ML20062D684

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Licensees Supporting Documentation for Approval of Recirculation Pump Trip(Rpt) for Reactor Protec Sys Fails to Address Most Criteria of IEEE 279 or Equip Qual & Adequate Surveillance Testing Tech Specs.Addl Info Requested
ML20062D684
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 11/14/1978
From: Lainas G
Office of Nuclear Reactor Regulation
To: Ippolito T
Office of Nuclear Reactor Regulation
References
NUDOCS 7811280361
Download: ML20062D684 (2)


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UNITED STATES

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November 14, 1978

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MEMORANDUM FOR:

T. Ippolito, Chief, Operating Reactors Branch #3, DOR-FROM:

G. Lainas, Chief, Plant Systems Branch, D0R

SUBJECT:

BRCWNS FERRY UNIT 1 END-0F-CYCLE RECIRCULATION PUMP TRIP Sy letter of July 18, 1978, TVA requested approval of a Recirculation Pump Trip (RPT) in order to improve the safety margin at end-of-cycle.

This request was supported by GE report NED0-24119, " Basis for Installa-tion of Recirculation Pump Trip - Browns Ferry Huclear Plant," and proposed Technical Specifications.

The RPT is required to be part of the reactor protection system, and hence to conform to IEEE E79 and to be appropriately qualified as Class 1E equipment.

As a result of our review (TAC 7783), we find that the licensee's supporting documentation does not address many of the criteria of IEEE 279 or equipment qualification.

The proposed technical specifications do not provide for adequate surveillance testing.

Accordingly, we have identified (see enclosure) a number of areas for which additional information is needed.

The Reactor Safety Branch will address non-electrical aspects of the proposed change.

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/ G. Lainas, Chief Plant Systems Branch Division of Operating Reactors

Enclosure:

b As stated

Contact:

J. T. Beard I

X-23077 cc:

See next page

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D. disenhut R. Satterfield F. Rosa D. Clark M. Mendenca G. Lainas D. Tondi J. T. Beard P. Check 1

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REOUEST FOR ADDITIONAL INFORMATION BROWNS FERRY UNIT _1 RECIRCULATION PUMP TRIP (RPTl__

l.

Document in appropriate detail that the end-of-cycle RPT systems will be part of the reactor protection system, will fully confona to IEEE 279-1971, and will be appropriately qualified as Class lE equipment.

2.

In order that compliance with the single failure criterion can be verified, provide the control logic diagrams, P&ID's, and schematic diagrams for the RPT systems (including sensors, ~ operating byoasses, and maintenance bypass features).

3.

Relative to IEEE 279 Section 4.20, describe the trip status indications for the RPT systems.

4.

Relative to IEEE 279 Sections 4.12 and 4.20, describe the bypass status indications for the RPT system.

5.

Relative to IEEE 279 Section 4.17, discuss the provisions for manual initiation of the RPT. system.

6.

The GE report NECO-24119 discusses the testability of the RPT system. However, some aspects of the licensee's submittal remain of concern.

Relative to IEEE 279 Section 4.11, describe the bypass caca-a.

bilities that are provided to facilitate on-lire t' sting b.

Relative to IEEE 279 Section 4.14, describe the.neans provided to control access to bypass capability.

c.

Propose new wording for Note 17 to Table 3.2.3 of the Technical Specifications which makes clear that only one of the two RPT systems may be bypassed for testing at one time.

d.

Propose a Technical Specification which provides for functional testing of the RPT system breakers during refueling outages, e.

Propese a Technical Specification which provides fer periodic.

testing of the response time of the RPT system. Specifically, such testing should demonstrate that the systen can teminate the current to the pump motors in less than 200 milliseccnds a

after tne receipt nf the sensor signal.

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