ML20195H777

Documents Completion of Tests & Evaluations Required to Meet IE Bulletin 85-003 & Provides Required Info Specified in Re motor-operated Valve Failures

ML20195H777
Person / Time
Site:	Oyster Creek
Issue date:	01/15/1988
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-85-003, IEB-85-3, NUDOCS 8812010039
Download: ML20195H777 (10)

Text

OPU Nuclear Corporation NQgIgf Post Off<e Box 388 Route 9 South Forked Rwer. New Jersey 087310388 609 971-4000 Writer's Direct Dial Number:

January 15, 1988 l

Mr. William F. Kane, Director Division of Reactor Projects Region I U.S. Nuclear Regulatory Comission 631 Park Avenue King of Prussia, PA 19406

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Bulletin 85-03, Supplemental Response On November 15, 1985, the USNRC Office of Inspection and Enforcement issued IE Bulletin 85-03, "Motor Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings." On May 15,1986, GPU Nuclear responded to the bulletin and stated, in part, that within the scope of the bulletin as written, IEB 85-03 was not appitcable to the Oyster Creek Nuclear Generating Station.

Subsequent discussions, as documented in letter dated October 28, 1986, l

Kane to Fiedler, expanded and clarified the scope of IEB 85-03 to include two systems at the Oyster Creek site.

This letter documents the completion of the tests and evaluations required to meet IEB 85-03, and provides the required information as specified in the October 28, 1986 letter.

1 i1.

o i

GPU Nurem CcreeraMn is a sut's a ary ct tre Gerer r P#c Utit es Ccrprat on i\\

it d

2 If any further information is required, please contact Mr. John Rogers of nty staff at (609)971-4893.

Very truly yours, Peter fedler Vice President and Director Oyster Creek Sworn to and Subscribed before me this /[ day of January,1988, i

1 LEw b].

bQ6 A Notary Publig of NJ 1

DIANA M. De8LASIO My Commsteen EmpireQ,M$1 NOTARY PUSOC 0F N

.)

i PBF/JR/dmd I

(0183A)

Enclosure / Attachments cc: Document Control Desk U.S. Nuclear Regulatory Commission j

Washington, DC 20555 j

Hr. Alexander W. Dronerick, Project Manager U.S. Nuclear Regulatory Cornission j

Division of Reactor Projects I/I!

i 7920 Norfolk Avenue, Phillips Bldg.

l Bethesda, MD 20014 NRC Resident Inspector Oyster Creek Nuclear Generating Station i

i I

l l

6 l

[

ENCLOSURE US.dC letter dated October 28, 1986, Kane to Fiedler, contained three (3) regt. i reme nts.

Item 1 and 2 were completed and submitted on December 23, 1986 Item 3 required:

rf November 15,1987 (sooner if practical), complete your program under 4EB 85-03 ielative to the Core Spray and Isolation Condenser systems; and provide a written report, within 60 days thereaf ter, that meets item f of IEB 85-03.

The IEB 85-03 program was completed and summarized on November 10, 1987.

Item f of IED 85-03 required:

Provide a written report on completion of the (above) program.

This report should provide (1) a verification of completion of the requested program, (2) a summary of the findings as to valve operability prior to any adjustments as a result of this bulletin, and (3) a summary of data in accordance with Table 2, Suggested Data Summary Fomat.

l The referenced program was described in IEB 85-03 as items a through d.

Item a:

1 Review and document the design basis for the operation of each val ve.

This documentation should include the maximum differential pressure expected during both opening and closing the valve for both nomal and abnoms1 events to the extent that these valve operations and events are included in the existing, approved design basis, (i.e., the design basis documented in pertinent licensee submittals such as FSAR analyses and fully-approved operating and emergency procedures, etc). When determining the maximum differential pressure, those single equipment failures and inadvertent equipment operations (such as inadvertent valve closures or openings) that are within the plant design basis should be assumed.

Response

The scope of IEB 85-03 as applicable to the Oyster Creek site has been detemined to be:

Y-14-30,33 (Iso, Cond. Inboard Isolation - steam side)

V-14-31,32 (Iso. Cond. Outboard Isolations - Steam side)

V-14-36,37 (Iso. Cond. Inboard Isolations - cond side)

Y-14-34,35 (Iso. Cond. Outboard Isolation - :ond, side)

V-20-3,4,32,33 (Core Spray Suction Isol.)

Y-20-12,18 (Core Spray Test Isol.)

V-20-15,21,40,41 (Outside Drywell Isol. )

V-2-26,27 (Core Spray Test)

Attachment I provides the design basis for the abrve listed valves.

6 GPUN has reviewed the above valves for potential water hammer problems and determined it not to be of concern. Water hamer can occur in high-speed valves with high flow rates and "long" pipe lengths downstream.

These conditions are not present to a degree which would cause the A P surges which significantly affect valve operability.

Item b:

Using the results from item a above, establish the correct switch settings.

This shall include a program to review and revise as necessary, the methods for selecting and setting all switches (i.e.,

torque, torque bypass, position limit, overload) for each valve operation (opening and closing).

Response

GPUN contracted Torrey Pines Technologies (TPT) to calculate the required thrust values for the subject valves. The Motor Operated Yalve Analysis and Test System (MOVATS) was then used to determine the correct torque switch setting needed to provide the required thru st. Additionally, MOVATS was used to establish correct torque switch bypass and other limit switch settings.

Results of this testing are summarized in Attachment II.

Also, thermal overloads for all the valves were checked and determined to be satisfactory per GPUN Engineering Standard ES-024 The conclusion from these tests is that all valves were determined to be operable and no reportable conditions existed.

Item c:

Individual valve settings shall be changed, as appropriate,

'.o those established in item b, above. Whether the valve setting is changed or not, the valve will be derronstrated to be operable by testing the valve at the maximun differential pressure determined in item a above with the exception that testing motor-operated valves under conditions simulating a break in the line containing the valve is not required.

Otherwise, justification should be provided for any cases where testing with the maximum differential pressure cannot practicably be performed.

This justification should include the alternative to maximum differential pressure testing which will be used to verify the correct settings.

Each valve shall be stroke tested, to the extent practical, to verify that the settings defined in item b above have been properly implemented even if testing with differential pressure cannot be performed.

Response

All M0 VATS testing of these valves was performed at zero differential pressure.

GPUf1 believes these tests are valid because results of Toledo Edison full pressure testing and a one-time a P test of 0.C.

valve V-20-27 support the adequacy of torque switch settings based on TPT calculations for valves in normal operating condition with properly set torque switch bypasses.

Valves are tested to verify proper working condition and additionally, all torque switch bypasses are set to cover 20-25% of stroke.

Yalve and operator basic information is shown in Attachment II.

The sumary of results for these tests is shown in Attachment !!!.

Item d:

Prepare or revise procedures to ensure that correct switch settings are determined and maintained throughout the life of the plant.

Ensure that applicable industry recornendations are considered in the preparation of these procedures.

Response

GPUf1 Procedure 700.2.010 governs maintenance, removal, installation, and set-up of limit and torque switches, and testing and analysis of M0V's.

This procedure is continually updated and revised to reflect applicat,le industry recommendations and to insure correct switch settings are set and maintained in the best possible manner.

N ATTACHMENT I

~

l IINLET l MAX.

1 I MAX.

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~

l l

IPRESS. 10PENINGl ICLOSINGl VALVE I

IPSIG l DELTA Pl IDELTA Pl TAG NO I FUNCTION i l PSI I

BASIS l PSI I

BASIS I

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I I

i l

i l

i l

i V-14-30,33l ISO Cond.

I 1250 1 1250 IThe highest RCS pressure i 1250 lThe highest RCS pressure 15teamside i

l Ibased on highest set I

lbased on highest set pres-linboarrt l

l l pressure of safety valves,1 Isure of safety valves,1239+-

liso14 tion i

1 11239+ 12 psig, i

112 psig (Ref. T.S.2.3) as 1

l l

l(ReCf.S.2.3) as inlet I

linlet pressure. HELB causes l

I I

lpressure.

I latm. pressure downstream.

l l

l I Assume closure of itSIV duel l

l 1

1 Ito a transient, causing nol i

i l

l l downstream pressure.

l l

l l

1 IValve is opened after i

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l l

l completion of IST.

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V-14-31,32l ISO Cond.

I 1250 1 1250 isaae as above i 1250 ISame as above.

Isteamside l

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lout board I

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l l

lisolation i

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I l

V-14-36,3711SO Cor.d.

I 1250 1 1250 ISame as above i 1250 ISame as above icondensate i I

I I

I linboard i

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lisolation i

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l l

l 1

1 I

I I

V-14-34,35l ISO Cond.

I 1250 1 0 IValves are normally 1 1250 IIf valves are open for ICondensate !

I l closed, and not expected I

linitiation, HELB will loutboard l

l Ito be open after a HELB l

Irequire closure.

lisolation i

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Page 1 of 3

1 IINLET I MAX.

l l MAX.

l I

iPRESS. 10PENINGl ICLOSINGl YALVE I

lPSIG IDELTA PI IDELTA PI J

TAG NO 1 FUNCTION I I PSI I

BASIS l PSI l

BASIS 1

1 I

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I I

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I V-20-3, 4,1 Core Spray I 5 l 10 JValves normally open to 1

35 lYalve is closed:

32,33 ISuction I

I Itorus which is at atmos-I i

1) During normal OPS as IIsolation lpheric pressure during l

l part of surveillance l Valves

]

l loperation. Yalve is cycledl i 2) As a result of a leak l

l lonly during surveillance !

I in the C.S. Piping 1

I I

ltesting. Max pressure 1

l 3) #2 concurrent with a l

l I

lis static head during l

l blowdown (Pmax=30 psia) l I

i lsurveillance.(This assumes!

ICase (3) is the max pressure l

l lthat a DBA does not l

l case. Closing 4P is based I

l l

loccur concurrently with I

lon (3)

I i

i Isurveillance testing.)

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V-20-12.181 Core Spray 1 350 1 350 IValves Normally open i 350 IYalve is closed:

1 Test l

l Iduring operation, cycled I i

1)During Surveillance IIsolation l

I lduring monthly testing.

l l

Testing IValves 1

I l Max. differential is pump i 1 2)If containment ISO 1

l l

lshut off head l

l valves leak back, the l

l l

l l

l test ISO valves can be l

l l

l l

1 closed.

l l

l l

l lWhile a leak of the I

l l

I lisolation valves would I

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Iresult in reactor pressure l

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l 1

lin the CS piping, the i

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l i

Ipressure rise would be i

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111mited by the relief valves l

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Iwhich are set at 350 psig.

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7164d Page 2 o f 3

m I

IINLET l MAX.

I I MAX.

l l

l PRESS.,10PENINC, ICLOSINGl VALVE I

lPSIG l DELTA PI IDELTA Pl TAG N0 l FUNCTION l l PSI I

BASIS I PSI I

BASIS I

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I V-20-15.2110utside DW I 350 1 350 IYalves are interlocked to i 1250 lRCS Destgn Pressure 40,41 IIsolation l

l lopen at pRCSl285. Pumps l

l IValves l

l lwill be operating on min. !

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Irecirc 0 close to shutoff l l

i i

i lhead (350 psig) when I

I I

I Ivalves go open.

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V-20-26,271 Core Spray l l 350 IValves are cycled during l 350 IValves nonna11y closed ITest Valves i I

lmonthly pump tests. Max l Iduring plant operation.

If I

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l pressure will be pump i

lopen during an event, the i

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lshutoff head (350 psig).

I Ivalves will go closed i

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lagainst max. pump head (350 1

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Ipsig).

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Page 3 of 3

J ATTACHMENT 2 j

VALVE AND OPERATOR IkFORMATION 1

Valve Oper.

Tag No.

Manufacturer Size Type Dwg. No.

Model No.

Pressure Rating j

j V 3 0 Anchor Darling 10" Gate AU-2085 58D-2-40 600 V 31 Anchor Dar11ag 10" Gate AU-2085 58D-2-40 600 i

V-14-32 Anchor Darling 10" Gate AU-2085 58D-2-40 600 V-14-33 Anchor Darling 10*

Gate AU-2085 58D-20-60 600 V-14-34 Crane 10*

Gate H-29529 58D-2 50 600 V-14-35 Anchor Darling 10*

Gate AU-2085 58D-2-60 600 Y-14-36 Anchor Darling 10" Gate AU-2085 SBD-2-40 600 V-14-37 Anchor Darling 10" Gate AU-2085 58D-2-40 600 V-20-3 Anchor Daritng 12" Gate AU-2075 SMB-00-10 150 V 4 Anchor Darling 12*

Gate AU-2075 SMB-00-10 150 Y-20-12 Anchor Darling 8"

Gate AU-2077 SMB-00-10 600 I

V-20-15 Anchor Darling 8*

Gate AU-2079 SMB-1-25 600 V -2 0 -18 Anchor Darling 8"

Gate AU-2077 SMB-1-25 600 j

V-20-21 Anchor Darling 8"

Gate AU-2079 SMB-1-10 600

)

Y-20-26 Anchor Darling 6*

Globe AU-2131 SMB-00-15 300 Y-20-27 Anchor Dar11ag 6"

Globe AU-2131 SMB-00-15 300 V-20-32 Anchor Darifag 12" Globe AU-2065 SMB-00-10 150 V-20-33 Anchor Dar11ag 12" Globe AU-2065 5M8-00-10 150 V-20-40 Anchor Darling 8*

Gate AU-2079 SMB-1-10 600 V-20-41 Anchor Darling 8*

Gate AU-2079 SMB-1-10 600

• All operators manufactered by Lleitorque Corporation.

ATTCCCMEOT 3 TEST DATA T

A5.FOUND AS-LEFT

~~

Open "lose Open Close Open 1987 Open

)

Torque Torque Open Torque Torque Torque Torque Torque I

SW Setpt.

SW Setpt.

5. Bypass

5. Bypass4 Tag No.

$W 5etpt.

5W 5etpt.

5. Bypass i

V-14-30 2.75 2.75 11.11 2.0 2.25 11.15 26.4%

]

V-14-31 3.0 3.0 121 1.75 1.75 121 19.01 V-14-32 2.75 2.75 7.9%

3.25 3.25 7.91 27.31

]

Y-14-33 1.5 1.5 12.6%

3.25 3.25 12.6%

23.01 j

V-14-34 2.0 1.0 12.71 2.0 1.5 12.7%

25.1%

V-14-35 1.0 1.0 10.21 1.75 1.75 10.2%

24.6%

V-14-36 3.25 2.75 11.81 3.25 3.25 11.81 17.3%

Y-14 -3 7 2.75 2.75 14.6%

3.0 2.75 14.6%

23.11 V-20-3 3.0 3.0 13.21 1.5 2.0 13.2%

20.0%

V-20-4 3.0 3.0 11.71 1.0 1.0 11.7%

20.8%

V-20-12 1.0 1.0 16.11 1.0 1.0 16.1%

22.131 V-20-15 2.0 2.0 11.81 1.5 1.5 11.81 16.6%

V-20-18 1.0 1.0 N/A3 1.0 1.0 N/A3 21.3%

l V-20-21 1.0 1.0 14.7%

1.5 1.5 14.71 23.51 V-20-26 1.0 1.5 10.5%

1.0 1.0 10.55 27.5%

Y-20-27 1.0 1.25 11.6%

2.0 2.0 11.6%

23.1%

V-20-32 2.5 2.5 11.81 1.0 1.0 11.81 20.8%

V-20-33 2.0 2.0 13.11 1.0 1.0 13.1%

20.7%

V-20-40 1.5 1.5 8.91 1.5 1.5 8.91 16.5%

V-20-41 2.0 2.0 10.91 1.5 1.5 10.91 23.621 Test Dates:

08/29/84 09/02/84 07/26/84 7/I7/84 and 7/20/842, NGTES:

1.

At the time of these first tests (1984), this torque switch bypass 1 was considered acceptable. Presently. GPUN sets t.s. bypass between 20-251.

2.

Note that tests were performed prior to issuance of 85-03 bulletin. Follow-up testing has been performed on most of these valves since then, which GPUN believes further insures their safety reliability.

)

3.

Open bypass time was not available due to a test-equipment problems during initial testing.

However, based on the Closing bypass ($ 21) the opening bypass was probably normal too, and therefore sufficient. Additionally, as-found thrust at torque switch trip (7586 lb) was adequate to open against TPT calculated required opening thrust under worst conditions (3912.5 lbs).

l 4.

post Davis-Besse As-Left Values.

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