ML20236F285
| ML20236F285 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/12/1987 |
| 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 8708030282 | |
| Download: ML20236F285 (26) | |
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[pa a e c ,#'e, UNIVEo SVATES NUCLEAR REGULATORY COMMISSION
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101 MARIETT A STRE ET, N.W.
ATLANTA, GEORGIA 30323
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dhN 121987 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 UNIT 1 DOCKET NO. 50-424, STATUS OF FACILITY COMPLETION, THIRD 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 l consistent with those used by the applicant.
Georgia Power Company (GPC) estimates a fuel load date during the week of January 12, 1987. Region II considers that GPC will be ready within -0 + 30 days of that date assuming that no unforeseen delays occur in the licensee's remaining construction and preoperational testing effort.
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[} o*Cf RogehD. Walker'&e ( h /f27
Enclosures:
- 1. Outstanding Items Including Enforcement and Unresolved Items
- 2. Preoperational and Acceptance Testing Status
- 3. Construction Status ;
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cc w/encis:
J. G. Partlow, Director, IP, IE q
E. L. Jordan, Director, DEPER - '
B. K. Grimes, Director, DQAVTTCP l M. A. Miller, Manager, NRR F. Hawkins, IE
._ Lt 9700030282 FOIA 070729 PDR pDR GRADEge7-271 (/ i ,
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1 ENCLOSURE 1 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 i date beyond fuel load and will be reported as such in later updates to this !
report. I l
I. Open, Unresolved and Enforcement Items Attachment 1 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?J power.
Summary
- 1. There are 27 open items, 7 unresolved items, and 6 enforcement items that must be resolved prior to fuel load.
- 2. There are 4 open items, 0 unresolved items, and 0 enforcement items that must be resolved prior to initial criticality.
- 3. There are 26 open items, 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 and initial criticality.
Summary ,
- 1. There are twenty 10 CFR Part 50.55(e) reports and no 10 CFR Part 21 reports that must be resolved prior to fuel load.
- 2. There is one 10 CFR Part 50.55(e) report that must be resolved by initial criticality.
III. IE Bulletins and Circulars l Attachment 3 Enclosure 1 is a list of all Bulletins that must be resolved to the satisfaction of the NRC prior to fuel load and initial criticality.
Summary
- 1. There is one Bulletin that must be resolved prior to fuel load.
- 2. There are two Bulletins that must be resolved prior to initial ,
criticality.
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Enclosure 1 2 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.
Summary
- 1. There is 1 TMI Action Plan item that must be resolved pr'ior to fuel 1 ]
load.
- 2. There 'are 3 TMI Action Plan items that must be resolved prior to initial criticality.
- 3. There are 5 TMI Action Plan items that must be resolved prior to exeeding 5% power.
- 4. There are 2 TMI Action Pitn items that must be rescived prior to full-power operation.
V. Vogtle Readiness Review Program (VRRP)
Attachment 5 to Enclosure 1 is a list of 2 VRRP modules and I appendix which are in the final stages of conpletion. It is anticipated that these-modules and appendix reviews will be completed prior to exceeding 5% power.
VI. Open Allegations There are currently Twenty-seven open Allegations that are assigned to the It is expected that these allegations will be reviewed I Region II staff.
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 LOAD A. The licensee will implement corrective actions for the following violations to the satisfaction of the NRC.
- 1. 86-61-13/PSS Failure to Maintain Control of QC Accepted Conduit Suppcets
- 2. 86-31-08/PSS Failure to Follow Procedures for Protecting Installed Equipment / Components
- 3. 86-95-01/PSS Failure to Adequately Process FCR's and Incorpora-ting DCN's 4, 86-95-02/PSS Failure to Train Elect. Engineers and QC. Staff on use of Raychem. Products.
- 5. 87-01-02/0PS Failure to Follow Procedures in Verification of
4 Drawings & Vendor Manuals for Maintenance
- 6. 86-95-03/PSS Failure to Adequately Inspect NSCW Cable Splices !
- 8. The licensee will coniplete the following unresolved items or .iations 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 '
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Chemical Spray of electrical penetrations
- 5. 87-01-04/0PS Verify Surveillance Procedures to Address Seismic and EQ Restroation Requirements
- 6. 86-99-01/TPS Sequence of Tests during Power Escalation (NRR Involved) i
- 7. 86-132-01/TPS Inadequate Approval of Changes to Acceptance Criteria
Enclosure 1 Attachment 1A 2 C. The licensee will complete the following open items to the satisfaction of ,
the NRC: I
- 1. 85-10-03/PSS Review Inspection Records That May be Incomplete Due to DR Closecuts
- 2. 85-28-04/PSS Acceptance of Response to Concept No. 3 Without Reviewing Calculations
- 3. 86-31-03/RP3C Separation of Unit 2 Const. Activities from Unit 1 I to Prevent Interference with Unit 1 Operation
- 4. 86-51-02/RP3C Review Licensee Action for TMI-I.C.4
- 5. 86-60-10/0PS Review Compi. with Shift Relief / Turnover - TMI I.C.2
- 6. 86-61-03/PSS Incomplete verification of commitments
- 7. 86-61-04/PSS Two Discrepancies in VRRP MOD 12, Section 6.1
- 8. 86-64-03/PSS Pre-Fire plans fail to properly identify adequate fire brigade strategies
- 9. 86-64-04/PSS Automatic sprinkler systems do not meet FSAR design commitments 10, 86-64-06/PSS Licensee to provide design / test control data for fire barrier penetration seals
- 11. 86-64-07/PSS Fire Detection System for the main control room complex fails to comply with SSER 1 commitments
- 12. 86-96-05/QAS Surveillance procedure not written and approved
- 13. 86-118-02/TPS 4160 Switchgear racking incidents
- 14. 86-117-02/0PS Venting Followup Items Including High Point Vents on AFW and Procedure Revisions for System Venting
- 15. 86-117-11/0PS Followup on Prerequisites Which Are Too General in SOPS and Surveillance Procedures
- 16. 86-117-13/0PS Resolution of Findings on A0P's.
- 17. 86-117-18/0PS Licensee to Implement Surveillance Tracking and Administrative Control Procedures
- 18. 86-117-19/0PS Review of Test Control and Implementation of Configuration Control During Performance of Surveillance Testing
Enclosure 1 Attachment 1A ,
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- 19. 86-117-21/0PS Review of Justifications for Use of Preop Tests for Surve111ances
- 20. 86-117-27/0PS Review of Surveillance Procedures Which Have Not Been Written (Credit for Surveillance taken Under Preop Test). Also Review of of Cross Reference List
- 21. 86-117-28/0PS Procedure Revisions for Consistent Definition of Surveillance Test Completion Date and Time
- 22. 86-117-29/0PS Review of Special Triggering Mechanisms
- 23. 86-117-33/0PS Misc. Technical Issues in Regard to Opertional Procedures
- 24. 87-01-03 Adequacy of Functional Test and Work Instructions for Maintenance
- 25. 87-01-05 Determine if Temp. Mods. Negate STP's completed After Prcops.
- 26. 87-01-06 Misc. Findings on Surveillance and Maint. Imp.
- 27. 87-01-07 Use of Master Setpoint Document for ARP's l
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Enclosure 1 ATTACHMENT 1B OPEN, UNRESOLVED AND ENFORCEMENT ITEMS THAT MUST BE RESOLVED PRIOR TO INITIAL CRITICALITY l
A. There are no identified violations to be completed as of January 12, 1987.
B. There are no identified unresolved items or deviations to be completed as of January 12, 1987.
C. The licensee will complete the following open and inspector followup items to the satisfaction of the NRC: l
- 1. 86-117-09/0PS Correction of discrepancies in RVLIS surveillance -
procedure and followup on vendor recommendations
- 2. 86-117-31/0PS Corrective action to assure that key control system (
allows prompt access to locked rooms and cabinets
- 3. 86-65-03/TPS Review Final Resolution to MSIV coil failure &
subsequent retest
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l Enclosure 1 ATTACHMENT 1C OPEN UNRESOLVED AND ENFORCEMENT ITEM THAT MUST BE RESOLVED PRIOR TO EXCEEDING 5's POWER l A. There are no identified violations to be completed as of January 12, 1987.
B. There are no identified unresolved items or deviations to be completed _as of l January 12, 1987. l 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. 86-12-47/FRP Install Calibrate and Otherwise Make Operational All Plant Areas Radiation Monitors
- 3. 85-20-01/PSS Corrective Actions Relating to IEEE 384 Separation l
- 4. 85-20-02/PSS Review Documentation Requirement for Cable Clamps to and Entry F.
l S. 85-21-02/RP2C Review Revision to Class IE Battery Maintenance Procedyres
- 6. 86-12-32/ REC Complete Equipment Installation & Insure Operational and Procedure Adequacy for Post Accident Gas & Particulate ,
l Effluent Sampling (4.1.1) I
- 7. 86-12-86,-REC Completion of Final PASS Operational Testing l
- 8. 86-12-88/ REC Assure Volume of Vent Air Sampled Representative of Actual Effluent Activity (5.4.2)
- 9. 85-36-02/0PS Operational Event Reports Addressed Programmatically Vice Technically
- 10. 86-60-06/RP2C Review of Plan to Collect and Evaluate Transient or Operational Cycles
- 12. 86-51-04/RP2C Review Licensee Procedure Changes to 10000-C and 10006-2 to Verify Safety Limits Not Exceeded 1
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Enclosure 1 '
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- 13. 86-60-10/0PS Review Compliance with Shif t Relief and Turnover (TMI I.C.2) l
- 15. 86-124-01/0PS Disposition of Incomplete Fire Protection Features Identified During Area Turnovers
- 16. 86-124-02/PSS Abnormal Single Ground Fault Condition Test Requirements
' to be Incorporated Into Fire Detection System Preopera-tional Test in Accordance with NFPA-72D
- 17. 86-88-01/PSS Verification of Installation of Access Ladder and Platform to Fire Zone 73 ,
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- 18. 86-88-02/PSS Review of the Installation of Additional Smoke Detection for Fire Zone 80
- 19. 86-88-03/PSS Review of Surveillance Procedure for Fire Area Bound-aries Required for Safe Shutdown Cable Separations 1
- 20. 86-88-04/PSS Revise Control Fuses in 4KV Switchgear
- 21. 86-88-05/PSS Justify Repairs Required to Maintain Hot Shutdown
- 22. 86-88-06/PSS Revise Repair Procedure 27579-C 1
- 23. 86-88-11/PSS Verify Acceptance of Non-Dedicated S/G Pressure Indication on Remote Shutdown Panel B
- 24. 86-88-12/PSS Review Access Plan for 125 VDC Distribution Cabinets l
- 25. 86-60-01/RP2C Failure to Implement Adequate Design Control
- 26. 86-121-02/TDS Complete Ultimate Heat Sink Testing l
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Enclosure 1 ATTACHMENT 2A DEFICIENCY REPORTS THAT MUST BE RESOLVED PRIOR TO FUEL LOAD The Licensee will complete, to the satisf action of the NRC, the following 10 CFR 50.55(e) and 10 CFR 21 items:
- 1. CDR85-78/PSS Safety Grade Core Exit Thermocouple
- 2. CDR86-97/TPS Malfunction of RPS Permissive P-10 Function
- 3. COR86-98/TPS Failure of Worm Gear Sections in Manual 0P Valves 4
- 4. CDR86-99/PSS No Calcs for Cable Internal Resistance During Loca
- 5. CDR86-100/PSS Spliced Cable Jackets Affect Environmental Qualification
- 6. CDR86-103/PSS Separation of Field Wires In Isolation Trans-formers
- 7. CDR86-105/PSS Improper Support of Cable in Vertical Raceway
- 8. CDR86-118/PSS Flaking of Positive Straps on 125 Volt DC Batteries
- 9. CDR86-120/PSS Failure in Velcor Company Solenoid Valves
- 11. CDR86-124/PSS Raychem Site Designed Electrical Splices
- 12. CDR86-126/PSS Conax Electrical Penetrations with Holes
- 13. CDR86-127/TPS Containment Cooling Vents Low Air Flow
- 14. CDR86-128/TPS DG Building Vent System Low Air Flow
- 15. CDR86-131/PSS Turb. Driven Aux Feed Pump Governor Malfunction
- 16. CDR86-132/PSS Containment Purge System-Register Damper
- 17. CDR86-133/PSS Low Voltage on ESFAS/BDP Channel
- 18. CDR86-134/PSS 55 ESFAS Relays Replaced Due to Excessive Current Drown by Valve Operator
d Enclosure 1 Attachment 2A 2 1 l
- 19. CDR87-136/PSS Failure of Charging Pump Bkr to Close During Load !'
Sequencing
- 20. CDR87-137/PSS DG May Not Receive SI Signal During Coast Down -
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Enclosure 1 ATTACHMENT 2B DEFICIENCY REPORTS THAT MUST BE RESOLVED PRIOR TO INITIAL CRITICALITY The Licensee will complete, to the satisfaction of the NRC, the following 10 CFR 50.55(e) and 10 CFR 21 items:
- 1. CDR86-130/TPS Main Stream Isolation Valve Closure Time i
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4 Enclosure 1 ATTACHMENT 3A IE BULLETINS THAT MUST BE RESOLVED PRIOR TO FUEL LOAD The Licensee will complete, to the satisfaction of the NRC, the following IE Bulletins:
- 1. 85BU-02/PSS Undervoltage-Trip Attachments of Westinghouse DB 50 Type Reactor Trip Breakers O
Enclosure 1 ATTACHMENT 38 1
IE BULLETINS THAT MUST BE RESOLVED PRIOR TO INITIAL CRITICALITY The Licensee will complete, to the satisfaction of the NRC, the following IE l Bulletins: j
- 1. 86BU-02/TPS Static "0" Ring Differential Pressure Switches
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Enclosure 1 ATTACHMENT 4A TMI ACTION PLAN ITEMS THAT MUST BE RESOLVED '
PRIOR TO FUEL LOAD -
The licensee will complete to the satisfaction cf the NRC, the following TMI i Action Plan Requ'irements: -
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- 1. I.C.2/0PS Sh,ft and Relief Turnover Procedures ;
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Enclosure I j ATTACHMENT 4B TMI ACTION PLAN ITEMS THAT MUST BE RESOLVED i I
PRIOR TO INITIAL CRITICALITY 1
The Licensee will complete, to the satisfaction of the NRC, the following TMI !
Action Plan Requirements: 1 4
- 1. II.E.I.2/TPS Auxiliary Feedwater System Initiation and Flow l
- 2. II.F.1/RP3C Part I Procedures, Subparts 2d and 2e, Containment i Pressure and Water Level Monitors
- 3. II.F.1/RP3C Subpart 2f Containment Hydrogen Concentration Monitor I
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l Enclosure I ATTACHMENT 4C TMI ACTION PLAN ITEMS THAT MUST BE RESOLVED PRIOR TO EXCEEDING 5?; POWER The Licensee will complete, to the satisf action of the NRC, the following TMI Action Plan Requirements:
- 1. II.B.3/ REC Postaccident Sampling
- 2. I.C.7/TPS NSSS Vendor Review of Procedures
- 3. I.D.2/EPS Plant-Safety Parameter Display Censole i
- 4. II.F.1/ REC Subparts 2a and 2b, Effluent Radiological Monitor-ing, Sampling and Analysis
- 5. II.F.1/FRP Subpart 2c, Containment High Range Radiation Monitor sun i
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i Enclosure 1 ATTACHMENT 4D 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. ;
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- 1. I.G.1/TPS Training During Low-Power Testing l 2. II.E.1.1/TPS Auxiliary Feedwater System Evaluation l
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1 Enclosure 1 ATTACHMENT 5 Review of Vogtle Readiness Review Program Modules and Appendices that must be completed prior to Exceeding 5% Power j l
i The reviewers will complete, to the satisfaction of the participating NRC Offices, the followini. VRRP Modules and Appendices:
I MODELES LEAD CURRENT NO REVIEWER STATUS
- 4. Mechanical Equipment Piping & E. Girard Note 2 I Components 7.A Plant Operations & Support J. Rogge Note 2 l
No. APPENDIX CURRENT STATUS 21.J Equipment Qualification Note 2 l
l Note 1: Final Report in Preparation Note 2: Report Approvals Required O
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ENCLOSURE 2 Preoperational and Acceptance Testing Status Preoperational test phase (preoperational and acceptance test) is approximately l 94% complete as of December 26,.1986. The overall status o' 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.* App. oval
- Review"*-
Tests Progress By NRC Completed by GPC By NRC Preoperational 162 26 45 134 119 8
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Tests Acceptance 21 1 (N/A) 20 19 (N/A) l Tests
- These numbers represent the combined total of both nondetailed verifications and detailed reviews.
"The licensee may provide ti.* 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.
(N/A) Not Applicable Status of the Open Preoperational Test / System Deficiencies for All System Tests as of December 28, 1986 (Categorization is by GPC.)
I Deficier;ies that impact fuel load:; Mode 6 1604 ;
Deficiencies that must be resolved prior to:
Mode 5 ~
275 i Mode 4 278 1 Mode 3 132 Mode 2 65 Mode 1 91 Turbine Roll 3 Commercial Operation 118 Power Operations / Outage 793 5% Power 27 50% Power 3 Refueling Outage 26 Deficiencies Not Assigned a Category 306 Total Post Fuel Load 2117 Total Deficiencies 3721
Enclosure 2 2 1
Status of Open OA Program - Initial Test Program and Nuclear Operations Items as of January 7,1987 (Categorizations is by GPC).
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Deficiencies that impact fuel load: 1 Deficiencies that must be resolved prior to exceeding 5% power: .
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Deficiencies that impact Commercial Operation: 18 I Deficiencies required to be resolved by first refueling or'after: 0' Deficiencies that have not yet been assigned a category: 0 l (may affect fuel load) J l
Total Deficiencies 25
' Status of Open Quality Concern Program Items as of January 7,1987 (Categorizations is by GPC).
Concerns that may impact fuel load: 0 Concerns that must be resolved prior to Startup 5 ,
Concerns that impact Power Operation: I f Concerns required to be resolved by first refueling '
or after: 32 Concerns that have not yet been assigned a category: 0 (may affect fuel load)
Concerns in closure crocess 54 l
Total Open Concerns 94 Additional General items: )
- 1. Preoperational Procedure re-review as nesessary
- 2. Preoperational Testing and system demonstration 34 Technical Specification walkdown
- 4. Operational procedure development and review I -
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ENCLOSURE 3 1
l Construction Status As of January 8,1987, construction at Vogtle Unit 1 is essentially 100% complete to the satisfaction of the NRC.
COMMODITY COMPLETE l Unit 1 Concrete 100 Backfill 100 Large Pipe 100 Large Hangers 100 Small Pipe 100 Small Hangers 100 Tubing Hangers 100 Tubing 100 HVAC Duct 100 l Cable Tray 100 l Conduit - PVC 100
-Rigid 100 Wire & Cable 100 Terminations 100 Pullman Instruments 100 Cleveland Instruments 100 Coatings 100 Additional General Items:
- 1. Fire protection system compliance (Penetration fire, seals, completion of safe shutdown analysis, hardware modification, fire dampers, etc.)
- 2. Resolution of Open Items, Deficiency Reports, Allegations and Punch List Items.
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- 3. Completion of the Emergency Preparedness facilities and program. !
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Enclosure 3 2 i
Status of Open QA Program - Construction Items as of January 7, 1987 (Categorization is by GPC)
Deficiencies that impact fuel load: 0 Deficiencies that must be resolved prior to startup 2 Deficiencies that impact Commercial Operation: 0 l Deficiencies required to be resolved by first refueling or after: 0 l Deficiencies that have not yet been assigned a category (may i 0
affect fuel load) l l
Total Deficiencies 23 TBD - To Be Determir.ed 1
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ENCLOSURE 4 Status of Inspection Required By MC 2512 and 2513 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 Programs Section OPS Quality Assurance Program Section QAS Operator Licensing Section OLS Division of Radiation Safety and Safeguards DRSS l
Emergency Preparedness Section EPS l Physical Security Section PSEC Facilities Radiation Protection Section FRP Environmental Protection Section REC l
MC 2512 - Construction Phase Procedure Percent Reason Not Number Complete Resp. Title Complete The MC 2512 program js 100% complete.
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Enclosure 4 3 Procedure Percent Primal Test / Test Procedure Review Reason Not Number Resp. Complete Title Complete 83526 FRP 90 Control of Radioactive Materials and Contamination, Surveys, and Note 8 Monitoring 83527 FRP 90 Facilities and Equipment Note 8 84522 FRP 50 Solid Wastes Note 8 84523 REC 95 Liquids and Liquid Wastes Note 4 84524 REC 95 Gaseous Waste System Note 4 The inspection requirements for Primal Test procedure review and test witnessing have been completed.
It is s stimated that the MC 2513 Program is approximately 70% percent complete as of December 19, 1986 Note 1: Inspection in progress or scheduled.
Note 2: Preoperational testing is still in progress and is being witnessed in accor-dance with an estabilshed schedule.
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.
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 gompletion.
Note 9: Waiting on licensee to perform test.
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.
Enclosure 4 2 MC 2513 - Preoperational Testing and Operational Preparedness Phase Procedure Percent Reason Not Number Resp. Complete Title Complete 42450 B 0PS 80 Operation Procedures Note 1 64703 PSS 7S Fire Protection / Prevention Program Note 1 70311 TPS 0 Preoperational Test Procedure Note 1 Verification 70322 TPS 40 Preoperational Test Results Note 4 Evaluation - ESF 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 B TPS 50 Preoperational Test Results Note 1 Evaluation Verification 70370 TPS 70 Testing of Pipe Support and Note 7 Restraint Systems 1
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4N FEB 0 ? 1986 GQ MEMORANDUM FOR: Harold R. Denton, Director, Office of Nuclear Reactor Regulation FROM: J. Nelson Grace, Regional Administrator
SUBJECT:
DUKE POWER COMPANY'S CATAWBA UNIT 2, DOCKET 'NO. 50-414,6 STATUS OF FACILITY COMPLETION Based on the implementation of the prescribed NRC inspection program and other related inspection activities, we have determined that construction and pre-operational testing of Catawba Unit 2 have been completed in accordance with the FSAR, other docketed commitments and regulatory requirements with the exceptions ,
listed in the enclosures. Region 11 notes the draft Catawba Unit 2 Low Power !
License, dated December 26, 1985, and the Duke Power Company letter requesting exemptions for Catawba Unit 2, dated January 21, 1985. We requested and received from Duke Power Company the status of completion letter dated January 24, 1986.
The letter is acceptable and consistent with our findings. Therefore, the enclosures to this memorandum are recommended for enclosure to the draft low power license for Catawba Unit 2.
Region 11 is presently scheduled to send to NRR our recommendations for issuance of a low power license on February 12, 1986.
Original signed by J.N. Grace J. Nelson Grace
Enclosures:
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- 1. Items to be Completed Prior to l Fuel Loading of Catawba Unit 2 l (DocketNumber50-414)
- 2. Items to be Completed Prior to Initial Criticality of Catawba Unit 2 (Docket Number 50-414)
- 3. Items to be Completed Prior to Exceeding 5% Rated Power at Catawba Unit 2 (Docket Number 50-414) cc w/encls: (See page 2) c ,7,,
ett id t! o n -
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yyi4-CONTACT:
C. W. Burger 242-4198
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FEB 071986 ')
Harold R. Denton 2 I
cc w/encls:
E. L. Jordan, Director, DEPER, IE G. T. Ankrum, Chief, Quality Assurance Branch, DQAVT, IE L. I. Cobb, Chief, Safeguards and Material Programs Branch, IP, IE !
R. F. Heishman, Chief, Reactor j Construction Programs Branch, IP, IE l K. N. Jabbour, Licensing Project Manager, NRR 1
CONTACT:
C. W. Burger 242-4198 RII b'
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FEB 0 71986 l
ENCLOSURE 1 ITEMS TO BE COMPLETED PRIOR TO FUEL LOADING 0F CATAWBA UNIT 2 (DOCKET NUMBER 50-414) (
A. The licensee will complete to the satisfaction of HRC Region 11, the requirements of the following bulletins:
- 1. Pipe support base plate designs using concrete expansion anchor bolts !
(79-BU-02/MP^).
- 2. Seismic anal sis for as-built safety-related piping systems (79-BU-14/MPS .
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. . t FEB 0 7 5986 ENCLOSURE 2 '.
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ITEMS TO BE COMPLETED PRIOR TO INITIAL CRITICALITY J OF CATAWBA UNIT 2 (DOCKET NUMBER 50-414) )
1 A. The licensee will complete to the satisfaction of NRC Region II, the j following Construction Deficiency Reports (50.55e items) and Part 21 i ident'ified items: i
- 1. Complete modification to provide roper clearances of NCX 750 and NCX 1200 batteries (COR 85-07/PSS .
- 2. Implement corrective action relative to Diesel Generator 2B bearin'g failures (CDR86-01/DRP)
B. The licensee will resolve to the satisfaction of NRC Region II, the following unresolved items:
Complete review of electrical interface between Units 1 and 2 (85-32-01/DRP).
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FEB 0 71986 i
ENCLOSURE 3 i
ITEMS TO BE COMPLETED PRIOR TO EXCEEDING 5% !
RATED POWER AT CATAWBA UNIT 2 (DOCKET NUMBER 50-414)
The licensee will complete to the satisfaction of NRC Region II, the TMI .,
related requirements for full power and low power testing (TI 2514/01, Rev. 2). I 1
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FE9 2 01986 I
MEMORANDUM FOR: Harold R. Denton, Director, Office of Nuclear Reactor Regulation FROM: J. Nelson Grace, Regional Administrator i
SUBJECT:
1 DUKE POWER COMPANY'S CATAWBA UNIT 2, DOCKET N0.
STATUS OF FACILITY COMPLETION 50-414, b Based on the implementation of the prescribed NRC inspection program and other related inspection activities, we have determined that construction- and pre-operational testing of Catawba Unit 2 has been completed in accordance with the FSAR, other docketed commitments and regulatory requirements. Included in the Region II assessment was the review of the ~ draft Catawba Unit 2 Low Power License dated February 3,19864 and of the Duke Power Company letter requesting exemptions for Catawba Unit 2 dated January 21, 1986. Region II has'no issues )
with regard to these two documents. We requested and received from Duke Power '
Company (DPC) the status of completion letter dated January 24, 1986, and supplement dated February 10, 1986. The letters are acceptable and consistent with our findings. We have reviewed DPC's preoperational and startup test schedule to full power operation and find it acceptable. We will follow these activities and keep you apprised of our findings during this period. )
1 Based on the above, Region II recommends issuance of a Low Power License for l Catawba Unit 2. I l
Original Signed by J. Nelson Grace l J. Nelson Grace cc: E. L. Jordan, Director, DEPER, IE G. T. Ankrum, Chief, Quality Assurance Branch, DQAVT, IE L. I. Cobb, Chief, Safeguards and -
l Material Programs Branch, IP, IE R. F. Heishman, Chief, Reactor Construction Programs Branch, i IP, IE K. N. Jabbour, Licensing Project Manager, NRR CONTACT:
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CD-LIS-87-344 May 8, 1987 !
Project 1816 IREEDO:i 0F li4 FORMATION Director ACT REQUEST Division of Rules and Records U.S. N.R.C. 07f-g)g y l Washington, D.C. 20555 f ~/2. '8 )
Dear Sir:
This is a Freedom of Information Act request for the following document to be placed in the Public Document Room:
- 1. Request for Region input to Headquarters NRC, Office of Nuclear Reactor Regulation (NRR) regarding status of plant readiness for an operating license IE Manual, Chapter 94300. Please provide the region input for the following plants:
Clinton Seabrook 1 Braidwood 1 Byron 2 Vogtle Hope Creek Perry Catawba 2 Shoreham Millstone 3 !
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If clarification is needed, please call me at (813) 796-2264. Thank you for your assistance.
Sincerely, Lyle Graber Licensing Engineer j Licensing Information Service
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