ML20215F564

Forwards Info on Status of Licensing Preparedness,Including Insp Items.Fuel Load Date Estimated as 861229

ML20215F564
Person / Time
Site:	Vogtle
Issue date:	12/16/1986
From:	Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Novak T Office of Nuclear Reactor Regulation
Shared Package
ML20215F555	List: ML20215F552 ML20215F564
References
NUDOCS 8612230454
Download: ML20215F564 (28)

Text

~

ENCLOSURE as marg UNITE 3 STATES

• O/* \g 'o NUCLEAR REGULATORY COMMIS$10N REGION li h s 101 MARIETTA STREET.N W.

• ATL ANTA. G EORGI A 30323

's, ,6

• ==**

DEC 161986 MEMORANDUM FOR: Thomas M. Novak, Acting Director, Division of Pressurized Water Reactor Licensing-A, NRR FROM: Roger D. Walker, Director, Diviston of Reactor Projects

SUBJECT:

GEORGIA POWER COMPANY - V0GTLE UNIT 1 DOCKET NO. 50-424, STATUS OF FACILITY COMPLETION, SECOND REPORT This memorandum is forwarded in accordance 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 (GPC) estimates a fuel load date of December 29, 1986.

Region II considers that GPC will be ready within -0 + 30 days of that date assuming that no unforeseen delays occur in the licens 's re aining construction and preoperational testing effort.

1 Roger D. Wal

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 MC 2514 cc w/encls:

J. G. Partlow, Director, IP, IE E. L. Jordan, Director, DEPER B. K. Grimes, Director, DQAVTTCP M. A. Miller, Manager, NRR F. Hawkins, IE 424 g22ghe6[pog 05 A

m .

ENCLOSURE 1 OUTSTANDING ITEMS INCLUDING ENFORCEMENT AND UNRESOLVED ITEMS At this date, all outstanding construction items are expected to be resolved 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 report.

I. Open, Unresolved and Enforcement Items Attachment I to. Enclosure 1 is a list of all open, unresolved and enforce-ment items that must be resolved to the satisfaction of the NRC prior to fuel load, initial criticality, and exceeding 5% power.

Summary

1. There are 37 open items, 8 unresolved items, and 7 enforcement items that must be resolved prior to fuel load.

2. There are 56 open items, 0 unresolved items, and 0 enforcement items that must be resolved prior to initial criticality.

3. There are 12 open i_tems, 0 unresolved items and 0 enforcement items that must be resolved prior to exceeding 5% power.

II. Open Deficiency Reports - 10 CFR Part 50.55(e) and 10 CFR Part 21 Reports Attachment 2 to Enclosure 1 is a list of all Deficiency Reports that must be resolved to the satisfaction of the NRC prior to fuel load.

Summary There are twenty-seven 10 CFR Part 50.55(e) reports and no 10 CFR Part 21 reports that must be resolved prior to fuel load.

III. IE Bulletins and Circulars Attachment 3 Enclosure 1 is a list of all Bulletins that must be resolved to the satisfaction of the NRC prior to fuel load.

Summary There are 8 Bulletins that must be resolved prior to fuel load.

IV. TMI Action Plan Attachment 4 to enclosure 1 is a list of all TMI Action Plan items that must be resolved to the satisfaction of the NRC prior to fuel load exceeding 5%

power and full power operation.

f

' Enclosure 1 2 Summary

1. There are 24 TMI Act, ion Plan items that must be resolved prior.to fuel load.

2. .There are 4 TMI Action Plan items that must be resolved prior to-exeeding 5% power.

3. There are 2 TMI Action Plan items that must be resolved prior to full power operation.

~

V. Vogtle Readiness Review Program (VRRP)

Attachment 5 to Enclosure 1 is a list of 4 VRRP modules and 1 appendix which are in the final stages of completion. It is anticipated that these modules and appendix reviews will be completed prior to fuel load.

VI. .Open Allegations There -are currently Twenty-seven open Allegations that are assigned to the Region II staff. It is expected that these allegations will be-reviewed prior to fuel load to determine the safety significance of each item.

Items of safety significance will be resolved and corrective action taken to the satisfaction of the NRC prior to the operational mode for which the item is require.

Enclosure 1 ATTACHMENT 1A OPEN, UNRESOLVED AND ENFORCEMENT ITEMS THAT MUST BE RESOLVED PRIOR TO FUEL LOA 0 A. The licensee will implement corrective actions for the following violctions to the satisfaction of the NRC.

1. 85-06-03/MPS Filler Plate: with Pipe Straps are Being Utilized Without Proper Documentation

2. 85-12-01/MPS Failure to Follow Procedures for Hanger Installation & Inspection

3. 86-61-13/PSS Failure to Maintain Control of QC Accepted Conduit Supports

4. 86-60-01/RP2C Failure to Implement Adequate Design Control

5. 86-31-08/PSS Failure to Follow Procedures for Protecting Installed Equipment / Components

6. 86-39-01/MPS Failure to Provide Accurate Information for Elimination of Intermediate Pipe Breaks &

Associated Whip Restraints

7. 86-118-01/TPS Failure to document diesel generator starts.

B. The licensee' will complete the following unresolved items or deviations to the satisfaction of the NRC:

1. 84-35-04/PSS Discrepancy Punchlist for Cable Terminations

2. 85-28-05/PSS Use of Shear Bars in the Auxiliary Building Base Mat

3. 85-40-02/MPS Assurance of Adequate Back Purge for Welding Stainless Steel Piping

4. 86-56-01/MPS Failure to Revise FSAR as Complete

5. 86-61-05/PSS Review Commitments to RG 189 Rev. O, vs RG 189, Rev. 1

6. 86-61-10/PSS Review FSAR Commitments to IEEE 317, 1976, for Chemical Spray of electrical penetrations

'. Enclosure 1-Attachment 1A 2

7. 86-64-05/PSS QA Program for fire Protection System Installation does not. meet NRC Branch Technical Position CMEB 9.5-1

8. 86-99-01/TPS Sequence of Tests during Power Escalation.

C. The licensee will complete the following open items to the satisfaction of the NRC:

1. 85-10-03/PSS Review Inspection Records That May be Incomplete Due to DR Closecuts

2. 85-22-01/MPS Reinspection & Evaluation of Rock Bolt Inspections

3. 85-28-04/PSS Acceptance of Response to Concept No. 3 Without Reviewing Calculations

4. 85-40-01/MPS Assurance of Necessary Minimum Clearance for Installed Piping

5. 85-44-01/QAS Verify QA Audit of Module 5 Findings & Corrective Action

6. 85-55-02/0PS Ensure Applicant Verification of Module 3A Review Sheet for RG 1.68A.1J (9)

7. 86-31-03/RP3C Separation of Unit 2 Const. Activities from Unit I to Prevent Interference with Unit 1 Operation

8. 86-31-06/RP3C Review Site Procedure 00402-C, Licensing Document Change Request, for Resolution of Comments

9. 86-31-07/RP3C Review Maintenance Procedure 20427-C for Incorporation of the ANSI Requirement to Document Closecut Inspection Results

10. 86-39-02/MPS Field Confirmation of Distance Between Welded Attachments & the Location of Intermediate Pipe Breaks

11. 86-40-03/FSEC Penetration in Vital Area Barrier

12. 86-40-04/PSEC Protection of Interim Barrier

13. 86-12-93/PSEC Complete Security Computer System, Detection System, Perimeter Protection Area Barrier &

Permanent Badge System J

- - _- . ~

' Enclosure 1 Attachment 1A 3

14. 85-55-01/0PS Incomplete Identification of Implementing Documents Within Commitment Tracking System

15. 86-12-61/EPS Complete Communication on Links with South Carolina Counties of Aiken, Darnwell and Allendale

16. 85-30-08/TPS Add statement to future modules applying QA Controls

17. 85-41-01/QAS Verify QA review of Module 3A Findings

18. 86-31-02/RP3C Review Imp of Neg. Logic Testing

19. 86-51-01/RP3C Review Licensee Action for TMI-I.C.3

20. 86-51-02/RP3C Review Licensee Action for TMI-I.C.4

21. 86-51-03/RP3C Review Management Directive for TMI I.A.1.2

22. 86-56-02/MPS FSAR inconsistencies

23. 86-61-02/PSS Examine Methods for Controlling 3 inch tube Steel Conduit Support

24. 86-61-03/PSS Incomplete verification of commitments

25. 86-61-04/PSS Review discrepancies on Section 6.1, Module 12

26. 86-64-03/PSS Pre-Fire plans ~ fail to properly identify adequate fire brigade strategies

27. 86-64-04/PSS Automatic sprinkler systems do not meet FSAR design commitments

28. 86-64-06/PSS Licensee to provide design / test control data for fire barrier penetration seals

29. 86-64-07/PSS Fire Detection System for the main control room complex fails to comply with SSER 1 committeents

30. 86-65-01/TPS Review corrective action for dresser RTD vlaves

31. 86-65-02/TPS Review corrective action to prevent CAFW Exaust into B Diesel Building

32. 86-65-03/TPS Review Final Resolution to MSIV coil failures &

subsiquent retest I

33. 86-65-04/TPS Review Resolution for documentation of deficiencies when using operations procedures to satisfy preoperational tests

-4 r - . - , , - , . . - , - , - - , , , . --.,..n.- - , . - ---~-,,--,.--w- , , . , ------.-n -v.. - - - - - - - - ~ -

• Enclosure 1 Attachment IA 4 34 86-65-05/TPS Verify FSAR Revision to specify variable pressurizer PORV setpoint

35. 86-65-06/TPS Followup on final resolution to errneous safety i njecti cr. signal during shif t of control to remote shutdown panels

36. 86-71-01/PSEC Access control at primary portal

37. 86-73-03/TPS Delete use of makeup to VCT during RCS leakage measurements

( .-

Enclosure 1 ATTACHMENT IB. -

OPEN. UNRESOLVED AND ENFORCEMENT ITEMS THAT MUST BE RESOLVED PRIOR-T0 INITIAL CRITICALITY A. There are no identified violations to be completed as of. November 30,~1986.

! B. There are no identified unresolved items or deviations to be completed as of

November 30, 1986.

C. .The licensee will complete .the following open and inspector followup items to the satisfaction of the NRC:

1. 85-21-01/RP3C Revision to Requalify Concrete Expansion Anchors

2. 85-26-02/RP3C Review Licensee Action on IE Information Notices

.3. 85-28-02/PSS Retrievability of Records

4. 86-09-03/RP3C Review Licensee Resolution Of Turned Over

{ Instrumentation not Getting to Vault

5. 86-09-05/RP3C Review Licensee Action to Resolve HVAC Handswitch -

Nomenclatu're

'6. 86-12-23/ REC Completion of installation and testing of TSC l

ventilation system.

2 I

i l

t, t

i I

l i t r t

- - - - ~ _ . . _ . _ _ , - _ _ . _ - . . _ _ . . - . - . , _ _ . _ , - _ - , _.._,.,.,,-...m. . . . _ _ _ . - , _..-._._.-4

r Enclosure 1 ATTACHMENT IC OPEN UNRESOLVED AND ENFORCEMENT ITEM THAT MUST.

BE RESOLVED PRIOR TO EXCEEDING 5% POWER A. There are no identified violations to be completed as of November 30,-1986.

B. There are no identified unresolved items or deviations to be completed as of November 30,'1986.

C. The licensee will complete the following open and inspector followup items-to the satisfaction of the NRC:

1. 84-34-01/PSS Removal of all combustible scaffolding, planking a temporary construction structures.

2. 86-40-05/PSEC Siting of Protected Area Microwave Equipment

3. 86-12-47/FRP Install calibrate and otherwise make operational all plant areas Radiation Monitors

4. 86-55-04/PSS Verification of C. A. of Fire Protection QA Open Items

5. - 85-20-01/PSS Corrective Actions Relating to IEEE 384 Seperation

6. 85-20-02/PSS Review Documentation Requirement for Cable Clamps to and Entry F.

7. 85-21-02/RP2C Review Revision to Class 1E Battery Maintenance Procedures

8. 85-55-03/0PS Resolve PRB Comment / Minute Deficiencies

9. 86-12-32/ REC Complete Equipment Installation & Insure Operational and Procedure Adequacy for Post Accident Gas & Particulate Effluent Sampling (4.1.1)

10. 86-12-83/ REC Completion of Pass Training Once the System Becomes Operations & Updating Tracking System

11. 86-12-86-REC Completion of Final PASS Operational Testing 12, 86-12-88/ REC Assure Volume of Vent Air Sampled Representative of Actual Effluent Activity (5.4.2)

Enclosure 1 ATTACHMENT 2

. DEFICIENCY REPORTS THAT MUST'BE CLOSED PRIOR TO FUEL LOAD The Licensee will complete, to the satisfaction of the NRC, the following 10 CFR 50.55(e) and 10_CFR 21 items:

1. CDR83-43/PSS Pullman Construction Industries Duct Shop Detail Welding

2. CDR84-60/PSS Control Room Filtration Unit Housings

3. CDR84-65/MPS Pullman Const. TND Duct Support Shop Welds

4. CDR84-68/MPS Radius on Opened Structural Members

5. CDR84-70/MPS Bettis Damper & Valve Actuators

6. CDR85-78/PSS Safety Grade Core Exit Thermocouples

7. CDR86-91/MPS Dresser IND Diaphragm Valves

8. CDR86-93/RP3C Process and Root-Vent-Drain Installation

9. CDR86-96/MPS Cracks in Wheel Hubs of AAF ESF Air Hldg Units

'10. CDR86-97/TPS Malfunction of RPS Permissive P-10 Function

11. CDR86-98/TPS Failure of Worm Gear Sections in Manual OP Valves

12. CDR86-99/PSS No Calcs for Cable Internal Resistance During loca

13. CDR86-100/PSS Sliced Cable Jackets Affect Environmental Qualification

14. CDR86-102/MPS Pipe Supports Installed to Supersede Criteria

15. CDR86-103/PSS Separation of Field Wires In Isolation Transformers

16. CDR86-105/PSS Improper Support of Cable in Vertical Raceway

17. CDR86-118/PSS Flaking of Positive Straps on 125 Volt DC Batteries

18. CDR86-120/PSS Failure in Valcor Company Solenoid Valves

19. CDR86-122/PSS Bearing Cavity Lubricant In Containment Coolers

' Enclosure 1 Attachment 2 2

20. CDRS6-123/PSS GE Relay Type 12NG15AG3 in DG Panels

21. CDRS6-124/PSS Raychem Site Designed Electrical Splices

22. CDRS6-126/PSS Conax Electrical Penetrations with Holes

23. CDR86-127/TPS Containment Cooling Vents low Air Flow 24 CDR86-128/TPS DG Building Vent System Low Air Flow

25. CDRS6-130/TPS Main Steam Isolation Valve Enclosure Time

26. CDRS6-131/PSS Turb. Driven Aux. Feed Pump Governor Malfunction

27. CDR86-132/PSS Containment Purge System-Register Damper

A' s Encl'osure 1 ATTACHMENT 3 IE BULLETINS'THAT MUST BE RESOLVED PRIOR TO FUEL LOAD The Licensee will complete, to the satisfaction of the NRC, the following IE Bulletins:

~ Bulletins:

1. 808U-08/MPS Examination of Containment Liner Penetration Welds

2. 818U-01/TPS Surveillance of Mechanical Snubbers

3. 81BU-02/TPS Failure of Gate Type Valves -to Close Against Differential Pressure

4. 85BU-01/TPS Steam Binding of Auxiliary Feedwater Pumps

5. '85BU-02/PSS- Undervoltage-Trip Attachments of Westinghouse DB 50 Type Reactor Trip Breakers

6. 85BU-03/TPS Motor Operated Valve Common Mode Failures During Plant Transients, Due to Improper Switch Settings

7. 86BU-02/PSS Static "0" Ring Differential Pressure Switches S. 868U-03/PSS Potential Failure of.ECCS Pumps l

i?

Enclosure 1 ATTACHMENT 4A TMI ACTION PLAN ITEMS THAT MUST BE RESOLVED PRIOR TO FUEL LOAD

'The licensee will' complete- to the satisfaction of the NRC, the following TMI Action Plant. Requirements:

! 1. I.A.I.1/RP3C Shift Technical Advisor 4

2. I.A.1.2/RP3C Shift Supervisor Responsibilities

3. I.A.1.3/RP3C Shift Manning

4. ~I.B.1.2/RP3C Evaluation of Organization & Management

5. I.C.1/RP3C' Guidence . for the Evaluation and Development of Procedures for Transients and Accidents

6. I.C.2/RP3C Shift and Relief Turnover Procedures

7. I.C.3/RP3C Shift Supervisor Responsibility

8. I.C.4/RP3C Control-Room Access

9. I.C.5/RP3C Feedback and Operating Experience

. 10. I.C.6/0PS Verify Correct Performance of Operating Activities

11. I.C.7/TPS NSSS Vendor Review of Procedures

12. II.D.1/TPS Relief & Safety Valve Test Requirements L 13. II.D.3/TPS Valve Position Indication j 14. II.E.1.1/TPS Auxiliary Feedwater System Evaluation

15. II.E.1.2/TPS Auxiliary Feedwater System Initiation and Flow

16. II.E.4.2/RP3C Containment System Dependability l

17. II.F.1/RP3C Part 1 Procedures, Subparts 2d and 2e, Containment Pressure and Water Level Monitors

18. II.F.1/RP3C Subpart 2f Containment Hydrogen Concentration j Monitor

, 19. II.F.2/RP3C Instrumentation for Detection of Inadequate i Core-Cooling  ;

i i

., . . - _ , _ _ ._. - -. _ ,._,_ .. _ ,.-. __.--..-.... _, _ ._. _ _ c--, ,- . _ . _ .,, . _ . - , - ~ -.- ,- _, - - .- _-.. ,,

o ,

• Enclosure 1 Attachment 4A 2

20. II.K.1.5/RP3C Review ESF Valves

21. II.K.1.10/RP3C Operability Status

22. II.K.1.19/RP3C Trip Per Low-Level E/S

23. II.K.3/RP3C Final Recommendations, B & 0 Task Force

24. III.D.I.1/RP3C Primary Coolant, Outside Containment

Enclosure 1 ATTACHMENT 4B TMI ACTION PLAN ITEMS THAT MUST BE RESOLVED PRIOR TO EXCEEDING 5*, POWER The Licensee will complete, to the satisfaction of the NRC, the following TMI Action Plan Requirements:

1. II.B.3/ REC Postaccident Sampling

2. I.D.2/EPS Plant-Safety Parameter Display Console

3. II.F.1/ REC Subparts 2a and 2b, Effluent Radiological Monitoring, Sampling and Analysis

4. II.F.1/FRP Subpart 2c, Containment High Range Radiation Monitor

"C S"#

ATTACHMENT 4C TMI ACTION PLAN ITEMS THAT MUST BE RESOLVED 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-Power Testing

2. I.C.8/RP3C Pilot Monitoring of Selected Emergency Procedure E_

\

\

9 '.

bV ,

s g

, >i 4

5 1

Enclosure 1 ATTACHMENT 5 Review of Vootle Readiness Review procram'Medules and Appendices that must be completes prier to fuel load.

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

MODELES LEAD CURRENT NO . REVIEWER STATUS

4. Mechanical Equipment Piping & E. Girard Note 2 Components 7.A' Plant Operations & Support J. Rogge Note 1 18.A HVAC W. Kleinsorge Note 1 ,

22. Independent Design Review R. Parkhill (I&E) Note 1 No. APPENDIX CURRENT STATUS 21TJ Equipment Qualification Note 2.

Note 1: Final Report in Preparation Note 2: Report Approvals Required

s .

ENCLOSURE 2 Preoperational and Acceptance Testing Status Preoperational test phase (preoperational and acceptance test) is approximately 81% 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 load.

Procedures Final Results Results No. No.*in Reviewed

• No.* Approval

• Review **-

Tests progress By NRC Completed by GPC By NRC Preoperational 162 49 45 109 78 8 Tests Acceptance 21 1 (N/A) 20 19 (N/A)

Tests

• • These numbers represent the combined total of both nondetailed verifications and detailed reviews.

• The 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 1986 (Categorization is by GPC.)

Deficiencies that impact fuel load: 3209 Deficiencies that must be resolved prior to:

Mode 5 1677 Mode 4 57 Mode 3 21 Mode 2 256 Mode 1 138 Turbine Roll 1 Commercial Operation 81 Power Operations / Outage 568 5% Power 17 5% Power 3 Refueling Outage 8 Total Post Fuel Load 2827 Total Deficiencies 6038 (N/A) Not Applicable

Enclosure 2 2 Status of Open OA Program - Initial-Test Program and Nuclear Operations

Items as of 1986 (Categorizations is by GPC).

Deficiencies that impact fuel load: 1

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 -

or after: -TBD

- Deficiencies that have not yet been assigned a' category: 44 (may affect fuel load)

F

. Total Deficiencies 45 1

- Status'of Open Quality Concern Program Items as of 1986 (Categorizations is by GPC).

Concerns that may impact fuel load: 43 Concerns that must be resolved-prior to exceeding SP, power: TBD 9 Concerns that impact Commercial Operation: TBD

Concerns required to be-resolved by first refueling i or after

TBD I Concerns that have not yet been assigned a category: 0 (may affect fuel load)

Total Open Concerns 201 i

I I

i i

i i

J

-~-,-.,---,,-.---.,_gg,,,m.. , ,_,yy-. ,%,,,,,-_.,_. ,_,,_,-_,_,m_ -,, . ym-.,,m_.m.._..m_.y, m .-, , , y

ENCLOSURE 3 Construction Status As of Nosember 30, 1956, construction at Vogtle Unit i is essentially 99P.

complete to the satisfaction of the NRC.

COMMODITY COMPLETE Unit 1 Concrete 99 Backfill 97 Large Pipe 99 Large Hangers 99 Small Pipe 99 Small Hangers 99 Tubing Hangers 99 Tubing 99 HVAC Duct 99 Cable Tray 100 Conduit - PVC 99

-Rigid 98 Wire & Cable 99 Terminations 97 Pullman Instruments 98 Cleveland Instruments 99 Coatings 92 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 Open Items, Deficiency Reports, Allegations and Punch List Items.

6. Technical Specification development and walkdown.

7. Operational Procedure development and review.

8. Completion of the Radiation Protection and Radaaste systems.

9. Completion of the Emergency Preparedness facilities and program.

a .

Enclosure 3 2 Status of Open QA Program - Construction Items as of 1986 (Categorization is by GPC)

Deficiencies that impact fuel load: 3 Deficiencies that m;st be resolved prior to exceeding 5!, power: TBD Deficiencies that impact 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) 29 Total Deficiencies 32 1

TBD - To Be Determined

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 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 DRP Branch 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 Programe Section OPS Quality Assurance i i ram Section QAS Operator Licensing ... tion OLS Division of Radiation Safety and Safeguards DRSS Emergency Preparedness Section EPS Physical Security Section PSEC Facilities Radiation Protection Section FRP Environmental Protection Section REC MC 2512 - Construction Phase Procedure Percent Reason Not Number Cnmplete Resp. Title Complete 37051 50 QAS Verification of As-Euilts Note 1 49055 B 70 MPS Reactor Coelant Pressure Boundary Note 1 Piping Record Revies 49065 B 30 MPS Safety-Related Piping - Records Review Note 1 50095 B 0 MPS Spent Fuel Storage Racks (To 2515 Program) Note 1 50100 90 MPS Safety-Related Heating, Ventilation Note 1

.It is estimated that the MC 2512 program is approximately 98% complete as of November 30, 1986.

Note 1: Inspection activity is schedule or in progress.

' Enclosure.4 2 MC 2513 - Preoperational Testing and Operational Preparedness Phase Procedure Percent Reason N:t Nu?ber Resp. Complete Title Comolete 35301 QAS 50_ Preoperational Testing Quality Note 1 Assurance 35740 B QAS 0 QA Program - QA/QC Administra- Note I tive 35741 B QAS ~0 QA Program - Audits Note 1 35742 B QAS -50. QA Program - Document Control Note 1 35743 0PS 0 'QA Program - Maintenance Note 1 35744 B QAS 25 QA Program - Design Changes and Modification 35745 B QAS 30 QA Program - Surveillance Testing . Note 1 and Calibration Control 35746 B QAS 50 QA Program - Procurement Control Note 1 35747 .Q A 5 50 QA Program - Receipt, Storage, Note 1 and Handling of Equipment and Materials 35748 8 QAS 50 QA Program - f.ecords Note 1 35749 8 Q A S- 50 QA Program - Tests and Experiments Note 1 35750 0AS 50 QA Program Measurement Test Note 1 Equipment 36301 B RI 80 Operational Staffing .

Note 1 37301 RI 85 Comparison of As-Built Plant to Note 1 FSAR Description 39301 B QAS 50 Preoperational Test Records Note 1 40301 B RI 0 Safety Committee Activity Note 1 42400 B RI 85 Plant Procedures Note 1 42450 B 0PS 50 Operation Procedures Note 1 42451 B 0PS 50 Maintenance Procedures Note 1 42452 B 0P5 50 Emergency Preceoures N te 1 64703 PSS 75 Fire Protection / Prevention Program Note 1 70304 B TPS 20 Engineered Safety Features Test - Note 1 Preoperational Test Procedure Review 70306 B TPS 0 Loss of Offsite Power Test - Note 3 Preoperational Test Procedure Review 70311 TPS 0 Precperational Test Procedure Note 1 Verification 70316 B TPS 0 Loss of Offsite Power Test - Note 1 Preoperational Test Witnessing 70317 8 TPS 50 Reactor Protection System Test - Note 2 Preoperational Test Witnessing 70322 TPS 40 Preoperational Test Results Note 4 Evaluation - ESF 70323 TPS 0 Preoperational Test Results Note 4 Evalu, tion - (Containment Inter ated Leak Rate Test)

I )

l

, Enclosure 4 3

70324 B TPS 0 Preoperational Test Results Note 11 Evaluation - Hot Functional Testing 70325 B TP5 0 Preoperational Test Results Note 4 Evaluatior - Reactor Protection System

'70326 B- TPS 0 Preoperational Test Results Note 4 Evaluation - Loss of Offsite Power 70329 B TPS 10 Preoperational Test Results Note 1 Evaluation Verification 70370 TPS 70 Testing of P pe Support and Note 4 Restraint Systems 71301 DRP 55 Technical Specification Review Note 5 71302 RI 80 .Preoperational Test Program Note 2 Implementation Verification 79501 REC 90 LWR Water Chemistry Control and Note 1 Chemical Analysis 79502 -REC 90 Plant Systems Affecting Plant Note 1 Water Chemistry 81018 PSEC 75 Security Plan and Implementing Note 6 Procedures 81020 PSEC 95 Management Effectiveness - Security Note 6 Program 81022 PSEC 90 Security Organization Note 6 81042 PSEC 85 Testing and Maintenance Note 6 81054- PSEC 95 Physical Barriers - Vital Areas, Note 6

. Material Access Areas, and Controlled Access Areas 81062 PSEC 75 Lighting Note 6 81066 PSEC 50 Assessment Aids Note 6 81070 PSEC 50 Access Control - Personnel Note 6 81072 PSEC 50 Access Control (Power Reactor) - Packages Note 6 81074 PSEC 0 Access Control - Vehicles Note 6 81078 PSEC 75 Detectior. Aids - Protected Areas Note 6 81080 PSEC 50 Detection Aids - Vital Areas, Note 6

! Material Access Areas, and i Controlled Access Areas 81054 PSEC 95 Alarm Stations Note 6 81501 PSEC 75 Personnel Training and Qualifica- Note 6 tion - General Requirements

81601 PSEC 75 Safeguards Contingency Plan Note 6

Implementation Review 81810 PSEC 75 Physical Protection Safeguards Note 6 Information 83526 FRP 90 Control of Radioactive Materials and Contamination, Surveys, and Note 1 Monitoring 83527 FRP 90 Facilities and Equipment Note 1 f

4

7

' Enclosure 4 4 84522 FRP 50 Solid Wastes Note 1 84523 REC 95 Liquids and liquid Wastes Note 1 84524 REC 95 Gasecus Waste System Note 1 E4525 REC 95 Radiological and Chemical Note 1 Ccnfirmatory Measurements

p l-

,s

' Enclosure 4 5 l

l l

h Procedure ~ Percent _ Primal Test / Test Procedure Review Reason Not j Nur.ber Resp. Complete Title Complete l

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

It is estimated that the'MC 2513 Program is approximately 55% percent complete as of October 31, 1986 j Note 1: Inspection in progress or scheduled.

l . Note 2: Preoperational testing is still in progress and is being witnessed in l accordance with an estabilshed schedule.

l Note 3: Waiting for approved procedures from licensee.

Note 4: Waiting for approved test results from licensee.

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

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

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

Note 8

Waiting completion of facilities and programmatic licensee activities prior

! to module completion.

Note 9: Waiting on licensee to' perform test.

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

Note 11: Inspection complete, report not issued.

' e' e-

• Enclosure 4 6 MC 2514 - Startup Testing Phase Procedure Percent Reason Not Number Complete Resp. Title _ Complete 35501 0 QAS QA for the Startup Test Program Note 1 72300* 0 TPS Startup Test Procedure Review Note 2 l 72301* 0 TPS Startup Test Results Evaluation Note 3 i '

72302* 0 TPS Startup Test Witnessing and Note 3 Observation 72400 90 TPS Overall Startup Test Program Note 3 72524 0 TPS Initial Fuel Loading Witnessing Note 3 82301 0 EpS Evaluation of Exercise for Power Note 3 Reactors 83521 0 FRP Radiation Protection - Startup Note 3 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) 72572 B 10 TPS Low Power Test Procedure Review Note 2 -

(Moderator Temperature Coefficient >

. Measuren.ent and Boron Reactivity ,

Worth, Group B, and Rod Worth and i Pseudo Rod Ejection, Group A) 72576 B 0 TPS Power Ascension Test Procedure Review Note 2 (Natural Circulation, Group A, and

! Power Reactivity Coefficient t Measurement, Group B)  ;

. 72578 B 0 TPS Power Ascension Test Procedure Review Note 2 l l (Evaluation of Core Performance) l (Group A and B) 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  !

4 Review: Loss of Offsite Power (Group A and B) i 72583 B 0 TPS Power Ascension Test procedure Note 2 Review: Shutdown from Outside i the Control Room (Group B)

72584 8 0 TPS Power Ascension Procedure Review Note 2

> (Evaluation of Flux Asymmetry or Pseudo Rod Ejection Test) (Group A) 72502 0 TPS Initial Criticality Witnessing Note 3 72596 B 0 TPS Precritical Data Review Note 3

72600 B 0 TPS Power level Plateau Data Review (25*4) Note 3  ;

l 7260b B 0 TPS Power Level Plateau Data Review (50*4) Note 3 '

i 72616 8 0 TPS Power Level Plateau Data Review (75's) Note 3 i i 72624 B 0 TPS Power Level Plateau Data Review (100*4) Note 3 i

i i

l

,* e l

Enclosure 4 7 Is is estimated that the MC 2514 Program is approximately 10*. percent ccmplete as of November 30, 1986.

"For tracking procedure review and verification of startup Test Program.

Note 1: Inspection in program or scheduled.

Note 2: Waiting for approved procedures from licensee.

Note 3: Will complete after issuance of OL.

919L 2872

_ _ _ _ _ _ _ _ _ - _ _ _ _ _