ML18033B420

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Provides Basis for Closure of Generic Ltr 83-28,Item 4.5.3. Util Has Concluded That Analyses Presented in BWR Owners Group Repts Acceptable for Resolving Issue,Subj to Listed Conditions
ML18033B420
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 07/05/1990
From: Wallace E
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-075, REF-GTECI-NI, TASK-075, TASK-75, TASK-OR GL-83-28, NUDOCS 9007100096
Download: ML18033B420 (8)


Text

. ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION, NBR:9007100096 DOC.DATE: 90/07/05 NOTARIZED:

NO DOCKET FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 AUTH.NAME AUTHOR AFFILIATION WALLACE,E.G.

Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Provides basis for closure of GL 83-28,Item 4.5.3'.

DISTRIBUTION CODE:

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TITLE: OR/Licensing Submittal:

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TOTAL NUMBER OF COPIES REQUIRED:

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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 32401 5N 157B Lookout Place U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 JUL 05 1990 Gentlemen:

In the Matter of Tennessee Valley Authority Docket No. 50-260 BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 2 GENERIC LETTER 83-28, REQUIRED ACTIONS BASED ON GENERIC IMPLICATIONS OF SALEM ATWS EVENTS%

ITEM 4.5.3$

REACTOR TRIP SYSTEM RELIABILITY(GSI 75$

MPA B093)

This letter is to provide the basis for closure of Generic Letter 83-28, Item 4.5.3, for BFN Unit 2.

This letter supercedes TVA's May 25, 1990 submittal on this subject.

The staff has reviewed the General Electric Topical Reports NEDC-30844, BWR Owners'roup (BWROG) Response to NRC Generic Letter 83-28, Item 4.5.3, and NEDC-30851P, Technical Specifications Improvement Analysis for BWR Reactor Protection

System, and on July 15, 1987 issued a favorable Safety Evaluation Report.

The staff has concluded that the analyses presented in the BWROG reports are acceptable for resolving this issue, subject to the conditions discussed below:

I Condition:

Confirm the applicability of the generic analysis to its plant.

Response

TVA endorses the BWROG position as documented in NEDC-30844A.

The generic analyses presented in NEDC-30851P is applicable to BFN.

Condition:

Demonstrate, by use of current drift information provided by the equipment vendor or plant-specific data, that the drift characteristics for instrumentation used in RPS channels in the plant are bounded by the assumption used in NEDC-30851P when the functional test interval is extended from monthly to quarterly.

Response

BFN's Reactor Protection System (RPS) functional test and instrument calibration frequencies are specified in Tables 4.1.A and 4.1.B of the BFN TSs.

No extensions to these intervals are proposed at this time.

Condition:

Confirm that the differences between the parts of the RPS that perform the trip functions in the plant and those of the base case plant were included in the analysis for its plant done using the procedures of Appendix K of NEDC-30851P (and the results presented in Enclosure 1 to letter OG5-491-12 from L. Rash (GE) to T.

Collins (NRC) dated November 25, 1985), or present plant-specific analyses to demonstrate no appreciable change in RPS availability or public risk.

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Response

The procedure which was used by BFN to evaluate plant specific applicability is provided in Appendix K of NEDC-30851P.

A list of BFN RPS configuration data was compiled, differences between the BWR generic model and BFN's specific configuration were identified, and the effects on system reliability were evaluated.

Using this method, TVA verified the BWROG generic analysis bounds the BFN RPS.

This review has been documented and is available for staff review.

Based on the above, TVA considers Generic Letter 83-28, Item 4.5.3, complete for BFN Unit 2.

TVA requested the Safety Issues Management System (SIMS) be updated to reflect TVA's completion.

TVA also requests the issuance of a Safety Evaluation Report documenting the closure of this item.

There are no commitments contained in this letter.

If you have any questions, please telephone Patrick P. Carier, Manager of Site Licensing, (205) 729-3570.

Very truly yours, TENNESSEE VALLEY AUTHORITY E.

G. Wallace, Manager Nuclear Licensing and Regulatory Affairs cc:

See page 3

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U.S. Nuclear Regulatory Commission JUL 05 1999 cc:

Ms. S.

C. Black, Deputy Director Project Directorate II-4 U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637

Athens, Alabama 35609-2000 Thierry M. Ross, Project Manager U. S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B.'. Wilson, Project Chief U.S. Nuclear Regulatory Commission'egion II 101 Marietta Street, NW, Suite 2900

'Atlanta, Georgia 30323

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