ML20236F101

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Forwards List of Items to Be Completed Prior to Fuel Loading,Per Insp Procedure 94300B.Licensee Projected Fuel Load Date Is 860725
ML20236F101
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 05/08/1986
From: Reyes L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Novak T
Office of Nuclear Reactor Regulation
Shared Package
ML20236F104 List:
References
FOIA-87-279 NUDOCS 8708030214
Download: ML20236F101 (30)
v • d • e


Text

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N May 8, 1986 MEMORANDUM FOR: Thomas M. Novak, Acting Director, Division of Pressurized Water Reactor Licensing-A, NRR FROM: Luis A. Reyes, Acting Director, Division of Reactor Projects I

SUBJECT:

CAROLINA' POWER AND LIGHT COMPANY - HARRIS UNIT 1 DOCKET NO. 50-400, STATUS OF FACILITY COMPLETION g_40C[(7, In accordance with Inspection Procedure Nc. 943008, the enclosures list the remaining open items that require resolution before a finding of readiness for i operation may be endorsed by Region II.

The licensee's projected fuel load date is July.25,1986. Region II considers this date to be realistic, assuming that no unforeseen delays occur in the i licensee's remaining construction and preoperational testing effort.

Original Signed by Virgil L. Brownlee /for I

Luis A. Reyes

{

Enclosures:

)

1. Items.to be Completed Prior to l Fuel Loading
2. Items to be Completed Prior to 4 Initial Criticality >
3. Items to be Completed Prior to Exceeding 5% Rated Power
4. Items to be Completed Prior to Full Power Operation
5. Pre ferotional Testing Status and Operational Preparedness
6. Construction Status
7. Status of Inspections Required by MC 2512, MC 2513, and MC 2514 cc w/cacis:

J. G. Partlow, Director, DQASIP E. L. Jordan, Director, DEPER G. T. Ankrum, Chief, Quality Assurance ,

Branch, DQASIP L. I. Cobb, Chief, Safeguards and Material Program Branch, DQASIP 4 R. F. Heishman, Chief, Reactor Construction Branch, DQASIP B. . C. Buckley, Licensing Project Manager, NRR bec w/encis: (See page 2) >

8708030214 870512 PDR FOIA ,

GRADER 87-279 N

PDR k

I

Thomas M. Novak 2 May 8, 1986  !

bec w/encls:

R. D. Walker .

G. R. Jenkins  !

V. W. Panciera -

W. E. Cline A. R. Herdt T. E. Conlon C. M.-Hosey C. A. Julian .

C. M. Upright

, J. J. Blake ,

i D. R. McGuire 1

! P. E. Fredrickson F. Jape G. Maxwell S. Burris o

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  • 4 May 8, 1986 ENCLOSURE 1 ITEMS TO BE COMPLETED PRIOR TO FUEL LOADING-(including licensee's projected completion date) 4 A. The licensee will complete, to the satisfaction of. the NRC, the following violations:
1. 83-29-01/RP2A Correct failure to control fastening material 2, 85-04-01/RP2A Correct inadequate inspection for electrical separation
3. 85-08-01/PSS Resolve inadequate design control for raceway separation l 4. 85-47-04/TPS Failure to provide Appropriate Acceptance criteria for TP 1-2005-P-01 B. The following unresolved items or deviations are required to be completed:

l 1. 82-24-01/MPS Resolve installation of nonsafety-related, nonseismic-supported, electrical conduit- in the vicinity of safety-related equipment or components

1 Enclosure 1 2 1

. . I

2. 84-44-04/MPS Resolve program for control of purchased materials j
3. 84-44-05/MPS Resolve program for inspection of activities 0 affecting quality 4-. 84-49-02/RP2A Resolve cable. tray overfill problem-
5. 85-08-02/PSS Staff approval of reduced separation between nonclassified conduit and open class IE raceway
6. 85-26-01/PSS Incorporation of instrument tubing separation criteria

)

7. 85-31-03/TPS Resolve Test Outline Reg. Guide 1.68
8. 85-33-01/RP2A Installation of Safety-related Equipment'
9. 85-37-02/RP2A Resolution of Concerns Associated with IE Bulletin 83-05 j
10. 85-37-03/RP2A Plant Organization Chart for Operations  ;
11. 85-39-02/PSS Review causes of NCR 85-1665 for deportability
12. 86-02-02/TPS Test procedure 1-2000-P-01 and 1-8010-P-02 do not identify data recorder

a Enclosure 1 3 1

13. .86-04-01/TPS AFWS test objectives and acceptance criteria are not fully incorporated l

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

1. 83-27-01/MPS Unavailable steam generator. records
2. 84-24-05/RP2A Certifications for plant. general manager  ;

i

3. 85-27-02/RP2A Plant nuclear safety committee procedure
4. 85-36-01/MPS Newly hired engineer training
5. 85-37-01/RP2A Difference between the as-built plant and the FSAR
6. 85-40-07/PSS Engineering Analysis Testing and Justification for Non-Standard Penetration Seal Configurations i l
7. 85-40-08/PSS Revisions Required to Fire Door Inspection Procedures to Meet NFPA Standards l

l l

8. 85-40-09/PSS Piping to Automatic Sprinkler System and Interior ,

1 '

l Fire Hose System for Diesel Generator Building. Fire Suppression Systems is Not Designed to Meet Single l

Failure Criteria as Required by FSAR

Enclosure 1 4

9. 85-40-11/PSS Reevaluation of Sprinkler System Obstructions 1

)

10, 85-40-12/PSS Two. Fire Pumps Are Not Provided for Supply to SSE i

Interior Fire Hose System 4

11. 85-40-13/PSS Reactor Coolant Pump Oil Collection System is Not

]

Designed to Maintain Structural or Pressure .

d Integrity Following a SSE and Was Not Constructed j i

Under A QA/QC Program  ;

i

12. 85-40-14/PSS Procedure Required to Drain or Verify Reactor Coolant Pump 011 Collection System Drain Tanks Are Empty Prior to Startup
13. 85-45-01/FRP Contamination of Demin Water Systems (Circular 80-14) 14, 85-47-01/TPS Clarify Initial Condition 2 9 of T.P. 1-1100-P  !

I

15. 85-50-01/ REC Water Chemistry Program

'16 . 85-52-02/RP2A Operational discrepancies of the component cooling ,

water system

17. 86-07-01/RP2A Independent Verification E_______________-_-________

. l Enclosure 1 5

18. 86-10-01/TPS Clarify Procedure AOP-004
19. 86-20-01/TPS Revise Initial Fuel Loading Procedure
20. 86-20-02/TPS Revise RCS Leakrate Procedure 1
21. 86-20-03/TPS Revise Initial Criticality Procedure  !

l

22. 86-20-04/TPS Revise Boron Endpoint Procedure  !
23. 86-16-01/RP2A Teflon Tape in the RHR System i

l l

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

1. CDR80-41/PSS Protection system following a secondary high energy line rupture (Steam Generator Ref Leg Heatup)
2. CDR83-130/PSS Potential deficiency with Westinghouse DS 416 breakers l
3. COR84-162/PSS Fire barriers-Tack welds
4. CDR85-179/TPS In-core flux mapping system-system interactions l 5. COR84-183/MPS Potential overpressurization of the component cooling water system

'4 Enclosure 1 6 l l

1 61 CDR84-188/MPS Air operated diaphragm valves do not. meet design value for r.atural frequency

7. CDR84-191/PSS 7.5 KVA inverters / insulation breakdown
8. CDR85-209/MPS 6.9 KV swit,chgear circuit breakers, secondary disconnect fingers 9 3
9. CDR85-213/PSS Undetected failures in ESF actuation system  !

l l

10. CDR85-214/MPS Standby DG, control panel ventilation
11. CDR85-215/MPS Westinghouse safety grade core exit thermocouple
12. CDR85-219/MPS Emergency service water pumps - material failure l

.I

13. CDR85-220-PPS Emergency diesel generator - control panel wiring
14. CDR85-223/PPS Emergency diesel - intake and exhaust valves E. The licensee will complete, to the satisfaction of the NRC, the following IE Bulletins:
1. 78-BU-12/MPS A typical weld material in reactor pressure vessel welds

.o Enclosure 1 7 I

2. 79-BU-18/EPS Audibility problems encountered on evacuation of personnel from'high-noise areas
3. 80-BU-10/FRP Contamination of nonradioactive system and resulting potential for unmonitored, uncontrolled release of radioactivity to environment
4. 80-BU-11/TPS Masonry wall design i
5. 82-BU-02/MPS Degradation of threaded fasteners in the reactor coolant pressure boundary of PWR plants
6. 83-BU-05/MPS ASME Nuclear Code pumps and space parts manufac-tured by the Hayward Tyler Pump Company
7. 84-BU-03/TPS Reactor vessel inflatable seal F. The licensee will complete, to the satisfaction of the NRC, the following TMI Action Plan Requirements:
1. I.A.1 (85-16-01)/RP2A Shift supervisor administrative duties
2. I.C.6 (85-16-04)/RP2A Verify correct performance of operating activities
3. I.D.1 (85-16-06)/RP2A Control' room design review L______________-__-_-__

Enclosure 1 8

4. II.D.1 (85-16-11)/RP2A Performance testing of boiling water reactor and pressurized water reactor relief and safety valves
5. II.D.3 (85-16-12)/RP2A Relief and safety valve indication

.~

6. II . F.1 (85-16-17)/RP2A Subparts (4) and (5) containment pressure l

and water level monitors

7. II . F.1 (85-16-18)/ REC Subpart (6) containment hydrogen concentration monitor  ;
8. II.F.2 (85-16-19)/RP2A Instrumentation for detection of l inadequate core cooling
9. II.K.1.5 (85-16-z2)/RP2A Review of ESF valves
10. II.K.1.10 (85-16-22)/RP2A Operability status
11. II.K.3.5 (85-16-24)/RP2A Automatic trip of reactor coolant pumps during LOCA
12. III.A.I.2 (85-16-25)/EPS Upgrade emergency support facilities
13. III.A.2 (85-16-26)/RP2A Improving licensee emergency preparedness long term

Enclosure 1 9

14. III.D.3.3(85-16-28)/FRP Improved inplant iodine instrumentation under accident conditions
15. I.D.2 (85-16-29)/RP2A Plant safety parameter display console
16. II.B.2 (85-16-32)/FRP Plant shielding to provide access to vital areas l

i

.f

May 8, 1986 ENCLOSURE __2 ITEMS TO BE COMPLETED PRIOR TO INITIAL CRITICALITY The following open and inspector followup items should be closed:

85-09-82/EPS Demonstrating the capability to perform staff augmentation within applicable time frames

i

- j May 8, 1986 )

l ENCLOSURE 3 J l

l 1

I ITEMS TO BE COMPLETED PRIOR TO EXCEEDING 5% RATED POWER l

A. The following unresolved items are required to be completed:

. 1 85-14-01/RP2A Resolve scheduling. and conduct of' battery.

equalizing charges 85-24-03/RP2A Overload trip set points for ITE type HE3-M040.-

molded case circuit breakers B. The following open and inspector followup items should be closed:

1 84-26-01/PSS Review of fire protection QA/QC program to address accessibility / operability and design requirements of NFPA fire codes ,

. . i 85-09-27/EPS Verify the completion of Turbine Building first aid I room and deployment of on-site ambulance kit 85-09-28/EPS Finishing of Turbine Building drum room and equipping of waste processing and ,TSC drum facilities

Enclosure 3 2 85-09-65/EPS Reviewing of applicant personnel accountability procedures 85-09-66/EPS Reviewing of Security program during emergencies 85-27-01/RP2A Sheathing bu,1ges in absorber cells 85-40-01/PSS Fire Protection Systems, Features and Administra-tive Procedures are Required to be Operational Prior to Fuel Load 85-40-02/PSS Revisions Required to Fire Protection / Prevention Procedures in Order to Meet NRC Guidelines 85-40-03/PSS Incomplete Operation Surveillance Test Procedures for Fire Protection Features 85-40-04/PSS Operation Surveillance Test Procedures are Wot Developed and Issued for Permanent Plant Fire Protection Features 85-40-05/PSS Additional. Personnel Required to be Provided with Fire Brigade Training Prior to Fuel Load 85-40-06/PSS Fire Brigade Equipment and Storage Lockers are Required to be Provided Prior to Fuel Load

4 Enclosure 3 3 85-40-10/PSS Verification that Pre-Action Fire Suppression Valve Installations Conform to the Manufacturer's Requirements 85-40-15/PSS Review of Completed Fire Detection System Inspections a,nd Pre-Operational Tests j

85-46-01/EPS Insuring that the Unusual Event matrix of PEP-101 I is sufficiently wide in scope to include any event causing rapid depressurization of the secondary side 85-46-02/EPS Verify TSC positive pressure specification i

.May 8, 1986 ENCLOSURE 4 l l

ITEMS TO BE COMPLETED PRIOR TO FULL POWER OPERATION The licensee will complete, to the satisfaction.of the NRC, the following TMI Action Plan requirements: ,-

~1 I.C.1'(85-16-02)/RP2A Guidance for'the evaluation and development l of procedures for transients and accidents I.C 7.1 (85-16-05)/RP2A NSSS vendor review of low power test procedure I.G.1 (85-16-07)/TPS Special low power' testing and training II.B.1 (85-16-08)/RP2A Reactor coolant system vents-II.B.3 (85-16-09)/ REC Post-accident sampling capability II.B.4 (85-16-10)/RP2A Training and mitigating core damage II.E.1.2 (85-16-13)/RP2A Auxiliary feedwater syst'em initiation and

't flow II.E.4.2 (85-16-14)/RP2A Containment isolation dependability ,

7 1

... l

.- k Enclosure'4 2 II.F.1 (85-16-15)/ REC Subparts (1) and (2) effluent radiological  !

monitoring sampling and analysis i

II.F.1 (85-16-16)/FRP Subpart (3) containment high-range radiation monitor i

. b III.D.1.1 (85-16-27)/RP2A Integrity of systems outside containment

-likely to contain radioactive material I.C.7.2 (85-16-31)/RP2A NSSS vendor review of power ascension procedures l l-

I May 8, 1986 i

ENCLOSURE 5 I j

PREOPERATIONAL TESTING AND OPERATIONAL PREPAREDNESS As of April 22, 1986, the overall status of the test program is summarized below:

i

)

i Total Tests Completed In Progress Not Started l

Preops Required k for Fuel Load 166 78 19 69 .

?

l Preops Required After Fuel Load 52 0 0 52 i

i i

i l

May 8, 1986

'dNCLOSURE 6 CONSTRUCTION STATUS As of April 22, 1986, construction was 96.5 percent complete. -

l I

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May 8, 1986-ENCLOSURE 7 l I

1 STATUS OF INSPECTIONS REQUIRED BY MC 2512, MC 2513, AND MC 2514 All modules in the Regional inspection program will be. completed to support the 1

projected fuel load date. ,-

I MC 2512 Procedure Percent Number Complete Resp. Title 50076 8 90 MPS Safety-Related . Components II -

Review of Quality Records 50095 B 60 MPS Spent Fuel Storage Racks - Observa- i tion of Work and Work Activities 50100 8 90 MPS Safety-Related Heating, Ventilation, and Air Conditioning (HVAC) Systems 52055 50 PSS Instrumentation (Components and Systems I) - Review of Quality Records l

e .

(

s e

,s Enclosure'7 2 55093 B 0 MPS Reactor Vessel Internals (Welding) -

Observation of Welding Activities 1

55186 8 90 MPS Other Safety-Related . Piping - Weld Heat Treatment i First Inspection Second Inspection 1l 57050 32 MPS Visual. Examination, Procedure j Review / Work, Observation / Record Review 64053 8 80 PSS Fire Loop Installation

.l.

i 11

's l' ,

i l

Enclosure ~7 3 ,

MC 2513

)

i Procedure Percent l-

' Number Complete Resp. Title General 35301 80 QAS Preoperational Testing Quality Assurance-35740 8 50 QAS QA Program - QA/QC Administrative 35741 B 0 QAS QA Program - Audits q 35742 B 50 QAS QA Program - Document Control 35743 0 0PS QA Program - Maintenance 35744 8 30 Q A S. QA Program - Design Changes and Modification 35745 B 30 QAS QA Program - Surveillance Testing and .j Calibration Control .i 35746 B 50 QAS QA. Program - Procurement Control 35747 B 50 QAS QA Program - Receipt, Storage, and l' Handling of Equipment and Materials c________-__:_-___-__--___-__:. ._-_ __-_ _ . _ . __ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _

Enclosure 7 4 35748 8 70 QAS QA Program - Records  ;

35749 B 50 QAS QA Program - Tests and Experiments 1 i

35750 30 QAS QA Program - Test and Measurement Equipment ,

36301 8 80 RI Operational Staffing l

37301 80 RI Comparison of As-Built Plant to FSAR Description l

39301 B 0 QAS Preoperational Test Records 40301 B 60 RI Safety Committee Activity l 41301 0 0PS Operating Staff Training i

1  :

l 42400 B 0 RI Plant Procedures l

42450 B 0 0PS Operating Procedures 42451 B 0 0PS Maintenance Procedures 42452 B 0 0PS Emergency Procedures l 1  !

l l l

64704 90 PSS Fire Prevention / Protection Program j l

l I

.__--____-_______a

Enclosure 7 5 70300 80 -T P S Preoperational Test Procedure Review-70311 65 TPS Preoperational' Test Procedure Verification 70312 60 TPS Preoperational Test Witnessing

.~

70329 0 TPS Preoperational Test Results Evaluation Verification 70370 B 0 TPS Testing of Pipe Support and Restraint Systems (PWR only in 2513 Program) 70400 0 TPS Preoperational Test Results Evaluation 71301 B 50 0RP Technical Specification Revies). ,

71302 60 RI Preoperational Test Program Implementation-Verification 79501 70 REC Chemistry Controls 79502 70 REC Systems Affecting Chemistry 81038 0 PSEC Records and Reports 81046 0 PSEC Locks, Keys, and Combinations

Enclosure 7 6 81058 20 P$EC Security System Power Supply  ;

81062 0 PSEC Lighting 81066 0 PSEC Assessment Aids l

l 81070 0 PSEC Access Control - Personnel 81072 0 PSEC Access Control (Power Reactor) - Packages 81074 0 PSEC Access Control - Vehicles ,

l 81078 10 PSEC Oetection Aids - Protected Areas 81080 0 PSEC Detection Aids - Vital Areas, Material Access Areas, and Controlled Access Areas 81084 0 PSEC Alarm Stations 81401 0 PSEC Plans, Problems and Reviews i

81403 0 PSEC Receipt of New Fuel at Reactor Facilities 81501 0 PSEC General Requirements for Parsonnel 81810 0 PSEC Physical Protection Safeguards Information

Enclosure 7 7 82101 40 EPS Emergency Preparedness - Preoperational Inspection 83522 25 FRP Rad' Protection, Plant Chemistry, Radwaste, and Environmental: Organization and Management Controls 83523 15 FRP Rad Protection, Plant Chemistry, Radwaste, Transportation and Environmental:-

Training and Qualifications 83524 0 FRP External Occupational Exposure Control and Fersonal Dosimetry 83525 15 FRP Internal Exposure Control and Assessment

~

83526 10 FRP Control of Radiation Materials and Containment, Surveys, and Monitoring 83527 50 FRP Facilities and Equipment 85102 B 0 MCA Material Control and Accounting (Reac+or)

Enclosure 7 8 s 1

J Mandatory Test Procedure' Review

- i l 70304 B 60 TPS. Engineered Safety Features Test - i 1

Preoperational Test Procedure Review 70305 B 80 TPS Reactor Protection System Test -

Preoperational Test Procedure Review 70306 B 0 TPS Loss of Offsite Power Test -

Preoperational Test Procedure Review Mandatory Test Witnessing 70315 B 30 TPS Engineered Safety Features Test:-

Preoperational Test Witnessing 70316 B 0 TPS Loss of Offsite Power Test -

Preoperational Test Witnessing l

70317 8 20 TPS Reactor Protection System Test -  ;

i Preoperational Test Witnessing

Enclosure 7 9 1

i i

Mandatory Test Result Evaluation l.

70322 B 0 TPS Preoperational Test Results Evaluation -

ESF 70323 0 TPS Preoperational Test R~esults Evaluation -

(Containment Integrated Leak Rate Test) 70324 B 0 TPS Preoperational Test Results Evaluation -

Hot Functional Testing (PWR only in 2513 Program) 70325 B 0 TPS Preoperational Test Results Evaluation -

Reactor Protection System i

70326 B 0 TPS Preoperational Test Results Evaluation -

Loss of Offsite Power i

i j

l

Enclosure 7 10 l

MC E514 Procedure Percent Number Complete Resp. Title l

35501 50 QAS QA fca the Startup Test Program 60502 C 0 RI Fuel Inspection, Assembly, and Storage 72300 0 TPS Startup Test Procedure Review (Reference Procedura) l 72400 B 0 TPS Overall Startup Test Program 72500 B 0 TPS Initial Fuel Loading Procedure l

l l

l 72564 B 0 TPS Precritical Test Procedure Review (Protective Trip Circuit or Rod Drop Measurement) 72566 B 0 TPS Precritical Test Procedure Review (RCS Leak Test or Pressurizer Effectiveness) l 72570 B 0 TPS Initial Criticality Procedure Review

4 Enclosure 7 . 11 1

72572 B 0 TPS Low Power Test Procedure Review (Moderator Temperature Coefficient and Boron Worth or Control Rod and Pseudo Rod Ejection Worth) 72576'B 0 TPS Power Ascension Test Procedure Review (Natural Circulation or Power Reactivity Coefficient Measurement) 72578 B 0 TPS Power Ascension Test Procedure Review (Evaluation of Core Performance) 72580 B 0 TPS Power Ascension Test Procedure Review (Turbine Trip or Generator Trip) 72582 B D TPS Power Ascension Test Procedure Review -  !

l Loss of Offsite Power (Group A) )

)

72583 B 0 TPS Power Ascension Test Proc' dure Review -

i Shutdown from Outside Control Room (Group B) 72584 B 0 TPS Power Ascension Test Procedure Review -

Evaluation of Flux Asymmetry or Pseudo Rod Ejection Test

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