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Revision 3A Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment December 2001 Prepared by: [1] ABS Consulting 1111 Broadway Oakland, CA 94607 MPR Associates, Inc. 320 King Street Alexandria, VA 22314 Stevenson & Associates 9217 Midwest Avenue Cleveland, OH 44125 URS Corporation / John A. Blume & Associates, Engineers 100 California Street San Francisco, CA 94111-4529 [2] Winston & Strawn 1400 L Street NW Washington, DC 20005

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Page 1: Generic Implementation Procedure (GIP)Revision 3A iii Preface [3]This revision of the Generic Implementation Procedure (GIP) is an augmented version of the latest revision of the GIP

Revision 3A

Generic Implementation Procedure (GIP)for Seismic Verification of Nuclear Plant Equipment

December 2001

Prepared by:

[1]ABS Consulting1111 BroadwayOakland, CA 94607

MPR Associates, Inc.320 King StreetAlexandria, VA 22314

Stevenson & Associates9217 Midwest AvenueCleveland, OH 44125

URS Corporation / John A. Blume & Associates, Engineers100 California StreetSan Francisco, CA 94111-4529

[2]Winston & Strawn1400 L Street NWWashington, DC 20005

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Copyright © 2001 Seismic Quality Utility Group

Limited license is given to owners of this document to make copies for use by their organization.All other rights granted under copyright are reserved, including the right to modify and the rightto copy this document for subsequent sale.

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Preface

[3]This revision of the Generic Implementation Procedure (GIP) is an augmented version of the

latest revision of the GIP that the Staff of the U.S. Nuclear Regulatory Commission (NRC) has

reviewed and approved (i.e., GIP Revision 3, Updated 5/16/97). This augmented version (GIP-

3A) includes changes to address the clarifications, interpretations, positions, and exceptions that

had been identified by the Staff during their review of the GIP Revision 2, Corrected 2/14/92

(GIP-2) and GIP Revision 3, Updated 5/16/97 (GIP-3). GIP-3A also includes changes to address

the issues identified by the Staff in their review of plant-specific implementation of the USI A-46

program at the SQUG member plants and in their review of SQUG’s guidance on use of the GIP

for new and replacement equipment (NARE).

The documents containing the Staff’s clarifications, interpretations, positions, exceptions, and

issues along with SQUG’s understanding of these are listed below.

1. NRC Generic Letter (GL) 87-02, dated February 19, 1987, Verification of SeismicAdequacy of Mechanical and Electrical Equipment in Operating Reactors, UnresolvedSafety Issue (USI ) A-46.

2. NRC Generic Letter 87-02, Supplement 1, dated May 22, 1992, forwarding SupplementalSafety Evaluation Report No. 2 (SSER No. 2) on GIP-2.

3. SQUG (N. Smith) letter to NRC (J. Partlow), dated August 21, 1992, describing SQUG’sunderstanding of SSER No. 2.

4. NRC (J. Parlow) letter to SQUG (N. Smith), dated October 2, 1992, with enclosurecontaining NRC Staff comments on SQUG’s 8/21/92 letter.

5. SQUG (N. Smith) letter to NRC (J. Partlow), dated March 26, 1993, forwarding Revision2A of the Generic Implementation Procedure (GIP-2A).

6. NRC (W. Butler) letter to SQUG (N. Smith), dated May 24, 1993, NRC Response toSQUG Letter Dated March 26, 1993, on GIP-2A.

7. SQUG (N. Smith) memorandum to SQUG members, dated August 4, 1993, Use of GIPRevision 2A.

8. NRC (J. Stolz) letter to SQUG (N. Smith), dated December 4, 1997, forwardingSupplemental Safety Evaluation Report No. 3 (SSER No. 3) on GIP-3.

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9. SQUG (N. Smith) letter to NRC (R. Capra) dated July 15, 1998, forwarding the Report onthe Use of the GIP for New and Replacement Equipment and Parts (NARE).

10. NRC (E. Adensam) letter to SQUG (N. Smith) dated June 23, 1999, forwarding the NRC’sReview of SQUG’s Report on the Use of the Generic Implementation Procedure for Newand Replacement Equipment and Parts (NARE).

11. SQUG (J. Richards and R. Kassawara) memorandum to SQUG members, dated July 25,2000, forwarding the NARE Guidelines, Revision 4, “Implementation Guidelines forSeismic Qualification of New and Replacement Equipment/Parts (NARE) Using theGeneric Implementation Procedure (GIP).”

The changes included in GIP-3A are similar to the changes included in Revision 2A of the GIP

(GIP-2A) that was sent to the NRC Staff for review and approval (Document 5 above). The

NRC Staff declined to review GIP-2A (Document 6 above) because they considered SSER No. 2

to be their official position on using GIP-2 for resolving USI A-46; they considered these two

documents (GIP-2 and SSER No. 2) to be sufficient to implement resolution of USI A-46. They

indicated that these two documents form the bases against which the Staff will judge the

acceptability of the plant specific implementation of the USI A-46 program.

Even though the NRC Staff declined to review GIP-2A, they did not object to its use as a

working document. Therefore, SQUG recommended to its members that they use GIP-2A for

their day-to-day seismic verification and for implementation of the USI A-46 program

(Document 7 above). The advantage of using GIP-2A was that it eliminated the need for users to

refer to two separate documents or to interpret potential conflicts. Since publishing GIP-2A,

additional changes to the GIP criteria and guidelines have been identified in Documents 8 to 11.

Therefore, the need for an augmented version of the GIP became even more important so that all

these additional changes and the NRC Staff positions on these changes can be viewed in a single

working document.

In developing GIP-3A, SQUG has incorporated the Staff clarifications, interpretations, positions,

exceptions, and issues in a manner that we believe would be acceptable to the Staff without

adding new, substantive criteria or guidance into the document. Therefore, even though GIP-3A

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has not been formally reviewed and approved by the NRC Staff, SQUG considers that this

document remains a statement of the accepted criteria and guidance, and is not a change.

At each location in GIP-3A where changes from GIP-3, Updated 5/16/97 have been made, a

superscript number in square brackets (e.g., [1]) is included prior to the change. These numbers

correspond to the endnotes at the end of each section where the reasons for the changes are

listed.

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Contents

Section Page

Front MatterPreface.................................................................................................................................. iii

Contents.................................................................................................................................vi

Revision Status .....................................................................................................................xv

Acknowledgements ..............................................................................................................xx

Glossary of Terms ............................................................................................................ xxiii

List of Effective Pages .......................................................................................................xxv

Reasons for Changes to GIP, Front Matter .......................................................................xxxi

Part I - Licensing and Implementation Guidelines

1 Introduction ..................................................................................................... I-1

1.1 Background ...............................................................................................................I-1

1.2 Purpose of the GIP.....................................................................................................I-2

1.3 GIP Commitments and Guidance ..............................................................................I-3

2 Issue and Positions ......................................................................................... I-5

2.1 Introduction ..................................................................................................................I-5

2.2 Interpretations of Guidelines......................................................................................I-62.2.1 Implementation Schedule and Commitments ..............................................I-62.2.2 Assumptions.................................................................................................I-72.2.3 Achieving and Maintaining Hot Shutdown..................................................I-82.2.4 Multiplier for Equipment Above the 40-foot Level.....................................I-82.2.5 Reportability and the Need for JCOs...........................................................I-82.2.6 The Role of SSRAP During Implementation of A-46 .................................I-92.2.7 Third-Party Audits .....................................................................................I-102.2.8 Completion Reports ...................................................................................I-102.2.9 Plant-Specific SERS...................................................................................I-102.2.10 Maintenance Programs...............................................................................I-112.2.11 Inter-SQUG Communication .....................................................................I-11

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2.3 Compliance with Regulations ..................................................................................I-112.3.1 Backfitting..................................................................................................I-112.3.2 Compliance with Commission Regulations Related

to Seismic Adequacy.................................................................................I-122.3.3 Revision of Plant Licensing Bases.............................................................I-122.3.4 Future Modifications and New and Replacement Equipment ...................I-162.3.5 Quality Assurance and Quality Control .....................................................I-182.3.6 Resolution of USI A-40 and A-17 .............................................................I-19

2.4 Equipment Selection and Verification.....................................................................I-192.4.1 Operability and Redundancy .....................................................................I-192.4.2 Regulatory Guide 1.97 Equipment.............................................................I-202.4.3 Instrumentation and Controls.....................................................................I-20

3 Revisions to the GIP ...................................................................................... I-22

4 References for Part I...................................................................................... I-24

Reasons for Changes to GIP, Part I ...................................................................... I-26

Part II - Generic Procedure for Plant-Specific Implementation

1 Introduction .................................................................................................... 1-1

1.1 Purpose .................................................................................................................... 1-1

1.2 Background............................................................................................................... 1-1

1.3 Approach................................................................................................................... 1-21.3.1 Seismic Evaluation Personnel..................................................................... 1-41.3.2 Identification of Safe Shutdown Equipment ............................................... 1-41.3.3 Screening Verification and Walkdown ....................................................... 1-61.3.4 Outlier Identification and Resolution.......................................................... 1-61.3.5 Relay Functionality Review........................................................................ 1-71.3.6 Tanks and Heat Exchangers Review........................................................... 1-71.3.7 Cable and Conduit Raceway Review.......................................................... 1-81.3.8 Documentation............................................................................................ 1-8

Reasons for Changes to GIP, Part II, Section 1 ................................................................. 1-9

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2 Seismic Evaluation Personnel ....................................................................... 2-1

2.0 Introduction............................................................................................................... 2-1

2.1 SQUG Commitments................................................................................................ 2-22.1.1 Systems Engineers ...................................................................................... 2-22.1.2 Seismic Capability Engineers ..................................................................... 2-22.1.3 Lead Relay Reviewer.................................................................................. 2-3

2.2 Systems Engineers .................................................................................................... 2-3

2.3 Plant Operations Personnel....................................................................................... 2-4

2.4 Seismic Capability Engineers ................................................................................... 2-5

2.5 Relay Evaluation Personnel...................................................................................... 2-72.5.1 Lead Relay Reviewer.................................................................................. 2-72.5.2 Assistant Relay Reviewer ........................................................................... 2-82.5.3 Systems Personnel....................................................................................... 2-82.5.4 Plant Maintenance Representative.............................................................. 2-82.5.5 Seismic Capability Engineers ..................................................................... 2-8

2.6 SQUG Training Courses ........................................................................................... 2-9

Reasons for Changes to GIP, Part II, Section 2 ............................................................... 2-10

3 Identification of Safe Shutdown Equipment ................................................. 3-1

3.0 Introduction............................................................................................................... 3-1

3.1 SQUG Commitments................................................................................................ 3-33.1.1 Identification of Safe Shutdown Path ......................................................... 3-33.1.2 Assumptions Used in Identifying Safe Shutdown Path .............................. 3-3

3.2 General Criteria and Governing Assumptions.......................................................... 3-53.2.1 Safe Shutdown Following an SSE .............................................................. 3-53.2.2 Normal Operating Conditions Defined ....................................................... 3-53.2.3 Safe Shutdown Defined .............................................................................. 3-53.2.4 Loss of OffSite Power................................................................................. 3-63.2.5 No Other Accidents..................................................................................... 3-63.2.6 Single Equipment Failure............................................................................ 3-73.2.7 Operator Action Permitted.......................................................................... 3-83.2.8 Procedures................................................................................................... 3-8

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3.3 Scope of Equipment.................................................................................................. 3-93.3.1 Equipment Classes ...................................................................................... 3-93.3.2 Exclusion of NSSS Equipment ................................................................. 3-143.3.3 Rule of the Box ......................................................................................... 3-143.3.4 Active Equipment ..................................................................................... 3-153.3.5 Inherently Rugged Equipment .................................................................. 3-163.3.6 Equipment in Supporting Systems............................................................ 3-173.3.7 Equipment Subject to Relay Chatter......................................................... 3-173.3.8 Instrumentation ......................................................................................... 3-183.3.9 Non-Safety-Grade Equipment .................................................................. 3-213.3.10 Tanks and Heat Exchangers...................................................................... 3-213.3.11 Cable and Conduit Raceways ................................................................... 3-22

3.4 Safe Shutdown Functions ....................................................................................... 3-223.4.1 Reactor Reactivity Control Function ........................................................ 3-233.4.2 Reactor Coolant Pressure Control Function ............................................. 3-233.4.3 Reactor Coolant Inventory Control Function ........................................... 3-243.4.4 Decay Heat Removal Function ................................................................. 3-25

3.5 Safe Shutdown Alternatives.................................................................................... 3-253.5.1 Reactor Reactivity Control Function (PWR)............................................ 3-273.5.2 Reactor Coolant Pressure Control (PWR) ................................................ 3-273.5.3 Reactor Coolant Inventory Control (PWR) .............................................. 3-283.5.4 Decay Heat Removal (PWR).................................................................... 3-293.5.5 Reactor Reactivity Control (BWR)........................................................... 3-293.5.6 Reactor Coolant Pressure Control (BWR)................................................ 3-303.5.7 Reactor Coolant Inventory Control (BWR).............................................. 3-303.5.8 Decay Heat Removal (BWR).................................................................... 3-31

3.6 Identification of Equipment .................................................................................... 3-323.6.1 Identification of Fluid System Equipment ................................................ 3-333.6.2 Identification of Supporting System Equipment....................................... 3-343.6.3 Preparation of Safe Shutdown Equipment List (SSEL) for

Seismic Evaluation.................................................................................... 3-353.6.4 Preliminary Walkdown to Locate and Identify Equipment for

Seismic Evaluation.................................................................................... 3-353.6.5 Preparation of Safe Shutdown Equipment List (SSEL) for

Relay Evaluation ...................................................................................... 3-373.6.6 Database Management System ................................................................. 3-37

3.7 Operations Department Review of SSEL ............................................................... 3-38

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3.8 Documentation........................................................................................................ 3-39

Reasons for Changes to GIP, Part II, Section 3 ............................................................... 3-41

4 Screening Verification and Walkdown .......................................................... 4-1

4.0 Introduction............................................................................................................... 4-1

4.1 SQUG Commitments................................................................................................ 4-54.1.1 Basic Criteria............................................................................................... 4-54.1.2 Determination of Seismic Capacity ............................................................ 4-64.1.3 Use of Caveats ............................................................................................ 4-64.1.4 Anchorage Verification............................................................................... 4-64.1.5 Seismic Interaction...................................................................................... 4-74.1.6 Documentation............................................................................................ 4-7

4.2 Seismic Capacity Compared to Seismic Demand..................................................... 4-74.2.1 Seismic Capacity Based on Earthquake Experience Data ........................ 4-104.2.2 Seismic Capacity Based on Generic Seismic Testing Data ...................... 4-124.2.3 Comparison of Seismic Capacity to Ground Response Spectra

(Method A in Table 4-1) ........................................................................... 4-134.2.4 Comparison of Seismic Capacity to Seismic Demand Based on

In-Structure Response Spectra (Method B in Table 4-1).......................... 4-17

4.3 Equipment Class Similarity and Caveats................................................................ 4-23

4.4 Anchorage Adequacy.............................................................................................. 4-254.4.1 Anchorage Installation Inspection ............................................................ 4-274.4.2 Anchorage Capacity Determination.......................................................... 4-474.4.3 Seismic Demand Determination ............................................................... 4-484.4.4 Comparison of Capacity to Demand......................................................... 4-56

4.5 Seismic Interaction ................................................................................................. 4-56

4.6 Documentation........................................................................................................ 4-57

Reasons for Changes to GIP, Part II, Section 4 ............................................................... 4-66

5 Outlier Identification and Reduction ............................................................. 5-1

5.0 Introduction............................................................................................................... 5-1

5.1 SQUG Commitments................................................................................................ 5-25.1.1 Identification of Outliers............................................................................. 5-25.1.2 Resolution of Outliers ................................................................................. 5-2

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5.2 Outlier Identification................................................................................................. 5-3

5.3 Outlier Resolution..................................................................................................... 5-5

5.4 Methods for Grouping and Pooling of Outliers ........................................................ 5-7

Reasons for Changes to GIP, Part II, Section 5 ............................................................... 5-11

6 Relay Functionality Review ........................................................................... 6-1

6.0 Introduction............................................................................................................... 6-1

6.1 SQUG Commitments................................................................................................ 6-26.1.1 Identification of Relays To Be Evaluated................................................... 6-26.1.2 Evaluation of Consequences of Relay Malfunction.................................... 6-36.1.3 Assessment of Relay Seismic Adequacy .................................................... 6-36.1.4 Relay Walkdown......................................................................................... 6-4

6.2 Relay Evaluation Methodology ................................................................................ 6-4

6.3 Identification of Essential Relays ............................................................................. 6-56.3.1 USI A-46 Safe Shutdown Criteria and Assumptions.................................. 6-56.3.2 Identification of Safe Shutdown Equipment ............................................... 6-96.3.3 Identification of Circuits, Relays, Consequences of Relay Malfunction.... 6-9

6.4 Comparison of Relay Seismic Capacity to Seismic Demand ................................. 6-116.4.1 Seismic Capacity of Relays....................................................................... 6-126.4.2 Seismic Capacity Compared to Seismic Demand..................................... 6-15

6.5 Relay Walkdown..................................................................................................... 6-21

6.6 Outliers.................................................................................................................... 6-22

6.7 Documentation of Results....................................................................................... 6-23

Reasons for Changes to GIP, Part II, Section 6 ............................................................... 6-25

7 Tanks and Heat Exchangers Review ............................................................. 7-1

7.0 Introduction............................................................................................................... 7-1

7.1 SQUG Commitments................................................................................................ 7-27.1.1 Scope of Equipment .................................................................................... 7-27.1.2 Evaluation Methodology............................................................................. 7-27.1.3 Documentation............................................................................................ 7-2

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7.2 Evaluation Methodology........................................................................................... 7-3

7.3 Vertical Tanks........................................................................................................... 7-57.3.1 Scope of Vertical Tanks.............................................................................. 7-57.3.2 Seismic Demand Applied to Vertical Tanks............................................... 7-67.3.3 Overturning Moment Capacity Calculation.............................................. 7-10

7.3.3.1 Bolt Tensile Capacity .................................................................. 7-117.3.3.2 Anchorage Connection Capacity................................................. 7-127.3.3.3 Tank Shell Buckling Capacity..................................................... 7-167.3.3.4 Overturning Moment Capacity.................................................... 7-18

7.3.4 Shear Load Capacity vs. Demand............................................................. 7-207.3.5 Freeboard Clearance vs. Slosh Height ...................................................... 7-217.3.6 Attached Piping Flexibility ....................................................................... 7-227.3.7 Tank Foundation ....................................................................................... 7-23

7.4 Horizontal Tanks..................................................................................................... 7-427.4.1 Scope of Horizontal Tanks........................................................................ 7-427.4.2 Seismic Demand/Capacity of Horizontal Tanks....................................... 7-42

7.5 Outliers.................................................................................................................... 7-56

7.6 Documentation........................................................................................................ 7-57

Reasons for Changes to GIP, Part II, Section 7 ............................................................... 7-58

8 Cable and Conduit Raceway Review ............................................................. 8-1

8.0 Introduction............................................................................................................... 8-1

8.1 SQUG Commitments................................................................................................ 8-48.1.1 Walkdown of Cable and Conduit Raceways .............................................. 8-58.1.2 Limited Analytical Review ......................................................................... 8-58.1.3 Documentation............................................................................................ 8-5

8.2 Walkdown Guidelines............................................................................................... 8-58.2.1 General Walkdown Procedure.................................................................... 8-68.2.2 Inclusion Rules............................................................................................ 8-98.2.3 Other Seismic Performance Concerns ...................................................... 8-108.2.4 Selection of Sample for Limited Analytical Review ................................ 8-138.2.5 Seismic Interaction.................................................................................... 8-14

8.3 Limited Analytical Review Guidelines................................................................... 8-148.3.1 Dead Load Check...................................................................................... 8-188.3.2 Vertical Capacity Check ........................................................................... 8-19

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8.3.3 Ductility Check ......................................................................................... 8-218.3.4 Lateral Load Check................................................................................... 8-238.3.5 Rod Hanger Fatigue Evaluations .............................................................. 8-268.3.6 Floor-to-Ceiling Support Evaluations....................................................... 8-298.3.7 Base-Mounted Support Evaluations.......................................................... 8-308.3.8 Allowable Capacities ................................................................................ 8-318.3.9 Raceway System Weights......................................................................... 8-33

8.4 Outliers.................................................................................................................... 8-348.4.1 Cable Tray Span........................................................................................ 8-358.4.2 Conduit Span............................................................................................. 8-358.4.3 Raceway Member Tie-Downs................................................................... 8-358.4.4 Channel Nuts............................................................................................. 8-358.4.5 Rigid Boot Connection.............................................................................. 8-368.4.6 Beam Clamps ............................................................................................ 8-368.4.7 Cast-Iron Anchor Embedments................................................................. 8-368.4.8 Analytical Outliers .................................................................................... 8-36

8.5 Documentation........................................................................................................ 8-40

Reasons for Changes to GIP, Part II, Section 8 ............................................................... 8-60

9 Documentation .............................................................................................. 9-1

9.0 Introduction............................................................................................................... 9-1

9.1 SQUG Commitments................................................................................................ 9-4

9.2 SSEL Report ............................................................................................................. 9-6

9.3 Relay Evaluation Report........................................................................................... 9-7

9.4 Seismic Evaluation Report........................................................................................ 9-9

9.5 Completion Letter................................................................................................... 9-11

Reasons for Changes to GIP, Part II, Section 9 ............................................................... 9-12

10 References ................................................................................................... 10-1

Reasons for Changes to GIP, Part II, Section 10 ............................................................. 10-5

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Appendices

Appendix A Procedure for Identification of Safe Shutdown Equipment .......... A-i

Appendix B Summary of Equipment Class Descriptions and Caveats ............ B-i

Appendix C Anchorage Data ............................................................................. C-i

Appendix D Seismic Interaction ........................................................................ D-i

Appendix E Preparatory Work Prior to Walkdown............................................ E-i

Appendix F Screening Walkdown Plan..............................................................F-i

Appendix G Screening Evaluation Work Sheets (SEWS)..................................G-i

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Revision Status

Rev. No. Pages Affected Date

0 Initial Issue of GIP 6/3/88

1 All pages revised except the following:

• Part II, Section 8, Appendices A, B• Part III

12/23/88

2 All pages revised 9/21/90

2, Correctedon 2/28/91

Front Matter: ii, iii, iv, v, ix, x, xv, xiii, xvi

Part IISection 4: 4-7, 4-25, 4-26, 4-29 thru 4-38, 4-41, 4-43 thru 4-50,4-63

Section 6: 6-1, 6-16 thru 6-27

Section 10: 10-1 thru 10-3

Appendix A: A-ii, A-49

Appendix B: B.1-6 thru B.1-8, B.2-2 thru B.2-7, B.3-3 thruB.3-8, B.4-3 thru B.4-7, B.7-10, B.8-6 thru B.8-8, B.8-10, B.8-11,B.14-5, B.14-6

Appendix C: C-ii, C-iii, C.2-2 thru C.2-6, C.2-8 thru C.2-28,C.3-3 thru C.3-14, C.4-2 thru C.4-6, C.5-2, C.6-2 thru C.6-4

Appendix D: D-4, D-7, D-8

Appendix G:

SEWS Class 1: Sheet 2

SEWS Class 2: Sheet 1, 2

SEWS Class 3: Sheet 1, 2

SEWS Class 4: Sheet 1, 2

SEWS Class 8A: Sheet 2

SEWS Class 8B: Sheet 2

SEWS Class 14: Sheet 2

2/28/91

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Rev. No. Pages Affected Date

2, Correctedon 6/28/91

Front Matter: ii, iii, iv, v, vi, vii, viii, ix, x, xi, xiv, xv, xvi, xvii,xviii

Part I – All pages

Part IISection 1: 1-2 thru 1-10

Section 2: 2-3, 2-5, 2-6, 2-7

Section 3: 3-1 thru 3-3, 3-5, 3-6, 3-8 thru 3-47

Section 4: 4-1, 4-3 thru 4-70

Section 5: 5-2 thru 5-11

Section 6: 6-4 thru 6-19, 6-21 thru 6-27

Section 7: All pages

Section 8: All pages

Section 9: All pages

Section 10: All pages

Appendix A: A-33, A35

Appendix B: All pages

Appendix C: C-iii, C-1, C.1-1 thru C.1-4, C.2-2, C.2-11, C.2-12,C.2-13, C.2-24, C.3-2, C.6-3 thru C.6-4

Appendix D: D-2

Appendix E: E-1, E-2, E-4

Appendix F: F-2

Appendix G: All pages except G-i

6/28/91

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Rev. No. Pages Affected Date

2, Correctedon 2/14/92

Front Matter: i, ii, xiv.i

Part I: 2, 8, 9, 12, 13, 15, 16, 25, 26

Part IISection 1: 1-6, 1-7

Section 4: 4-17, 4-18, 4-23, 4-53

Section 5: 5-1

Section 6: 6-13, 6-14, 6-16, 6-25

Section 7: 7-67, 7-68

Section 8: 8-2, 8-4, 8-34, 8-39, 8-40, 8-43

2/14/92

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Rev. No. Pages Affected Date

3 [4]Front Matter: i, ii, iii, x, xiii, xiv, xiv.i, xv, xvi, xix, xx, xxi,xxii, xxiii, xxiv, xxv

Part I: 1, 3, 4, 6, 10, 22, 24, 26

Part IISection 1: 1-10

Section 3: 3-2, 3-12, 3-16 thru 3-18, 3-26, 3-40

Section 4: 4-19, 4-20, 4-22, 4-27, 4-29, 4-33, 4-38, 4-53, 4-54,4-65,

Section 5: 5-8

Section 6: 6-1, 6-17, 6-18, 6-20, 6-21

Section 7: 7-17, 7-54

Section 8: 8-28, 8-32, 8-39, 8-61 thru 8-65

Section 9: 9-3, 9-6, 9-11, 9-12

Section 10: All pages

Appendix A: A-38,

Appendix B: B-ii, B.1-2, B.1-3, B.1-5, B.2-2, B.5-1, B.6-2, B.7-2,B.7-4, B.8A-1 thru B.8A-9, B.8B-1 thru B.8B-8, B.17-3, B.18-6,

Appendix C: C-2, C.1-1, C.2-3, C.2-4, C.2-7, C.2-14 thru C.2-17,C.2-20, C.3-9, C.3-11, C.3-13, C.3-14,

Appendix E: E-4

Appendix G: G-ii, G.1-1, G.1-2, G.2-1, G.2-2, G.3-1, G-3-2,G.4-1, G.4-2, G.5-1, G.6-1, G.7-1, G.8A-1, G.8A-2, G.8B-1,G.8B-2, G.9-1, G.10-1, G.11-1, G.12-1, G.13-1, G.14-1, G.14-2,G.15-1, G.15-2, G.16-1, G.16-2, G.17-1, G.18-1, G.18-2, G.19-1,G.20-1, G.20-2

7/31/95

3, Updatedon 5/16/97

[4]Front Matter: i, ii, iii, xix, xxi, xxii, xxiii

Part I: 1, 3, 24, 26

Part IISection 8: 8-32, 8-61 thru 8-65

Section 10: 10-3

Appendix B: B.7-2, B.8A-2, B.8B-1

Appendix C: C.2-3, C.2-4

5/16/97

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Rev. No. Pages Affected Date

3A [4]All pages revised. The changes include those to address theNRC Staff clarifications, interpretations, exceptions, and issuesfrom their review of GIP-2 (SSER No. 2), GIP-3 (SSER No. 3),plant-specific implementation of the USI A-46 program, and theNARE Guidelines. Editorial and typographical changes were alsomade to incorporate lessons learned from using the GIP.

12/21/01

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Acknowledgements

This document is the product of a team effort by many different organizations and individuals.Listed below are those which made significant contributions to the development of the guidelinesand criteria contained herein.

The [1]companies that were members of SQUG when the GIP was first developed and newermembers are listed below. In those cases where the company that owns the SQUG plant haschanged, the new company name is included in parentheses. Companies not currently membersof SQUG are denoted by an asterisk (*).

Alabama Power Co. (Southern Nuclear OperatingCo.)

American Electric Power Co., Inc.Arkansas Power & Light Co. (Entergy Nuclear

South)Baltimore Gas & Electric Co. (Calvert Cliffs

Nuclear Power Plant, Inc.)Boston Edison Co. (Entergy Nuclear Northeast)Carolina Power & Light Co. (CP&L A Progress

Energy Co.)CEA [France]Central Nuclear de Almaraz [Spain]Commonwealth Edison Co. (Exelon Nuclear)Consolidated Edison Company of New York, Inc.

(Entergy Nuclear Northeast)Consumers Power Co. (Consumers Energy –

Nuclear Management Co.)Detroit Edison Company*Duke Power CompanyDuquesne Light Co. (First Energy Corp. – Beaver

Valley)Electrabel Tractebel, S.A. [Belgium]ElectricitJ de France [France]ENEL ctn (NIRA)* [Italy]Florida Power Corp. (FPC A Progress Energy Co.)Forsmarks Kraftgrupp AB [Sweden]Georgia Power Co. (Southern Nuclear Operating

Co.)GPU Nuclear Corp. (AmerGen Energy Co.)Iowa Electric Light & Power Co. (Alliant Energy –

Nuclear Management Co.)Korea Electric Power Research Institute [Korea]Magnox Electric [UK]Maine Yankee Atomic Power Co.*Nebraska Public Power District

New York Power Authority (Entergy NuclearNortheast)

Niagara Mohawk Power Corp. (ConstellationNuclear)

Northeast Utilities (Dominion NuclearConnecticut, Inc.)

Northern States Power Co. – Nuclear ManagementCo.

Nuclear Electric PLC [UK] (British EnergyGeneration)

Nuclenor, S.A. [Spain]OKG AB [Sweden]Omaha Public Power DistrictPennsylvania Power & Light Co.*Philadelphia Electric Co.* (Exelon Nuclear)Portland General Electric Co.*Public Service Company of Colorado*Public Service Electric & Gas Co. (PSEG Nuclear)Rochester Gas & Electric Corp.Sacramento Municipal Utility District*Siemens AG/KWU [Germany]Southern California Edison Co.*Tennessee Valley AuthorityToledo Edison Co. (First Energy Corp.-Davis

Besse)Vattenfall AB, Ringhals [Sweden]Vermont Yankee Nuclear Power Corp. (Entergy

Nuclear Northeast)Virginia Power (Dominion Generation)Westinghouse Savannah River Co.*Wisconsin Electric Power Co. – Nuclear

Management Co.Wisconsin Public Service Corp. – Nuclear

Management Co.Yankee Atomic Electric Co.*

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The SQUG Steering Group and the Electric Power Research Institute (EPRI) have provided theoverall direction and supervision of the development of the guidelines and criteria contained inthis document. The [1]individuals who have served or are serving in this capacity are listedbelow. Those individuals no longer serving are denoted by an asterisk (*).

Richard Cutsinger, Tennessee Valley AuthorityHarv Hanneman, Wisconsin Electric Power Co.*Abdy Khanpour, CP&L A Progress Energy Co.William Metevia, Maine Yankee Atomic Power Co.*Donald Moore, Southern CompanyDennis Ostrom, Southern California Edison Co.*John Richards (SQUG Chairman), Duke Power Co.Jey Sekaran, American Electric PowerNeil Smith (former SQUG Chairman), Commonwealth Edison Co. (Exelon Nuclear)*Jim Thomas, Duke Power Co.*Robert Kassawara (Project Manager), EPRIRichard Schaffstall (SQUG Administrative Coordinator), EPRI*William Schmidt (SQUG Technical Coordinator), MPR Associates, Inc.*

The [1]companies under contract to SQUG and EPRI and the [1]individuals currently andpreviously employed by these organizations who made significant contributions to thedevelopment of the guidelines and criteria in this document are listed below. Individuals notcurrently employed by the company listed are denoted by an asterisk (*).

ABS Consulting (formerly EQEInternational)

Paul BaughmanSteve EderGreg HardySteve HarrisNancy Horstman*Gayle JohnsonJames Johnson*Paul Smith*Sam SwanPeter Yanev*

ANCO EngineersKelly Merz*

MPR Associates, Inc.Kelley Baker*Jess Betlack*William Schmidt*Richard Starck

Southern CompanyDonald Moore

Stevenson & AssociatesWalter DjordjevicJohn Stevenson*Gary Thomas

URS Corporation / John A. Blume &Associates, Engineers

Martin CzarneckiDilip Jhaveri*

Winston & StrawnJohn MacEvoy*Malcolm Philips*Bill Shields*

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The Senior Seismic Review and Advisory Panel (SSRAP) served as an expert advisory panel tothe NRC and SQUG during the development of the guidelines and criteria contained in thisdocument. Their contributions and advice are greatly appreciated. The individuals who servedon this panel are listed below.

Paul Ibanez, ANCO Engineers, Inc.Robert P. Kennedy (Chairman), RPK--Structural Mechanics ConsultingWalter A. von Riesemann, Sandia National LaboratoriesAnshel J. Schiff, Stanford UniversityLoring A. Wyllie, Jr., H. J. Degenkolb Associates, Engineers

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Glossary of Terms

AC - Alternating CurrentADS - Automatic Depressurization SystemAF - Amplification FactorAFW - Auxiliary FeedwaterARS - Amplified Response SpectraASME - American Society of Mechanical EngineersB&PV - Boiler and Pressure VesselBWR - Boiling Water ReactorCCW - Component Cooling WaterCRD - Control Rod DriveCST - Condensate Storage TankCVCS - Chemical and Volume Control SystemDC - Direct CurrentDG - Diesel GeneratorDH - Decay HeatEE - Earthquake ExperienceEPRI - Electric Power Research InstituteESW - Emergency Service WaterFRS - Floor Response SpectrumFS - Factor of SafetyFSAR - Final Safety Analysis ReportFWCI - Feedwater Coolant InjectionGERS - Generic Equipment Ruggedness SpectraGIP - Generic Implementation ProcedureGRS - Ground Response SpectraHCLPF - High Confidence, Low Probability of FailureHELB - High Energy Line BreakHPCI - High Pressure Coolant InjectionHPCS - High Pressure Core SprayHVAC - Heating Ventilating and Air ConditioningHX - Heat ExchangerIRS - In-structure Response SpectrumLOCA - Loss of Coolant AccidentLPCI - Low Pressure Coolant InjectionLPCS - Low Pressure Core SprayMCC - Motor Control CenterMS - Main SteamMSIV - Main Steam Isolation ValveNEP - Non-Exceedance ProbabilityNPSH - Net Positive Suction HeadNRC - Nuclear Regulatory Commission

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NSSS - Nuclear Steam Supply SystemOSVS - Outlier Seismic Verification SheetP&ID - Piping and Instrumentation DiagramPGA - Peak Ground AccelerationPORV - Power-Operated Relief ValvePWR - Pressurized Water ReactorRBCCW - Reactor Building Closed Cooling WaterRC - Reactor CoolantRCIC - Reactor Core Isolation CoolingRCS - Reactor Coolant SystemRTD - Resistance Temperature DetectorRHR - Residual Heat RemovalRHRS - Residual Heat Removal SystemRWC - Reactor Water CleanupRWST - Refueling Water Storage TankSAV - Specified Acceleration ValueSC - Shutdown CoolingSCE - Seismic Capability EngineerSEWS - Screening Evaluation Work SheetsSLC - Standby Liquid ControlSQUG - Seismic Qualification Utility GroupSRP - Standard Review PlanSRT - Seismic Review TeamSRV - Safety Relief ValveSSE - Safe Shutdown EarthquakeSSEL - Safe Shutdown Equipment ListSSRAP - Senior Seismic Review and Advisory PanelSVDS - Screening Verification Data SheetSW - Service WaterUSI - Unresolved Safety IssueZPA - Zero Period AccelerationZPGA - Zero Period Ground Acceleration

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C.3-7C.3-8C.3-9C.3-10C.3-11C.4-1C.4-2C.4-3C.4-4C.4-5C.4-6C.5-1C.5-2C.5-3C.6-1C.6-2C.6-3C.6-4C(reasons)-1D.iD.iiD-1D-2D-3D-4D-5D-6D-7D-8E-iE- iiE-1E-2E-3E-4E-5F-iF-iiF-1F-2F-3F-4F-5G-iG-iiG-1G-2G.0-1G.0-2G.1-1G.1-2G.1-3G.2-1G.2-2G.2-3G.3-1G.3-2G.3-3

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Reasons for Changes to GIP, Front Matter

Listed below are the specific reasons for making the changes marked with a vertical line in the

margin of this front matter to create GIP-3A from GIP-3, Updated 5/16/97. The endnote

numbers listed below correspond to the bracketed numbers (e.g., [1]) located in the text of this

front matter where the changes are made.

1 Update of company and personnel names.2 The list of companies that prepared the GIP was rearranged in alphabetical order.3 Preface added to explain the reasons and bases for the changes made in going from GIP-3, Updated 5/16/97 to

GIP-3A.4 Updated list of pages affected by changes to previous revisions of GIP.