ML20090D670

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Preliminary AO-50-219/75-12:on 750426,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 178 & C Found to Trip at Pressure Less than Tech Spec Value.Caused by Switch Repeatability.Switches Recalibr
ML20090D670
Person / Time
Site: Oyster Creek
Issue date: 04/28/1975
From: Carroll J
JERSEY CENTRAL POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
AO-50-219-75-12, NUDOCS 8303020269
Download: ML20090D670 (4)


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James P. O'Reilly q,,

Directorc e of Regulatory Operations Region 1

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63) Park Avenue King of Prussia, Pennsylvania 19406 e

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Jersey Central Pcuer C Li ht Co:2pahy c

Oyster Creek Nuclear Generating Station Dociet #50-219 Forked River,.;ew Jersey GS731 Subj ect :

Abnorcal Occurrence Report No. 50-219/7f/ 12

'fhe'fo110..ing is r. prclininary report being wbnitted in complicace with the Technical Specification.s paragraph 6.6.2.

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Preliminary Approval:.

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./ J. T. Carroll, J r. /

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Date

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.,n 11 8303020269 750428 POR ADOCK 05000219 PDR G

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Initio1 Telephone

[ lc of Report Date:

4-26 76~

bcturrence:

4-26-75 Time of Initial Written Report Date:

4-28-75 Occurrence:

0300 OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, ':EW JERSEY 08731 Abnormal Occurrence Report No. 50-219/75/12 IDENTIFICATION Violation of the Technical Specifications, paragraph 0F OCCURRENCE:

3.1.1.D.3, Low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE 17B and C t.

rc found to trip at pressures less than the minimum required value of 285 psig.

This event is considered to be an abnormal occurrence as defined in the Technical Specifications, paragraphs 1.153 and D.

CONDITIONS PRIOR Steady State Power Rout?.no Shutdown TO OCCURRENCE:

llot Standby Operation Cold Shutdown Load Changes During X Refueling dnutdown Ruui.lue Foner Oglati=

Routine Startup

. Other (Specify)

Operation The reactor mode switch was in the REFUEL position with reactor coolant temperature less than 212 F.

DESCRIPTION OF On Saturday, April 26, 1975 at approximately 0300, while OCCURRENCE:

performing quarterly surveillance testing on the four (4)

Low Reactor Pressure Core Spray Valve Permissive Pressure Switches, it was discovered that RE 17B and C tripped at 278 psig and 280 psig, respectively.

These values are Icss than the Technical Specification limit of 285 psig. Pressure switches RE 17B and C were immediately recalibrated.

'AbfioEmal Occurrence O

Report. No. 50-219/75/12 Page 2 The "as found" and "as Icft" switch settings were:

"As Found" Settings "As Left" Settings RE 17A 286 psig 286 psig RE 17B 278 psig 285 psig RE 17C 280 psig 287 psig RE 17D 28S psig 28S psig APPARENT CAUSE Design

_ Procedure 0F OCCURRESCE:

Manufacture Unusual Service Condition Installation /

Inc. Environmental Construction

, Component Failure Operator X-Other (Specify)

The cause of this occurrence is switch repeatability which is a recognized problem.

ANALYSIS OF The Core Spray System Parallel Isolation Valves open when OCCURRENCE:

a low-low reactor water level and/or high drywell pressure condition exists in addition to a low reactor pressure condition (285 psig). The four (4) Low Reactor Pressure Core Spray Valve Permissive Pressure Switches sense the low reactor pressure condition and provide signals to the valve opening logic. Two (2) of these switches (RE 17A and B) are associated with Core Spray System 1 and the other two (2) switches (RE 17C and D) are associated with Core Spray System 2.

A trip of one switch in each core spray system is required to effect parallel isolation valve opening in that system. A review of the "as found" switch settings indicates that parallel isolation valves in both dore rpray systems would have opened at reactor pressures 2:285 psig had a reactor low-low water level and/or high drywell pressure condition existed concurrently. The safety significance of this event is considered to be the loss of switch redundancy.

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r Abnormal Occurrence r ; port No. 50-219/7I?

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0 In addition, it is noted that the reactor has been maintained at atmospheric pressure during the current refueling outage and that the low reactor pressure permissive was consequently satisfied during this time period.

CORRECTIVE ACTION:

Immediate corrective action involved the recalibration u

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of pressure switches RE 17P and C.

Set point accuracy and tolerance in not only these instruments, but in others as well, are under investigation by Jersey Central Power G Light Company, GPU Service Corporation, and General Electric Company personnel.

FAILURE DATA:

Manufacturer data pertinent to these switches are as follows:

l Manufacture:

Barksdale Type:

Pressure Actuated Switch Range:

50-1200 psig Scr. No:

B2T-A12SS (RE 17B)

B2T-M12SS (RE 17C) 1\\\\SJ. 'YS Prepared by:

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Date:

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