ML20054M618

Initial Status Rept Independent Design Review for Shoreham Nuclear Power Station, Technical Rept

ML20054M618
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Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	07/09/1982
From:	TELEDYNE ENGINEERING SERVICES
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References
TR-5633-2, NUDOCS 8207140053
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i l TELEDYNE ENGINEERING SERVICES "RTELEDYNE i CONTROLLED ENGINEERING SERVICES DOCUMENT TES PROJ. NO, [833

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TECHNICAL REPORT i

TR-5633-2 1

1 INITIAL STATUS REPORT i INDEPENDENT DESIGN REVIEW FOR TIIE i SIIOREIIAM NUCLEAR POWER STATION

,i JUI,Y 9,1982 1

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O Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801 6

3 TECHNICAL REPJRT TR -5633-2 3

INITIAL STATUS REPORT INDEPENDENT DESIGN REVIEW FOR THE g

SHOREHAM NUCLEAR POWER STATION O

JULY 9, 1982 g

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.o WTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 O ci7.aco-3350 i

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'RTF1 FrWNE ENGNEERING SERVCES n Technical Report V TR-5633-2 TABLE OF CONTENTS PAGE O

1.0 INTRODUCTION

1 2.0 SCOPE 1 3.0

SUMMARY

AND CONCLUSIONS 2

O 4.0 PROGRAM STATUS 3 4.1 Task 1 - Review Design Process and 3 Procedures 4.2 Task 2 - Review Design Requirements 3 O 4.3 Task 3 - Review As-Built Design Documents 4 4.4 Task 4 - Determine As-Built Plant Configuration 6 4.5 Task 5 - Compare As-Built Documentation 6 to Plant Configuration O 4.6 Task 6 - Review LILC0 and S&W QA/QC/EA 6 Process and Documentation 4.7 Task 7 - Reporting 7 4.8 Task 8 - Project Review Internal Committee 8 O

APPENDIX A Document List APPENDIX B Trip Report for Task 4 APPENDIX C Trip Report for Task 6 O APPENDIX D Engineering Procedure EP-1-017 APPENDIX E Engineering Procedure EP-1-018 APPENDIX F Engineering Procedure EP-1-019 APPENDIX G Engineering Procedure EP-1-020

O APPENDIX H Enginaering Procedure EP-1-021 APPENDIX I Engineering Procedure EP-5-006 APPENDIX J TES Project QA Program

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'W TELEDYNE ENGINEERING SERVCES n Technical Report TR-5633-2

1.0 INTRODUCTION

O Teledyne Engineering Services (TES) has been authorized by Long Island Lighting Company (LILC0) to perform an Independent Design Review of a portion of the Low Pressure Core Spray System at the Shoreham O Nuclear Power Station.

This Initial Status Report describes the progress to date of each of the eight review tasks defined in the Program Plan, submitted to O LILCO, and covers the period from April 29, 1982 to July 9, 1982.

2.0 SCOPE O The Independent Design Review is being performed on one loop of the safety-related, Seismic Category I, Low Pressure Core Spray System (E-21), as indicated by the darkened portion of Figure 1 of TES Report TR-5633-1, " Program Description of Independent Design Review for the O Shoreham Nuclear Station". This scope has been clarified by LILC0 letter to TES of June 8, 1982.

The review program is separated into eight tasks as follows:

O Task 1 -

Review Design Process and Procedures Task 2 - Review Design Requirements Task 3 - Review As-Built Design Documents O Task 4 - Determine As-Built Plant Configuration l

Task 5 - Compare As-Built Documentation to Plant Configuration l Task 6 -

Review LILC0 and S&W QA/QC/EA Process and Documentation Task 7 -

Reporting

O Task 8 -

Project Review Internal Committee

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Technical Report TR-5633-2 3.0 SUPNARY AND CONCLUSIONS q -.

Work efforts on all tasks of the Independent Design Review Program for Shoreham Nuclear Power Station are in different stages of progress as outlined in Subsections 4.1 through 4.8 of this report.

3 Schedule slippage, detailed in Subsection 4.3, in the delivery of as-built design documents, including pipe stress summaries and pipe support calculation packages, to TES from Stone and Webster (S&W) has resulted in D revising the date of issuance of the Final Report to August 25, 1982.

As of this date, nineteen open items have been identified by TES reviewers from the various tasks. These open items are presently under evaluation in the TES internal reporting process. A final disposition has O

not been reached for any of these open items.

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'WTF1 FrVNE ENGINEERING SERVCES n Technical Report O TR-5633-2 4.0 PROGRAM STATUS O

The current status of each task comprising the Independent Design Review Program is as follows:

g 4.1 Task 1-Review Design Process and Procedures This task was initiated during the LILC0/TES/S&W interface meeting at Stone and Webster on May 19, 1982. At that time Mr. Sal O Yerardi of S&W gave a general description of the design process utilized for the LPCS system of the Shoreham Station, including internal and external interfaces.

g In the near future, TES reviewers assigned to this task will meet with S&W personnel to pursue a more detailed review of the design process to assure that its implementation was adhered to. In the interim time the reviewers are perusing the applicable procedures, instructions and methods associated with the design of the LPCS system.

O It is estimated that this task is 30% complete.

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O 4.2 Task 2 - Review Design Requirements This task involves a review of the adequacy of the design requirements as they apply to the piping, supports, pipe and floor lO mounted equipment and containment penetration of the LPCS system. The applicable General Electric (GE) and S&W specifications, standards and l

procedures are currently being reviewed for compliance with Code, FSAR

and NRC requirements committed to in the FSAR. This task is l

lO approximately 30% complete.

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'RTF1 FrWNE ENGINEERING SERVCES Technical Report TR-5633-2 D 4.3 Task 3 - Review As-Built Design Documents The review of as-built design documents which covers piping, supports and selected pipe and floor mounted equipment is being O performed in accordance with TES Engineering Procedure EP-1-018.

As of this date five of the seven as-built pipe stress summaries of the LPCS system, East Lead, have been deliverd to TES. The O remaining two summaries, AX-8K and AX-10A are scheduled for transmittal on July 9, 1982. Review of the five pipe stress summary packages is in process, and is approximately 50% complete.

O The as-built pipe support calculation packages, including drawings, for model AX-ll, have been delivered to TES. The packages for models AX-8K, -10A, -10B and -10D are scheduled for a July 15, 1982 transmittal. Models AX-8AA and -10G do not have any pipe supports.

O This portion of the Task 3 review is essentially on hold pending delivery of the pipe support calculation packages for the four pipe stress summary models.

O TES has received SQRT documentation packages for eleven items of mechanical or electrical equipment from S&W. Documentation for one equipment item, core spray pump and motor (Mark No. 1E21 P-0138) will be transmitted to TES at a future date.

O This equipment has been selected by LILC0 to be included in the Independent Design Review.

O Four equipment items are undergoing a full design review, while the remaining eight items are being reviewed for satisfaction of interface l requirements only. This equipment review is in process and is l

approximately 25% complete.

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'#PTELEDYNE ENGINEERING SERVICES Technical Report 3 TR-5633-2 The following listing of the selected equipment items indicates the 3

level of review being performed.

LIST OF SAFETY-RELATED COMPONENTS

) CORE SPRAY -LOOP B Mark No. Description Type of Review 1E21 P-0138 CS PUMPS & MOTORS INTERFACE 1E21 PIS-098B PRESS INDIC SWITCH (E21P019) INTERFACE lE21 PS-013B PRESSURE SWITCH INTERFACE 1E21*PS-0128 PRESSURE SWITCH FULL 3

lE21*P-0498 LOOP LEVEL PUMPS FULL 1E21*MOV-031B MOTOR OPERATED VALVE INTERFACE 1E21*MOV-033B MOTOR OPERATED VALVE INTERFACE lE21*MOV-034B MOTOR OPERATED VALVE INTERFACE D

• lE21 MOV-035B MOTOR OPERATED VALVE FULL lE21 RV-0968 RELIEF VALVE INTERFACE 1E21 RV-0928 RELIEF VALVE FULL D

lE21 RV-093B RELIEF VALVE INTERFACE D

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'RTF1 FrWNE ENGINEERING SERVICES o Technical Report V TR-5633-2 4.4 Task 4 - Determine As-Built Plant Configuration O

A field walkdown of the LPCS system has bene complete'd. This work was performd in accordance wtih TES Engineering Procedure EP-5-006.

Trip Report No.1474 describing this work activity is included as Appendix 0 B of this report.

The pipe support drawings for four piping models (AX-8K, -10A, -

108 and 100) used by the TES Field Team as part of their task are to the O latest revision; however, since they are not 'as-built' drawings, a future visit by the Field Team may be necessary in order to verify the as-built condition for these pipe supports.

O 4.5 Task 5 - Compare As-Built Documentation to Plant Configuration The as-built configuration obtained by the TES Field Team in Task 4 is currently being compared to the submitted documentation of O Task 3. The Task 3 packages represent revisions resulting from nonconformance and dispositioning reports (N&D) and engineering and design coordination reports (E&DCR). This allows the reviewer to determine if changes and interfaces have been properly implemented in the design lO process. This task is approximately 30% complete.

4.6 Task 6 -

Review LILC0 QA and S&W QA/QC/EA Process and l Documentation M

V The QA sampling review of field welds is currently in process.

The TES QA review team is performing this portion of Task 6 at the Shoreham i field site, and in accordance with TES Engineering Procedure EP-1-021. Trip lO Report No. 1480, in Appendix C, describes this review activity for the week of June 21, 1982. This review is now approximately 70% complete.

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'RTF1 FrWNE ENGINEERING SERVICES Technical Report 0 TR-5633-2 The TES review of LILC0 QA audit findings, schedules,

.O implementation and follow-up on corrective action related to activities at S&W, will commence during the week of July 19, 1982 at the LILC0 offices in Hicksville, New York.

O The TES review of S&W QA and EA audit findings schedules, implementation and follow-up on corrective action related to activities on the LPCS system at Shoreham, will commence during the week of July 26, 1982 at the Stone and Webster offices in Boston.

O 4.7 Task 7- Reporting The following definitions are being used by TES reviewers in O reporting to the Project Manager /QA Manager on their review efforts.

(a) Open Item (TES Internal) - An item requiring further review or more information before a decision can be reached. An

.O Open Item can become a Potentiai Finding, an Observation or a Closed Item but cannot remain an Open Item in the TES Final Report.

l O (b) Closed Item - An Open Item which after further review can be l closed.

(c) Potential Finding (TES Internal) - An item which 'the O reviewer and TES Project Manager feel could have an impact

( on the adequacy of the design or QA process. All Potential Findings will be submitted to the Project Review Internal Committee for disposition. A Potential Finding can become a

,0 Finding, or an Observation but cannot remain a Potential Finding in the TES Final Report.

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'R TF1pnYNE ENGNEERING SERVCES O Technical Report TR-5633-2 (d) Finding -

An item which the Project Review Internal O Committee has reviewed and has determined impacts the adequacy of the design or QA process.

(e) Observation - An item that does not impact the adequacy of O the design or QA process but has significance relative to conservatism, design practice or applicable procedures.

At the present time there are nineteen open items which are under O evaluation in the TES internal reporting process. A final dispositon has not been reached for any of these open items.

4.8 Task 8 - Project Review Internal Comittee O

The TES Project Review Internal Committee is involved in reviewing any potential findings of the review team, in accordance with Engineering Procedure EP-1-019.

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'#PTELEDYNE ENGINEERING SERVICES Technical Report O TR-5633-2 O

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APPENDIX A O DOCUMENT LIST i

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'RTELEDYNE ENGINEERING SERVICES Technical Report 5633-2 Appendix A

-Al-LILCO MANUALS J

1. Safety Evaluation Report (SER) for Shoreham Nuclear Power Station, Unit No. 1, NUREG-0420, Docket No. 50-322, April 1981

2. Supplement No. I to SER, NUREG -0420 Supplement No.1, September 1981

3. Supplement No. 2 to SER, NUREG-0420 Supplement No. 2, February 1982

4. LILC0 Quality Assurance Manual, Revision 14, 12/01/81

5. LILC0 Quality Assurance Procedures, 4/9/81

6. LILC0 Project Manual for Shoreham Nuclear Power Station, Unit No. I 12/21/81

7. Shoreham Plant Design Assessment Report, Volumes 1 and 2 G.E. DESIGN DOCUMENTS

8. G.E. Document No. 22A1435 Rev. 1, Core Spray System Design Specification, 4/10/79

9. G.E. Document No.22A1435 Rev. 2, Core Spray System Design Specification Data Sheet, 12/30/76

10. G.E. Document No. 22A4250AF Rev. O, Core Spray Nozzle Safe End and Welded Thermal Sleeve Design Specification Data Sheet, 7/26/76 D

STONE & WEBSTER SPECIFICATIONS

11. SH1-68 Design & Fabrication of Nuclear Power Plant Piping

) Supports, Rev. 2, December 14, 1981.

12. SH1-171 Piping Engineering & Design, Rev. 1, May 1, 1980

13. SH1-158B Furnishing & Installation of Thermal Insulation-Outside Primary Containment, Rev. 1, October 27, 1980 D 14. SH1-157 Furnishing & Installation of Thermal Insulation-Inside Primary Containment, Rev. 1, September 25, 1981

15. SH1-24 Shop Fabricated Piping, Rev. 3, August 19, 1981

16. SH1-75 Shop Fabricated & Field Erection of Reactor Containment J Steel Plate Liner, Revision 4, March 3, 1982.

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'A'TF1 Frh'NE ENGINEERING SERVICES O Technical Report 5633-2 Appendix A

-A2-0 17. SH1-180V Carbon Steel Valves 2 " &' Larger, Revision 1, July 23, 1981

18. SH1-232 Special Check Valves, Revision 1, September 23, 1980

19. SH1-253 Motor Operated Carbon Steel Valves, 2h" & Smaller, O Revision 1, January 21, 1982 '

20. SH1-88V Motor.0perated Carbon Steel Valves, 2h" &. Larger, Rev. 1, November 16, 1981

21. SH1-88AD Motor-0perated Carbon Steel Valves, 2 " & Larger, Rev. 1, O October 29, 1981

22. SH1-056 Field Fabrication & Erection of Piping, Rev. 3, October 27, 1980

23. SH1-171 E & DCR's that Effect Specification SH1-171, P-3931A, P-0 3962, P-3962A, P-39628, P-3965, P-3965A, P-3966, P-3966A, P-39668, P-3880A, P-3887A

24. E & DCR'P-3887B

25. E & DCR P-3965B O 26. System Description rore Spray System, Rev. O, November 20, 1975

27. Final Safety Analysis Report (FSAR)

28. Quality Assurance & Control Manual-ASME Section III,~ Book No. 22 as .

O defined by Table of Contents dated February 4, 1982

29. Quality Assurance Manual as defined by Index Issue 82-2

30. Pipe Stress, Pipe Support, & Duct Support Criteria Document for the Shoreham Nuclear Power Station, dated December 1981, including O Revision.1 dated May 1982.

31. Stone & Webster Shoreham Project Procedures Manual Project General i

Instructions 4/15/82

32. Engineering Assurance Division Procured Services Group Surveys &

O Audits for 1980, 1981 & 1982, EA-516

33. Engineering Assurance Audit Schedules for Project Audit Nos. 32, ,

33, 34, 35, 36, 37, 38, 39, & 40 0

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34. Engineering Assurance Audit Schedule, Site Engineering Office Audit

) Nos. 9, 10, 11, 12 &l3.

35. Q.A. Cost & Auditing Division Audit Schedule -Third Quarter 1980

36. Audit Agenda for Shoreham Site Audit Nos. 33, 34, 35, 36, 37, 38, 39, 40 & 41

] 37. Suppression Pool ARS Curves, dated February 28, 1978

38. Reactor Building ARS Curves, dated March 1973 ,

STONE & WEBSTER STRESS CALCULATION PACKAGES s

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39. Problem AX-8AA-3

40. Problem AX~10G

41. Problem AX-11A-2 '

) 42. Problem AX-108

43. Problem AX-100 e .-

STONE & WEBSTER SQRT DOCUMENTATION PACKAGES  :-

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44. SQRT-88AD-1: 1E21 MOV-035AB ,

45. SQRT-88AD-3: 1E21 MOV-031AB

46. SQRT-88V-3: 1E21 MOV-034AB 3- 47. SQRT-88V-13: 1E21 M0V-033AB

48. SQRT-191-1: 1E21 RV-092,'093, 096 1E2Ihd

49. SQRT-235-1:

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50. SQRT E21N008B: ,

U 1' 01:'i3 -

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3 51. SQRT E21N009B: ll3AB

52. SQRT E21N00108: 1E21 h d 8AB 3

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Appendix A

-A4-1 2 STONE & WEBSTER PIPE SUPPORT CALCULATIONS U#'. 5 3'. 1E21-PSST-053-5 Piping Supports dated 61/82 s 54~.- 1E21-PSSH-054-2 Piping Supports dated 6/2/82 55.' IE21-PSR-057-3 Piping Supports dated 6/2/82

56. 1E21-PSST-058-8 Piping Supports dated 6/1/82 3 .

STONE & WEBSTER CALCULATIONS

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57. 11600.02 -

EMD-NPB-129-X5 " Seismic Displacement Mode by Mode

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Contribution", dated September 17, 1979

58. 11600.02-NP(B)-202 (Calc. Excerpt) T-Quencher ARS Curves

59. 11600.02-NP(B)-202 (Calc. Excerpt) AP ARS Curves

60. 11600.02-NP(B)-261-FA-0, "Waterhammer Analysis fe- RHR Containment Spray System g

61. 11600.02-NP(B)-126-F1A, "Waterhammer Analysis for Minimum Flow Bypass Line of the HPCI System" 62 11600.02-NP(B)-360-FA-0 "Waterhammer Analysis for Core Spray System due to Flow in Empty Line.

63. 11600.02-NP(B)-120-F1A "Waterhammer Analysis for the Test Line of the Core Spray System.

64. 11600.02-NP(B)-124-F1A Waterhammer Analysis for the RHR System

65. 11600.02-NP(B)-79-F1A " Core Spray Prob. 100 & 101 Waterhammer 3

STONE & WEBSTER DRAWINGS

66. Owg. # 11600.02-FM23A Core Spray System Boundaries D 67. OWG. # 11600.02-FV-1E-10 Primary Containment Penetration

68. DWG. # 11600.02-PV-1H-9 Primary Containment Penetration

69. DWG. # 11600.02-FV-1J-7 Primary Containment Penetration

70. DWG. # 11600.02-FV-1L-8 Primary Containment Penetration D 71. DWG. # 11600.02-3.14-61D Primary Containment Penetration

72. DWG. # 11600.02-3.14-62B Primary Containment Penetration

73. DWG. # 11600.02-3.14-63C Primary Containment Penetration l 74. DWG, # 11600.02-3.14-105B Primary Containment Penetration

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-O Appendix A

-AS-1

75. DWG. # 11600.02-5.18-66E Reactor Vessel Drawings

~O 76. DWG. # 11600.02-5.18-67E Reactor Vessel Drawings-

77. DWG. # 11600.02-5.17-5A Reactor Vessel Drawings- .,

78. DWG. # 11600.02. 16-10 Reactor Vessel Drawings

79. 'DWG. # 11600.02.15-36C Reactor Vessel Drawings

O 80. DWG. # 11600.02-FM-23-10 Flow Diagrams & Piping Drawings

81. DWG. # 11600.02-FP-10A-8 Flow Diagrams & Piping Drawings

82. DWG. # 11600.02-FP-108-9 Flow Diagrams & Piping Drawings

83. 9WG. # 11600.02-FP-10C-8 Flow Diagrams & Piping Drawings lQ. 84. DWG. # 11600.02-FP-100-7 Flow Diagrams & Piping Drawings

85. DWG. # 11600.02-FP-10E-8 Flow Diagrams & Piping Drawings 4 86. DWG. # 11600.02-FP-10F-7 Flow Diagrams & Piping Drawings

87. DWG # P1005-5 Small Bore Isometric Drawings O 88. DWG # P1006-3 Small Bore Isometric Drawings

89. DWG # P1008-6 Small Bore Isometric Drawings

90. DWG # P1011-5 Small Bore Isometric Drawings 3

l' 91. DWG # P1012-6 Small Bore Isometric' Drawings iO 92. DWG # P1053-8 Small Bore Isometric Drawings

93. DWG # P1054-7 Small Bore Isometric Drawings 94 DWG # P1056-4 Small Bore-Isometric Drawings j 95. DWG # P1083-3 Small Bore Isometric Drawings lO 96. 1E11 RHR Issue 7 System Line Designation Table

97. 1E21 Core Spray Issue 6 System Line Designation Table

98. 1E41 HPCI Issue 10 System Line Designation Table

99. Flow Dim; ram Color Coded & Work Sketches Relating AX-

O 8K,8AA,10A, 108, 100, 10G, & 11A to the Total Spray System.

100, 1E21 PSST-053-6 Pipe Support Drawings 101, 1E21 PSSH-054-5 Pipe Support Drawings I- 102. 1E21 PSST-058-8 Pipe Support Drawings 0 103. DWG. # 11600.02-BZ-108-20-5 (1E21-PSR-057) Pipe Support Drawing 104. DWG. # E2821 IC 7 As-Built Isometric 105. DWG. # E2821 IC 56 As-Built Isometric 106. DWG. # E2821 IC 2 As-Built Isometric lO i

J "RTELEDYNE ENGNEERING SERVICES 3 Technical Report TR-5633-2 J

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APPENDIX B 3 TRIP REPORT FOR TASK 4 DETERMINE AS-BUILT PLANT CONFIGURATION 4

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'RTELEDYNE ENGINEERING SERVICES TRIP REPORT 1474 g

PROJECT 5633 VISIT TO SHOREHAM NUCLEAR POWER STATION O

JUNE 14-18, 1982 Monday morning, June 14, 1982, Teledyne Employees, E.A. Solla, L.E.

g Barron, and E.K. Woods, arrived at the SNPS site and were met by Gene Montgomery of LILCO. The purpose of this trip was to perform Task 4 of the TES Program Plan, Determination ~f o the "As-Built" Plant Configuration. We had a kick off meeting after we arrived. Present at the meeting were Gene Montgomery, Craig Seamen, and Mike Milligan from O

LILCO, and Ken Butler, and Eric 0'Brien from Stone and Webster. We informed Gene that we needed all the support drawings and associated E&DCR's to perform our walkdown. He expressed concern about getting all the drawings in time since he was given no advance notice. Gene also O

informed us that the wetwell would be inaccessible since it was filled with water.

g After the meeting we began our walkdown. We started with ISO IC-64 inside the drywell. Ken Butler and Eric 0'Brien accompanied us on the I

walkdown. We had brought along a twenty foot tape, a fifty foot tape, a six foot wood ruler, and a plumb bob to aid us in taking field measurements. To record our field measurements, we brought with us a O

! set of TES undimensioned isometric drawings of the Low Pressure Core Spray System. A camera was also brought along to document support j configuration, valve orientation, and other areas of interest.

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! Starting at the Reactor Nozzle and working toward the Containment t

l Penetration we procceded to document the field configuration of the Low Pressure Core Spray System. Dimensions were taken between the reactor vessel n z 1, valves, pipe whip restraints, supports, tangent point of lO I elbows, penetrations, and all other attachments on the pipe. Dimensions l

to welded seams were sometimes taken for ease of measurement. All dimensions were taken by two people separately and recorded on the lO

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'RTA AWNE ENGNEERING SERVICES g Trip Report 1474 Project 5633 isometric with each dimension initialed by both. Possible clearance O problems were also checked for. All springs were checked for size settings, and clearances around and below the clamps. None of the springs had the scale divisions labeled so the approximate setting was taken. Snubbers were checked for size, setting, load rating, and pin to O pin dimension. There are only two snubbers on this system. On one support the snubbers were missing and work was currently being done on the support. Rigid supports were checked for clearance and direction.

All supports were checked for general support configuration. There was O only one pipe whip restraint and this was checked for location and clearance. All support data was recorded on a separate sheet for each support and the sheet was initialed by two people. Two photographs were taken of all supports. Where there were attachments - to the pipe the O locations were recorded and photographs taken. Small bore piping was dimensioned to the first support off the pipe except for the two small bore lines we had IS0S for. The name plate data was recorded for all valves. The length and orientation of the valve was recorded, and O photographs were taken.

On Monday we finished most of the work inside of the drywell. We requested that insulation be removed from several areas. These areas O were around the penetration, around support locations, and around the .

valve next to the reactor nozzle. We then started war down by the core spray pump.

O On Tuesday we continued work outside the drywell. After lunch we received the support drawings for the drywell and were informed that the-insulation had been removed. We finished all piping inside the drywell Tuesday and continued work outside the drywell.

O On Wednesday morning we traced the small bore IS0's which Eric Woods had picked up at Stone and Webster on Friday, June 11. We also requested four more IS0's that were still missing. In the afternoon we

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'RTELEDYNE ENGINEERING SERVICES Trip Report 1474 O Project 5633 received the support packages, the associated E&DCR's, and IS0's IC-56 g and IC-7. Wednesday night Eric 0'Brien was relieved by Richard.Kenyon.

On Thursday morning we reviewed the support packages and redrew the two IS0's received Wednesday. We received a tracing of ISO IC-2 and g informed LILC0 that the fourth 150 was no longer necessary. We checked supports on all pipe already walked down and then continued to walk pipe.

O On Friday morning we finished our walkdown about 10:30. We had a close out meeting at 11:00. Present were Gene Montgomery, Eric 0'Brien, and Ken Butler. Gene asked us if we had any problems such as inaccessible areas or outstanding information. We told him that no new g . problems came up. He also reviewed the procedure with us to insure that we covered everything. He also questioned us about the four pieces of equipment that are included in the review . After the meeting we went back out to the plant to take a final look at those four pieces of lQ equipment.

We left the site Friday af ternoon and flew back to Boston Friday Evening.

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! Eric A. Solla, Project Engineer O M S bmswnG Leo E. Barron, Engineer k b. k/#M Eric K. Woods, Engineering Assistant O

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APPENDIX C C TRIP REPORT FOR TASK 6 QA SAMPLING REVIEW O

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o "RTF1 mYNE ENGINEERING SERVICES TRIP REPORT NO. 1480 0

PROJECT 5633 VISIT TO LILCO, SHOREHAM NUCLEAR STATION O

JUNE 22 thru 25, 1982 PURPOSE TES QA review of SWEC construction activities as a part of Task 6 of the program description of Independent Design Review for the Shoreham Nuclear Station.

g' This Interim Report is furniso ed to report progress on performance of Task 6 and will be superseded by the report issued on completion of the review (Task 6).

PRE REVIEW MEETING A meeting was conducted at Shoreham at 11:00 AM June 22, 1982; Attendees are listed as follows:

TES:

J.H. Malonson QAE - Team Leader S.D. Levine QAE - Reviewer J.J. Ondzes QAE - Reviewer LILC0 J.M. Kelly- Field QA Mgr.

n R.E. Glazier Field QA Engr.

SWEC T.T. Arrington Supt. Field QC R.T. Perra ,st. Supt. Field QC

,) Courter B.G. Gelfand QA Administrative Supr.

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"#eTri prT(NE ENGINEERING SERVCES Trip Report 1480 0, Project 5633 The TES Team Leader identified himself and S.D. Levine, as lead g auditors, presently qualified per ANSI N45.2.23, and J.J. Ondzes as a TES QAE trainee.

The purpose and scope of the review were discussed, as well as the O necessity for the independence of TES personnel in the review activities.

It was explained that the TES report of findings, observations or 9 open items would not be discussed with LILCO, SWEC, or Courter personnel during the course of the review and would not be presented for discussion at an exit meeting upon completion of the review.

g Mr. Kelly provided a description of the LILC0 organization, and construction activity, and an explanation of the type and availability of the record packages.

O R.E. Glazier was assigned to retrieve the record packages and submit them to TES reviewers.

l It was agreed that during performance of the review some discussion O might be necessary to explain or clarify details, characteristics, or other items encountered in the review. Mr. Kelly stated that he would I

perform as the principal interface and that he.would participate in the j discussion when required.

O TES Engineering Procedure EP-1-021 QA Review Sampling Procedure was presented and discussed to obtain a common understanding of the method and characteristics to be applied to the review.

O lO L

O "WTELEDYNE ENGINEERING SERVCES O Trip Report 1480 Project 5633 O TES ACTIVITY As-built piping isometric drawings were marked for the selection of weld locations to be reviewed.

O A work sheet form was prepared to provide identification of material, procedures, personnel qualifications, certificates or other information required for the task. (Sample Attached)

O Fif teen (15) pipe weld and four (4) attachment weld packages were received for the characteristics as applicable. TES review of all packages received is not yet completed.

It is estimated that this part of Task 6 is 30% complete.

O J.H Malonson, QAE 6/30/82 JHM/ao O

O O

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'RTELEDYNE ENGINEERING SERVCES O Trip Report 1480 Project 5633 l

TES REVIEW WORKSHEET O

PROB # AX- ISO f WELD NO. FW a Name (Sym)_ Function Co. Date O

O b Material P.O. TyEe_ Heat Lot or Batch #

O c Procedure # Process Co. Date O

d NCR's O

e Receiving Insp. Records O

f Material Certs.

O g NDE Records O

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'WTF1 prf(NE ENGINEERING SERVICES Technical Report

! TR-5633-2 O

g O

APPENDIX D O ENGINEERING PROCEDURE EP-1-017 O

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ENGINEERING PROCEDURE h EP-1-017 3 TELEDYNE ENGINEERING SERVICES PROGRAM PLAN FOR INDEPENDENT DESIGN REVIEW 0F SHOREHAM NUCLEAR POWER STATION LPCS SYSTEM J

REVISION O PROJECT 5633 9

June 8, 1982 9

8 Prepared by: h m_ Date d-I" S Approved by: * "b $ Date 6 /( 5[6 z.

Project Manager

/ -.

Reviewed by: f} qg,co Date / [8 Quality Assurance [

WTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE O WALTHAM, MASSACHUSETTS 02254 617-890-3350 l

e

"#TF1 irrWNE ENGINEERING SERVICES ENG4NEERING PROCEDURE e

TLE: EP _1-017  %

REV. .O REV.

TES PROGRAM PLAN FOR INDEPENDENT DESIGN ORIG. g L.q-88.0 RIG.~

ENG. AS. p/11/2 ENG. TS. __

m REVIEW OF SHOREHAM NUCLEAR P0'rER STATION

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LPCS SYSTEM Q. A. cCS 6NAQ.A.

PROJ. MGR. W -' PROJ. MGR.

DATE DATE ta)4t?%

DESCRIPTION REV.

g SECTION 1.0 SCOPE l 1.1 This Engineering Procedure provides the method to be used by Teledyne Engineering Services (TES) in performing the Shoreham 3 Nuclear Power Station LPCS System Independent Design Review Program under Project 5633.

2.0 APPLICATION 2.1 Details Enclosure (1) to this procedure contains the Program Plan for the Independent Design Review, including:

a) Criteria b) Personnel responsibilities 2.2 References a) Project QA Program, Project No. 5633 b) EP-5-006, " Method of Determination of As-Built

, Configuration of Low Pressure Core Spray System at J Shoreham Nuclear Power Station" c) EP-1-018, " Method of Review of As-Built Design Documents for the LPCS System at the Shoreham Nuclear Power Station" it ) I P-1 -019, " Procedure for Project Review Internal x.) Committee Shoreham Nuclear Power Station Independent Desiqn Review l

e) EP-1-020, " Procedure for Reviewing and Reporting by TES 10CFR Part 21 Conmittee Shoreham Nuclear Power Station Independent Design Review".

~

f) EP-1-021 "QA Sampling Inspection Procedure Shoreham Nuclear Power Station Independent Design Review".

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2/81 1

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"#TCl FrWNE ENGINEERING SERVICES m ENGINEERING PROCEDURE v

PAGE-TITLE: EP 017 2 REV. O REV.

TES PROGRAM PLAN FOR INDEPENDENT DESIGN ORIG. U RC. L t # 1 ORIG.

ENG. AS. #AaC ENG. AS.

O REVIEW OF SHOREHAM NUCLEAR POWER STATION LPCS SYSTEM Q. A. CCJ (M/p> Q.A.

PR0j. MGR. T)FL PROJ. MGR.

DATE ug/Fg DATE r r DESCRIPTION REV.

O SECTION 3.0 METHOD j 3.1 Independent Design Review Program O 3.1.1 Section 1.0 of Enclosure (1) describes the Independent Design Review Program Scope, including:

a) Specific system to be reviewed b) Exclusion of items and areas from review O

3.1.2 The objective of the Independent Design Review Program conducted by TES is to determine the adequacy of the design process as it relates to Normal and Upset service loadings of a specific system. That system is the LPCS System, as shown n darkened in Figure 1 of Enclosure (1), and as clarified by V LILC0 letter to TES of 6-8-82.

It is anticipated that this type of review would result in i conclusions that are applicable to all work performed by the l organizations subject to the review.

10 3.1.3 The Independent Design Review Program includes eight tasks.

I Section 3.0 of Enclosure (1) describes the tasks in detail.

3.2 Project Organization l Section 4.0 of Enclosure (1) describes the TES project organi-lO zation.

1 i 3.3 TES Technical Efforts h.

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a "RTELEDYNE ENGINEERING SERVICES ENGINEERING PROCEDURE V

PAGE 3 TITLE: EP 017 REV. .D REV.

TES PROGRAM PLAN FOR INDEPENDENT DESIGN ORIG. 'UML L4730 RIG. -

REVIEW 0F SHOREHAM NUCLEAR POWER STATION ENG. AS.//MF ENG. AS.

O" LPCS SYSTEM Q.A. 4d Q.A. ~

PROJ. i s. PROJ. MGR.

DATE (.f4t h DATE DESCRIPTION REV.

O SECTION 3.3.1 In general, TES will not perform any detailed analyses to arrive at conclusions. Review of existing analyses performed V by the organizations involved will be sufficient and, further, will provide better insight as to the design of other plant systems for which they were responsible. Any calculations or analysis performed by TES and used to substantiate a TES conclusion shall be subject to the checking, verification and design control requirements of the TES QA Manual.

O 3.4 TES Reporting 3.4.1 Section 3.8 of Enclosure (1) describes the TES reporting of the results of this project. This is Task 7 of the Program Plan.

O Task 8 of the Independent Design Review Program Plan of Enclo-3.4.2 sure (1) describes the Project Review Internal Committee.

This committee will assess the impact of any potential findings on the overall design adequacy of the LPCS System.

g 4.0 RECORDS All records shall be controlled in accordance with the PQAP.

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017 PAGE y i;i c. EP REV. .0 REV.

TES PROGRAM PLAN FOR INDEPENDENT ORIG. pp 6-3 'diORIG.

DESIGN REVIEW 0F ENG.AS.///JOJ) ENG. AS.

O SHOREHAM NUCLEAR POWER STATION LPCS SYSTEM Q. A. (df 6////p2 Q.A.

PROJ. MGR. % PROJ. MGR.

DATE W41tb DATE REV.

O SECTION DESCRIPTION I

O ENCLOSURE (1) TO EP-1-017 O

TES PROGRAM PLAN FOR THE SHOREHAM NUCLEAR POWER STATION LPCS SYSTEM n" INDEPENDENT DESIGN REVIEW l

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W TELEDVNE ENGINEERING SERVICES Enclosure (1)

) EP-1-017

1.0 INTRODUCTION

) Teledyne Engineering Services, at the request of the Long Island Lighting Company (LILCO), is performing an Independent Design Review at the Shoreham Nuclear Power Station. The design review is limited to the LPCS system shown darkened in Figure 1, for Normal and Upset Service

) levels. This enclosure provides the Program Plan to be utilized by TES in performing this review.

2.0 PROGRAMPLANOUTLig D

2.1 General The final result of this independent review is to determine

) the adequacy of the design process as it relates to the Shoreham Nuclear Power Station. It is anticipated that this type of review would result in conclusions that are applicable to all work performed by the organizations subject to the review. In general, the reviewer will not

]

perform any detailed analyses to arrive at conclusions. Review of existing analyses performed by the organizations involved will be sufficient and further, will provide better insight as to the design of other plant systems for which they were responsible. This does not preclude the reviewer from performing any calculations and analyses that 3

are deemed necessary. Any calculations or analysis performed by TES and used to substantiate a TES conclusion shall be subject to the checking, verification and design control requirements of the TES QA Manual.

D The generation of dynamic spectra and the validation of computer programs utilized by the organizations involved are specifically excluded from review. The reviewer will accept dynamic spectra for the buildings involved as presented and will only assure that their application to the system is appropriate. It is assumed that any computer program used has already been subjected to proper validation and verification procedures.

D J

e WTELEDYNE ENGINEERING SERVICES Enclosure (1) EP-1-017

/

2.2 Plan Outline .

1 Essentially the' reviewer will start with the final design package which is presented as being representative of the as-built sjstem. From this point the reviewer will work back through the design process to the initial design assuring that interface control (internal

~

md external) was applied.

The program is separated into eight tasks as follows:

Task 1 - Review Design Process and Procedures Task 2 - Review Design Requirements Task 3 - Review As-Built Design Documents Task 4 - Determine As-Built Plant Configuration 3

Task 5 - Compare As-Built Documentation to Plant Configurat. ion and S&W QA/QC/EA Process and

. Task 6 - Review LILCO QA Documentation fask / - Reporting Task 8 - Project Review Internal Committee 3.0 PROGRAM PLAN IMPLEMENTATION a.I General The following sections discuss the detailed implementation of oh task outlined in Section 2.0 above. It is anticipated that some i .L ' will proceed in parallel while implementation of others will be dependent on completion of associated tasks. Terminology is used in the q

O

'eTELEDYNE ENGNEERNG SERVCES O

Enclosure (1)

EP-1-017 O following task descriptions that may not be particular to S&W and/or LILCO. However, the intent is to define scope and method, and terminology can be revised .to suit the particular organizations involved.

O 3.2 Task 1 - Review Design Process and Procedures The reviewer will meet with S&W to determine what process is g

used in taking design requirements and developing construction drawings.

Further, the process of developing revisions to the design will be re-viewed. Interfaces between internal organizations will be determined in n following the process of:

v a) specification of design requirements b) development of preliminary design O c) piping ar alysis d) support location and selection e) support analysis O f) effect on building structure i

g) equipment loading requirements h) development of construction drawings i) revisions to design O

i Interfaces between external organizations will be determined in following the process of:

'O l

a) transmittal of information to the external organization b) review of procedures

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"$W M ENGNEERNG SEFMCES D

Enclosure (1)

EP-1-017 D c) review of design d) transmittal of developed information to vendor organi-zations. (i.e., loads on building structure, etc.)

3 e) dealing with Field Change Requests (FCR), or the equivalent f) dealing with Engineering Change Notices (ECN) or the equivalent g) dealing with nonconformance and associated corrective action Procedures, instructions and methods associated with J

developing the design of the LPCS system will be made available to the reviewer. The reviewer must become f amiliar with these procedures to assure that implementation was adhered to by the design organizations.

O 3.3 Task 2 - Review Design Requirements The adequacy of the design requirements as delineated in the S General Electric (GE) and S&W LPCS system specifications, standards and procedures will be reviewed for compliance with FSAR commitments and NRC requirements. This review will include piping, supports, pipe and floor mounted equipment and containment penetration.

9 The documents subject to review will be determined in Task 1.

3 J

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'WTF1 STY (NE ENGNEERING SERVICES U Enclosure (1)

EP-1-017 3.4 Task 3 - Review As-Built Design Documents O The as-built documentation supplied by S&W will be reviewed to determine compliance with FSAR and Design Specification commitments. A detailed review of the Design Specification will be performed in Task 2 since that document forms the basis for the design approach. The review

O of as-built design documents will cover the piping, supports, and selected pipe or floor mounted mechanical and electrical components.

- Mechanical and electrical components that have previously received third-party review by S&W or G.E. to current NRC (SQRT) guidelines will O be reviewed for satisfaction of interface requirements only. This work will be performed in accordance with Engineering Procedure EP-1-018,

" Method of Review of As-Built Design Documents for the LPCS System at the Shoreham Nuclear Power Station."

O 3.5 Task 4 - Determine As-Built Plant Configuration A field walkdown of the system will be performed. This walkdown will develop the geometry of the as-built piping, supports and O,.

equipment mounting for all accessible locations. Clearances at any penetrations, pipe whip restraints or other structures or components will be determined. A copy of the as-built isometric will be made (preferably traced) by TES. The TES isometric will not include dimensions or support locations. This work will be performed in accordance with Engineering Procedure EP-5-006, " Method of Determination of As-Built Configuration of the LPCS System at Shoreham Nuclear Power

,s Station."

V 3.6 Task 5 - Compare As-Built Documentation to Plant Configuration The reviewer will obtain from LILC0 or S&W the as-built O documentation which is specified to be representative of the plant configuration. The as-built configuration obtained in Task 4 will be compared with the submitted documentation.

O

a SPTF1 ET?(NE ENGNEERING SERVCES O Enclosure (1)

EP-1-017 3 The as-built documentation used in this task is the same package that will be used in the detailed review of Task 3. This package should represent revisions resulting from ECN's, FCR's and any applicable corrective action for nonconformance and therefore will allow g TES to review the process of the design back to initiation; and determine if changes and interfaces were implemented properly in the design process.

g 3.7 Task 6 - Review LILCO QA and S&W QA/QC/EA Process and Documentation The reviewer will obtain LILC0 QA audit findings related to g activities at S&W. The specific activities cited will be reviewed to determine if corrective action was taken and if LILC0 audit personnel assured that this occurred. Audit schedules and implementation will also be reviewed.

O With respect to S&W activities the following review will be performed on a sample basis, in accordance with Engineering Procedure EP-1-021, "QA Sampling Inspection Procedure".

a. training and qualification records of construction

.O personr.el

b. identification and control of material, parts and components

c. control of special processes lO d. non-conformance and dispositioning report process

e. receiving inspection records

! f. material certification records

g. NDE records l,

p/ Additionally, the reviewer will obtain S&W QA and EA audit findings related to activities on the LPCS system at Shoreham. Schedule l

l implementation and follow-up on corrective action will be reviewed.

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'eTELEDYNE ENGINEERING SERVCES 3

Enclosure (1)

EP-1-017 3 This activity will be performed by the Project QA Engineer who will report directly to the Manager, Quality Assurance, for this task and in his role as QA Engineer <on this project.

D 3.8 Task 7 - Reportir.g Reporting of TES review team members will comply with the fol-lowing.

O 3.8.1 Definitions The following definitions are to be used by TES review 3 team members in preparing reports to the Project Manager on their review work.

a) Open Item (TES Internal) - An item requiring

] further review or more information before a decision can be reached. An Open Item can become a Potential Finding, an Observation or a Closed Item but cannot remain an Open Item in the TES Final O Report.

b) Closed Item - An Open Item which after further review can be closed.

O c) Potential Finding (TES Internal) - An item which the reviewer and TES Project Manager feel could have an impact on the adequacy of the design or QA process. All Potential Findings will be submitted O to the Project Revie ' Internal Committee for disposition. A Potential Finding can become a Finding, or an Observation but cannot remain a  ;

Potential Finding in the TES Final Report. (

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o

'R Ts1FnYNE ENGINEERING SERVICES o

Enclosure (1)

EP-1-017 O d) Finding - An item which the Project Review Internal Committee has reviewed and has determined impacts the adequacy'of the design or QA process.

e) Observation - An item that does not impact the g

adequacy of the design or QA process but has significance relative to conservatism, design practice or applicable procedures.

O 3.8.2 Reporting Process The following process of reporting will be adhered to by the TES review team members.

n a) Items will be submitted to the Project Manager in v

writing using the Reviewer Report Form (RRF). The definitions of Section 3.8.1 will be used in classifying the item by the reviewer. The original of this form will be forwarded to the TES Project g

Manager. Additional information regarding an item required by a reviewer will be obtained by means of l a Request for Information Form (RFI).

O b) The Project Manager will review the RRF and i complete a Project Manager Resolution Form (PMR).

l The PMR must be signed by the TES reviewer who initiated the RRF to indicate his agreement with

!O the resolution. The original RRF and PMR will be maintained as QA records. If the item is classified as a Potential Finding, or if resolution j

of the item cannot be reached by the Project O Manager, or if the TES reviewer does not agree with the resolution, the RRF and PMR will be forwarded l

to the Project Review Internal Committee for resolution.

O

)

W TELEDYNE ENGNHiRNG SERVICES J Enclosure (1)

EP-1-017 c) The Project Review Internal Comittee will review

) the RRF and PMR and develop a position on the consequence of the item as it relates to the adequacy of' ihe design or QA process. The Internal Committee will present this position by completing

) an Internal Comittee Resolution (ICR) form, a copy of which requires signature by two of the three members of the comittee. A copy of the ICR will be submitted to the Project Manager and the TES 3 reviewer. The original ICR will be attached to the original RRF and PMR and will be maintained as QA records.

3 d) The Project Manager shall review the ICR, and may return this report to the comittee if their conclusions do not meet established review criteria. If agreement between the Project Manager 3 and/or the Reviewer and the Internal Comittee cannot be reached the Project Manager will, in writing, request the TES 10CFR Part 21 Comittee to review the issue. Findings of the Internal 3 Comittee accepted by the Project Manager will ce reported to LILCO. LILC0 may propose a plan for remedial action for the Finding, which will be included in the TES Final Report.

e) The TES Part 21 Comittee will review any items forwarded to it in writing by the Project Manager and/or the Reviewer in accordance with Engineering Procedure EP-1-020, " Procedure for Reviewing and Reporting by TES 10CFR Part 21 Comitte Shoreham Nuclear Power Station Independent Design Review".

Reporting will be directly to LILC0 and the NRC in accordance with the Engineering Procedure EP-1-020.

D 1

3

'#PTriFrVNE ENGNEERNG SERVICES O

Enclosure (1)

EP-1-017 0 3.8.3 Report Submittal TES will submit reports to LILC0 and the NRC O concurrently. The following schedule for submittal is provided and assumes receipt of required information on a timely basis.

Findings - within three working days of O determination by TES Initial Status Report - June 30, 1982

' Final Report - August 11, 1982 v

a) Findings will be transmitted to LILC0 in letter form with copies of the RRF, PMR, and ICR corresponding to that Finding.

g b) The Initial Status Report will outline the progress to that date of the review. Any Findings which have been submitted by letter report to LILCO will O be included in this report. Reported Findings which LILC0 has responded to with a remedial action plan will be so noted, and the plan will be included in the TES report. Areas which have been O reviewed and are still under discussion by the review team or Internal Committee will be noted.

c) The Final Report will contain all Findings, including an assessment of extent, evaluation of O safety impact and appropriate recommendations.

Observations will be reported including an 1

assessment of why they are not Findings. Closed Items will not be included in the Final Report.

_O

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"RTA FrWNE ENGNEERNG SERV!CES

)

Enclosure ('.)

EP-1-017 )

d) TES will maintain as Project QA records all items reported by TES reviewers with associated resolu-tions. These will be available for review by LILC0

)

or the NRC.

3.9 Task 8 - Project Review Internal Committee

)

TES will form .an Internal Committee whose responsibility will be to review all Potential Findings of the review team, in accordance with Engineering Procedure EP-1-019. This review will include the definition and accuracy of any findings and assess the impact of the

) Geporting by the finding on the design and QA process adequacy.

Internal Committee will be in accordance with Task 7.

)

)

)

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e "WTFipnYNE ENG!NEERING SERVCES Enclosure (1)

EP-1-017 3 4.0 PROJECT STAFFING 4.1 Project Review Team This Independent Design Review will be under the general 3 direction of Mr. Donald F. Landers, Senior Vice-President. The Assistant Project Manager will be Mr. James P. King who is authorized to perform all functions of the Project Manager in Mr. Landers absence.

TES will provide staffing to this project as required to complete the

) effort outlined. Figure 2 provides the Project Review Team senior staffing members by Tasks.

In order to qualify as an independent reviewer for the design verification program at Shoreham, all personnel assigned will sign a

') statement regarding potential or apparent conflicts of interest. These statements shall be retained by the TES Personnel Relations Manager. A copy of this statement format is presented herein.

m 4.2 Project Review Internal Committee This committee approach is currently used by TES for projects that involve state.of-the-art engineering. TES forms a committee in such cases composed of senior level personnel who have the necessary D expertise to resolve technical issues presented by the particular project under review. The committee members for this project are shown in Figure 3.

4.3 TES 10CFR Part 21 Committee l~ The TES 10CFR Part 21 committee will be utilized in this project as a means of final review, as described in Engineering Procedure EP-1-020. The Committee will only consider items where agreement between the Project Manager and/or Reviewer and the Project

~.>

Review Internal Committee cannot be reached. The resolution by the committee is final. Reporting will be directly to LILC0 and the NRC in accordance with EP-1-020.

O

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e "RTELEDYNE ENGINEERING SERVICES p

Enclosure (1)

EP-1-017 D D

J 0. F. Landers Senior Vice-President J. P. King

] Assistant Project Manager D Tasks 1, 2 & 3 Tasks 4 & 5 Task 6 R. D. Ilookway J. P. King J. H. Malonson R. A. Enos E. A. Solla PQAE V. M. Chauhan D

3 Figure 2 TES Project Review Team Senior Staffing D

0

)

"RTF1 PTWNE ENGINEERING SERVCES 3

O G. Moy, Chairman

-]

G. E. O'Connor G. A. Carpenter 3

Figure 3 Project Review Internal Committee O

D g

O O

O

J

'#PTB FD(NE ENGINEERING SERVCES 3

Enclosure (1) EP-1-017 3

Independent Design Review J Shoreham Nuclear Power Station Reviewer Report Form RRF No.

3 5633-Reviewer Name: Date:

Classification of Item (Per 3.8.1):

3 Reference Documents:

O Description of Item:

O O

O

-O

O SPTA WNE ENGNEERING SERVICES Enclosure (1) g EP-1-017 Independent Design Review 0 Shoreham Nuclear Power Station Project Manager Resolution Form PMR No.

g 5633-Reference RRF No. 5633- Date:

i g Descrirtion of Resolution:

O

,0 O

O Classification of Item after Resolution:

l lO Reviewer Signature Project Manager signature g

l 1 - - _ .

o SPTA AWNE ENGNEERING SERVCES Enclosure (1) O EP-1-017 Independent Design Review Shoreham Nuclear Power Station O Internal Comittee Resolution Form ICR No.

5633-

Reference:

RRF No. 5633- Date:

PMR No. 5633-Internal Comittee Resolution of Potential Finding: ,

O o

O O

Classification of Item after Comittee Resolution:

O Comittee Chairms Signature Project Manager Signature O Comittee Member Signature Comittee Member Signature

O O O O O O O O O U U WTELIDfhE SfGMBajGSSMCES Enclosure (1) EP-1-017 Independent Design Review Shoreham Nuclear Power Station - LPCS System Review log RRF Reviewer Proj. Mgr. ICR Rev. Com.

Item No. Description No. Category PMR No. Category No. Category Final Resolution 4

O SPTFI WNE ENGNEERNG SERVICES O Enclosure (1)

EP-1-017 INFORMATION REQUEST O

SHOREHAM INDEPENDENT DESIGN REVIEW PROJECT: 5633 O REVIEWER: DATE: T0: S&Wl l CALC.#: REV.: LILCO O SUPT.#: REV.:

DWG. NO.: REV.: RFI: 5633-O DESCRIPTION: PAGE OF O

O REPLY BY: PHONE R TELEC0PY TO FOLLOW l l MAIL M O

l 0

L_] ATTACHMENTS O SIGNATURE DATE O

a "RTri Fr#NE s ENGNEERING SERVK)ES a Enclosure (1)

EP-1-017 Statement Regarding Potential __or Apparent Conflicts of Interest

" Project 5633 To: Teledyne Engineering Services Whereas, the undersigned employee (" Employee") or Contract Engineer

(" Contractor") understands that he or she is being considered as a

'3 participant to provide services to Long Island Lighting Company (LILCO) with respect to the Independent Design Review of the Shoreham Nuclear Power Station; and Whereas, Employee / Contractor understands that it is necessary that n proposed participants be screened for any potential or apparant conflicts of interest with respect to this assignment; Therefore, for the above-stated purposes Employee / Contractor makes the following representations to Teledyne Engineering Services:

n (1) Employee / Contractor has no present or past work experience in

" design, construction or quality assurance of the Shoreham Nuclear Power Station or LILCO.

(2) Neither Employee / Contractor, nor any member of his or her immediate family (parents, spouse, children and granchildren) m shall be employed by Long Island Lighting Co. (LILCO), Stone and Webster Engineering Corp. (S&W) or General Electric Co.

(G.E.).

l (3) Neither Employee / Contractor, nor any members of his or her

! immediate family shall have cumulative ownership interest in g LILCO, S&W or GE which exceeds 5% of their gross family income.

l This statement is based upon the Employee's/ Contractor's best information and belief and any exceptions to the representations contained herein have been described on the reverse side of this O document.

1

'O Dated:

Signature:

i O Print Name

o

'#TF1FrWNE ENGINEERING SERVICES Technical Report O TR-5633-2 O

O

'O O APPENDIX E ENGINEERING PROCEDURE EP-1-018

'O O

O O

I O

9 J

ENGINEERING PROCEDURE EP-1-018 O

METHOD OF REVIEW 0F AS-BUILT DESIGN DOCUMENTS 3 FOR THE LOW PRESSURE CORE SPRAY SYSTEM AT THE SH0REHAM NUCLEAR POWER STATION REVISION O 3

PROJECT 5633 3 JUNE 2, 1982 3

Prepared by: M m Date b"b81 Approved by:

0 M Date b i

g Project Manager

/ .

Reviewed by: h Date /8 M2 QualityAssu[ance /

lO l

WTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE

!O WALTHAM, MASSACHUSETTS 02254 j 617-890-3350

e

"# ETA PTWNE ENGINEERING SERVCES ENGINEERING PROCEDURE D _ -.

PAfE TITLE: EP 018 i REV. _ .0 REV.

METHOD OF REVIEW 0F AS-BUILT DL IGN ORIG. N L.2,38 ORIG.

, DOCUMENTS FOR THE LOW PRESSURE CORE SPRAY ENG. AS. ///p/P ENG. AS.

J SYSTEM AT SH0REHAM NUCLEAR POWER STATION Q . A . <-C5 EN/AQ.A.

PROJ. MGR.'tPL PROJ MGR.

DATE bl4 et_ DATE O SECTION DESCRIPTION REV.

1.0 SCOPE This procedure describes the method to be used in reviewing g

the As-Built Design Documents of LPCS System at Shoreham g' Nuclear Power Station. The purpose of this procedure is to outline the extent of review and the major approaches to be used. This procedure is not intended to be a detailed checklist nor is it intended to limit the reviewer.

2.0 APPLICATION q~

2.1 References a) Project QA Program, Project No. 5633 b) EP-1-017, "TES Project Plan for Independent Design Review of Shoreham Nucler Power Station LPCS System c) EP-5-006, " Method of Determination of As-Built Configuration of LPCS System at Shoreham Nuclear Power Station 3.0 METHOD D

3.1 Design Requirements 3.1.1 A detailed review of FSAR commitments in the area of Design Requirements (Loads, Load Combinations, Operating Conditions, Design Criteria, etc.) will be made.

O' 3.1.2 A detailed review of the Certified Design Specification for the LPCS System will be made to determine if it satisfies Code, FSAR and NRC requirements committed to in the FSAR.

3.1.3 All referenced documents in the Certified Design

3 Specification which are applicable to the scope of this Independent Design Review will also be reviewed for compliance.

O l 1

o

'RTri pnVNE ENGINEERING SERVCES ENGINEERING PROCEDURE g

EP 018 PAQE TITLE:

REV. .O REV.

METHOD OF REVIEW 0F AS-BUILT DESIGN ORIG. T E 6 24% 0 RIG.

O DOCUMENTS FOR THE LOW PRESSURE CORE SPRAY ENG. AS. //#/) ENG. AS.

SYSTEM AT SHOREHAM NUCLEAR POWER STATION Q. A. c65 #/Ar/AQ.A.

PROJ. MGR.TA PROJ. MGR.

.. DATE W4 fr2. DATE O SECTION DESCRIPTION REV.

3.2 Design and Analysis g ! Based upon the Design Requirements, the adequacy of the design and analysis shall be revicwed. For each qualification analysis the reviewer, as a minimum, will verify:

1) the mathematical and/or computer model used O 2) the loadin and load combinations (Normal and Upset Conditions)g ,

3) the use of applicable Codes, Standards, Regulatory Guides,

4) conformance with acceptance criteria, applicable to the O LPCS system.

5) resolution of interface requirements (allowable nozzle loads, accelerations,etc.),

6) resolution of design change and field change requests, and l

7) the final reports and drawings.

3.3 Technical Review of Analysis The technical review will consist of the following O activities as a minimum:

1) Pipe Stress Analysis Review a) Input Data Check (Normal and Upset Conditions)

O o Internal piping pressure o Thermal load cases o System operating modes o Seismic spectra and anchor movements o SRV spectra and anchor movements o Fluid transients and other occasional loads, if ap-plicable O

e "RTri pnYNE ENGINEERING SERVICES ENGINEERING PROCEDURE 3

TITLE: EP 018 PAGf REV. _ 0 _

REV.

METHOD OF REVIEW 0F AS-BUILT DESIGN ORIG. 1FJL 4-2-ft. ORIG.

DOCUMENTS FOR THE LOW PRESSURE CCRE SPRAY ENG. AS. #J//pR ENG. AS.

D SYSTEM AT SHOREHAM NUCLEAR POWER STATION Q. A. CJ 6/442 Q.A.

PROJ. MGR. %~ PROJ. MGR.

DATE q 4I fr2. DATE 3 SECTION DESCRIPTION REV.

b) Piping Model Check o Piping geometry check 3 o Piping section physical and material properties o Support and restraint stiffness, location and orientation o Fittings, nozzles and valves o System boundaries 3 c) Related Calculations o Stress intensification factors and indices o Flow induced transient and steady-state loads (pool drag, impact loads, etc.)

o Valve model natural frequency J o T T T -T o Temperature Load summaries (31(*

sup A ho,rt$, rIs)traints, penetrations, nozzles,etc.)

d) Stress Reports D o Certification o Load cases o Load combinations o Code compliance o Valve requirements O System functional capability D

2) Pipe Support Analysis Review a) Input Data Check o Loads D o load combinations o Support types and location o Deflection calculations o Pipe stresses at welded attachments D

O WTA PTT(NE ENGINEERING SERVICES ENGINEERING PROCEDURE O

PAGg TITLE: EP 018 REV. ~ _0 _

REV.

METHOD OF REVIEW 0F AS-BUILT DESIGN ORIG. U FK,6 M 1 0 RIG.

DOCUMENTS FOR THE LOW PRESSURE CORE SPRAY ENG. AS. ENG. AS.

O SYSTEM AT SHOREHAM NUCLEAR POWER STATION Q. A. cci_ ft/ff Q.A.

PROJ. MGR.E~ PROJ. MGR.

DATE &/4Ms, DATE O SECTION DESCRIPTION REV.

b) Design Calculations C o Member sizing, stiffness, stability o Weld calculations o Stress allowables o Vendor allowables for standard hardware o Computer model geometry, section properties anc meterial properties V, o Expansion bolt load calculations o Baseplate flexibility 3.4 Vendor Qualified Mechanical and Electrical Components n

1) Components that have previously received third-party review v by S&W or GE to current NRC (SQRT) guidelines will be verified for satisfaction of interface requirements (allowable nozzle loads, accelerations, etc.) only. A list l of this equipment must be obtained from LILC0 with

certification that the third-party review has been successfully completed.

O

2) Selected pipe-mounted and floor-mounted mechanical and electrical equipment qualification reports (from above) will be independently reviewed to assure that their mechanical and structural design requirements are satisfied. LILC0 will select the components for review.

g 3.5 Check List I

) This procedure does not limit the reviewer as to scope and l depth of review. However, as a minimum, the check lists of Enclosures 1 and 2 must be completed by the reviewer.

O 4.0 RECORDS l QA Records

'O All records shall be controlled in accordance with the PQAP.

l l

O

'RTF1 FrT(NE ENGINEERING SERVICES ENGINEERING PROCEDURE O

TITLE: EP 018 ^T REV. O REV.

METHOD OF REVIEW 0F AS-BUILT DESIGN ORIG. M L 4 2 4 1.0 RIG.

O DOCUMENTS FOR THE LOW PRESSURE CORE SPRAY ENG. AS. //122(M ENG. XS.

SYSTEM AT SH0REHAM NUCLEAR POWER STATION Q.A. c f_C4 vp2 Q.A.

PROJ. MGR.' W ~~ PROJ. MGR.

DATE ge tt2. DATE SECTION DESCRIPTION REV.

O O

ENCLOSURE (1) TO EP-1-018 CHECK LIST FOR PIPE STRESS ANALYSIS REVIEW

O SHOREHAM NUCLEAR POWER STATION LPCS SYSTEM INDEPENDENT DESIGN REVIEW O

l l

O

o O

e

'RTELEDYNE

["n;';se(1) ENGINEERING SERVICES I

h l ~' PIPE STRESS ANALYSIS REVIEW CHECK LIST l PIPE STRESS

SUMMARY

AX NO.

l Item Initial Date

')

1.0 Input Data Check (Normal and Upset Conditions Only) 1.1 Internal piping pressure 3 1.2 Thermal load cases 1.3 System operating modes 1.4 Seismic spectra and anchor movements 1.5 SRV spectra and anchor movements 1.6 Fluid transients and other occasional

" loads, if applicable 2.0 Piping Model Check 2.1 Piping geometry check 3 2.2 Piping section physical and material properties 2.3 Support and restraint stiffness, location and orientation 2.4 Fittings, nozzles and valves

'D 2.5 System boundaries 3.0 Related Calculations 3.1 Stress intensification factors and indices U 3.2 Flow induced transient and steady-state loads (pool drag, impact loads,etc.)

3.3 Valve model natural frequency 3.4 Temperature T( A 1, 2a T a, T -T) b 3.5 Load summaries (supports, restraints, penetrations, nozzles,etc.)

4.0 Stress Reports

, 4.1 Certification J

4.2 Load cases 4.3 Load combinations 4.4 Code compliance 4.5 Valve requirements O 4.6 System functional capability

O WTF1 FrT(NE ENGINEERING SEFNICES O ENGINEERING PROCEDURE TITLE: EP 018 ^T REV. .

O REV.

METHOD OF REVIEW 0F AS-BUILT DESIGN ORIG. 2Ris P T-5 40 RIG.

n ENG. AS.

" DOCUMENTS FOR THE LOW PRESSURE CORE SPRAY ENG. AS. q Q. A. cc5 eM/p2 Q.A.

SYSTEM AT SH0REHAM NUCLEAR POWER STATION PROJ. MGR, PROJ . MGR JFL.

DATE Ll4fft.

i-DATE O REV.

SECT'ON DESCRIPTION l

O O

ENCLOSURE (2) TO EP-1-018 CHECK LIST FOR PIPE SUPPORT ANALYSIS REVIEW g

SHOREHAM NUCLEAR POWER STATION LPCS SYSTEM INDEPENDENT DESIGN REVIEW O

lO l

,0 O

l i

O WTA WNE ENGNEERNG SERVCES O EP-1-018 Enclosure (2)

O PIPE SUPPORT ANALYSIS REVIEW CHECK LIST PIPE STRESS

SUMMARY

AX NO.

PIPE SUPPORT NO.

O Item Initial Date 1.0 Input Data Check n

1.1 Loads 1.2 Load combinations 1.3 Support types and location 1.4 Deflection calculations O

1.5 Pipe stresses at welded attachments 2.0 Design Calculations 2.1 Member sizing, stiffness, stability O 2.2 Weld calculations 2.3 Stress allowables 2.4 Vendor allowables for standard hardware O 2.5 Computer model geometry, section properties and material properties 2.6 Expansion bolt load calculations 2.7 Baseplate flexibility

>g o

O

O W TELEDYNE ENGNEERING SERVCES Technical Report O TR-5633-2 O

O 1

!O I

iO APPENDIX F ENGINEERING PROCEDURE EP-1-019 l

l

'O O

O O

O

O O

ENGINEERING PROCEDURE O EP-1-019 O PROCEDURE FOR PROJECT REVIEW INTERNAL COMMITTEE SHOREHAM NUCLEAR POWER STATION INDEPENDENT DESIGN REVIEW REVISION 0 0

PROJECT 5633 O JUNE 2, 1982 O

.O Prepared by: /[% Date /-24E-Approved by: - , N Date (e j % k 1 Project Manager, O / -

Reviewed by: quh Date I!/ 7/[3 Quality Assurance [

.O WTELEDYNE ENGINEERING SERVICES O 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 617-894 3350

O WTpt Fr1YNE ENGINEERING SERVICES g ENGINEERING PROCEDURE ,

TITLE: PAGC EP 019 "1 REV. O REV.

PROCEDURE FOR ORIG.-'1(4L L teft ORIG. .

O PROJECT REVIEW INTERNAL COMMITTEE ENG. A5. # r//P _ ENG. AS.

SHOREHAM NUCLEAR POWER STATION Q.A. g 6 5 M #ff Q.A.

INDEPENDENT DESIGN REVIEW PROJ. MGR, 'DFL PROJ. MGR.

DATE 4/9/pv DATE SECTION DESCRIPTION REV.

1.0 SCOPE This procedure provides the general guidelines to be used by O the Project Review Internal Committee in reviewing Potential Findings forwarded by the Project Manager and/or the Reviewer.

2.0 APPLICATION 2.1 References O

a. Project QA Program, Project 5633

b. EP-1-017, TES Program Plan for Independent Design Review of Shoreham Nuclear Power Station Low Pressure Core Spray System O c. EP-5-006, Method of Determination of As-Built Configuration of Low Pressure Core Spray System at Shoreham Nuclear Power ,

Station  !

d. EP-1-018, Method of Review of As-Built Design Documents for the Low Pressure Core Spray System at the Shoreham Nuclear l' o

Power Station

e. EP-1-020, Procedure for Reviewing and Reporting by TES 10CFR Part 21 Committee Shoreham Nuclear Power Station Independent {

Design Review

f. EP-1-021, QA Sampling Inspection Procedure Shoreham Nuclear g Power Station Independent Design Review 3.0 METHOD 3.1 Personnel I V, The Project Review Internal Committee will be composed of the following members of the TES senior staff:

George Moy, Chairman l

George A. Carpenter i George E. O'Connor I O  :

I I

a

'RTA RWNE ENGINEERING SERVICES ENGINEERING PROCEDURE tg IITLC: EP 019 ^b REV. . O REV.

PROCEDURE FOR ORIG. M L-2,. MORIG.

J_ PROJECT REVIEW INTERNAL COMMITTEE ENG. AS. //4/N ENG. AS.

SH0REHAM NUCLEAR POWER STATION Q.A. MJ 6/w/gzQ.A.

INDEPENDENT DESIGN REVIEW PROJ. MGR. % ~ PROJ. MGR.

DATE Qc h DATE SECTION DESCRIPTION REV.

3.2 Outies The Comittee is responsible for reviewing Potential Findings g" forwarded by the Project Manager and/or the Reviewer to determine whether to categorize Potential Findings as Findings or to lower the categorization to an Observation or to close the item.

3.3 Process O The Comittee has access to all the data, criteria, analyses, etc., that are required for them to reach a majority decision.

The Comittee can discuss the Potential Finding with the Reviewer and Project Manager in order to develop more detailed information for their use.

U 3.4 Reporting 3.4.1 The Comittee is required to complete an Internal Comittee Report (ICR) form for each Potential Finding presented to them. The Chairman or his designee completes the ICR  !

presenting the majority opinion of the Comittee. At least i'

.O two members of the Committee must sign the ICR. In the case  ;

where the third member of the Committee does not agree witr. ,

the Committee action he can attach his opinion to the ICR.

3.4.2 The ICR will be forwarded to the Project Manager for his review. The Project Manager will review the resolution O reached by the Internal Comittee to determine if it complies with the Independent Design Review process. If it does not, he will return the ICR with an explanation of the review process that has not been adhered to. The Project Manager will sign the ICR if he is in agreement with the Internal Comittee resolution.

O 3.4.3 The Project Manager or the Reviewer has the opportunity to appeal the resolution of the Internal Comittee to the TES 10CFR21 Committee. The resolution of the 10CFR21 Committee is final and will be reported directly to LILC0 and NRC concurrently.

O 4.0 RECORDS i

Originals of all ICR's will become Proiect GA Rennerk. I i

a "RTF1FnYNE ENGINEERING SERVICES Technical Report O TR-5633-2 3

J 3 APPENDIX G ENGINEERING PROCEDURE EP-1-020 J

O 3

D D

O O

ENGINEERING PROCEDURE EP-1-020 O

g PROCEDURE FOR REVIEWING AND REPORTING BY TES 10CFR PART 21 COMMITTEE SH0REHAM NUCLEAR POWER STATION INDEPENDENT DESIGN REVIEW g REVISION O PROJECT 5633 JUNE 2, 1982 O

Prepared by: 4 Date d- 7.r ET-Approved by: L N Date bfIN $2 Project Manager g

Reviewed by: h h; Date V/88 Quality d N ance [

O TTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE O WALTHAM. MASSACHUSETTS 02254 617-EM33SO

e "MTF1 PTWNE ENGINEERING SERVCES ENGINEERING PROCEDURE g

PAGE TITLE: EP 020 1 PROCEDURE FOR REVIEWING AND REV. _0 _

REV.

REPORTING BY ORIG. JffK kr,it. 0 RIG.

O TES 10CFR PART 21 COMMITTEE ENG. AS.,efo 9 . ENG. AS.

SHOREHAM NUCLEAR POWER STATION Q.A.gCS 6/ev/AQ.A.

INDEPENDENT DESIGN REVIEW PROJ. MGR. W L PROJ. MGR.

DATE DATE d. ,e.Ji.oL O SECTION DESCRIPTION REV.

1.0 SCOPE l This procedure provides the general guidelines to be used by  !'

g the TES 10CFR Part 21 Committee in reviewing and reporting items.

2.0 APPLICATION 2.1 References

a. Project QA Program, Project 5633 )

b. EP-1-017, TES Program Plan for Independenc Design Review of Shoreham Nuclear Power Station Low Pressure Core Spray System.

c. EP-5-006, Method of Determination of As-Built Configuration of Low Pressure Core Spray System at Shoreham Nuclear Power Station.  ;

I

d. EP-1-018, Method of Review of As-Built Design Documents i j for the Low Pressure Core Spray System at the Shoreham h

i Nuclear Power Station. ,

e. EP-1-019, Procedure for Project Review Internal Committee Shoreham Nuclear Power Statirn Independent Design Review. l 3.0 METHOD h

3.1 Personnel The 10CFR Part 21 Committee, as a minimum, will be composed of the Manager of Engineering Analysis, as Chairman, a TES Consulting Engineer, and a member of the TES staff with applicable expertise.

t l

1 .

)

"RTF1 FnYNE ENGINEERING SERVICES ENGINEERING PROCEDURE

)

PAGE TITLE: EP 020 2 PROCEDURE FOR REVIEWING AND',

REV. .0 REV.

ORIG. y l.2,72 ORIG.

REPORTING BY ENG. AS. //J;de

) ENG. AS.

TES 10CFR PART 21 COMMITTEE Q. A. cCJ 64y/AQ.A.

SHOREHAM NUCLEAR POWER STATION PROJ. MGR. % C PROJ7M6R.

INDEPENDENT DESIGN REVIEW -

DATE SM ft DATE

) SECTION DESCRIPTION REV.

3.2 Duties The Committee is responsible for reviewing items forwarded by the Project Manager and/or the Reviewer in writing. The only

) items to be consicered are those where agreement between the Project Manager and/or Reviewer and the Project Review Internal Committee cannot be reached. The committee will determine whether to categorize .the items as Findings, Observations or to close the item.

) 3.3 Process The Committee has access to all the data, criteria, analyses, etc. , that are required for them to reach a decision. The Committee can discuss the item with the Reviewer, Project, Manager and Project' Review Internal Committee, in order to

) develop more detailed information for their use.

3.4 Reporting i The resolution by the 10CFR Part 21 Committee is final. A p 1

written report will be made to LILCO and the NRC concurrently i

) within three working days of resolution oJ an item.  ;

}

4.0 RECORDS  !

Originals of Reports will'beccme Project QA Records.

)

a t /

)

i I

o

'RTF1 FrWNE ENGINEERING SERVICES Technical Report 3.. - TR-5633-2 0

i O

1 1,

O APPENDIX H j ENGINEERING PROCEDURE EP-1-021

)

O 4

O i

4 Q

i i

i

'O

.O

l

)

ENGINEERING PROCEDURE EP-1-021 l

l l

l QA REVIEW SAMPLING PROCEDURE SHOREHAM NUCLEAR POWER STATION 3 INDEPENDENT DESIGN REVIEW FOR THE LPCS SYSTEM REVISION O PROJECT 5633

-3 JUNE 18,1%2

)

3 Prepared by: g_ W Date d"/["[4 Approved by: _ _

• Date [e$3-hD Project ar >er Reviewed by: C- ,

<>f J ' - ~?

I Date MI" d Quality Assurance F WTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE 3 WALTHAM, MASSACHUSETTS 02254 617 6 3350

J "RTF1 FrWNE ENGINEERING SERVICES 3 ENGINEERING PROCEDURE PAGE TITLE: EP-1-021 I REV. m 0 REV.

QA REVIEW SAMPLING PROCEDURE 3 SHOREHAM NUCLEAR POWER STATION ORIG. W 1 ORIG.

ENG. ENG. AS.

INDEPENDENT DESIGN REVIEW FOR THE LPCS SYSTEM Q.A. 7/ M C 64 PROJ. MGR.~UFK

. Q.A.

PROJ. MGR.

DATE 6//P/B.2 DATE D

SECTION DESCRIPTION REV.

1.0 SCOPE 3 This procedure describes the sampling plan to be used for the TES QA review of SWEC construction activities for the LPCS System at the Shoreham Nuclear Power Station.

This procedure is provided solely to define the lot size and samle size and to assure random selection and review of the 3 sample.

The procedure is not intended to provide a statistical inspec-tion sampling plan.

2.0 APPLICATION 2.1 The sampling plan will be applied to the review of documenta-tion and records for the following:

a) training and qualification records of personnel

) b) identification and control of material, parts and com onents c) control of special processes d) nonconformance and dispositioning report process e) receiving inspection records f) material certification records g) NDE records g

j

2.2 REFERENCES

2.2.1 Mil-Standard 105D 29 Apr 1%3 to the extent specified herein.

2.2.2 TES EP-1-017 TES Program Plan For Independent Design Review of 3 Shoreham NPS LPCS System t

3 "RTF1 FnYNE ENGINEERING SERVICES O ENGINEERING PROCEDURE PA TITIE: EP-1-021 QA REVIEW SAMPLING PROCEDURE REV. m 0 REV.

O SHOREHAM NUCLEAR POWER STATION ORIG. WEfff ORIG.

INDEPENDENT DESIGN REVIEW ENG. 66'.#4st:P ENG. AS.

FOR THE LPCS SYSTEM Q.A. cc:s _, Q.A.

.. PROJ. MGR. '7 tpk PROJ. MGR.

DATE 4 4 p /# v DATE O

SECTION DESCRIPTION REV.

2.3 Lot size is established as a nominal count of field pipe welds O and support or restraint welds to . pipe for the E21 LPCS System as shown darkened in Figure 1 of Enclosure 1 to EP-1-017 and as clarified by LILC0 (M. Milligan) letter to TES dated 6/8/82 For purposes of this review, the lot size will be 281 to 500 3 2.4 Sample size is determined from MIL-STD 105D 29 April 1963, Single Sampling Plan For Normal Inspection.

For purposes of this review the sample size is 50.

2.5~ The lot is regarded as homogeneous, including pipe, valve, J support and attachment welds.

3.0 METHOD 3.1 The reviewer will prepare a checklist per the form attached.

O 3.2 Identify the weld location per the As Built isometric drawing.

3.3 Apply a random selection of characteristics a thru g (see 2.1) to each of the weld records reviewed. Assure a reasonably equal distribution of characteristics for each record reviewed.

] 3.4 Enter all reportable conditions in the coments section of the checklist form.

4.0 REPORTS 4.1 Results of this review will be forwarded to TES QA MGR for 3 reporting in accordance with EP-1-017 Enclosure 1 Section 3.8.2.

5.0 RECORDS Documents produced as a result of this review will become TES project records. -

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a "RTELEDYNE ENGINEERING SERVICES Technical Report 3 TR-5633-2 3

O O APPENDIX I ENGINEERING PROCEDURE EP-5-006 O

O O

O O

4 ,

3 ENGINEERING PROCEDURE D

EP-5-006 O

METHOD OF DETERMINATION OF AS-BUILT CONFIGURATION OF LOW PRESSURE CORE SPRAY SYSTEM AT SHOREHAM NUCLEAR POWER STATION O

REVISION O PROJECT 5633 O

JUNE 2, 1982 O

!O L

1 Prepared by: h h_ Date d'Idt Approved by: Date hI Sl I\

Prcject Manager

/

O Reviewed by: #M #

[

h Date /V 8.&

QualitfAssurance WTELEDYNE ENGINEERING SERVICES .,

l O 130 SECOND AVENUE l WALTH AM, MASSACHUSETTS 02254 617-8EG310

3 ' '

"RTF1 FDYNE ENGINEERING SERVICES ENGINEERING PROCEDURE TITLE: EP 006 PAG {

REV. _Q REV.

METHOD OF DETERMINATION OF AS-BUILT ORIG. JFK irMLORIG.

CONFIGURATION OF LOW PRESSURE CORE SPRAY ENG. AS. M ENG. AS.

O SYSTEM AT SHOREHAM NUCLEAR POWER STATION Q. A. 66J 6hW/2, Q.A.

PROJ. MGR. W L- PROJ. MGR.

DATE 6/4/f1 DATE (i

SECTION DESCRIPTION REV.

g 1.0 SCOPE This procedure describes the method to be used in determining the "as-built" configuration of Low Pressure O Core Spray System at Shoreham Nuclear Power Station. The purpose of this procedure is to obtain dimensional verification of portions of the LPCS system to provide the independent reviewers (TES) sufficient data to verify that the design was properly implemented.

m 2.0 APPLICATION u

2.1 References a) Project QA Program, Project No. 5633.

b) EP-1-017, "TES Project Plan for Independent Design Review of Shoreham Nuclear Power Station LPCS System.

o" 2.2 Equipment For the equipment to be used in obtaining measurements required by this procedure, no formal calibration is required. However, only undamaged measuring tapes, scales, etc., shall be used.

n 3.0 METHOD 3.1 As-Built Data i 3.1.1 The Project Manager shall obtain from S&W the as-built data package, following interface definitions described in the

-. References Section 2.1. All documents received shall be recorded on a document list, noting the revision and any l applicable Engineering Change Notices (ECN's) or other records of changes in process.

3.1.2 A copy of the as-built isometric obtained from S&W will be made (prefcrably traced) by TES drafting excluding all O dimensions and support locations. Copies of the TES isometric will then be used in the determination of as-built piping configuration.

2AJM

a "RTA FtWNE ENGINEERING SERVICES ENGINEERING PROCEDURE 3

TITLE: EP 006 2 REV. _0 REV.

ORIG. "fP6 hi& ORIG.

, METHOD OF DETERMINATION OF AS-BUILT ENG. AS.//4tf ENG. AS.

J CONFIGURATION OF LOW PRESSURE CORE SPRAY #

SYSTEM AT SHOREHAM NUCLEAR POWER STATION 0 A* d 6 # /M AQ A-PROJ. MGR. WN PROJ. MGR.

DATE bf4 f% DATE DESCRIPTION REV.

SECTION 3.1.3 Copies of the support details supplied by S&W will be used to verify support as-built configuration.

3.2 Field "As-Built" System Verification 3.2.1 The Lead Engineer and other engineers performing the verification shall review the documents acquired under Section 3.1. The TES Project Manager shall review and O approve the selection of personnel for the field verification.

3.2.2 A general walk-down of the system shall be performed to f amiliarize TES personnel with the location, general layout, accessibility, and quantity of piping and pipe supports.

g 3.2.3 The portion of the LPCS System outlined in Figure 1 of EP-1-017 thall be verified. As a minimum, the following  !

shall be verified:

o a) Piping geometry 1

1) Type of fittings and location

2) location of valves and orientation

3) Length and orientation of pipe b) Supports O

1) location

2) lype and direction restrained

3) Spring sizes and settings

4) Snubber sizes and settings g' 5) Pin-to-pin length for snubbers and struts

6) Clearances

7) Support hardware - size of primary structural members, component standard part designations (part numbers), overall support configuration Y

l

e

'MTF1 FDYNE ENGINEERING SERVICES ENGINEERING PROCEDURE 3

PAGE T ITLE:

EP 006 3 REV. ._0 REV.

ORIG. 3 L-2 78.0 RIG.

METHOD 0F DETERMINATION OF AS-BUILT b CONFIGURATION OF LOW PRESSURE CORE SPRAY ENG. AS. &?at ENG. AS.

SYSTEM AT SHOREHAM NUCLEAR POWER STATION Q.A. cC5 6//r//oQ.A.

PROJ. MGR. -1A PROJ. MGR.

DATE W4 ft DATE D DESCRIPTION REV.

SECTION D c) location and nature of pipe attachments, such as lugs, stanchions, etc.

d) location and nature of any interferences which may inhibit pipe motion D e) Valves

1) Record nameplate data on valves and valve operators

2) Determine length between the centerline of the valve to the approximate centerline of the valve D operator Determine the orientation of the valve operator 3) using the horizontal or vertical plane for reference f) Equipment mounting characteristics ,

O I 3.2.4 Should some locations be inaccessible the Lead Engineer shall document this including reasons why and report this to the Project Manager.

3.2.5 Photographs shall be taken where deemed necessary by TES O personnel, to augment the field review, particularly in case of inaccessibility.

3.2.6 A list of all personnel contacted in the field and the reason for the contact will be made.

O 3.2.7 A written record of all activities accomplished at the site will be made.

O

"RTFI FnYNE ENGINEERING SERVICES J ENGINEERING PROCEDURE TITLE: EP 006 N REV. .O REV.

ORIG. UPK, L 1 11 ORIG.

^ METHOD OF DETERMIMTION OF AS-BUILT ENG. AS. #//0# ENG. AS.

CONFIGURATION OF LOW PRESSURE CORE SPRAY SYSTEM AT SHOREHAM NUCLEAR POWER STATION Q.A. c G J (/u /#1,Q.A.

PROJ. MGR. "DFL. PROJ. P6R.

DATE g all M., DATE D REV.

SECTION DESCRIPTION 3.3 Documentation

, 3.3.1 Each dimension and system characteristic checked shall be

'J signed by two of the TES personnel present. Upon return to the TES offices the original TES copy of the as-built piping documentation shall be marked up with all information contained on the record copy used in determining as-built configuration. TES personnel initials need not be included but all the members of the field team must sign the TES g'-

original isometric indicating that the transfer of information from the record copy to the tracing is correct. ,

3.3.2 All data sheets shall be initialed and dated by two of the TES personnel present. All data shall be recorded in ink.

g Any errors / changes shall be lined-out and initialed.

l 4.0 RECORDS The originals of all recorded data, photographs and the tracing shall become project QA records.

, i l

l O

lO >

i i

lO

'eTF1 FrWNE ENGINEERING SERVICES 4

Technical Report

^O TR-5633-2

O I

I 4

.O l

O l

O APPENDIX J TES PROJECT QA PROGRAM O

O O

!O O

3

'RTA rD(NE ENGINEERING SERVCES D

PROJECT QA PROGRAM 3 D. F. Landers /

Project No. 5633 Project Manager J. P. King Initiated On 4-29-82 REV Date 6-30-82 Client Long _

Island Lighting Company, Shoreham Nuclear Power nauon yV PROJECT SCOPE Provide an Independent Design Review of the Low Pressure O Core Spray System as defined in Figure 1 of EP-1-017, and as clarified

_ by LILC0 letjer to _ TES_of 6-8-82. This review shall encompass the structural and mechanical aspects of this system only.

J . . _ . _ _ . . _ .

Applicable Sections 1, 2, 3, 5, 6, 15, 16, 17 and 18 J

REVISION LEGEND Revision Date Changes in Section 3 0 6-30-82 Initial Issue D

$ 11510N APPROVAL Project Manager [.m Date d 72-E #**d9er , ,$u la N l Date d'-Jo-f2 8 d' )M 4

'"' 3 " 3 9 E ' A--- /e Date -7_ /_ g E Y '

D {

>/s?

D TE N PROJEC T 5633 g

REV. 3 DATE 6/30/82-O PROJECT QA PROGRAM PAGE 1 0F L q NOTE: The following paragraphs are numbered to correspond to the TES QA Manual.

1.0 PROJECT ORGANIZATION p 1.1 TES Organization 9

Project Manager: D. F. Landers Assistant Project Manager: J. P. King QA Engineer: J.H. Malonson Project Review Internal Committee: G. Moy, Chairman 10CFR Part 21 Committee: R. Wray, Chairman 1.2 Client Organization Project Manager: William Muscler, Manager Construction

& Engineering-(Shoreham)

Contractual: Andy Wofford, V.P. Purchasing 3 Quality Assurance: Frank Gerecke, Division Manager, Q.A.

1.3 Interfaces TES LILC0 S&W Project Manager: D. F. Landers / M.H. Milligan R.C. Wiesel 3 J. P. King Contractual: W.S. Moonan A. Wofford N/A Quality Assurance: J.H. Malonson J.Kelley (Site)/ R. Costa E. P. Cassiano Eng. Assurance: J.H. Malonson N/A A.J.Benecchi Technical Data: D. F. Landers / E. Montgomery R.Hankinson J. P. King 1.4 Project Document Distribution Controlled Document Distribution: The following personnel at TES are authorized to withdraw RECORD COPY from Document Con-trol. (This is an exception to SQAP-81-01, Section 3.3(d).)

D. F. Landers J. P. King 3 J. H. Malonson Report Distribution: D. F. Landers /J. P. King (TES)

D

3 YE PROJECT 5633 R EV . _, g DATE 6/30/82 PAGE 2 0F 7_

D PROJECT QA PROGRN4 2.0 PROGRAM 2.' Client Requirements No additional requirements to TES QA Manual.

2.2 TES Requirements -

This Project QA Program, latest revision, constitutes the QA

_J requirements for Shoreham Nuclear Power Station Independent Design Review Program for the LPCS system.

2.3 TES Quality Assurance Manual Applicability Quality Assurance activities 1, 2, 3, 5, 6, 15, 16, 17, and 18 J apply as supplemented by this PQAP.

2.4 Implementation TES Engineering Procedure EP-1-017, "TES Project Plan for Independent Design Review of Shoreham Nuclear Power Station a LPCS System," latest revision, defines the plan for implementation.

2.5 Indoctrination Each TES employee assigned to this project shall complete and J sign a copy of Attachment 1. These documents shall become QA Records.

3.0 DESIGN CONTROL

, Any calculations or analysis performed by TES and used to J substantiate a TES conclusion shall be subject to the checking, verification and design control requirements of the TES QA Program.

5.0 PROCEDURES, INSTRUCTIONS AND DRAWINGS 5.1 General 3

TEP-1-001, Revision 2 " Initiation, Approval, Implementation, Revision and Control of TES Procedures and Engineering Instructions"

, TEP-1-002, Revision 2 " Guidelines for Writing TES Engineering J Procedures" O

.i TE M PROJECT 5633 REV. O DATE 6/30/82 g PROJECT QA PROGRAM PAGE 3 0F 7 5.2 Supplementary

, Program requirements will be implemented in accordance with

EP-1-017, "Teledyne Engineering Services Program Plan for Independent Design Review of Shoreham Nuclear Power Station LPCS System," and the,f,ollowing:

EP-5-006, Revision 0 " Method of. Determination of As-Built

, Configuration of Low Pressure Core o Spray System at Shoreham Nuclear Power Station" EP-1-018, Revision 0 " Method of Review of As-Built Design Documents for the. LPCS System at the Shoreham Nuclear Power Station" 3

EP-1-019, Revision 0 " Procedure for Project Review Internal Committee Shoreham Nuclear Power Station Independent Design Review".

EP-1-020, Revision 0 " Procedure for Reviewing and Reporting 3 by TES 10CFR Part 21 Committee Shoreham Nuclear Power Station, Independent Design Review".

EP-1-021, Revision 0 "QA Review Sampling Procedure Shoreham Nuclear Power Station Independent Design Review".

6.0 DOCUMENT CONTROL 6.1 General 7-The requirements of the TES QA Manual apply except as modified by TES SQAP 81-01, Revision 0, and this PQAP.

6.2 Controlled Documents - TES Generated 3 Documents developed by TES shall be controlled documents.

Telecons, minutes of meetings, trip reports, and memoranda shall become project QA records.

O O

O TTELEDGE PROJECT 5633 REV. _ 0 DATE6 /30/82 PAGE 4 0F 7, O PROJECT QA PROGRAM 6.3 Controlled Documents - Client Generated O LILC0 documents shall be transmitted to:

Teledyne Engineering Services Project 5633 130 Second Avenue Waltham, MA 02254 O

Attention: Document Control 6.4 All LILC0 documents received for the performance of the tasks shall be returned to LILCO six months after submittal of final

.O report.

15.0 NONCONFORMING MATERIAL OR ITEMS No additional requirements to TES QA Manual.

O 16.0 CORRECTIVE ACTION No additional requirements to TES QA Manual.

O 17.0 QUALITY ASSURANCE RECORDS 17.1 The TES QA records shall be retained in accordance with Attachment 2, QA Records Requirements List.

O 17.2 Personnel statements regarding potential or apparent conflicts of interest by TES employees / contract engineers shall be retained by the TES Personnel Relations Manager.

18.0 AUDITS O

The requirements of the TES QA Manual apply as implemented by Attachment 3 of this PQAP.

O O

O .

\

TM PROJECT 5633 REV. O DATE(/30/82 PR0 JECT QA PROGRAM PAGE 5 0F 7 O _

Project 5633 O

ATTACHMENT 1 O

T0: D. F. Landers, Project Manager J. H. Malonson, QA Engineer

.O

SUBJECT:

Project 5633 Independent Design Review, Shoreham Nuclear Power Station: Project Indoctrination O

I certify that I have read and understand, and that I will comply with, the following documents which control this project.

(

1. Project QA Program, Revision 0.

O .% ,

2. TES Engineering Procedure EP-1-017 "TES Project ' Plan for Independent Design Review of Shoreham Nuclear Power Station LPCS System", Revision 0.

O l

Signed:

O

Title:

IO Date:

1 lO

1 O

WM Project 5633 NN Rev. O n ATTACHMENT 2 QA RECORDS REQUIREMENTS LIST Page 6 of 7 i

TYPE RETENTION PERIOD 9 CODE CLIENT PROJECT BY OWNER BY TES

1. CLIENT DOCUMENTS A. Specifications - X 6 mon %s B. Procedures A 6 months C. Drawings x 6 months ,

'O i D. Instructions X 6 montns E. Other x 6 months

11. TES DESIGN DOCUMENTS A. Specifications B. Procedures X 6 months O C. Drawings x b montns D. Instructions X b montns E. Analyses x b montns F. Reports X o mundis G. Reviews H. Other 111.

PERSONNEL QUALIFICATIONS N/A A. Welders B. NDE C. QC Inspectors D. Other O

IV. EQUIPMENT QUALIFICATIONS N/A A. Calibration B. Standards C. Other O V. VENDOR REQUIREMENTS g A. Personnel Qualifications B. Measurement / Test C. Procurement D. Other j O VI. TES DOCUMENTS A. Project QA Program X z years B. Special QA Procedures A 2 years C. Project Instructions D. NDE Reports E. Other VII. AUDITS A. Per Audit Plan X 1 year B. Vendor C. Other O 3/80

D 5633 PROJECT ENGPEERNG SERVICES REV. DATE .6/7n/n?

) PROJECT QA PROGRAM PAGE 7 cr 7 J

Project 5633 Rev. O D

ATTACHMENT 3 D

1.0 PROJECT AUDITS D 1.1 During progress of Independent Design Review activity the QA Engineer shall perform an internal project audit of work in process. This audit shall be performed using a prepared checklist to cover document control and requirements of the PQAP and TES Engineering Procedures.

D 1.2 Prior to project close-out the PQAE shall conduct a final project audit to assure the identification, accumulation and storage of Project QA Records and update of Project Personnel Training Records.

1.3 Upon completion of the QA Audit and documenting the results, O the QA Engineer shall discuss his findings with the TES QA Manager and the Project Manager.

2.0 AUDITOR QUALIFICATION For this scope of work, all personnel performing QA auditing D and assignments shall have been qualified per ANSI N45.2.23, 1978.

O O