ML20236F255

From kanterella
Jump to navigation Jump to search
Forwards Info on Facility Preparedness for Licensing,Per Manual Chapter 94300.Encls 1-4 Include Items Requiring Insp & Resolution Before Finding of Readiness for Operation Can Be Endorsed by Region II
ML20236F255
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 09/24/1986
From: Walker R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Novak T
Office of Nuclear Reactor Regulation
Shared Package
ML20236F242 List:
References
FOIA-87-271 NUDOCS 8708030272
Download: ML20236F255 (41)
v • d • e


Text

-

l UtJITED ST ATES

. < [p stic NUCLEAR REGULATORY COMMIS$lON 3 REGloNll E

" o 101 MARIFTTA STREET,N.W. 4 -

g ATLANYA. GEORGI A 30323 h s,

. y,.  !

..... SEP 2 41986 MEMORANDUM FOR: Thomas M. Novak, Acting Director, Division of Pressurized Water Reactor Licensing-A, NRR FROM: Roger D. Walker, Director, Division of Reactor Projects ,

SUBJECT:

GEORGIA POWER COMPANY - V0GTLE UtIT 1 DOCKET NO. 50-424, STATUS OF FACILITY COMPLETION, INITIAL REPORT This memorandum is forwarded in at:ordance with IE MC 94300 to provide you information on the preparedness for licensing of Vogtle Unit 1. Enclosures 1 through 4 include items requiring inspection and resolution before a finding of readiness for operation can be endorsed by Region II. The categories used are consistent with those used by the applicant.

Georgia Power Company estir.iates a fuel load date of December 15, 1986. Region II l considers this date to be realistic, assuming that no unforeseen delays occur in )

the licensee's remaining construction and preoperat testing effort.

l s L,y

Roger D. W1' r J

Enclosures:

1. Outstanding Items Including .

Enforcement and Unresolved Items  ;

2. Preoperational and Acceptance Testing Status
3. Construction Status
4. Status of Inspections Required by MC 2512, MC 2513 and l MC 2514 j cc w/ enc;s: l J. G. Partlow, Director, DIP, IE i E. L. Jordan, Director, DEPER l B. K. Grimes, Director, DQAVTTCP M. A. Miller, Manager, NRR B700030272 870729 PDR FOIA GRADERB7-271 PDR

~_

83 l

J

...* . l ENCLOSURE 1 OUTSTANDING ITEMS INCLUDING ENFORCEMENT AND UNRESOLVED ITEMS l

At this early date, all outstanding construction items are expected to be closed by fuel load. It is anticipated that some of these items may be deferred to some date beyond fuel load and will be reported as such in later updates to this reoort.

I. Open, Unresolved and Enforcement Items Attachment 1 to Enclosure 1 is a list of all open, unresolved and enforcement items that must be closed prior to fuel load, initial criticality, and exceeding 5% power.

Summary _

1. There are ' 121 open items, 30 unresolved items, and 22 enforcement items that must be closed prior to fuel load. {

l

2. There are 37 open items, 0 unresolved items, and 0 enforcement items that must be closed prior to initial criticality. ,

There are 27 open items, 0 ' unresolved items and 0 enforcement '

items that must be closed prior to exceeding 5% power.

II. Open Deficiency Reports - 10 CFR part 50.55(e) and 10 CFR Part 21 Reoorts i

Attachment 2 to Enclosure 1 is a list of all Deficiency Reports that must be.  !

J.;3ed prior to fuel load. -

l Summery There are fif ty-nine 10 CFR Part 50.55(e) reports and seven 10 CFR Part 21 reports that must be closed prior to fuel load.

III. IE Bulletins and Circulars - - ~ '

Attachment 3 EnIlosure 1 is a list of all Bulletins and Circulars that must be closed prior to fuel load.

Summary 1 There are 9 Bulletins that must be closed prior to fuel load. The number of Circulars that must be closed prior to fuel load has  !

not been determined.

4 j

Enclosure 1 2 IV. YMI Action Plan Attachment 4 to enclosure 1 is a list of all TMI Action Plan items that must be closed prior to fuel load and full power operation.

Summary

1. There are 35 TMI Action Plan items that must be closed prior to fuel load.
2. There are 3 TMI Action Plan items that must be closed prior to full power operation.

V. Vogtle Readiness Review Program (VRRP)

Attachment 5 to Enclosure 1 is a list of all 23 VRRP modules and 7 appendices, It is anticipated that all module and appendix reviews will be completed prior to fuel load.

Summary There are 16 module and 5 appendix reviews that must be completed prior to fuel load.

i i

e  !

o -______-__________- _______-____-_-- _ Q

b

.= .

l Enclosure 1 3 VI. Open Allegations l

There are currently forty-one open Allegations that are assigned to and will be investigated by Region II staff. It is expected that these allegations will be investigated prior to fuel load. Closure of the allegations will depend on the outcome of the investigations and acceptance of the licensee responses / actions if any are required.

ALLEGATION NUMBER BR/DIVSN DATE OPEN DESCRIPTION RII83A0103 PB3/0RP 11/14/83 Dismissal for contact with NRC/ Quota System.

RII84A0070 ENG/DRS 04/13/84 PPP Test shop-Improperly certifying welders.

RII84A0118 ENG/DRS 08/23/84 Lack of support for QC inspectors RII84A0128 PB3/DRP 08/31/84 Improper installation of ventilation ducts RII84A0145 ENG/DRS 09/14/84 SENSITIVE - Engineering Design Concern RII84A0168 IAC/RII 10/26/84 Harassment of QC Inspector RII84A0169 PB3/DRP 10/29/84 Construction deficiencies RII84A0181 PB3/DRP 11/09/84 Falsification of NDE RII84A0186 ENG/DRS 12/03/84 Improper disposition of DRs

! RII85A0002 PB3/DRP 01/04/85 Improper installation of hangers '

RII85A0016 PB3/DRP 02/06/85 Drug abuse & falsification documents l RII85A0043 IAC/RII 04/12/85 Quality assurance concern RII85A0049 PB3/DRP 05/02/85 Non-US engineers unqualified RIIB5A0051 IAC/RII 05/02/85 Harassment of QC inspectors RII85A0175 IAC/RII 09/17/85 Welding & Materials traceability RII85A0186 PB3/DPR 10/07/85 Design concerns

RII85A0200 IAC/RII 10/22/85 Termination for reporting safety concerns / DOL 1

RII86A0203 PB3/DRP 10/26/85 00L-Harassment for failure to sign inspection report RII85A0209 IAC/RII 11/05/85 QC supy alowng use of uncontried RCI & EM, and DR RIIS5A0210 PB3/DRP 11/05/85 Insp alleges himself unalfd&inadeq response to DR RII85A0230 PB3/DRP 12/16/85 Improper welding practices RII86A0078 ENG/DRS 02/18/86 Improper reactor trip-circuit cable routing '

RII86A0082 PB3/DRP 03/10/86 DOL complaint RIIB6A0083 PB3/DRP 03/10/86 DOL complaint RII86A0084 IAC/RII 03/10/86 DOL complaint l RII86A0088 IAC/RII 03/13/86 00L Complaint RII86A0090 ENG/DRS 03/13/86 Welding w/o proper documentation RII86A0096 . ENG/DRS 03/13/86 Improper HVAC inspection RII86A0134 OI/RII 04/17/86 00L inv re union activities RII86A0142 PBS/DRP 04/23/86 Q Class welding done by non-certified welders RIIS6A0151 PB3/DEP 05/19/86 Inadequate response to qualicy concerns ,

RII86A0161 PB3/DRP 06/02/86 Containment dome improperly constructed j RII86A0179 ENG/DRS 06/10/86 Materials issue out-of procedure (lockshifts) 1 RII86A0192 PB3/DRP 06/24/86 Violation of work procedures RII86A0200 ENG/DRP 07/07/86 Damage to wall from concrete buster {

RII86A0203 ENG/DRS 07/07/86 Improper electrical splices RII86A0204 PB3/DRP 07/07/86 QC inspector favored by craft i

o l

I!

i Enclosure'l- 4 RII86A0207 PB3/DRP 07/11/86 Inadequate licensee investigation of emp concerns RIIB6A0216 IAC/RII 07/24/86 Termination for reporting concerns ,

RII86A0220 P83/DRP 07/29/86 Improper electrical cable work j RIIB6A0232 IAC/RII 08/19/86 Improper welding on class 2 pipe TOTAL: 41 )

"t m

l i

e i

f

l Enclosure 1 ATTACHMENT 1A OPEN, UNRESOLVED AND ENFORCEMENT ITEMS THAT MUST BE CLOSED PRIOR TO FUEL LOAD A. The licensee will implement corrective actions for the following violat ons j

.: the satisfaction of the NRC. l

1. 83-13-01/MPS Failure to Follow Installation & Inspection Procedure for Pipe Supports
2. 83-13-02/MPS Failure to Implement Procedures & Drawings or Provide Appropriate Acceptance Criteria
3. 84-36-03/MPS Inadequate Procedure for installation & Inspection, of Pipe Supports 4 84-36-05/MPS Design Control
5. 85-06-03/MPS Filler Plates with Pipe Straps are Being Utilized I Without Proper Documentation  ;

l

o. es-12-01/MPS Failure to Follow Procedures for Hanger j Installation & Inspection i 1
e. 85-23-02/MPS Failure to Install Pressure Taps in Accordance with I the FSAR and P&ID .
8. 85-40-04/MPS Failure to Protect Permanent Plant Equipment
9. 85-42-01/QAS Failure to Incorporate Manufacturers Requirements into EMSL Program
10. 85-62-01/QAS Failure to Provide End Clamps to Protect Weld End Preparations for Valves Fittings Flanges Piping &

Tubing & Failure to Store Subassemblies on Cribbing

11. 86-07-02/MPS Failure to Protect Permanent Plant Equipment
12. 86-09-01/RP3C Failure to Perform an Adequate System Walkdown
  • During the Turnover of Safety Related Systems
13. 86-11-01/MPS Inadequate Measures to Assure Correction of Design Criteria Documents
14. 86-11-02/MPS Failure to Promptly Identify Undersize Welds
15. 86-11-03/MPS Removal of Temporary Pipe Supports

J!

l Enclosure 1 Attachment 1A 2 l

16. 86-15-01/QAS Inadequate PPF Drawing Control Corrective Action 1 1
17. 86-20-01/MPS Failure to Follow Procedures for the Marking &

Verification for Small Component Parts used in i Mechanical Shock Arrestors l i 18. 86-31-01/RP3C Failure to Establish Appropriate Procedures to properly Control the Filling & Venting of Safety-Related Systems 1

19. 86-31-08/PSS Failure to Follow Procedures for Protecting Installed Equipment / Components ,
20. 86-39-01/MPS Failure to Provide Accurate Information for Elimination of Intermediate Pipe Breaks &

Associated Whip Restraints 21, 86-45-01/PSS Failure to Accomplish the Corrective Actions -

Prescribed in Deviation Report #12074

22. 86-61-13/PSS Failure to maintain control of QC accepted conduit 1 supports.

B. The following unresolved items or deviations are required to be completed:

1. 83-02-01/MPS Construction Deficiency Reporting
2. 83-13-09/MPS Control of Field Memos Which Affect Inspection ,

Acceptance Criteria  !

3. 84-04-02/MPS Improper Identification of Bolt Spa-ing f o r.'  !

Concrete Expansion Anchor Inspection & Training Requirements

4. 84-27-01/PSS Adequacy of Coating Contractor QC Inspection procedures 5, 84-34-05/PSS Apparent Fire Damper QA Inspection and Documentation Discrepancies
6. 84-35-04/PSS Discrepancy Punchlist for Cable Terminations
7. C-97-02/MPS Preservice Inspection Program Procedures <
8. 85-19-01/PSS Review of Results of Testing Performed on Concrete Materials by Independent Testing Laboratory
9. 85-19-02/PSS Open Civil Item Reports
10. 85-19-03/PSS Allowable Water on Batch Tickets

-+,

l J

. 4 Enclosure 1 1 Attachment 1A 3 l

11. 85-19-04/PSS Certification of QC Inspectors on Concrete Pour l A-118-004 & 008 i
12. 85-28-01/PSS Purchase of Superplasticizer as Non Q Material
13. 85-28-05/PSS Use of Shear Bars in the Auxiliary Building Base Mat
14. 85-35-09/MPS Adequacy of Drawing & DCN Reviews
15. 85-35-11/MPS Review of Procurement Specifications
16. 85-35-12/MPS Inadequate Review of Vendor Drawings
17. 85-35-13/MPS Inadequate Resolution of Readiness Review Design Verification Finding
18. 85-40-02/MPS Assurance of Adequate Back Purge for Welding Stainless Steel Piping
19. 85-60-02/MPS Unposted Drawing Change Documents  !

l 20, 85-61-01/QAS Verification of Corrective Actions Specified for Ref. 05, 06, D7, & D8 l

21, 86-03-03/MPS High Strength Bolted Connections

22. 86-10-02/MPS Control of Process Sheet Used for QC Signatures
3. 86-10-03/MPS Handling Storage & Preservation of Material for Pipe Supports 24, 86-11-04/MPS Failure to Inspect Supports
25. 86-19-01/MPS Construction Loads on Installed Equipment
26. 86-45-02/PSS Separation of the-Common Component Tap
27. 86-56-01/RPS Failure to Revise FSAR as Complete
28. 86-61-05/PSS Review Commitments to RG 189 Rev. O, vs RG 189, Rev. 1
29. 86-61-06/PSS Review 1500 psi pressure rating for LT 459, LT 460, LT461
30. 86-61-10/PSS Review FSAR Commitments to IEEE 317, 1976, for Chemical Spray of electrical penetrations l

l t

d Enclosure 1 Attachment 1A 10 C. The following open items are required to be completed:

1. 83-11-03/PSS Use of Deleted Steel 2, 84-09-02/PSS Effect of Moisture Variation Between Placed Fill &

Laboratory Optimum

3. 84-34-01/PSS Removal of all Combustible Scaffolding, Planking &

Temporary Construction Structures Required

4. 85-10-03/PSS Review Inspection Records That May be Incomplete Oue to DR Closeouts
5. 85-22-01/MPS Reinspection & Evaluation of Rock Bolt Inspections 6, 85-26-01/RP3C Boron Injection Tank Description & Operator Review
7. 85-28-03/PSS Timeliness of Writing & Addressing a Deficiency Report on Cadweld Failures
8. 85-28-04/PSS Acceptance of Response to Concept No. 3 Without  !

Reviewing Calculations  !

9. 85-29-02/MPS Applicability of Statistical Methods to Readiness Review I
10. 85-29-03/MPS Questions Regarding Module 4 Commitments
11. 85-29-04/MPS Acknowledgement of Access & Shielding 1 Considerations in Designing for Inservice '

Inspections & Tests l

12, 85-30-01/TPS List Commitment to Reg Guide 1.95 in Module 3A

13. 85-30-02/TPS Limit Remarks in Module 3A & 3B Concerning Reg Guide 1.68 to those Applicable to the Respective r Module
14. 85-30-03/?PS Revise FSAR Concerning Containment Fan Coolers During the ILRT
15. 86-30-09/TPS 86-30-09/TPSAdd Commitment to Code & Standards Rule
  • 10CFR 50.55A to Module 16 & Response to 0210.47 to Module 7 16, 85-31-01/QAS Update Final Safety Analysis Report 17, 85-35-02/MPS Omission of Westinghouse Offsite Activities From Readiness Review

4 .

Enclosure 1 Attachment 1A 5

18. 85-40-01/MPS Assurance of Necessary Minimum Clearance for Installed Piping
19. 85-44-01/QAS Verify Of. '.udit of Module 5 Findings & Corrective Actice
20. 85-45-03/0PS Conduct Further Review of Imp' lamentation of TMI Item I.C.5  ;

l 21, 85-51-02/0PS Development of a Course of Study for Initial Licensing Training 22, 85-51-04/0PS Establ,sh Corrective Actions . for Examinations &

Training Records Not Retained

23. 85-55-02/0PS Ensure Applicant Verification of Module 3A Review 1

Sheet for RG 1.68A.1J (9) .,

24. 85-62-02/QAS Scope of Appendix E is % consistent with Contents
25. 85-62-03/QAS Audit Materix & Finc .g Matrix of; Appendix E Fail to Involve All Violations Germane to Materials Control
26. 85-62-04/QAS Ramsey to Foster Letter Addresses Structural Steel -

l

27. 85-62-05/QAS Readiness Review Finding El is Classified as Level III, Which is Inappropriate )
28. L5-62-10/QAS Aud'it Summary Inconsistent in Number of Audit ~

Findings l

29. 85-62-11/QAS EMLS of Safety Injection Pumps & Motors Contain Errors
30. 85-C2-12/QAS Improper Classification of Violations for Records 31, 85-62-13/QAS Regulatory Guide 1.28 Not Included
32. 86-IN-27/PSEC Access Control at Nuclear Facilities
33. 86-07-01/MPS Module 8 Items Assigned to Other Modules e
34. 86-13-04/PSS Implementation of Permanent Plant Fire Protection Program During Area Turnovers
35. 86-31-03/RP3C Separation of Unit 2 Const. Activities from Unit 1 to Prevent Interference with Unit 1 Operation
36. 86-31-06/RP3C Review Site Procedure 00402-C, Licensing Document Change Request, for Resolution of Comments

t' l

l Enclosure 1 Attachment 1A 6 l

l

37. 86-31-07/RP3C Review Maintenance Procedure 20427-C for l Incorporation of the ANSI Requirement to Document i Closeout Inspection Results
38. 86-39-02/MPS Field Confirmation of Distance Between Welded l Attachments & the Location of Intermediate Pipe Breaks 1
39. S6-39-03/MPS Failure to Follow Procedures for Control of Welding Consumables
40. 86-40-01/PSEC Intrusion Alarm Commitments in Fuel Storage Plan
41. 86-40-02/PSEC Penetrations in Vital Area Barriers
42. 86-40-03/PSEC Penetration in Vital Area Barrier
43. 86-40-04/PSEC Protection of Interim Barrier i
44. 86-40-05/PSEC Citing of Protected Area Microwave Equipment
45. 86-45-03/PSS Qualified Replacement for IPT0934-0935-0936 1
46. 86-51-04/RP3C Review Licensee Procedure Changes to 10000-C &

10006-2 47, 86-52-01/TPS Review Evaluation of 00R T-1-86-1839 i

48. 86-53-01/PSS Stressing Ram Calibration & Conversion Accuracy
49. 86-55-02/PSS Inadequate Procedural Implementation for Control'of I Combustibles Within Safety-Related Plant Areas l a
50. 86-55-05/PSS Functional Testing of Hydrogen Gas Excess j
51. 86-57-01/TPS Verify Heat Removal Sys. Testing During HFT ]
52. 86-12-78/EPS Procedure Should Include Telephone Number for TSC i or EDF if Radio Fails l l
53. 86-12-79/EPS Procedure Should Include Section on Radiological  !

Control Air Sample Filters

54. 86-12-81/ dP S Emergency Procedure 91302-C Should Reference Plant .

Health Physics Manual Procedure to Sample Air & l Calculate Air Activities 55, 86-12-89/EPS Complete Implementing Procedure 33065-C 1

l l

l L j

1 Encic3ure 1

-t 1A 7

l I

56 86-12-93/EPS Complete Security Computer System, Detection System, Perimeter Protection Area Barrier &

Permanent Badge System 57, 86-12-94/EPS Checklist EPIP in 91308-C, Rev 1 is not referred to Procedural Text 58, 86-12-99/EPS References to Batteries on the Inventory Should Be Specific

59. 86-12-101/EPS The Dissemination of Public Brochures 4
60. 86-12-102/EPS The Dissemination of Emergency Radios
61. 86-12-103/EPS The Design & Installation of an Emergency Siren System
62. 86-12-110/EPS Perform a Study or Drills to Verify Ability to I I

Meet Minimum Augmentation Criteria in NUREG-0654, Rev. 1 Section II.H (7.2.4)

63. 86-12-112/EPS Complete Training of On-Shif t HP Foreman in Dose i Assessment & Protective Action Recommendation Formulation
64. 86-12-08/FRP Complete GET Training for all personnel onsite to ,

be Badged to Enter the Protected Area  !

l

65. 86-12-47/FRP Install, Calibrate, Test & Otherwise Make Operational all Plant Areas Radiation Monitors ,
66. 85-55-01/0PS Incomplete Identification of Implementing Documents Within Commitment Tracking System
67. 86-12-21/EPS Complete Installation & Testing Control Room Equipment used in Accident Detection /Mitiga, Classification, notification & Protective Action Recomm Formulation
68. 86-12-30/EPS Complete the Installation of the Telephone System
69. 86-12-45/EPS Correct the Discrepancy in Either Plan or Implementing Procedures Concerning the 1.ocation of the Field Monitoring Kits
70. 86-12-48/EPS Determine Accuracies of Petrological Parameters Transmitted by Microwave System RG-1.23 (4.2.1)
71. 86-12-49/EPS Displaying & Retrieving Petrological Data Through ERF Computer

s Enclosure 1 Attachment 1A 8

72. 86-12-54/EPS Specify Averaging Period for Petrological Data &

Correcting Reference to Sigma-Theta from our Level l

73. 86-12-61/EPS Complete Communication on Links with South Carolina Counties of Aiken, Darnwell and Allendale
74. 86-12-62/EPS Complete all Communication Links Specified in VEGPEP & Assurance of their Operability
75. 86-12-64/EPS Update EPIPS to Include Reserve Emergency Supplies

& Equipment & Tac Stocking Plan for Warehouse & I Designation of Primary Location for Same  !

76. 86-12-73/EPS Correct of Modify EPIP 91302-C as Necessary to ~

i Remove Administrative Deficiencies

77. 86-12-76/EPS Apparent Discrepancy Between HP-210 Detector Iodine Detection (5.4.2)
78. 86-12-01/EPS Responsibility for annual review of Emergency Plan
79. 86-12-03/EPS Description of emergency staffing assignments by corporate level personnel
80. 86-12 07/EPS Provisions for Tra t s. . ng of non-licensee )

augmentation personne%

81. 86-12-34/EPS Procedure for Transmitting sample analysis results during emergencies
82. 86-12-38/EPS Correcting the kit inventories to include missin'g items

- 83. 86-12-44/EPS EOF Kit equipment

84. 86-12-70/EPS Revise " Subsequent Operator Actions" of of f-normal procedures
85. 86-12-72/EPS

~

Conduct training and practical Drills for persons implementing IPIPs.

86. 86-12-97/EPS Inventc y of equipment and Supplies used in
  • emergency response
87. 86-12-98/EPS Revise Procedure 91702 r
88. 86-12-17/EPS Training for Emergency Response Organization Perrrsonel
89. 86-12-22/EPS Training of Control Room Personnel on equipment used in accident detection I

l Enclosure 1 Attachment 1A 9

90. 86-12-23/EPS Completion of installation and testing of TSC i ventilation system.
91. 86-12-47/EPS Installation of all plant area and process monitors
92. 86-12-58/EPS Completion of the ultimate goal of 100 SCBAs for backup use
93. 86-12-8'7/EPS Revise Procedure 33016-C to include instruction on '

valve numbers, etc.

94. 84-05-09/MPS Clarification of Commitments
95. 05-12/MPS Weld Symbols
96. 84-05-13/MPS Unqualified Weld Procedure  ;

~

97. 84-14-03/QAS Revision / Clarification of GO-T-01, to Rev.11
98. 85-30-08/TPS Add statement to future modules applying QA Controls
99. 85-41-01/QAS Verify QA review of Module 3A Findings av. 65-51-26/0PS Additional deversity in final and make up exams i 101. 85-54-01/0PS Review Continuing Training Program 102, 85-54-02/0PS Concern that Simulator Training does not meet ANS 3.5 ,

103. 85-55-01/0PS Incomplete identification of implementation documents within comm'tment Tracking System 104 86-31-02/RP3C Review Imp. of Neg. Logic Testing 105. 86-31-04/RP3C Review Minimum Shif.t Crew Requirements 106. 86-31-05/R*3C Review Authorization Levels for approval of 0.T.

107 86-51-01/RP3C Review Licensee Action for TMI-I.C.3 108. 86-51-Lt/RP3C Review Licensee Action for TMI-I.C.4 109. 86-51-03/RP3C Review Management Directive for TMI I.A.1.2 110. 86-55-03/PSS Verficiation of Fire Bridgade Personnel Qualification and Shift Fire Bridgade 111. 86-55-04/PSS Verification of C.A. of. Fire Prot. QA Open items

Enclosure 1 Attachment 1A 10 112. 86-56-02/MPS FSAR inconsistencies 113. 86-61-01/PSS Examine the longitudinal Bracing Program 114. 86-61-02/PSS Examine Methods .for Controlling 3h inch tube Steel Conduit Support 115. 86-61-03/PSS Incomplete verification of commitments 116. 86-61-04/PSS Review discrepancies on Section 6,1, Module 12 117. 86-61-07/PSS Examine Separation requirements for PT-405, PT-458, and LT-462 118, 86-61-08/PSS TI 977 Not installed according to Isometric Drawing 119. 86-61-09/PSS Review conditions when MOV-HV-25838 for interferes with valve position indicator 120. 86-61-11/PSS Review testing justification for Low Torque Hold Down Clips 121. 86-61-12/PSS Review Inadequate Separate of Conduit I

l I

l

.. j l

Enclosure 1 I ATTACHMENT IB OPEN, UNRESOLVED AND ENFORCEMENT ITEMS THAT MUST-BE CLOSED PRIOR TO INITIAL CRITICALITY A. There are no identified violations to be completed as of August 31, 1986.

B. There are no identified unresolved items or deviations to be completed as of August 31, 1986.

C. The following open and inspector followup items are required to be completed:

1. 84-34-02/PSS Fire Pump Installation Discrepancies
2. 84-34-04/PSS Two Hour Fire Rated Cabinet
3. 85-14-01/MPS Clarification of Liquid Penetrant Inspection Procedure 4 85-17-02/QAS Audit CP01-85/33 Followup l
5. 85-20-01/PSS Corrective Actions Relating to IEEE 384 Separation j
6. 85-20-02/PSS Review Documentation Requirements for Cable Clamps

& Entry F

7. 85-21-01/RP3C Revision to Requal_ify Concrete Expansion Anchors,,
8. 85-21-02/RP3C Review Revision to Class IE Battery Maintenance Procedures
9. 85-26-02/RP3C Review Licensee Action on IE Information Notices
10. 85-28-02/PSS Retrievability of Records
11. 85-30-04/TPS Revise FSAR Concerning Appendix J Requirements 4
12. 85-30-05/TPS Revise FSAR Concerning Containment Isolation Valve Leakage
13. 85-30-06/TPS Revise FSAR Concerning Secondary Side of 0+.eam Generators
14. 85-30-07/TPS Revise FSAR to be Consistent with ANSI /ASME on -3
15. 85-31-02/QAS Unavailable Early Procedure Revisions

I' Enclosure 1 2

Attachment 1B

16. 85-45-01/0PS Complete Resolution of Training Program & Qual .

Discrepancies

17. 85-51-03/0PS Procedural Definition
18. 85-51-06/0PS Reevaluation of Previously Regarded Examinations
19. 85-51-07/0PS Review the Grading of Previous Exams
20. 85-51-09/0PS Resolution of Concerns Surrounding Regarding
21. 85-51-13/0PS Procedural Definition Validation of Computerized Listing of Training i

22, 85-51-16/0PS Records i

23. 85-51-18/0PS Completion of Simulator Upgrade Modifications
24. 85-51-19/0PS Resolution of Walkthrough Concerns & Shift Experience Concerns
25. 85-51-25/0PS Evaluation of Additional Emergency Planning Training
26. 85-51-21/0PS Training Procedures Covering Lic & Cert Instructor Qualifications & Participation in Requal.
27. 85-51-22/0PS Evaluations of Instructors who Teach License Requal
28. 85-51-23/0PS Resolution of Concerns with Course Content Adequacy
29. 85-51-25/0PS Additional Emergency Planning Training
30. 85-62-06/QAS Storage Requirements for Electrical r.quipment l
31. 85-62-07/QAS Weatherproof & Outside Storage
32. 85-62-08/QAS Conflict in Number of Audits
33. 85-62-09/QAS Inpo Findings are Inconsistent l 34. 86-IN-55/PSEC Delayed Access to Safety Related Areas & Equipment
  • During Plant Emergencies
35. 86-03-01/MPS Strive Load Tracking Program
36. 86-09-03/RP3C Review Licensee Resolution Of Turned Over Instrumentation not Getting to Vault

1 Enclosure 1 b+a- rent 1B 3 i

37. 86-09-0!,/RP3C Review Licensee Action to Resolve HVAC Handswitch l Nomenclature 1

l l

l l

1 4

1 I

l I

I I

l l

l l

l l

l

. l l

1 Enclosure 1 ATTACHMENT IC, OPEN UNRESOLVED AND ENFORCEMENT ITEM THAT MUST BE CLOSED PRIOR TO EXCEEDING 5% POWER A. There are no identified violations to be completed as of August 31, 1986.

B. There are no identified unresolved items or deviations to be completed as of August 31, 1986.

C. There following open i.nd inspector followup items are required to be l cortp l eted .

1. 85-51-24/0PS Development & Conduct of Additional Tech Spec Training
2. 85-51-27/0PS Delineation of Performance Based Training Given to Maintenance Personnel
3. 85-51-29/0PS Proceduralization of Feedback of Operation Experience to Maintenance Personnel
4. 85-51-30/0PS Implementation of Continuin,g Education of QA Auditors l S. 85-51-31/0PS Improve QA Certification Exam Security
6. 85-51-32/0PS Expand QA Certification Examination Question Bank to insure Proper Exam Administration ,
7. 85-51-33/0PS Maintenance of Support Engineer Records
8. 85-51-34/0PS NRC Evaluation of Instructional Methods
9. 85-51-36/0PS Evaluation of the Use of Lesson Plan or other Uncontrolled Documents for Delineating FSAR Commitments

& the Establishment of Appropriate Controls

~

10. 85-55-03/0PS Resolve PRB Comment / Minute Deficiencies
11. 86-19-02/MPS Unavailable HVAC Filter Records e
12. 86-32-01/ REC Revise Procedure 33000-C, Step 6-5, to Delete Reference to Concentrating as Way to Improve LLD
13. 86-32-02/ REC Evaluation an Acceptable Alternative to Reporting Zero in the Semiannual Effluent Report
14. 85-55-03/0PS Resolve PRB Comment / Minute Deficiencies

Ii Enclosure 1 Attachment IC 2

15. 86-12-32/ REC Complete Equipment Installation & Insure Operational l and Procedure Adequacy for Post Accident Gas &

Particulate Effluent Sampling (4.1.1) 1

16. LS-12-33/ REC Complete all Procedures Required for Post Accident l Liquid Effluent Sampling (4.1.1)
17. 86-12-82/ REC Complete Procedures for Calibrations & Verification and Troubleshooting
18. 86-12-83/ REC Completion of Pass Training Once the System Becomes Operations & Updating Tracking System
19. 86-12-84/ REC Complete " Flagging" Process on Training Tracking System for Pass Personnel for Semi-Annual Training.
20. 86-12-86/ REC Final Placement Designated Equipment' at Local Panel, TSC Storage Cabinet & Radiochemistry Lab.
21. 86-12-86-REC Completion of Final Pass Operational Testing
22. 36-12-88/ REC Assure Volume of Vent Air Sampled Representative of Actual Effluent Activity (5.4.2)  !
o. so-12-90/ REC Develop and Implement a Procedure for Safety & l Accurately Sampling Liquid Effluents
24. 86-12-91/ REC Develop procedures for Safely & Accurately Analyzing Liquid Effluent Samples
25. 86-19-02/MPS Unavailable HVAC Filter Records
26. 86-32-01/ REC Revise Procedure 33000-C, Step 6-5, to Delete Reference to Concentrating as way to Improve LLD
27. 86-32-02/ REC Evaluate an Acceptable Alternative to Reporting Zero in The semiannual Effluent. Report

l::;

s Enclosure 1 ATTACHMENT 2 DEFICIENCY REPORTS THAT MUST BE CLOSED PRIOR TO FUEL LOAD 1

The Licensee will complete, to the satisfaction of the NRC, the following 10 CFR 50.55(e) and 10 CFR 21 items:

1. CDR81-19/MPS Design Calculations Concerning Primary Loop j Crossover Leg Pipe Supports j l
2. CDR82-22/RP3C Leaks in Containment Cooling Coil Units
3. CDR82-24/PSS RCS Wide Range Pressure Transmitters ,
4. CDR82-28/RP3C Bechtel Calculation I
5. CDR82-30/PSS Sheared Pinion Key in Limitorque Motor Operators
6. CDR82-32/PSS WVAC Duct Supports
7. CDR83-43/PSS Pullman Construction Industries Duct Shop Detail Welding
8. CDR83-46/MPS Pullman Power Products Hanger Reinspection Findings j 1
9. CDR83-47/PSS Westinghouse Gate Valve Position Indication ,
10. CDR83-53/PSS Control Level Electrical Penetration Protection l
11. CDR84-58/PSS Transamerica Delaval D/G Drive Couplings
12. CDR84-59/PSS Transamerica Delaval D/G Thrust Bearing Lubrication
13. CDR84-60/PSS Control Room Filtration Unit Housings 14 CDR84-61/PSS Nuclear Service Cooling Water Tower C ossover Piping Backfill Location
15. CDR84-6/PSS HVAC interior Duct Lining
16. CDR84-65/MPS Pullman Const. TND Duct Support Shop Welds
17. CDR84-68/MPS Radius on Opened Structural Members l 18. CDR84-69/PSS Limitorque Operation Motors Qualification
19. CDR84-70/MPS Bettis Damper & Valve Actuators

.i l

7 I

i Enclosure 1 Attachment 2 2

20. CDR84-73/MPS NSCW Piping System Design Temp.
21. CDR85-78/PSS Safety Grade Core Exit Thermocouple
22. CDR85-81/MPS Turbine Pedestal Seismic Calculations 23, CDR85-83/PSS Flux Mapping System Seismic Restraints
24. CDR85-84/PSS Elect. Cable Tray Holddown Clip Spring Nuts ]
25. CDR85-85/PSS CNTMT Tubing & Instmt. Supports ]
26. CDR85-86/TPS Inadvertent Capping of Accumulator Vent Lines l
27. CDR85-87/RP3C Space Htr Internal Wiring Burn Damage Limitorq.  ;
28. CDR85-88/MPS Longitudinal Pipe Breaks -
29. CDR85-89/PSS Transamerica Delaval DG CYL Head Weld Repair j i
30. CDR85-90/MPS Anchor Darling Main Feedwater Isolation Valves 1
31. CDR86-91/MPS Dresser IND Diaphragm Valves
32. CDR86-93/RP3C Process and Root-Vent-Drain Installation
33. CDR86-94/PSS Failure of Diesel Generator Intake 7 Exhaust Valves Springs
34. CDR86-95/TPS Voltage Drop During Ops of CNTMT Cooling Motors , ,
35. CDR86-96/MPS Cracks in Wheel Hubs of AAF ESF Air Hldg Units
36. CDR86-97/TPS Malfunction of RPS Permissive P-10 Function
37. CD456-98/TPS Failure of Worm Gear Sections in Manual OP Valves
38. CDR86-99/PSS No Calcs for Cable Internal Resistance During Loca
30. CDR86-100/PSS Sliced Cable Jackets Affect Environmental Qualification
40. CDR86-101/PSS Conduit Support Inst'is Not IAW Design Rqmts
41. CDR86-102/MPS Pipe Supports Installed to Supersede Criteria
42. CDR86-103/PSS Separation of Field Wires In Isolation Transformers
43. CDR86-104/PSS Seismic Separation of Electrical Components .

. . h Enclosure 1 Attachment 2 3 l

1

44. CDR86-105/PSS Improper Support of Cable in Vertical Raceway 1 l
45. CDR86-106/TPS Hi Noise & Vib. in Dragon Needle Valves  ;
46. CDR86-107/PSS Power Cables Routed in Solid Tray W/D Ventilated Covers l
47. CDR86-109/PSS DG HT Xchgr Tube Support Pits Not as Designed l
48. CDR86-110/PSS Damage to Diesel Generator Turbo Chg Impellers
49. CDR86-111/MPS CVCS Charging Pump Hold-Down Bolts Material ]
50. CDR86-112/MPS Defective Anchor Darling Shock Arrestors
51. CDR86-114/PSS Improperly Designed Circuit in Diesel Generator Breaker Circuit
52. CDR86-115/PSS Valve Liner Failure in Delaval Diesel Generators
53. CDR86-116/MPS Missing Lock Welds Anchor Darling Check Valves l 1
54. CDR86-117/TPS Ring Settings on Crosby Main Steam Safety Valves i l
55. CDR86-118/PSS Flaking of Positive Straps on 125 Volt DC Batteries
56. CDR86-120/PSS Failure in Valcor Company Solenoid Valves
57. CDR86-122/PSS Bearing Cavity Lubricant In Containment Coolers
58. CDR86-123/PSS GE Relay Type 12NG15AG3 in DG Panels
59. DRP85-01/RP3C Station Battery Operation, Maint, & Inspection
60. P2184-01/RP3C Fuel Control Levers on DG Engine are not Pinned
61. P2184-02/RP3C Bonney Force Lacks The Chemical Overcheck Documentation
62. P2184-03/RP3C Deficient Gimpel Valve for Aux. F/W Pump Drive Turbine
63. P2185-02/RP3C Possible Field Failure of Space Heaters Supplied on GE Motors 64 P2185-03/RP3C Failure of a Crankshaft Oil Pulg on TDI Diesel
65. P2185-04/RP3C Errors In-Core Exit Thermo Couple System During &

Af ter Hi Energy Line Break

66. P2185-05/RP3C Generator Control Panels Overheat

Enclosure 1 ATTACHMENT 3

-IE BULLETINS AND CIRCULARS THAT MUST BE CLOSE0 PRIOR TO FUEL LOAD l

The Licensee will complete, to the satisfaction -of the NRC, the following IE l

....s.:ns and Circulars:

1. 798U-02/MPS Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts
2. 79-BU-14/MPS Seismic Analyses for AS-Built Safety-Related Piping Systems  ;

1

3. 80BU-08/MPS Examination of Containment Liner Penetration Welds l
4. 818U-01/TPS Surveillance of Mechanical Snubbers
5. 818U-02/TPS Failure of Gate Type Valves to Close Against Differential Pressure
6. 85BU-01/TPS Steam Binding of Auxiliary Feedwater Pumps

/. 85BU-02/PSS Undervoltage-Trip Attachments of Westinghouse DB 50 l Type Reactor Trip Breakers

8. 858U-03/TPS Motor Operated Valve Common Mode Failures During Plant Transients, Due to Improper Switch Settings
9. S6BU-02/PSS Static "0" Ring Differential Pressure Switches Note: IE Circulars requiring additional followup will be delineated in the next report.

l l

1 l

l l

1; i

Enclosure 1 ATTACHMENT 4A TMI ACTION PLAN ITEMS THAT MUST BE CLOSED PRIOR TO FUEL LOAD The Licensee will complete to the ratification of the NRC, the following TMI Action Plant Requirements:

1. I.A.1.1/RP3C Shift Technical Advisor 1
2. I.A.1.2/RP3C Shift Supervisor Responsibilities l l
3. I.A.1.3/RP3C Shift Manning i 1
4. I.A.2.1/0PS Immediate upgrade of RO & SR0 training and l Qualifications l S. I.B.1.2/RP3C Evaluation of Organization & Management
6. I.C.1/RP3C Guidence for the Evaluation and Development of i Procedures for Transients and Accidents (

i

7. I.C.2/RP3C Shift and Relief Turnover Procedures B. I.C.3/RP3C Shift Supervisor Resp'onsibility 1
9. I.C.4/RP3C Control-Room Access l
10. I.C.S/RP3C Feedback and Operating Experience
11. I.C.6/0PS Verify Correct Performance of Operating Activities
12. I.C.7/TPS NSSS Vendor Review of Procedures
13. I.D.2/EPS Plant-Safety Parameter Display Console
14. II.B.1/RP3C Reactor-Coolant System Vents

~

15. II.B.2/FRP Plant Shielding
16. II.B.4/0PS Training for Mitigating Core Damage
17. II.D.1/TPS Relief & Safety Valve Test Requirements
18. II.D.3/TPS Valve Position Indication
19. II.E.1.1/TPS Auxiliary Feedwater System Evaluation
20. II.E.J.2/TPS Auxiliary Feedwater System Initiation and Flow l

l Enclosure 1 Attachment 4A 2 l

l l

21. II.E.3.1/RP3C Emergency Power for Pressurizer Heaters
22. II.E.4.1/RP3C Dedicated Hydrogen Penetrations i 23. II.E.4.2/RP3C Containment System Dependability l
24. II.F.1/ REC Subparts 2a and 26, Effluent Radiological l Monitoring, Sampling and Analysis l
25. II.F.1/FRP Subpart 2c, Containment High Range Radiation Monitor  !
26. II.F.1/RP3C Part 1 Procedures, Subparts 2d and 2e, Containment Pressure and Water Level Monitors
27. II.F.1/RP3C Subpart 2f Containment Hydrogen Concentration Monitor i
28. II.F.2/RP3C Instrumentation for Detection of Inadequate ,

Core-Cooling l

29. II.K.I.5/RP3C Review ESF Valves l
30. II.K.1.10/RP3C Operability Status )
51. II.K.I.19/RP3C Trip Per Low-Level B/S
32. II.K.3/RP3C Final Recommendations, B & 0 Task Force
33. III.A.I.2/EPS Upgrade Emergency Support Facilities J4. III.D.3.3/FRP Inplant Iodine Radiation Monitoring I
35. III.D.1.1/RP3C Primary Coolant, Outside Containment 1

1 l

1 1

Enclosu~e 1 ATTACHMENT 4B

)

TMI ACTION PLAN ITEMS THAT MUST BE CLOSED l PRIOR TO FULL POWER OPERATION  !

The Licensee will complete, to the satisfaction of the NRC, the following TMI Action Plan Requirements:

1. I.G.1/TPS Training During Low-Pcwer Testing
2. II.B.3/ REC Postaccident Sampling l l
3. I.C.8/RP3C Pilot Mointoring of Selected Emergency Procedure l

l l l

l i

o W

-Enclosure 1 ATTACHMENT 5 Review of Vogtle Readiness Review Program Modules and Appendices that must be completed prior to fuel load.

The reviewers will complete, to the satisfaction of the participating NRC Officers, the following VRRP Modules and Appendices:

MODELES LEAD CURRENT NO .

REVIEWER STATUS

4. Mechanical Equipment Piping & E. Girard Note 1 Components
6. Electrical Equipment M. Hunt (EG&G) Note 1 -

7.A Plant Operations & Support J. Rogge Note 2 9.A Radiological Protection J. Troup

-Note 1 9.8 Chemistry P. Stoddart Note 1

11. Pipe Stress & Supports S. Vias (EG&G) Note 1

'12. Electrical Cables & Terminesions M. Hunt (EG&G) Note 1 13.A Foundations & Backfill J. Harris Note 1 13.8 Coatings J. Harris Note 1 13.C Post Tensioned Containment J. Lanahan Note 1

16. NSSS J. York Note 1
17. Raceways M. Hunt Note 1 18.A HVAC W. Kleinsorge Note 2
19. Electrical Supports M. Hunt (EG&G)- Note 1
20. I&C M. Hunt (EG&G) Note 1 ,
22. Independent Design Review R. Parkhill (I&E) Note 2 -

No. APPENDIX CURRENT STATUS 21.C E urement Note 1 21.E Material Control Note 1 21.F Inspector Qualification / Note 1 Certification 21.G Measuring and Test Equipment Note 2 21.J Equipment Qualification Note 1 Note 1: Final Report in Preparation Note 2: Portion of Review not complete

1 ENCLOWRE 2 i I

Preoperational and Acceptance Testing Status Preoperational test phase (preoperational and acceptance test) is approximately 59 complete. The overall status of the test program is listed below.

NOTE: Some tests included in the status below may not be required prior to fuel i load. j i

Procedures Final Results Results I No. No.*in Reviewed

  • No.* Approval
  • Review"* )

Tests Progress By NRC Completed by GPC By NRC l I

Preoperational 160 51 45 44 9 3 Tests Acceptance 42 9 (N/A) 7 11 (N/A) I Tests ]

l

    • These numbers represent the combined total of both nondetailed verifications l and detailed reviews. l
  • Tne licensee may provide the NRC with a list of tests that they intend not to complete prior to fuel load. Following any NRC approval of the requested exemptions, the above Test Status will be revised to reflect tests required to be completed prior to fuel load, and tests delayed.

Status of the Open Preoperational Test / System Deficiencies for All System -

Tests as of August 31, 1986 (Categorization is by GPC.)

Deficiencies that impact fuel load: 4527 Deficiencies that must be resolved prior to exceeding 5% l power 8 Deficiencies that impact Commercial Operation: 15 Deficiencies required to be resolved by first refueling or after 1 Deficiencies that have not yet been assigned a category (may affect fuel load) 0

  • Total Deficiencies 4551 i (N/A) Not Applicable l

l

l Encicsure 2 2 States of Open OA Program - Initial Test Program and Nuclear Operations Ite.s as of August 31, 1986 (Categorizations is by GPC).

1 Def iciencies that impact fuel load: 1 Deficiencies that must be resolved prior to exceeding

4er: TBD Deficiencies that impact Commercial Operation: TBD DaHeiencies required to be resolved by first refueling TBD Deficiencies that have not yet been assigned a category: 46 (may affect fuel load) <

l Total Deficiencies 47 Status of Ocen Quality Concern Program Items as of August 31, 1986 (Categorizations is by GPC). l l

Cancerns that impact fuel lo6J: TbD Concerns that must be resolved prior to exceeding 5'. power: TBD C....ei.s that impact Commercial Operation: TBD l Cencerni required to be resolved by first refueling l or af ter: TBD l vo ~e r n > uiat have not yet been assigned a category: 114 pay ariect fuel load)

Total Open Concerns 114 l

l l

l

\ l 1

0

1 l

1 l

l ENCLOSURE 3 Construction Status As of Aug st 31, 1986, construction at Vogtle Unit 1 is essentially 96% complete.

COMMODITY COMPLETE Unit 1 Concrete' 99 Backfill 90 Large Pipe 99 Large Hangers 99 Small Pipe - 99 .

Small Hangers 96 Tubing Hangers 89 Tubing 99 HVAC Duct 99 Cable Tray 97 Conduit - PVC 96

-Rigid 94 wire & Cable 96 ,

Terminations 95 Pullman Instruments 97 Cleveland Instruments 94 Coatings 88 .

Additional General Items:

1. Preoperational procedure re-review as necessary.
2. Preoperational testing and systems demonstrations.
3. Fire protection system compliance (Penetration fire, seals, completion' of safe shutdown analysis, hardware modification, fire dampers, etc.)
  • 4 Readiness to implement security.
5. Resolution of 6 en Items, Deficiency Reports, Allegations and Punch ' List Items.
6. Technical Specification development.
7. Operational Drocedure development and review.
8. Completien c' the Radiation Protection and Radwaste systems.
9. Completion of the Emergency Preparedness facilities and program.
  • GPC has indicated that implementation of security is a critical path item.

I I

Enclosure 3 2 l

Status of Open Construction / System Deficiencies (Punch List) for all System Construction as of August 31, 1986 (Categorization is by GPC) j Deficiencies that ' impact fuel load: 1781 Deficiencies that must be resolved prior to exceeding 5% power: TBD ,

Deficiencies that im? set Commercial Operation: TBD  !

Deficiencies required to be resolved by first refueling or after: TBD Deficiencies that have not yet been assigned a category (may affect fuel load 8291 l l

Total Deficiencies 10,072 Status of Open 0A Program - Construction Items as of August 31, 1986 (Categorization is by GPC) i Deficiencies that impact fuel load: 4 Deficiencies that must be resolved prior to exceeding 5% power: TBD Deficiencies that impact Commercial Operation: TBD Deficiencies required to be resolved by first refueling er after: TBD Deficiencies that have not yet been assigned a category (may affect fuel load) 21 Total Deficiencies 25 TBD - To Be Determined i

l O

ENCLOSURE 4 Status of Inspection Required By MC 2512, 2513, and 2514 All modules in the NRC Region II inspection program required to be complete prior l to fuel load have been completed except the following:

NOTE:

Identified with each module title are the division and/or section responsible for completing the module. Abbreviations used for the organizations are listed below:

Division of Reactor Projects ORP Brarch 3, Section C RP3C Resident Inspector RI Division of Reactor Safety DRS Materials and Processes Section MPS Plant Systems Section PSS Test Programs Section TPS Operational Programs Section OPS Quality Assurance Program Section QAS Operator Licensing Section OLS Division of Radiation Safety and Safeguards DRSS Emergency Preparedness Section EPS Physi., Security Section PSEC Facil _ os Radiation Protection Section . FRP Eny' ~aental Protection Section EPS l

MC 2512 - Construction Phase Procedure Percent Reason Not Number Complete Resp. Title Comolete 30050 0 0RP CP Corporate Management Meeting Note 1 35020 0 -

QAS Audit of Applicant's Surveillance Note 1 I of Contractor QA/QC Activitier 35100 10 QAS Review of QA Manual (Reference Note 1 procedure) 35960 L* QAS QA Program Evaluation of Engineering Note 1 Service Organization ,

0AS Verification of As-Builts Note 1 37051 0 42051 C 85 RI Fire Prevention / Protection - Observa- Note 1 tion of Work and Work Activities 4605E B 0 PSS Structural Concrete Record Review Note 1 49051 0 MPS Reactor Coolant Pressure Boundary Note 1 Piping - Review

Enclosure 4 2 49055 40 MPS Reactor Coolant Pressure Boundary Note 1 Piping Record Review j 49061 0 M P. S Safety-Related Piping - QA Review Note 1 l 49063 60 MPS Safety-Related Piping - Work Note 1 l Observation 49065 30 MPS Safety-Related Piping - Records Review Note 1 50051 20 MPS Reactor Vessel and Internals QA Review Note 1 50055 60 MPS Reactor Vessel and Internals Record Note 1 Review 50071 30 MPS Safety-Related Components - Procedure Note 1 Review 50075 50 MPS Safety-Related Components - Records Note 1 )'

Review 50090 45 MPS Safety-Related Pipe Support and Note 1 Restraint Systems 50095 0 MPS Spent Fuel Storage Racks Note 1 50100 60 MPS Safety-Related Heating, Ventilation Note 1 and Air Conditioning (HVAC) Systems 51053 60 PSS Electrical Components and Systems - Note 1 Work Observation 51055 60 PSS Electrical Components and Systems - Note 1 Records Review 51061 80 PSS Electrical Cables Procedure Review Note )

51063 70 PSS Electrical Cables Work Observation Note 1 51065 50 PSS Electrical Cables - Records Review Note 1 52051 10 PSS Instrument Components and Systems - Note 1 Procedure Review i 52055 0 PSS Instrument Components and Systems - Note 1 Records Review 53051 0 MPS Containment Penetrations - Procedure . Note 1 Review 53053 0 MPS Containment Penetration (Mechanical) Note 1 Work Observation 53055 0 MPS Containment Penetrations - Note 1 Record Review 55093 B

~

0 MPS Reactor Vessel Internals (Welding) - Note 1 Observation of Welding and

., Associated Activities 55150 0 MPS Weld Verification Checklist Note 1  !

55158 8 70 MPS Steel Structures & Supports - Note 1 55175 B 0 MPS Reactor Coolant Loop Piping - Visual Note 1 Examination of Welds 55176 0 MPS Reactor Coolant Loop Piping Weld Heat Note 1 Treatment 55178 8 0 MPS Reactor Coolant Loop Piping - Special Note 1 Welding Applications 57070 85 MPS Magnetic Particle Examin. tion / Work Note 1 Observation / Record Review 57080 60 MPS Ultrasonic Examination / Work Note 1 Observation / Record Review ,

i

Enclosure 4 3 57090 85 MPS Radiographic Examination / Work Note 1 Observation / Record Review 63050 0 PSS Containment Structural _ Integrity Note 1 Test 65051 0 FRP Low Level Radioactive Waate Stor:,ge Note 1 Facilities 73051 95 MPS Inservice Inspection - Review of Note 1 Program 73052 95 MPS Inservice Inspection - Review of Note 1 Procedures 73053 B 60 MPS Preservice Inspection - Observation Note 1 of Work and Work Activities 73055 B 95 MPS Preservice Inspection - Data Review Note 1 and Evaluation 80210 0 1MEP Environmental Protection - Initial Note 1-and Periodic Inspections 94300 B 25 0RP Operating License Issuance Note 1 It is estimated that the MC 2512 program is approxic.ately 80 complete as of August 31, 1986.

Note 1: Inspection activity is scheduled or in progress.

Note 2: Significant deficiencies exist that require licensee action prior to module completion.

0 1

1 Er.:lesure 4 4 MC 2513 - Preoperational Testing and Operational Preparedness Phase frececure Percent Reason Not N -bor Resp. Complete Title Complete

~ T51iO1 QAS 0 Preoperational Testing Quality Note 1 Assurance 35740 B QAS 0 QA Program - QA/QC Administra- Note 1 tive s, . 8 QAS 0 QA Program - Audits Note 1 35742 B QAS 0 QA Program - Document Control' Note 1 35743 0PS 0 QA Program - Maintenance Note 1 35744 8 QAS 0 QA Program - Design Changes and Modification 35745 8 QAS 0 QA Program - Surveillance Testing Note 1 and Calibration Control 35746 B QAS 0 QA Program - Procurement Control Note 1 35747 QAf 40 QA Program - Receipt, Storage, Note 1 and Handling of Equipment and Materials 357d8 8 0AS 0 QA Program - Records .

Note 1 35749 8 QAS 0 QA Program - Tests and Experiments Note 1 35;'60 0AS 40 QA Program Measurement Test Note 1 Equipment 36301 B RI 80 Operational Staffing Note 1 37301 RI 45 Comparison of As-Built Plant to Note 1 FSAR Description 39301 8 QAS 0 Preoperational Test Records Note 1

-uaut e RI 0 Safety Committee Activity Note 1 41301 0PS 50 Operating Staff Training .

' ' RI 35 Plant Procedures Note 1 l 42450 B 0PS 0 Operation Procedures Nbte 1 l 42451 B 0PS 0 Maintenance Procedures Note 1 l 42452 B 0PS 0 Emergency Procedures Note 1 ,

60501 B RI 30 Fuel Receipt and Storage Note 1  !

64703 PSS 75 Fire Protection / Prevention Program Note 1 j 70301 TPS 100 Overall Preoperational Test Program Note 1 Review 70302 RI 20 Preoperational Test Program Note 1  ;

Implementation 70304 B TPS 0 Engineered Safety Features Test - Note 1 Preoperational Test Procedure Review 70305 B T P *. 50 Reactor Protection System Test - Note 'l Preoperational Test Procedure Review 70306 B TPS 0 Loss of Offsite Power Test - Note 3 Preoperational Test Procedure Review

- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - - -  :]

Enclosure 4 5 70307 8 TPS 10 Preoperational Test Procedure Note 13 Review - (Containment Integrated i Leak Rate Test) 70311 TPS 0 Preoperational Test Procedure Note 1 Verification 70313 TPS 10 CILRT Witnessing Note 13 70316 B TPS 0 Loss of Offsite Power Test - Note 1 i Preoperational Test Witnessing 70317 8 TPS 0 Reactor Protection System Test - Note 2 Preoperational Test Witnessing J 70322 B TPS 40 Preoperational Test Results Note 4  !

Evaluation - ESF 70323 TPS 0 Preoperational Test Results Note 4 Evaluation - (Containment Integrated Leak Rate Test) l 70324 B TPS 0 Preoperational Test Results Note 11 Evaluation - Hot Functional Testing 70325 B TPS 0 Preoperational Test Results Note 4 Evaluation - Reactor Protection System 70326 B TPS 0 Preoperational Test Results Note 4 Evaluation - Loss of Offsite Power 70329 8 TPS 0 Preoperational Test Results Note 1 Evaluation Verification 70370 B TPS 70 Testing of Pipe Support and Note 4 Restraint Systems 71301 B DRP 5 Technical Specification Review Note 5 71302 RI 20 Preoperational Test Program Note 2 Implementation Verification 79501 IMEP 0 LWR Water Chemistry Control and Note 1 Chemical Analysis 79502 IMEP 0 Plant Systems Affecting Plant Note 1 Water Chemistry ,

80521 IMEP 0 Radiological Environmental Note 1 Monitoring 81018 PSEC - 75 Security Plan and Implementing Note 6 Procedures 81020 PSEC 0 Management Effectiveness - Security Note 6 Program 81022 PSEC 75 Security Organization Note 6 81034 PSEC 0 Security Program Audit Note 6 81038 PSEC 0 Records and Reports Note 6 81042 PSEC 0 Testing and Maintenance Note 6 81046 PSEC 0 Locks, Keys, and Combinations Note 6 81052 PSEC 60 Physical Barriers - Protected Areas Note 6 81054 PSEC 40 Physical Btrriers - Vital Areas, Note 6 Material Access Areas, and Controlled Access Areas a

1 Enclosure 4 6 {

81058 PSEC 0 Security System Fower Supply Note 6 [

81062 PSEC 0 Lighting Note 6 j 81064 PSEC 50 Compensatory Measures Note 6 )

81066 PSEC 30 Assessment Aids Note 6 81070 PSEC 30 Access Control - Personnel Note 6 S1072 PSEC 0 Access Control (Power Reactor) - Packages Note 6 81074 PSEC 0 Access Control - Vehicles Note 6 81078 PSEC 30 Detection Aids - Protected Areas Note 6 81080 PSEC 0 Detection Aids - Vital Areas, Note 6 Material Access Areas, and Controlled Access Areas 81084 PSEC 70 Alarm Stations Note 6 81088 PSEC 25 Communications Note 6 81401 PSEC 0 Plans, Procedures, and Reviews Note 1 81403 PSEC 0 Receipt of New Fuel at Reactor Note 1 Facilities i 81431 PSEC 0 Fixed Site Physical Protection Note 1 of Special Nuclear Material of Low Strategic Significance 81501 PSEC 25 Personr:e1 Training and Qualifica- Note 6 tion - General Requirements 81601 PSEC 0 Safegurrds Contingency Plan Note 6 Implementation Review eiew PSEC 0 Physical Protection Safeguards Note 6 Information 92522 FRP 0 Rad Protection, Plant Chemistry, Note 1 Radwaste, and Environmental:

Organization and Management Controls 83523 FRP 0 Rad Protection, Plant Chemistry, Kote 1 Radwaste, Transportation and Environmental: Training and Qualifications 83524 FRP 0 External Occupational Exposure Note 1 Control and Personal Dosimetry 83525 FRP 0 Internal Exposure Control and Note 1 Assessment 83526 FRP -

0 Control of Radioactive Materials '!

and Contamination, Surveys, and Note 1 Monitoring 83527 FRD 0 Facilities and Equipment Note 1 83528 FR* 0 Maintaining Occupational Exposures Note 1 ALARA 84522 FRP 0 Solid Wastes Note 1 84523 EPS 10 Liquids and Liquid Wastes Note 1 84524 EPS 10 Gaseous Waste System Note 1 84525 EPS 10 Radiological and Chemical Note 1 Confirmatory Measurements 85102 MCA Material Control and Accounting Note 1 (Reactor)

1

.. j i

)

Enclosure 4 7 1

)

Procedure Percent Primal Test / Test Procedure Review Reason Not Number Resp. Complete Title Complete

)

I The inspection requirements for Primal Test procedure review and test witnessing has been completed.

It is estimated that the MC 2513 Program is approximately 40% percent complete as of July 30, 1986 Note 1: Inspection in progress or scheduled.

Note 2: Preoperational testing is still in progress and is being witnessed in <

accordance with an estabilshed schedule.

Note 3: Waiting for approved procedures from licensee. j Note 4: Waiting for approved test results from licensee.

Note 5: Significant deficiencies exist that require licensee action prior to module completion.

Note 6: Licensee must first complete and implement the Security System. )

l Note 7: Waiting completion of preoperational testing prior to module completion.

Note 8: Waiting completion of f acilities and programmatic licensee activities l prior to module completion. l l

Note 9: Waiting on licensee to perform test. -

1 Note 10: Programmatic protion of modules are complete to support fuel load, implementation portion will be completed approximately 6 months after fuel load.

Note 11: Inspection complete, report not issued.

h

A Enclosure 4 8 l

MC 2514 - Startup Testing Phase  !

Procedure Percent Reason Not i Comolete Resp. Title Complete Number 35501 0 QAS QA for the Startup Test Program Note 1 72300* 0 TPS Startup Test Procedure Review Note 2 ,

72301* 0 TPS Startup Test Results Evaluation Note 3 l 72302" 0 TPS Startup Test Witnessing and Note 3 Observation 724008 0 TPS Overall Startup Test Program Note 3 725008 0 TPS Initial Fuel Loading Procedure Note 2 72524 0 TPS Initial Fuel Loading Witnessing Note 3 82301 0 EPS Evaluation of Exercise for Power Note 3 l Reactors l 83521 0 FRP Radiation Protection - Startup- Note 3 l 84521 0 REC Radwaste - Startup Note 3

, 72564 B 0 TPS Precritical Test Procedure Review Note 2 (Protective Trip Circuit, Group-B, and Rod Drop Measurement, Group A) 72566 B 0 TPS Precritical Test Procedure Review Note 2 (RCS Leak Test, Group A, and Pressurizer Effectiveness, Group E',

72570 8 0 TPS Initial Criticality Procedure Review Note 2 i (Group A and B) 72772 B 0 TPS Low Power Test Procedure Review Note 2 (Moderator Temperature Coefficient Measurement and Boron Reactivity Worth, Group B, and Rod Worth and Pseudo Rod Ejection, Group A) $

72576 B 0 TPS Power Ascension Test Procedure Review Note 2 (Natural Circulation, Group A, and Power Reactivity Coefficient l Measurement, Group B) l 72578 8 -

0 TPS Power Ascension Test Procedure Review Note 2 l (Evaluation of Core Performance)

(Group A and B) l 72580 B 0 -

TPS Power Ascension Test Procedure Review Note 2 (Turbine Trip, Group B, and Generator Trip, Group A) 72582 B 0 TPS Power Ascension Test Procedure Note 2 Review: Loss of Offsite Power (Group A and B) 72583 B . 0 TPS Power Ascension Test procedure ~ Note 2 Review: Shutdown from Outside the Control Room (Group B) 72584 B 0 TPS Power Ascension Procedure Review Note 2 (Evaluation of Flux Asymmetry or Pseudo Rod Ejection Test) (Group A)

i Enclosure 4 9 l

1 72502 0 TPS Initial Criticality Witnessing Note 3 l 72596 B 0 TPS Precritical Data Review Note 3 72600 B 0 TPS Power Level Plateau Data Review (25%) Note 3 l 72608 8 0 TPS Power Level Plateau Data Review (50%) Note 3 72616 8 0 TPS Power Level Plateau Data Review (75%) Note 3 72624 8 0 TPS Power Level Plateau Data Review (100%) Note 3  !

The MC 2514 Program has not commenced as of August 31, 1986.

  • For tracking procedure review and verification of startup Test Program. I Note 1: Inspection in program or scheduled.

Note 2: Waiting for approved procedures from licensee.

Note 3: Will complete after issuance of OL.

1 l

0 919L 2872

.

Retrieved from "https://kanterella.com/w/index.php?title=ML20236F255&oldid=3273925"