporting Petition for Rulemaking PRM-50-60 Re Amend to 10CFR50.54 by Changing Frequency W/Which Each Licensee Conducts Independent Reviews of Emergency Preparedness Program1994-06-27027 June 1994 Comment Supporting Petition for Rulemaking PRM-50-60 Re Amend to 10CFR50.54 by Changing Frequency W/Which Each Licensee Conducts Independent Reviews of Emergency Preparedness Program DCL-94-135, Comment Supporting Petition for Rulemaking PRM-50-59 Re Proposed Amend to 10CFR50.54(p) Concerning Frequency W/Which Licensee Conducts Independent Reviews of Security Programs1994-06-27027 June 1994 Comment Supporting Petition for Rulemaking PRM-50-59 Re Proposed Amend to 10CFR50.54(p) Concerning Frequency W/Which Licensee Conducts Independent Reviews of Security Programs ML20064D1791994-03-0707 March 1994 Pacific Gas and Electric Co Reply in Opposition to San Luis Obispo Mothers for Peace Motion to Reopen Record.* Motion to Reopen Record Denied.W/Certificate of Svc ML20064D1961994-03-0404 March 1994 Affidavit of Mj Angus Re Motion to Reopen Record ML20063L5721994-02-25025 February 1994 San Luis Obispo Mothers for Peace Re Util Application for License Amend to Extend Term of Operating License for Plant.* Advises That Record of Proceeding Should Be Reopened to Consider Insp 93-36 Re Util Surveillance of Asw Sys DCL-94-021, Comment Supporting Petition for Rulemaking PRM-21-2 Re Commercial Grade Item Dedication Facilitation1994-01-26026 January 1994 Comment Supporting Petition for Rulemaking PRM-21-2 Re Commercial Grade Item Dedication Facilitation ML20059D2431994-01-0707 January 1994 Package of Intervenor Exhibits Consisting of Related Correspondence Not Admitted Into Evidence.Related Correspondence ML20062N0001993-12-30030 December 1993 PG&E Reply Findings of Fact & Conclusions of Law.* Mothers for Peace Proposed Findings & Conclusions Do Not Provide Any Supportable Rationale to Change Findings & Conclusions Previously Proposed by Pg&E.W/Certificate of Svc ML20058P3931993-12-22022 December 1993 NRC Staff Findings of Fact & Conclusions of Law in Form of Initial Decision.* Certificate of Svc ML20058K7491993-12-0202 December 1993 NRC Staff Motion for Extension of Time.* Board Has Extended Filing Time for Util Until 931230.W/Certificate of Svc. Served on 931206.Granted for Board on 931203 ML20058K8771993-12-0202 December 1993 NRC Staff Motion for Extension of Time.* Requests That Board Extend Date for Staff to File Findings Until 931222. W/Certificate of Svc ML20059M5291993-11-19019 November 1993 Applicant Exhibits A-21,A-22,A-24,A-25,A-26,A-29 & A-F1, Consisting of Related Correspondence Not Admitted Into Evidence.Related Correspondence ML20058E0741993-11-19019 November 1993 San Luis Obispo Mothers for Peace Proposed Findings of Fact & Conclusions of Law Re Licensee Application for License Amend to Extend Term of Operating License for Plant.* W/ Certificate of Svc ML20059E8931993-10-28028 October 1993 Memorandum & Order (Motion for Extension of Time).* San Luis Obispo Mothers for Peace 931018 Request for two-wk Extension of Time to File Proposed Findings of Fact & Conclusions of Law Granted.W/Certificate of Svc.Served on 931029 ML20059E8531993-10-27027 October 1993 NRC Staff Response to Board Memorandum & Order Re Extension of Time.* Staff Believes That San Luis Obispo Mothers for Peace Has Shown No Good Cause for Requesting Extension to File Proposed Findings of Fact.W/Certificate of Svc ML20059E8631993-10-25025 October 1993 Pacific Gas & Electric Co Response to Motion for Extension of Time.* Util Does Not Agree W/Board Assessment That Mothers for Peace Request Appears to Be Reasonable But Will Not Oppose Request.W/Certificate of Svc ML20059B2191993-10-19019 October 1993 Memorandum & Order (Responses to Motion for Extension of Time).* Board Believes Intervenor Request for Extension of Time to File Proposed Findings of Fact Appears Reasonable. W/Certificate of Svc.Served on 931019 ML20059B1071993-10-18018 October 1993 San Luis Obispo Mothers for Peace Motion for Extension of Time for Filing Proposing Findings of Fact & Conclusions of Law.* Requests Extension of Two Wks or Until 931119 to File Proposed Findings of Fact.W/Certificate of Svc ML20057D0531993-09-23023 September 1993 Notice of Appearance.* Notice Given That Undersigned Attorney Enters Appearance in Listed Matter & Listed Info Provided.W/Certificate of Svc ML20057B0401993-09-14014 September 1993 NRC Staff Reply to PG&E Response to Staff Motion to Amend Protective Order.* NRC Staff Moves Board to Adopt Language Requested in 930817 Motion as Stated.W/Certificate of Svc ML20056G4891993-08-30030 August 1993 Pacific Gas & Electric Co Response to Motion to Amend Protective Order.* Staff Asks That Protective Order Be Clarified by Adding New Footnote to Paragraph 3 of Order. W/Certificate of Svc ML20059M1381993-08-24024 August 1993 Staff Exhibit S-1,consisting of Re 920519 Enforcement Conference ML20059D2071993-08-24024 August 1993 Intervenor Exhibit I-MFP-193,consisting of Review of LER 1-90-015-00,re Docket 50-275,dtd 910118 ML20059D2241993-08-24024 August 1993 Intervenor Exhibit I-MFP-220,consisting of Protest of Util ML20059M8621993-08-24024 August 1993 Intervenor Exhibit I-MFP-35,consisting of Rept, Self- Evaluation of Diablo Canyon Power Plant, Dtd Jul 1993 IR 05000275/19920261993-08-24024 August 1993 Intervenor Exhibit I-MFP-118,consisting of Notice of Violation & Insp Rept Re Docket 50-275/92-26 & 50-323/93-26,dtd 921113 ML20059D0841993-08-24024 August 1993 Intervenor Exhibit I-MFP-139,consisting of Insp Rept Re Dockets 50-275 & 50-323,dtd 920417 IR 05000275/19920131993-08-24024 August 1993 Intervenor Exhibit I-MFP-140,consisting of 920416,mgt Meeting Repts 50-275/92-13 & 50-323/92-13 IR 05000275/19910061993-08-24024 August 1993 Intervenor Exhibit I-MFP-71,consisting of Rept of EC W/Util Mgt,Re Rept Numbers 50-275/91-06 & 50-323/91-06,dtd 910411 IR 05000275/19930111993-08-24024 August 1993 Intervenor Exhibit I-MFP-26,consisting of Re Insp Repts 50-275/93-11 & 50-323/93-11 1999-09-20
[Table view] |
Text
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. 3L3-OdA 50-275l/5F7
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(s//7 PGandE Exhibit No. 8 00LKEIII'
[~[ U9K O exc z r zc c.ie imu s tz er arc .g e%%3rr 3 17 J: 3 77 BEALE sfREET
- SAN r e A NC t 3CO. C A L' r0 A NI A 94:06 . (4 0 781 421. * !*x 9 '. C U; 6 '! ?
.... U,'I* Hay 18, 1987 NWCLgaa . owes came.af tN PGandE Letter No.: DCL-87-115 U.S. Nuclear Regulatory Commission ATTW: Document Control Desk Washington D.C. 20555 Re: Docket No. 50-275, OL-DPR-80
, Docket No. 50-323, OL-DPR-82 Diablo Canyon Units I and 2 Additional Information on Reracking Analyses Gentlemen:
In the May 6, 1987, reracking meeting between the NRC Staff and PGandE. th'ree questions were identified which require a response from PGandE. PGandE responses to these questions are contained in the enclosure. ,
Kindly acknowledge receipt of this material on the enclosed copy of this letter and return it in the enclosed addressed envelope.
Sincerely, Enclosure cc: L. J. Chandler l
J. 8. Martin i M. M. Mendonca P. P. Narbut B. Norton C. M. Transnell CPUC Diablo Distribution Reracking Service List i 1438S/0050K/DH0/1998 l
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DATE Contractor Witness Other
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J PGandE Letter No.: DCL-87-115 ENCLOSURE RESPONSES TO NRC STAFF QUESTIONS RAISED AT THE MAY 6, 1987 RERACKING MEETING l
I 1
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O 1438S/0050K 1
4 NRC Ouestion No. I
\
Provide documentation that the spent fuel pool liner is not safety-related.
PGandE ResDonse No. 1
- FSAR Update Table 3.2-3 provides the seismic classification of structures, components, and systems. Sheet 3 of 58 (attached) indicates that the pool l liner is classified as Design Class II. A description of Design Class II applicability and requirements is provided in Table 3.2-1 (attached).
!!RC Ouestion No. 2 Discuss the rack baseplate spring constant which would appropriately represent the stiffness of the baseplate interaction with the pool wall.
/ ~
\
PGandE Resoonse No. 2
( STIFFNESS CALCULATION FOR BASEPLATE In order to evaluate the upper-bound stiffness of the fuel rack baseplate spring, the local spring constant of the baseplate was evaluated using classical linear elasticity theory. The basis of the spring constant calculation is the classical solution for a point load on the edge of a semi-infinits half-space. The configuration is shown in Figure 1.
The solution for the displacement, U(r,0) at 6 - 0, is shown to be given )
as (P has the units of lb/ inch of plate thickness):
U-- Inr+C vE where E is the modulus of elasticity and C is the constant of integration.
O 1438S/0050K l
O .
P Edge of Plate Load Point u .
s s O I e Nr N s, .
d v
i U(r,0) y Figure 1. l O
,A, To compute the spring constant, we assume that the baseplate is held at d -
108 inch'es,. Then, relative to that point, the displacement in the direction of P, along the line 0 = 0 is:
d U
r" I"kj where r is the location under the load where the relative displacement is to be calculated. Since the total applied load on a plate of thickness t is Pt.
the s'tiffness of the baseplate is:
l Pt , g ,
wet U
r 2in(dj
~
Taking note of the fact that immediately under the concentrated load, there will be plasticity effects that have not been included, a limiting value for r was selected equal to the thickness of the plate. Also, since the impact spring under evaluation is at the edge of the plate, the above solution is appropriately adjusted for the " quarter-plate" condition. This results in a reduction of the stiffness by 50 percent. Therefore, the stiffness, K, for a single baseplate is:
i K -
wet 4In(dj 6
For E = 27.9 x 10 psi, t = 0.625 in., and d = 108 in., we obtain: !
l
. i K = 2.658 x 106 lb/in.
For rack-to-rack impacts, two plates are involved. Therefore, the spring i
constant in the model can be set to be 50 percent of th above value for rack-to-rack 17 pact, resulting in K (rack / rack) = 1.33 x 106 lb/in.
1438S/0050K ____-____ ____-_
( For rack-to-Wall impacts, the preceding value would be reduced further, since the spring constant for the concrete wall is less than that for the baseplate. ' Assuming concrete properties of E - 3 x 100 psi and u - 0.15, the solution for a half-space under a concentrated load gives the maximum displacement as:
2 g""* , 2(1-u ) P waE l
where P is the load applied over a circular area of radius a. To simulate baseplate impact on the wall, let a - t/2, where t is the baseplate thickness. Then:
K c* 2
" 1 P$' '
4(1-u )
The effective spring constant for baseplate-to-wall impact is:
I 1 1 1 K K K e plate e or 1 / 1 1 3 -6 -6
+ )
_.- =1 1x 10 = x 10 K, (2.658 1.507 ) 0.962 0
Therefore, for baseplate-to-wall impacts, K, = 0.962 x 10 psi i
The inclusion of local flexibility of the gridwork above the baseplate would reduce the calculated spring constant even further. Therefore, the value calculated above should be considered to be an upper-bound.
O l l
1438S/0050K It can be seen that the K, calculated above is approximately equal to the value'used*in the design basis analysis. It should be noted that the analyses of the racks'have shown that the ratio of the girdle bar impact force to the baseplate impaci: force is insensitive to the ratio of the girdle bar spring constant to the baseplate spring constant. .Thus, significant changes in the design basis predictions for impact loads are not expected if the baseplate impact spring constant used in the design basis model is revised to the values calculated above.
NRC Ouestion No. 3 l
Provide weld capacities based on a suggested alternate interpretation by an NRC consultant at the May 6, 1987 meeting, and compare the result with PGandE's calculations presented at that meeting.
PGandE Response No. 3 -
The capacity of the weldments joining the support feet to the rack baseplate was calculated using allowables established by Section III, Subsection NF of the ASME Code. The allowables PGandE used are as follows:
- Fillet Held
- The direct tension stress limit is 18 ksi for the 304L material baseplate l
l Groove Held: The direct tension stress limit is 21 kst for the 304L material baseplate
- Level 0 Service Limit The allowable stresses are increased by a factor of 2.0 for Level D service (Hosgri) conditions. (Appendix F, Paragraph F-1334, j
Summer 83 Addendum) l 1438S/0050K _
?
The maximum Naction !oads on the support baseplate weldment are:
i Lateral shear: 226 kips Axial thrust: 290 kips BeNing moment: 1294 kip-inches Although these loads are applied for an extremely short duration, ne' credit is taken for their dynamic nature.
l Based on the above, a support foot conservative weld calculation for, cast ACORN 10 was provided to the NRC Staff in the meeting of May 6,1987. This calculation indicated that for support foot No. 3, the maximum compression and bending stress results in a stress ratio of 1.5, and the maximus shear stress results in a stress ratio of 1.26; the allowable stress ratio is 2.0 for Level 0 service conditions. This corresponds to a minimum factor of safety of 1.33. -
Ouring the meetiny of May 6,1987, an alternate interpretation of the ASME Code was suggested (by an NRC consultant) to PGandE for the Level D Service Limit, which wu as follows: m
-E The allowable stresses for groove welds can be increased by a factor of 2.0 over the Level A Service Limit; this corresponds to the allowable i value of 42 ksi.
The allowable stresses for fillet welds can be increased such that the value does not exceed 0.42uS , where S is the ultimate tensile u
stress of the base metal; this corresponds to the allowable value of 28.6 ksi.
Thealiowableshearstressforallweldsisalsotakenas28.6ksi.
O 1438S/0050K 3- y ._
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- Table 1 gives the weld data on the support foot. Referring to Table 1 and the foregoing data on the allowable shear stress, the factor of safety against i
weld shear failure is:' ,
4-(34.24)(28.6) r 3
= _ , _ = 4.33 226 The factor of safety against direct stress is computed by considering the combined effect of the axial thrust and bending moment. Figure 2 shows the interaction curve. This curve is generated by assuming a rectangular stress profile for each weld line (perfectly plastic response; no credit for strain-rate effect). Referring to Figure 2, the factor of safety is defined as:
rd =
= = 1.92 O
The above values result in a higher factor of safety than the values reported in the May 6, 1987, meeting, thereby confirming the conservatism in PGandE's methodology.
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I 143BS/0050K _ 7_ i
__----- - - _ - - - - - _ - - - - - - - - - - _ - - - - - - - - - - - - - - - - -- -----------J
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Table 1
'. Held Data Effective Shear Area Weld Line Throat (.in.) radius (in.) (in.2)
- 1. Interior groeve 0.442 3.33 9.25
- 2. Exterior groove 0.442 4.29 11.91 3.
Exterior fillet 0.442 4.71 13.08 TOTAL 34.24 in.2 O .
.i O
4 1438S/0050K _ - _ _ - - - _ _ _ _ . _ - _ - _ _ _ - - _ _ - _ _ - _ - _ _ . -_ ._ _- _ ..-_>
1 g i 3 1 '
4 fN u) t s
Figure 2. Load Interaction Curve s
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s ip N
N .s x 3.1 ---
N l
I N N I
i B i
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