ML18030B282

Forwards Request for Addl Info Re Util Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Test Requirements for Reactor Trip Sys Reliability.Schedule for Response Requested within 15 Days

ML18030B282
Person / Time
Site:	Browns Ferry
Issue date:	04/28/1986
From:	Grotenhuis M Office of Nuclear Reactor Regulation
To:	White S TENNESSEE VALLEY AUTHORITY
References
GL-83-28, TAC-52901, TAC-52902, TAC-52903, TAC-53737, TAC-53738, TAC-53739, TAC-53964, TAC-53965, TAC-53966, NUDOCS 8605020418
Download: ML18030B282 (4)

Text

Docket Nos. 50-259/260/296 Mr. S.

A. White Manager of Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 DISTRIBUTION NRC PDR Local PDR Gray File RBernero'Thomp'son APR 3 8 P$

SNorris MGrotenhuis RClark BGrimes JPartlow EJordan ACRS (10)

DLasher OELD Dear Mr. White

SUBJECT:

GENERIC LETTER 83-28, ITEMS 3. 1.3 and 3.2.3 Re:

Browns Ferry Nuclear Plant, Units 1, 2 and 3

We have completed our review of your responses to Items 3. 1.3 and 3.2.3 of Generic Letter (GL) 83-28 dated November 7, 1983.

Your responses were evaluated for compliance to the staff's positions delineated in GL 83-28 for Action Items 3. 1.3 and 3.2.3 and found to be inadequate.

Descriptions of the deficiencies are discussed in greater detail in the enclosed Request for Additional Information.

We request that you provide a schedule for your response within 15 days of receipt of this letter.

If there are any questions, please contact the Project Manager, M. Grotenhuis (301) 492-7358.

The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, 0riginai signed bY hl ( rotenhuis Marshall Grotenhuis, Project Manager BWR Project Directorate ¹2 Division of BWR Licensing

Enclosure:

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Mr. S.

A. 1!hite Tennessee Valley Authority Brains Ferry Nuclear Plant Units 1, 2, and 3

CC:

I!. S. Sanqer, Jr., Esouire General Counsel Tennessee

'ta)fey Authority 400 Commerce Avenue E 1'!B 330 Knoxville, Tennessee 37902 Mr. Ron Rogers Tennessee Valley Authority 5'30B Lookout Place Chattanooga, Tennessee 37402-2801

Chairman, Limestone County Commission Post Office Box 188

Athens, Alabama 35611 Ira L. Meyers, M.D.

State Health Officer State Department of Public !!ealth State Office Building

!1ontgomery, Alabama 36130 Mr. K. 1!. Mhitt E3A8 400 liest Summit Hill Drive Tennessee Valley Authority Knoxville, Tennessee 37902 Reqional Administrator, Reqion II U. S. tluclear Regulatory Comnission 101 Marietta Street, Suite 3100 Atlanta, Georaia 30303 1". C. Bibb Site Director, BFNP Tennessee Valley Authority Post Office Box 2000

Decatur, Alabama 35602 Resident Inspector U. S. Nuclear Reaulatory Commission Route 2, Box 311

Athens, Alabama 35611 Mr. Donald L. 1!illiams, Jr.

Tennessee Valley Authority 400 Hest Summit Hill'rive, 1!10B85 Knoxville, Tennessee 37902

'obert L. Lee(is, t1anager, BFNP Tennessee Valley Authority Post Office Box 2000

Decatur, Alabama 35602 Mr. Steven Roessler U. S. Nuclear Regulatory Commission Reactor Training Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411

RE UEST FOR ADDITIONAL INFORMATION SALEM ANTICIPATED TRANSIENT WITHOUT SCRAM ATWS GNRICLE R

TEMS

.1.

ND..3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 By letter dated November 7, 1983, the Tennessee Valley Authority, (TVA, the licensee for Browns Ferry Unit Nos.

1, 2 and 3) provided a response to items

3. 1.3 and 3.2.3 of Generic Letter 83-28 on November 7, 1984.

Within the

response, the licensee's evaluation for item 3. 1.3 is that they are not aware of any program currently being done by GE to specifically determine if current testing requirements degrade the reliability of the Reactor Trip System equipment, nor do they have any information indicating that existing testing degrades rather than enhances safety.

The licensee's response to item 3.2.3 is that it is not their philosophy to propose changes in technical specifications which are perceived to degrade rather than enhance safety.

If such should be determined, appropriate changes would be submitted along with supporting justification.

The licensee's responses to items 3. 1.3 and 3.2.3 of Generic Letter 83-28, are considered to be inadequate by the staff.

There items will be held open pending receipt and assessment of information responsive to these concerns.

In order to continue our review the following information is required:

Item 3. 1.3 - Please state that TVA has searched their technical specifications for post maintenance test requirements that may degrade safety as requested by the generic letter.

Also state whether any were found.

If none were found then a clear statement to that effect is requested..

If such requirements are found, proposed technical specifications changes should be submitted to resolve the degrading condition together with supporting justification.

This item applies only to Reactor Trip Components.

Item 3.2.3 - Please make a similar response to that for Item 3. 1.3 for all other safety-related components.