Text

Informs of 970221 Meeting W/Util to Discuss Unresolved Items Documented in Insp Repts 50-327/96-16 & 50-328/96-16 Re Environ Qualification.List of Attendees & Presentation Handouts Encl
	ML20135C815
Person / Time
Site:	Sequoyah
Issue date:	02/24/1997
From:	Lesser M; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Kingsley O; TENNESSEE VALLEY AUTHORITY
References
	NUDOCS 9703040312
	Download: ML20135C815 (25)
	v • d • e

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February 24, 1997

Tennessee Valley Authority

ATTN: Mr. Oliver D. Kingsley, Jr.

President. TVA Nuclear and

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Chief Nuclear Officer

6A Lookout Place

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1101 Market Street

Chattanooga, TN 37402-2801

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SUBJECT: MEETING SUMMARY

SEQUOYAH NUCLEAR PLANT, DOCKET NOS. 50-327 AND

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50 328

Dear Mr. Kingsley:

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On February 21, 1997, the NRC staff met at the Region II office with

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representatives of the Tennessee Valley Authority's Sequoyah Nuclear Plant

staff. The purpose of this meeting was to discuss unresolved items documented

in NRC Inspection Report 50 327,328/96-16, regarding environmental

qualification. Enclosure 1 is a list of the individuals who attended the

meeting, and Enclosure 2 contains a copy of the material supplied by the

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licensee at the meeting.

In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2,

)

Title 10 Code of Federal Regulations, a co)y of this letter and its enclosures

will be placed in the NRC Public Document

Room.

Should you have any questions concerning this letter, please contact us.

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Sincerely,

(Original signed by P.

K. VanDoorn)

Mark S. Lesser, Chief

Reactor Projects Branch 6

Division of Reactor Projects

Docket Nos. 50 327, 50 328

License Nos. DPR 77, DPR-79

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Enclosures:

1. List of Attendees

2. Handout Material

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cc w/encls:

(See page 2)

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9703040312 970224

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TVA

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cc w/ encls:

Mr. O. J. Zeringue

Mr. J. T. Herron

,

Senior Vice President

Plant Manager

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Nuclear Operations

Sequoyah Nuclear Plant

Tennessee Valley Authority

6A Lookout Pla e

P. O. Box 2000

1101 Market Street

Soddy Daisy. TN 37379

Chattanooga, TN 37402 2801

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Mr. Michael H. Mobley, Director

Dr. Mark 0. Medford

Division of Radiological Health

Vice President

3rd Floor L and C Annex

Engineering and Technical Services

401 Church Street

6A Lookout Place

Nashville, TN 37243-1532

,

1101 Market Street

Chattanooga, TN 37402 2801

County Executive

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Hamilton County Courthouse

Mr. R. J. Adney

Chattanooga, TN 37402 2801

Site Vice President

Sequoyah Nuclear Plant

Distribution w/encls:

(See page 3)

Tennessee Valley Authority

P. O. Box 2000

Soddy-Daisy, TN 37379

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General Counsel

Tennessee Valley Authority

ET 10H

400 West Summit Hill Drive

Knoxville, TN 37902

Mr. R. R. Baron

General Manager Nuclear

Assurance & Licensing

4J Blue Ridge

1101 Market Street

Chattanooga, TN 37402-2801

Mr. P. Salas, Manager

Licensing and Industry Affairs

Tennessee Valley Authority

4J Blue Ridge

1101 Market Street

Chattanooga, TN 37402-2801

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Mr. R. H. Shell, Manager

Licensing and Industry Affairs

Sequoyah Nuclear Plant

Tennessee Valley Authority

P. O. Box 2000

Soddy-Daisy, TN 37379

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Distribution w/encls:

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J. R. Johnson, RII

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M. S. Lesser, RII

S. E. Sparks, RII

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F. J. Hebdon, NRR

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R. W. Hernan, NRR

H. L. Whitener, RII

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C. F. Smith, RII

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D. H. Thompson, RII

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J. H. Moorman, RII

E. D. Testa, RII

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PUBLIC

NRC Resident Inspector

U. S. Nuclear Regulatory Commission

2600 Igou Ferry

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Soddy Daisy, TN 37379

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NRC Resident Inspector

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U. S. Nuclear Regulatory Commission

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1260 Nuclear Plant Road

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Spring City, TN 37381

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LIST OF ATTENDEES

NRC

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J. P. Jaudon, Director,' Division of Reactor Safety (DRS), Region II (RII)-

- H. O. Christensen, Branch Chief, Engineering Branch, DRS, RII

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G. A. BelisN, Branch Chief Branch 5, Division of Reactor Projects (DRP), RII

M. Shannon, lenior Resident Inspector DRP, RII

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S. E Sparks, Project Engineer, DRP, RII

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N. Merriweather, Reactor Inspector. Engineering Branch, DRS, RII

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C. F. Smith, Reactor Inspector Engineering Branch, DRS, RII

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R. W. Hernan, Senior Licensing Project Manager, Office of Nuclear Reactor

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Regulation

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Licensee Attendees:

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M. Burzynski, Engineering and Materials Manager

H. Lorek, Mechanical / Nuclear Engineering Manager

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R. Ryan, Manager, Nuclear Engineering

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M. Fetch, Nuclear Assessment and Licensing Manager

J. Smith, Site Licensing Supervisor

P. Salas, Licensing and Industry Affairs Manager

K. Whittenburg, Manager, Nuclear Communications

Other Attendees:

Jim Riccio, Staff Attorney, Public Citizen

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Enclosure 1

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Secuoya:a Nuclear Plant

TVA/NRC Tec:mical Meeting

February 21,1997

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Environmen::a. Qua.i ~1 cation Unreso..vec. I: ems

X1C Inspection Report 96-:.6

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Enclosure 2

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Sequoyah Nuclear Plant

TVA/NRC Technical Meeting

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February 21,1997

Agenda

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Opening Remarks

M. J. Burzynski

Sequence of Events

M. J. Lorek

Discussion of Unresolved Items

M. J. Lorek/R. H. Bryan

Regulatory Perspective

J. D. Smith

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Closing Remarks

M. J. Burzynski

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Opening Remarks

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Sequence of Events

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Sequoya1 Nuclear Plant

Sequence'ofEvents

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TVA licensed with source terms established in accordance with

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TID-14844

March 19,1987

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- TVA (corporate fuels engineer) identified and initiated a

corrective action document that the FSAR did not reflect the

change in dose calculations based on an increase in core life. EQ

was not addressed in the corrective action document

December 30,19'88 U2C3 core exceeded 650 EFPD

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December 29,1989 UIC4 core exceeded 650 EFPD

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Sec uence:of Event 4;

July 30,1990

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- Dose calculation TI-RPS-48, Revision 3 issued to reflect the

results from the increase in core life

September 12,1990

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- SQN design engineer identified and initiated a corrective action

document that the effects in the increase in core life was not

addressed relative to EQ Program

July 22,1991

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- TVA requested Westinghouse to provide ajustification for

continued operation (JCO) for the EQ issue

September 4,1991

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- Westinghouse provided a JCO to TVA for the EQ issue

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Secuence of Events

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December 6,1991

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- Dose calculation TI-RPS-48, Revision 5 issued to remove the results

from the increase in core life

October 21,1993

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- Conference call with the NRC (NRR and Region II) pertaining to the

EQ JCO and the methodology being used for the dose calculations.

The JCO was faxed to NRC

November 30,1993

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- NRC evaluation of the JCO provided to TVA. The evaluation

concluded that the RegGuide 1.77 methodology was not appropriate

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and that the dose calculation needed to be based on TID 14844

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Sequoyaa Nuc. ear Plant

Sec uence'of Events

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March 4,1994

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- Revised JCO using TID 14844 methodology provided to NRC. The JCO

was based on 1000 EFPD and a U-235 enrichment of 4.5 percent

- Evaluated impact of JCO on EQ binders and determined that the results

remained bounded. No hardware changes were needed

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April 8,1994

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- NRC evaluation of revised JCO provided to TVA. The JCO was

determined to be acceptable

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June 3,1994

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- EQ drawings revised to include a note that the source term information

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was under review and to consult Mechanical Engineering before making a

design change using the information

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August 26,1994

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- Received new source term from Oak Ridge National Laboratory

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Secuence of Events

October 11,1994

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- Dose calculation revised to reflect 1000 EFPD and U-235 enrichment

of 5.0 percent

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- Evaluated impact of revised dose calculation on EQ binders and

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determined that results remained bounded

- Qualified life within NUREG 0588 requirements

- Started EQ binder revisions

November 6,1996

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- Design criteria issued for the EQ Program superseding the EQ

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drawings

February 20,1997

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- EQ binders revised to reflect revised dose calculations

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Discussion of Unresolved Items (URI)

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Discussion of U11reso_vec Items

URI 96-16-01

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Inadequate Safety Evaluation Resulted in Unreviewed Safety Ouestion

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- TVA identified and initiated corrective action document that the effects in

the increase in core life was not addressed relative to the EQ Program

- A proposed change, test, or experiment shall be deemed to involve an

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Unreviewed Safety Question

If the probability of occurrence or the consequences of an accident or

malfunction of equipment important to safety previously evaluated in the safety

analysis report may be increased; or

If a possibility for an accident or malfunction of a different type than any

evaluated previously in the safety analysis report may be created; or

If the margin of safety as defined in the basis for any technical specification is

reduced

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Discussion 0::~Unreso..vec Items

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URI 96-16-01 (cont.)

- No unreviewed safety question existed

Offsite dose remains well within 10 CFR 100 limits

Components remained within their environmental qualification requirements

Issue communicated to NRC three years ago

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NRC had no immediate safety concern

Radiation environment margins adequate for reassessment for extended reactor

core burnup

- No hardware changes needed

- Corrective actions are complete

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Discussion of Unreso.vec ::tems

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URI 96-16-02

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Untimely Corrective Action for Nonconforming Plant Conditions

Licensee had continuedplant operations under the JCO without revising

the EQ binders and EEB calculations

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- Timeliness was consistent with safety significance

Containment dose calculation (TI-RPS-48) issued October 1994

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EQ binders qualification verified to remain bounded

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Significant amount of work required to incorporate corrected numbers m

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design documents (cascading documents) and EQ binders

Consistent work effort Ibcused on resolution during this period

EQ binder work coordinated with other activities that were ongoing

concurrently

- Resolution involved interface with NRC

NRC requested TVA to revise JCO in November 1993

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NRC accepted revised JCO in April 1994

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Discussion of Unreso.vec Items

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URI 96-16-03

Inadequate Design Control for Nonconforming Plant Conditions

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Three examples

- Calculation TI-RPS-48, Revision 3 documented 100-day integrated

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accident dose with 1000 EFFD was not incorporated into design

output documents

- Calculation TI-RPS-48, Revision 5 documented 100-day integrated

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accident dose with 650 EFPD and does not accurately depict actual

p'lant conditions

- A formal calculation was not prepared, reviewed and approved to

support the JCO for the increase in the 100-day integrated accident

dose inside containment and the annulus

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Sec uoyal Nuc.. ear Plant

Discussion o ~Unreso..vec Items

URI 96-16-03 (cont.)

Example One

- TI-RPS-48, Revision 2, was the design basis calculation

- TI-RPS-48, Revision 3, was issued to resolve the 100-day

integrated accident dose with 1000 EFPD

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- TI-RPS-48, Revision 3, not incorporated into design output

documents because of problems identified with TID-14844 source

term for extended core burnups and inappropriate results from beta

dose

- TI-RPS-48, Revision 4, svas issued to address the inappropriate beta

dose results

- TI-RPS-48, Revision 5, was issued to return source term to

Revision 2 level while source term problem was resolved

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Sec uoya1 Nuc. ear P:. ant

Discussion of Unreso..vec. Items

URI 96-16-03 (cont.)

Example Two

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- TI-RPS-48, Revision 5 returned calculation to original design basis

conditions

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- JCO was developed to show acceptable conditions pending

resolution of TID-14844 problem

- Deficiency in design basis calculation was identified and covered

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by existing PER

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- Plant was bounded by JCO for actual plant conditions

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Sequoya a Nuc_ ear Plant

Discussion of Unreso..vec. Items

URI 96-16-03 (cont.)

Example Three

- JCO was supported by QA computer software

- Results were prepared and checked

- Hard copy calculations issued December 1996 supported JCO

conclusions with no change

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~~Sec uoya1 Nuc.. ear Plant~~

~~Regu atory Perspective~~

~~Issue was identified by TVA~~

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~~No Unreviewed Safety Question existed~~

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No hardware changes needed
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Timely corrective actions were initiated and completed
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~~Issue communicated to NRC~~

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- No immediate concerns
- Radiation environment margins recognized
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- Resolution path consistent with,NRC expectations at that time
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No safety significance
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- Margins existed at time ofissue discovery
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- Equipment remained environmentally qualified

~~Long-term actions are complete~~

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Secuoyaduc_ ear P: arr:

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Closing Remarks
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ML20135C815

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