Similar Documents at Salem |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18107A5291999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9
ML20211Q8771999-08-27027 August 1999
Rev 0 to Inservice Testing Manual for Pumps & Valves Program
ML18107A5171999-08-25025 August 1999
Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2
ML18107A5121999-08-23023 August 1999
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Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability.
ML18107A4961999-08-23023 August 1999
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ML18107A4671999-07-29029 July 1999
Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements
ML18107A4601999-07-23023 July 1999
Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown
ML18107A4241999-07-0202 July 1999
Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR
ML18107A3811999-06-10010 June 1999
Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means
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Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC
ML18107A2961999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9
ML18107A2131999-04-14014 April 1999
Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431
ML18106B1591999-03-31031 March 1999
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ML18106B0641999-02-0808 February 1999
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ML18106B0611999-02-0808 February 1999
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Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys
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Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1
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Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03
ML18106A9181998-10-12012 October 1998
Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10
ML18106A8941998-09-29029 September 1998
Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch
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ML18106A6961998-07-0707 July 1998
Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan
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Rev 11 to Salem Nuclear Generating Station Odcm
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Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2
ML18106A3921998-03-13013 March 1998
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ML18106A3221998-02-18018 February 1998
Marked-up TS Pages for Section 4.2.1 of App B
ML18106A3091998-02-0202 February 1998
Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation
ML18106A2541998-01-0808 January 1998
Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page
ML18106A2141997-12-15015 December 1997
Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing
ML18106A1961997-12-11011 December 1997
Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4
ML18102B6791997-11-14014 November 1997
Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels
ML18102B6751997-11-14014 November 1997
Proposed Tech Specs Re Administrative & Editorial Corrections
ML18102B6591997-11-0404 November 1997
Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid
ML18102B6631997-11-0404 November 1997
Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown
ML18102B6431997-10-29029 October 1997
Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing
ML18102B6391997-10-29029 October 1997
Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10
ML18102B6491997-10-24024 October 1997
Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases
ML18102B6461997-10-24024 October 1997
Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1
ML18102B6321997-10-21021 October 1997
Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position
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Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2
1999-09-10
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18107A5291999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9
ML20211Q8771999-08-27027 August 1999
Rev 0 to Inservice Testing Manual for Pumps & Valves Program
ML18107A5121999-08-23023 August 1999
Procedure 71151, Performance Indicator Verification.
ML18107A5091999-08-23023 August 1999
Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability.
ML18107A2961999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9
ML20216B0641998-05-0101 May 1998
Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page
ML18106A5571998-04-16016 April 1998
Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents
ML20239A1251998-03-31031 March 1998
Rev 11 to Salem Nuclear Generating Station Odcm
ML18106A3921998-03-13013 March 1998
Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency.
ML18106A8281998-03-0404 March 1998
Rev 1 to Reactivity Manipulations Documentation Guide.
ML18102B6681997-10-0101 October 1997
Rev 8 to Inservice Testing Manual for Pumps & Valves Program.
ML18106A8291997-09-0404 September 1997
Rev 2 to Reactivity Manipulations Documentation Guide. Page to Training Manual NC.TQ-TP.ZZ-0302,encl
ML18102A7941997-01-21021 January 1997
Event Classification Guide,Technical Basis, for Hope Creek Generating Station & Salem
ML18102A7931997-01-21021 January 1997
Event Classification Guide,Technical Basis, Salem Generating Station
ML18102A6661996-11-19019 November 1996
Rev 2 to Pse&G Simulation Facility Certification Program.
ML20115B7791996-07-0303 July 1996
Final Draft, Hope Creek Event Classification Guide, Sections 1-9
ML18101B1141995-11-14014 November 1995
Revised Salem Generating Station Event Classification Guide, Including Rev 46 to Table of Contents,Rev 37 to Attachments Signature Page,Rev 26 to Attachment 6,Rev 25 to Attachment 7 & Rev 24 to Attachment 9
ML20091M9911995-10-15015 October 1995
Event Classification Guide HCGS, Including Revised Eals, Technical Basis Document & NUMARC EAL-to-Hope Creek Comparison Summary
ML18101A6911995-05-31031 May 1995
Nbu Issue Mgt & Prioritized Action Plan, Dtd May 1995
ML18101A7711995-05-11011 May 1995
Rev 1A to Vol a of Salem Generating Station Unit 2 Second 10-Yr Insp Interval ISI Program Plan.
ML20134K0831995-02-27027 February 1995
Pse&G/Nuclear Business Unit Organizational Effectiveness Assessment Plan,
ML18101A6751995-02-16016 February 1995
Rev 11 to EOP 1-EOP-TRIP-1, Reactor Trip or Safety Injection.
ML18101A6761995-02-16016 February 1995
Rev 12 to EOP 1-EOP-TRIP-2, Reactor Trip Response.
ML18101A5381995-01-27027 January 1995
Revised Salem Generating Station Event Classification Guide.
ML18101A2111994-08-17017 August 1994
Revised Salem Event Classification Guide.
ML18101A6771994-07-11011 July 1994
Rev 10 to EOP 1-EOP-TRIP-3, Safety Injection Termination.
ML20147B1601994-04-23023 April 1994
Rev 3 to S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation
ML18100A8081994-01-0707 January 1994
Rev 30 to Salem Generating Station Event Classification Guide.
ML20147B1491993-11-0202 November 1993
Rev 2 to Procedure S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation
ML18100A4201993-06-15015 June 1993
Justification for Sgs Units 1 & 2 Restart & Operation Rod Control Sys Failures.
ML18100A3771993-05-0505 May 1993
Rev 27 to Salem Generating Station Event Classification Guide.
ML18100A3661993-04-27027 April 1993
Rev 8 to Section 18 to Event Classification Guide, Correcting Typo on Pages 3 & 5 of 6
ML20147B1171993-04-13013 April 1993
Rev 1 to Procedure NC.NA-AP.ZZ-0015(Q), Safety Tagging Program
ML18096B3251993-02-26026 February 1993
Integrated Scheduling Program.
ML18096B2911993-02-10010 February 1993
Revised Event Classification Guide,Including Rev 25 to Table of Contents,Rev 14 to Attachment 6,Rev 13 to Attachment 7, Rev 8 to Attachment 8,Rev 13 to Attachment 9,Rev 3 to Section 10,Rev 4 to Section 17 & Rev 7 to Section 18
ML20147B1021993-01-21021 January 1993
Rev 5 to Procedure NC.NA-AP.ZZ-0009(Q), Work Control Process
ML20135B6521992-12-29029 December 1992
Rev 0 to Loss of Overhead Annunciator Sys
ML20147B1371992-12-22022 December 1992
Rev to Procedure SC.RP-TI.ZZ-0209(Q), Release of Items from Rca
ML20147B2051992-09-21021 September 1992
Rove Time Keeping Procedure
ML18096A9601992-08-28028 August 1992
Electrical Distribution Sys Functional Insp (Edsfi) Methodology & Plan.
ML18100A3151992-07-28028 July 1992
Rev 1 to Process Computer Maint & Mod Control Program.
ML18096B3191992-07-17017 July 1992
Rev 8 to Salem Nuclear Generating Station Odcm.
ML20147B1691992-05-0707 May 1992
Rev 1 to Procedure NC.NA-AP.ZZ-0013(Q), Control of Temporary Modifications
ML18096A6791992-04-30030 April 1992
Vols A-D of Salem Generating Station Unit 2 Inservice Insp Program (Second Insp Interval) Long-Term Plan.
ML18096A4421992-01-15015 January 1992
Rev 17 to Salem Generating Station Event Classification Guide
ML18096A3211991-10-0404 October 1991
Rev 13 to Event Classification Guide,Including Table of Contents,Section Signature Pages,Spill/Discharge Notification Form & Related Pages
ML18096A1431991-06-28028 June 1991
Rev 12 to Salem Generating Station Event Classification Guide.
ML18095A9661991-05-30030 May 1991
Artificial Island Salem Event Classification Guide, Rev 11
ML18096A1191991-05-28028 May 1991
Rev 2 to NFU-0039, Salem Reactor Physics Methods.
ML18095A9391991-05-16016 May 1991
Revised Replacement Pages to Facility Inservice Testing Program
1999-09-10
[Table view] |
Text
_ _ _ . _
t ATTACHMENT 2 PIPE' SUPPORT - BASE PLATE FLEXIBILITY EVALUATION PROCEDURE .
FOR USNRC I & E BULLETIN 79-02 SALEM NUCLEAR GENERATING STATION ASSOCIATED TECHNOLOGIES, INC.
CLIFTON, NJ t
!1
-i 8410010374 840920
- G PDR
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4 ATTACHMENT 2 (cent'd)
- (
s
-PIPE' SUPPORT - BASE PLATE FLEXIBILITY EVALUATION PROCEDURE 4
- N
-Prepared by* .
i Ajit K. Khaund Approved by: . -t '< ' :- [' ; -
Oscar P. Wong-Y I'
3._ -- - -
ATTACHMENT 2.(c nt'd)
~
1.0 PURPOSE
- The purpose of this procedure is to provide the methqd by which pipe support base plates are evaluated for flexibility conditions and the ensuing effects'on anchor bolt loading. This evaluation is in reponse to NRC Bulletin 179-02 7
Rev. 2.
2.0 SCOPE This procedure applies to all nuclear safety re-
' lated structures, systems and components on the Salem Nuclear-Generating Station. The procedure will be augmented by specific client and project design. criteria which are.provided in the references below.
3.0 REFERENCES
3.1 PSE&G letter dated January 18, 1980, R. D.
Rippe to' Oscar Wong.
3.2 USNRC IE Bulletin No. 79-02.
3.3 USNRC IE Bulletin No. 79-02 (Supplement No. 1) 3.4 AISC Manual 3.5 ATI Engineering Standard PS-ADl-02
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7 _
- ATTACHMENT-2 (cant'd) 4.0 PROCEDURE The procedure for base plate evaluation is in ad-dition to that used for pipe support design. De-
. termination of loadings on the base plate are ob-tained from design calculations of the pipe. support (per PS-ADI-02) which in turn are designed on the basis of piping stress calculations. The additional.
consideration of this evaluation takes into account the flexibility of the base plate which may increase the normally calculated bolt pull out values. Standard procedures assume rigidity of the plate.
For the purposes of this procedure, three methods of calculation will be considered acceptable for the determination of the bolt design loads.
1 . _. Manual calculations
- 2. BASEPLT program used as a pre- and post-processor for STARDYNE. BASEPLT was developed by E. A.
Botty and Associates.
- 3. ANSYS finite element computer program developed by Swanson Associates.
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. ATTACHMENT 2 (cant'd) 4 . l' Manual determination of bolt loads will be carried out as follows:
U 4.1.1 Assume rigid plate conditions and calculate bolt tension from applied loads.
4.1.2 Determine thickness of base plate required per AISC.
4.1.3 If actual thickness.is significantly greater than required by design then the loads deter-mined in 4.1.1 are acceptable.
-4.1.4 If the actual thickness is marginal or less than that required by AISC then the rigid plate assumption is not acceptable and further review is required. Section 4.2 is applicable.
4.2 Using the BASEPLT or ANSYS program determine the bolt design load. The computer analysis takes into account the flexibility of the plate and its inter-action with the concrete and anchor bolt.
r- _ _
~
ATTACHMENT 2 (csnt'd) 5.b DOCUMENTS Bolt' loads for-maximum shear and tension shall be transmitted to PSE&G and identified by pipe stress calculation, hanger mark and transmittal numbers.
See Attachment 1.
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- ATTACHMENT 3 O
g Burns and Roe,Inc.
fu GCU 2662hNY (213 SS3UC0 ge e.anamecs %sa s Oracem. Nov ,*sey lirpf e Tat 1metume e nes- neuas
- w vn 150 <rgew Nas t we+ n=.cw,: us
- :n:xc February 6, 1984 f
Public Service Electric and Gas Company P.O. Box 236 - T3-002 08038 liancocks Br2.dge, N.J. .
Attention: Mr. R.L. Gura Manager Plant Engineering Gentlemens This is to inform you of the procedure used by Burns and Roe for performing base plate and concrete anchor bolt calculations for Salem 1 and 2, to show compliance with NRC Bulletin No. 79-02.
~he majority, in fact practically all the Salent 1 and '
2 base plates analyzed by Burns Therefore, and Roea were simplified angle,pro- and channel type connections.
cedure was developed for analyzing these connections, This procedure, using the ANSYS Finite element program. PSP-001, titled "
- was approved by PSE4G per letter R.D. Rippe to P.W. Chan, l titled " Bolt Load Design Review", March 7,1980.
j .
For the few cases where the connection was other than an angle or channel shape, a more extensive ANSYS finite element analysis was performed.
' In case the corutection was made with a flat plate, an
- extensive finite element analysis wasthis Since performed programusing was de-t
- Toledynes BASEPLATS program.
- veloped specifically for base plates, it is simpler and l
cheaper to use than the ANSYS program.
i t
[
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r-o aES 400 ;"8- i ATTACHMENT 3 (cont'd) Pago 2 )
i We trust this provides the information you require.
Very truly yours,
- 4. l . _b.r= - -
R.T. Si::rons Project Engineer RTS:ga ec: F. Sullivan R.C. Kirk i
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