ML20147F276

Concludes That Issues Addressed in Stated S&W Repts Either Closed,Identified for Routine Insp Followup or Included in TVA Startup Action List in Separate Programs Such as Maint. Closeout of Remaining Repts Should Not Affect Restart

ML20147F276
Person / Time
Site:	Sequoyah
Issue date:	03/02/1988
From:	Zech G NRC OFFICE OF SPECIAL PROJECTS
To:	White S TENNESSEE VALLEY AUTHORITY
References
NUDOCS 8803070303
Download: ML20147F276 (7)

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i UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 e e j s

..... March 2, 1988 Docket Nos. 50-327/328 j

Mr. S. A. White H Manager-of Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street .

Chattanooga, Tennessee 37402-2801 -l

SUBJECT:

STONE AND WEBSTER ENGINEERING (SWEC) REPORTS Re: Sequoyah Nuclear Plant, Units 1 and 2 I In January 1986 SWEC performed an analysis of issues and concerns external to j

the Tennessee Valley Authority (TVA) as one means of assessing TVA performance '

and determining root causes of previously identified problems. This informa-tion was used to prepare revised Volume 1 of the TVA Nuclear Performance Plan. i All issues and concerns identified by SWEC were provided to the Employee 1 Concerns Task Group (ECTG) for evaluation and closeout. ECTG grouped the 192 issues provided by SWEC and documented their verification activities in a series of 57 reports called SWEC-SQB Element Reports. Completion of this activity was summarized in Sequoyah Subcategory Report SWEC-SQN-100.

SWEC-SQN-100 and the individual reports addressed tracking and closeout of Sequoyah issues and concerns previously identified by the NRC, the Institute of Nuclear Power Operations (INPO), the Federal Emergency Management Agency (FEMA), and the American Nuclear Insurers (ANI). The additional corrective actions described in SWEC-SQN-100 for SWEC-SQN-09, -13, -22/29, and -30 have been reviewed and found acceptable by the NRC staff. A summary of each SWEC report and its current status is provided in the enclosure. Issues that NRC staff has closed in inspection reports are indicated by (C) in the enclosure.

All NRC items have been reviewed against the NRC staff approved restart criteria by the Sequoyah resident inspectors. The NRC staff concludes that the NRC issues addressed in the SWEC reports have been either closed, identified for routine inspection followup, or included in the TVA Startup Action List in separate programs such as environmental qualification, seismic qualification, welding project, maintenance, post-modification testing, and surveillance instruction upgrade. For example, SWEC-SQN-6 involves piping design ar,alysis and has been addressed in various Engineering Category element reports applicabic to'Sequoyah. .SWEC-SQN-47, -49, and -55 involve issues for which corrective actions are addressed in the TVA Nuclear Performance Plans.

Therefore, final closecut of individual SWEC reports is not considered a Sequoyah restart item since all of the safety significant issues will be addressed in other NRC staff safety evaluations.

8803070303 880302 PDR ADOCK 05000327 P PDR ,

As mentioned above, several SWEC reports involve issues that had 'een b identified by INP0, FEMA, and ANI. Although NRC closure of these issues is not required as indicated in the enclosure, the review described above concluded that all safety significant items from these SWEC reports have been factored into programs tied to the TVA Startup Action List.

Therefore, NRC staff concludes that TVA's proposed tracking and closeout of SWEC reports is acceptable and that closeout of the remaining open SWEC reports should not be tied to Sequoyah restart. If you have any questions regarding this information, please contact Mr. Thomas S. Rotella, NRC staff Sequoyah.

Project Manager at (301) 492-0788..

Sincerely, Original Signed by Gary G. Zech, Assistant Director for Projects TVA Projects Division Office of Special Projects

Enclosure:

SWEC Report Summary cc w/ enclosure:

See next page Distribution

' Docket File 2' NRC PDR Local PDR Projects Reading S. Ebneter J. Axelrad S. Richardson G. Zech B. D. Liaw K. Barr C. Jamerson T. Rotella C. Upright, RII M. Fields J. Donohew OGC J. Rutberg F. Miraglia E. Jordan J. Partlow l ACRS(10)  !

TVA l SQN Reading File cc: Plant Service List .- ,pA

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l Mr. S. A. White Tennessee Valley Authority 'Sequoyah Nuclear Plant cc:

General, Counsel Regional Administrator, Region II Tennessee Valley Authority .U.S. Nuclear Regulatory Comission-400 West Sumit Hill Drive 101 Marietta Street N.W.

E11 B33 Atlanta, Georgia 30323 Knoxville, Tennessee 37902 Resident Inspector /Sequoyah NP Mr. R. L. Gridley c/o U.S. Nuclear Regulatory Commission Tennessee Valley Authority 2600 Igou Ferry Road SN 1578 Lookout Place ~ Soddy Daisy, Tennessee 37379 Chattanooga, Tennessee 37402-2801 Mr. Richard King. '

Mr. H. L. Abercrombie c/o U.S. GA0 Tennessee Valley Authority 1111 North Shore Drive Seouoyah Nuclear Plant Suite 225, Box 194 P.O. Box 2000 Knoxville, Tennessee 37919 '

Soddy Daisy, Tennessee 37379 Tennessee Department of Mr. M. R. Harding Public Health Tennessee Valley Authority ATTN: Director, Bureau of Sequoyah Nuclear Plant Environmental Health Services P.O. Box 2000 Cordell Huli Building Soddy Daisy, Tennessee 37379 Nashville, Tennessee 37219 Mr. D. L. Williams Mr. Michael H. Mobley, Director Tennessee Valley Authority Division of Radiological Health 400 West Summit Hill Drive T.E.R.R.A. Building W10 B85 150 9th Avenue North Knoxville, Tennessee 37902 Nashville, Tennessee 37203 County Judge Dr. Henry Myers, Science Advisor Hamilton County Courthouse Committee on Interior' Chattanooga, Tennessee 37402 and Insular Affairs U.S. House of Representatives Washington, D.C. 20515 l

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ENCLOSURE SWEC REPORT

SUMMARY

SWEC Report Description Oocket 50-328 NRC Item Numbers SWEC-SQN-01 AFWS & 0/G Procedures VIO 84-18-01 (C)

VIO 84-18-02 (C)

UNR 84-18-03 (C) i IFI 84-18-04 (C) '

SWEC-SQN-02 i Emergency Operating Instructions /

Abnormal Operating Instructions VIO 84-02-02 (C) )

IFI 84-02-01 (C)

SWEC-SQN-03 Technical Specifications Non- 1 compliance VIO 84-21-01 (C)

VIO 84-21-02 (C)

VIO 84-21-03 (C)

VIO 84-18-05 (C) -

SWEC-SQN-04 & 10 NRC Assessment of Training VIO 19-01 SWEC-SQN-05 Testing and Event Documentation VJQ.84-25-03 (C)

VIO 84-25-01 (C)  !

VIO-84-25-02 (C)

SWEC-SQN 06 Piping Design Analysis VIO 84-24-01 SWEC-SQN-07 Nondestructive Testing i Occumentation UNR 84-26-01 l

UNR 84-26-02 (C) i SWEC-SQN-08 Location of Embedded Equipment VIO 84-27-01 (C)

SWEC-SQN-09 F1re Protection VIO 84-31-04 (C)

VIO 84-31-03 (C)

OEV 84-31-02 (C)

OEV 84-31-01 (C)

VIO 80-10-01 (C)  !

SUEC-SQN-11 Sequoyah Refuel Procedure ,

Violation UNR 84-32-01 (C)

VIO 84-36-01 (C)

SSEC-SQN-12 TVA Comparison to Industry Medians  :

(INPO Report) "ormal NRC closure not required.

SWEC-SQN-13 Plant Leakage Monitoring (NRC Formal NRC closure-not Observation in IR 50-327/84-28) required.

SWEC-SQN-14 Testing of Air Purifying Respirator Fil.ters VIO 84-34-01 (C)

SWEC-SQN-15 Sequoyah Nuclear Plant Radiological Emergency Plan, Rev. 9 REP VIO 85-13-02 (C)

VIO 85-13-01 (C)

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SWEC-SQN-16 Surveillance Instruction Inadequacy VIO 84-29-01 (C)

SWEC-SQN-17.

Containment Leak Rate Test Failure IFI 84-37-01 (C)

SWEC-SQN-18 Documentation of Inspection VIO 84-33-01 (C)

.VIO 84-33-02 (C)-

SWEC-SQN-19 Valve Checklist: Fuel Handling Instruction VIO 84-35-01 (C)  :

IFI 85-35-04 SWEC-SQN-20 Inadequate Implementation of fuel Handling Procedure.* VIO 84-36-01 (C) i

'SWEC-SQN-21 Post Modification Testing -

VIO 84-38-01 (C)

VIO 84-38-02 (C)  ;

VIO 84-38-03 (C) l IFI 84-38-06 (C)

SWEC-SQN-22 & 29 Sequoyah Calibration Control 1 VIO 85-05-01 (C) i SWEC-SQN-23 NRC Notification Inadequate .

I VIO 85-06-01 (C) i SWEC-SQN-24 Thimble Tube Ejection Event (Unit 1 - Docket 50-327) VIO 84-24-01 (C)*

VIO VId 84-24-03

.84-24-02 (C) (C)

!FI 84-24-04 (C)

SWEC-SQN-25 .

Jhdsviolations/IFI a

IFI 85-25-01 (C)

SWEC-SQN-26 <

b sposition for Pressure Transmitters IR/50-327 85-70 (C) 4 SWEC-SQN-27 Appendfx R, Fire Protection VIO 85-01-01 (C)

VIO 85-01-02 (C) ,

VIO 85-01-03 (C)  !

/IO 85-01-04 (C) t v!O 85-01-05 (C)  !

/IO 85-01-08 (C) i VIO 85-01-09 (C) i UNR 85-01-06 (C)

IFI 85-01-07 (C)

SWEC-SQN-30 Chemical and Radiological Procedures '!IO 85-15-02 (C)

IFI 85-15-04 (C)

SUEC-SQN-31 Nonconformance Reporting VIO 84-38-02 (C)  !

SSEC-SQN-32 Radiation Monitor Testing VIO 85-16-01 (C)

(VEC-SQN-33 Operability of Containment Spray Pump UNR 85-18-01 (C) i l

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i SWEC-SQN-34 Radiation Safety VIO 85-20-01 (C)

'VIO 85-20-02 (C)

VIO 85-20-03 (C)

SWEC-SQN-35 Incomplete Design Records Inadequate Review - Environmental IFI 85-21-01 Questions Determination IFI 85-21-02 (C)

SWEC-SQN-36 Failure to Follow Established Procedures, CA Program VIO 85-17-03 (C)

Failure, Procedural UNR 85-16-03 Noncompliance VIO 85-17-02 (C)

VIO 85-20-02 (C)

VIO 85-17-04 (C)

SWEC-SQN-37 Operational Safety Verification VIO 85-23-01 (C)  !

VIO 85-23-02 (C)

VIO 85-23-03 (C)

IFI 85-23-05 (C)

UNR 85-23-07 IFI:85-23-08 (C)

SWEC-SQN-38 Maintenance Management '

IFI 85-24-01_(C)

VIO 85-24-02 (Q)

VIO 85-24-03 I EC-SQN-39 Sequoyah Emergency Management l Formal NRC closure not '

(FEMA Report - Recommendations) required SWEC-SQN-40,.

INPO Maintenance Performance Formal NRC closure not Data Survey - 1985 required '

SWEC-SQN-41 Electrical Problem, Radiological l Protection, and Security Violation VIO 85-26-11 (C)  !

VIO 85-26-03 (C) l SWEC-SON-42 SON Rev. 20 Emergency Plan Modifications Revision no longer in effect SOEC-SQN-43 High Failure Raw for Auxiliary Formal NRC closure not Feecwater Syste,m (INPO Report) required SWEC-SQN-44 Operational Safetf Verification VIO 85-28-01 (C)

VIO 85-28-05 l IFI 85-28-02 (C)

SUEC-SQN-45 & 51 Surveillance, Frisking and Outage Work 85-32/85-38 (C)

SdEC-SQN-46 Cable Tray Support Systems and CVCS Sampling Line Cracks VIO 85-29-01 (C)

VIO 85-29-02 (C)

UNR 85-29-03 (C) 1 I

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' SW EC-SQN-47 I Environmental Qualification (NRC Corrective action described Concerns - Letter of 4/5/85 and in Sequoyah Nuclear 11/14/85) Per mance Plan SWEC-SQN-48 SQN' Operational Readiness Review i (INPO Report)_ '

Formal NRC action not i required SWEC-SQN-49 Employee Concerns Program (NRC Concerns - Letters of 11/19/85 Corrective action described in Employee Concerns Program and 1/6/86)  ;

SWEC-SQN-50 Instrument Maintenance Testin; VIO 85-35-01 (C)

SWEC-SQN-53 -

Containment Leak Rate Test: IFI 85-4'4-01 Prevention of Inadvertent IFI 85-44-02 Procedure Changes (Docket 50-327)

SWEC-SQN-54 ' Failure to Update Operating Instruction: Containment URI 85-43-01 (C)

Instrumentation: Operator URI 85-43-02 (C) .

Training IFI 85-43-07'(C)

IFI 85-43-08 (C) -

IFI 85-43-09 (C)

IFI 85-43-10 (C)

IFl 85-43-11 (C)

.IF' 85-43-12 (C)

IFI 85-43-05 (C)

IFI 85-43-06 (C)

. VIO 85-46-04 (C)

VIO 86-19-01 (C)

UNR 86-28-15 (C)

SWEC-SQN-55 NRC Systematic Assessment of Corrective action described l SQN Performance - 1985 (SALP in corporate and Sequoyah Program Findings). i Nuclear Performance Plans  !

SUEC-SQN-56 Leak Rate Testing Group l Organization (NRC Trainee Formal NRC closure not l required '

Opinion)

SWEC-SQN-57 Oraft Generic Emergency Preparedness Pldn (.7/29/85 Formal NRC closure not required Letter) .

SWEC-SQN-58 American Nuclear Insurers Formal NRC closure not Inspection Report September 1985 required SVEC-SQN-59 American Nuclear Insurers Formal NRC closure not Inspection Report Material required Handling

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