ML20132C209

Discusses Basis for Feedwater Isolation on High Steam Generator Level Design Requirements.Applicant Should Respond to Instrumentation & Control Sys Branch Licensing Position 1

ML20132C209
Person / Time
Site:	Beaver Valley
Issue date:	06/18/1984
From:	Houston R Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
Shared Package
ML19283C868	List: IA-85-926, Forwards Rept of 840726-27 in-progress Audit Re Detailed Control Room Design Review (Dcrdr).Dcrdr Proceeding Satisfactorily.Concern Expressed Re Differences Between Unit 1 & 2 Control Rooms & Role of Human Factors Specialist ML19283C867 ML19292E104 ML20132B767 ML20132B791 ML20132C010 ML20132C076 ML20132C105 ML20132C131 ML20132C209 ML20132C245 ML20132C247 ML20132C253 ML20132C285 ML20132C290 ML20132C295 ML20132C301 ML20132C310 ML20132C323 ML20132C334 ML20132C338 ML20132C344 ML20132C365 ML20132C379 ML20132C383 ML20132C389 ML20132C394 ML20132C421 ML20132C427 ML20132C433 ML20132C442 ML20132C453 ML20132C459 ML20132C464 ML20132C468 ML20132C474 ML20132C479 ML20132C484 ML20132C487 ML20132C493 ML20132C499 ML20132C512 ML20132C518 ML20132C536 ML20132C542 ML20132C559 ML20132C569 ML20132C575 ML20132C633 ML20133M691 ... further results
References
FOIA-84-926 NUDOCS 8406230186
Download: ML20132C209 (2)

Text

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ENCLOSURE 1 JUN 18 1984 j

MEMORANDtM FOR: Thomas M. Novak, Assistant Director for Licensing Division of Licensing i

i FRON:

R. Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integ~ ration

SUBJECT:

BASIS FOR REAYER VALLEY 2 FEEDWATER ISOLATION ON HIGH STEAM GENERATOR LEVEL DESIGN REQUIREMENTS Plant Name:

Beaver Valley 2

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Docket No.:'

50-412 i'

Licensing Status:

OL Responsible Branch: LBf3 Project Manager:

L Lazo Review Branch:

ICSB Review Status:

Incomplete In Section 7.3.3.12 of the Beaver Valley 2 draft SER ICSB expressed a concern that the design of feedwater isolation on a high steam generator level -did not meet the requirements of paragraph 4.7 of IEEE-STD-279.

The applicant's response to that concern, dated March 28, 1984, stated that IEEE-STD-279 is not applicable to the issue.

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In response. ICSB stated, in our Licensing Position il for Beaver Valley 2 dated April 30, 1984, that either the design of the feedwater isolation on a high steam generator level be modified to meet the re-quirements of IEEE-STD-279 or an analysis be provided to show that the consequences of feedwater addition not being terminated by the high steam generator level signal are not safety significant.

In a May 30, 1984, response, the applicant claims that ICSB's position is a new requirement and should be processed in accordance with NRR procedures for plant specific backfitting.

ICSB has reviewed the epplicant's claim and believes that the char-acterization of this issue as a backfit is inappropriate. As stated in ICSB Licensing Position #1, the applicant, in Chapter 15 of the Beaver Valley 2 FSAR, takes credit for feedwater isolation on a high steam generator level signal and identifies this isolation action as an engineered safety feature actuation function.

Consistent with this, the applicant, in Section 7.3 of the FSAR, has identified IEEE-STD-279 as an acceptance criterion for the feedwater isolation func-tion and has further claimed to meet those requirements (specifically including paragraph 4.7 of IEEE-STD-279).

CONTACT:

F. Burrows, ICSB

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ICSB's position oti this issue is based on our reiriew following the guidance of Sections 7.1 and 7.3 of the NUREG-0800 (SRP) to confirm

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that the design of the feedwater isolation function satisfies the requinsments of the appropriate acceptance criteria. We, therefbre,

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conclude, based on the doc 6 tion provided by the applicant's FSAR, that this should not be considered a new nquirement (backfit)a and we again request that the applicant respond to ICSB Licensing Post-tion il on this issue.

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