ML19319C912

Transfers Lead Responsibility Re Limit Switches Used to Prevent Pump Runout in Safeguards Sys from IE to Ofc of Nuclear Reactor Regulation

ML19319C912
Person / Time
Site:	Crystal River
Issue date:	03/17/1976
From:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:	Deyoung R Office of Nuclear Reactor Regulation
Shared Package
ML19319C913	List: ML19319C912
References
IE-RID-76-6, NUDOCS 8003040861
Download: ML19319C912 (2)

Text

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MAR I 7 1978 l

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Serial No.: IE-RID-76-6 n9% M

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b Transfer of Lead Responsibility T,c, s R. C. DeYoung, Assistant Director for Light Water Reactors, DPM o

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Subject:

USE OF LIMIT SWITCIIES TO PREVENT PUMP RUNOUT IN SAFEGUARDS SYSTEMS - CRYSTAL RIVER 3,. DOCKET NO. 3C 20',

4 Bov i

Responsible Braneh Chief:

K. V. Seyfrit Ij s

Description of Itent Requiring Haeolutions During preoperational testing of ths high pressure and low pressure injection systems,' it was determined that if the loop injection valves were allowed to open fully pump runout would occur. In lieu J

i of the e - practice of locked manual throttle valves or' flow I

restricting orifices, the licenses has proposed to resolve the problem

'l by adjusting tho' pump discharge motor operated globe valve limit switches.

Tests were conducted to verify flow rate of 500 gym in each high pressure injection train ~and 3000 gym in each low pressure injection train. Test-ing.also verified that if one of the " limit adjusted" motor operated valves in a train goes-to the-full open position. runout'will. occur.

This could result in the possible loss of the pump in the affected train.

'i The architect engineer, Gilbert Associates, stated that runout would occur at 545~gpu in the high pressure injection system and 3650 gym in the low pressure injection system._

i The licensees' position is that both the high pressure and the lowppressure 4

injection systems are designed to accept a single failure. The failure of a limit switch would not prevent the system from performing its intended function.~

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A similar request,. reference Transfer of Lead Responsibility Serial i

No. IE-C&O-75-15 dated July-7, 1975, was submitted concerning Millstona

.2.

Millstone 2 differs from Crystal River 3; in that Millstona has four parallel paths in each safety injection train and Crystal River has only two.

Recent discussions with Electrical Instrumentation and Control Systems

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Branch personnel indicate there may have been a change in the NRC pjob position on motor operated valve limit switch reliability since the response to the Millstone 2 question.

p w IE Recommendations and Proposed Course of Action:

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NRR will-detm -ine-if-the-lisueees' s mlution-of the pwp au d problem - flow control by adjusting _ motor operated valve limit switches -

is an accepenble technique.

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Forna AEC.318 (Rev. 9 53) AECM 0240 '

W u. 9 sovERNMENT PRINTING OFFICEI 3

1974.826 8SS 800so4a M V

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O I 7 1976 Transfer of Lead Responsibility _

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If the 14e======' course of action is acceptable NRR will

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datarmine if additions to the technical specifications are required concerning frequency of surveillance on valve-travel

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and limit switch action.-

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T1sa Office of Inspection and Enforcement will Provide additional

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' information as required.

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The Office of Inspection and Enforcement will verify adherence to any requiramanen imposed by the Division'of Project Management.

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References:

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1.

Manorandum, Long to Seyfrit, dated February 11, 1976.

(Enclosure 1) e 3

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Partinent'iisections of I&E inspection reports Nos. 50-302/75_-8, 75-13 and 76-1.

(Enclosure 2)

Concurrences:

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B. -1.tricP' Date B. H. Grier, Director Division of Reactor Inspection Programs,.IE Original signed by R. C. DeYounil-M I O EM Date R. C. DeYoung, Assistant Direceor for Light Water Rasctors,-DFM

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ces J. G. Davis, IE

. E. M. Howard, IE:IV R. S Boyd, DPM R. H. Engelken, IE:V-D.. Thompson, IE T. Abell, MIPC W. R. Butler,,DPM H. K. Shapar, ELD L. B. Engle, DPM K. V. Seyfrit IE '

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J. H._Snissak, IE G. W. Reinmuth, IE S. E. Bryan, IE J. P. O'Reilly, IE:I' N.

C.' Moseley,'IE:II

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J. GP Kapplers IE:III

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