ML20207L502

Package of Info Re HPI stop-check Valves

ML20207L502
Person / Time
Site:	Davis Besse
Issue date:	08/02/1982
From:	De Agazio A Office of Nuclear Reactor Regulation
To:
References
TAC-48560, NUDOCS 8701120193
Download: ML20207L502 (30)

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L DHANF ARNOID FNS NOTIFICATION ON 6/07/82 AT 2:40 P.M. WHILE PERFORMING FOl_LOWUP PER MC 7515.

RIIRVEILLANCE TESTING THE LICENSFE FOUND THAT A

THF "C" INBOARD MSIV WOULD NOT INITIATF A

'41.05 RPS TRIP AT 10 PFRCENT VALVE CLO911RE.

A TRIP 11.06 OF THF RPS WOULD OCCtlR IF THE OPFRATOR HELD 11.07 THE HAND SWITCH IN THE CLOSFD POSITION BUT IT f

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-4 11.13 sunCRITICAL AT 10:00 P.H.

THE LICENSFE EXPFCTS 11.14 -

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11.17 DAVIS-RFRSF TFLFCON FROM THE ON 6/01/87 THF LICFNSFF DETFRMINFD THAT THRFE FOLLOWUP PFR MC 2515.

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16.

I 16.01 DIVISION OF FNOllEERING 8: TFCHNICAL PROGRAMS

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16.03 MIDt.AND 1 Sc 2 MIDLAND ACRS MEETING.

16.04 -

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MR. H. MALLFTT. CHIEF. l.ICENSING SECTION.

INFORMATION.

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10.

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20.

Facility / Licensee Notification Item or Event Restonal Action 71.

71.01 DIVISION OF FMFRO(NCY'PRFPAREDNESS 3r OPERATIONAL SUPPORT 71.02 71.O'4 OFNFRAL MR. M. SCHUMACHER IS ATTENDING A MEETING IN INFORMATION.

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RIIRVEILLANCE TESTING THE LICENSFE FOI.IND THAT

~. #3 THE "C" INBOARD MSIV WOULD NOT INITIATF A

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+

WITHIN TOLFRANCE. THE SYSTFM WAS DECLARED 1t.t INOPFRAPI.E AND PL ACED IN THF TRIP CONDITION PFR

~11.11 TFCHNICAL SPFCIFICATION RFOUIRFMFMTS. A POWFR 11.12 RFIMICTION WAS INITTATED AND THE UNIT PFCAMF 11.13 4

SURCRITICAL AT 10:00 P.H.

THE LICENSFE EXPECTS 11.14 -

11.15

._N THF REPAIR 9 Til PE COMPLETED WITHIN 24 HOIRS.

l 11.tA ON 6/nt/97 THF LICFNSFF DETFRMINFD THAT THRFE FOLLOWUP PFR MC 2515.

+

11.f7 DAVIS-RFSSF TFLFCON FROM T E f

RESIDENT INSPFCIOR IVir OF THE l-IMIR HPI LINES WIN A.D NOT PASS FLsW 11.tR s_

AT 135 PSI DIFFFRFNTIAl. ACROSS THF CHECK VALVFS T

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11.25 ACTIVITIES.

tt.76 17.

_ 6/03/92 i

13.

Da11v Report-RIII 14.

15.

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16.01 DIVISION OF FNDINEERINO 8: TFCHNICAL PROORAMS 16.02 MR. W l.ITTLE WILL PF IN HG TO ATTEND THF INFORMATION, 16.03 MIDI.AND 3 3r 2 MIDLAND ACRS MEETING.

16.04 -

1A.05 MR. H. MALLFTT, CHIEF, LICENSIts SECTION, INFORMATION.

g f6.OA OFNFRAl.

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SEALED SOURCE AND DEVICE REGISTRATION".

S A.1 17

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19 s

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EllRVEILLANCE TESTING THE LICENSFE FOUND THAT

.s4 THE "C" INBOARD MSIV WOULD NOT INITIATF A

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1t.76 9

17.

R* Port-RIII 6/03/82 13.

Daily to.

Resional Action 15.

Facilitv/licenace Notification Item or Event 16.

16.01 DIVISION OF FNOINEERING 8: TFCHNICAL PROGRAMS 16.02 NR. W. IITTLE WILL PF IN HQ TO ATTEND THF INFORMATION.

16.03 MIDt.AND j Se 2 MIDLAND ACRS MEETING.

16.04 -

16.06 OFNFRAl.

MR. H. MALLFTT, CHIEF, LICENSING SECTION, INFORMATION.

j 1 A. 05 16.07 AND MS.

R..J. HOI.T ARE IN HQ TO ATTEND A TRAINING COllRSE TITI.ED "HARD COPY AND AllTOMATED 1A.09 SYSTEMS FOR THE MANAnFMENT CONTROL SYSTFM FOR 16.09 I

SA.1 SEALED SOURCE AND DEVICE REDISTRATION".

i 17.

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1411v Report-RIII 6/03/82

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19 s

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SSINS No. 6835 O

IN 82-

/j)N ' /[ NUCLEAR REGULATORY COP 94ISSION UNITED STATES If/#

k#

WASHINGTON, D. C. 20555 i

July, 1982 IE INFORMATION NOTICE NO. 82-FAILURE OF THREE CHECK VALVES ON HIGH PRESSURE INJECTION LINES TO PASS FLOW Addressee:

~

All operating pressurized water reactors (PWRs) with an operating license or construction permit.

1 l

Purpose:

This information notice is provided as notification of an event that may t

have safety significa'nce.

It is expected that recipients will review the information for applicability to their facilities. No specific action or l

response is required.

t i

Description o_f Circumstances:

At Davis Besse Unit 1 on June 4, 1982, during refilling of the reactor coolant system (RCS) through the nonnal makeup path following a refueling and maintenance outage, it was found that stop check valve HP-57 failed to pass flow. Normal makeup at Davis Besse is via one of the four 21" high pressure injection (HPI) lines.

Each HPI line has a stop check valve and swing check j

valve in series (see enclosure "A" for system diagram).

L The valves are manufactured by Velan.

Similar valves may be used on other B & W plants (an exact listing of affected plants is not yet available).

According to the manufacturer, all Velan 21 stop check valves are of the same basic design. The internals consist of a disc lightly spring loaded against the valve seat, which opens to allow flow for pressure sufficient to overcome spring tension. A valve stem, which is not connected to the disc, can be turned down on the disc to block it against the seat.

In this mode, the valve provides an isolating function in addition to preventing backflow (see enclosure "B" for valve internals diagram). A handwheel is attached to the stem (not pictured) and can be used to close the valve.

The causes for valve failure are thought to be a combination of over torqueing by operators and a steep valve seat angle. Wear may have also been a contributing factor, howecer, no obvious signs of wear have been detected by 4

visual inspection.

For reasons which are as yet unclear, the operators used the stop check valves to isolate the HPI system from the RCS. Nonnally the motor operated valves (MOVs) located outside containment are used for HPI isolation.

Investigation of this event revealed that before the event, due to the fact that the stem packing of the valves was so tight, the operators used a li foot valve wrench to close the valves rather than the handwheel. The maximum 4

recomended closing torque for the valves is 150 ft-lbs. With the valve I

1__.______,_.___

.h

IN 82-July, 1982 Page 2 of wrench, the operator could have torqued the valve to 400 ft-lbs. This forced the disc into the seat and caused the valves to bind.

Special testing was conducted to determine the status of the four HP.I stop I

check valves.

This testing yielded the following results:

1.

Valve HP-57 required 580 PSID to open. Since the valve is in the normal makeup path, however, its operability was not in question before the outage.

2.

Valve HP-48 required 180 PSID to open.

Its operability'is uncertain since the last pass flow surveillance tests were conducted on the valves on September 17, 1980.

3.

Valve HP-56 did not pass flow with up to 120 PSID pressure.

Its operability since the last surveiilance test is also in question.

The valve,t the closed valve and determine the failure mechanismw to inspec No damage to the seat, disc, or valve body was detected upon visual inspection of, internals..

4.

Valve HP-49 opened with less than 5 PSID as designed, thus, it was determined to be functional. prior to the refueling outage.

5.

Valves HP-57, HP-56 and HP-48 had seat angles of 15* while valve HP-49 had a seat angle of 25*.

This is because HP-49 was a later replacement valve and the manufacturer changed seat angle i

specifications after three original valves were installed.

6.

All valves were_ tested by applying torque to the stems of up to 150 ft-lbs. and observing the differential pressure required to open them after the stem was raised. Only valve HP-56 continued to bind, i

even with as low as 25 ft-lbs applied to the stem. According to i

these tests, it has been calculated that RCS system back pressure while in the operating mode, would have caused HP-56 to bind.

1 Thus, in addition to over torqueing the valves, the seat angle of 15* could have contributed to the valves' binding. The licensee has replaced the plugs and relaped the seats for the affected valves to help prevent binding. Greater torque being unnecessary, the val e manufacturer recommends that no more than v

150 ft-lbs of torque be used to close the valve.

e i

IN 82-July,1982 Page 3 of If you have any questions regarding this Information Notice, please call your appropriate Regional Administrator or this office.

Edward L. Jordan, Director.

Division of Engineering and Quality Assurance Office of Inspection and Enforcement Technical

Contact:

Geor e Lanik, IE (301 49-29636 R. Andrew Holland, IE (301) 49-24512

Enclosure:

1.

Valve Internsis Diagram 2.

HPI System Diagram t'

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