ML17296B044

Final Deficiency Rept Re Borg-Warner motor-operated Gate Valve Failure to Close Under Operating Conditions.Caused by Inadequate Guiding of Valve Gate.Valves Will Be Reworked by 810101.Unit 3 Valve Design Change Planned

ML17296B044
Person / Time
Site:	Palo Verde
Issue date:	10/31/1980
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
10CFR-050.55E, 10CFR-50.55E, ANPP-16653-BSK, NUDOCS 8011120373
Download: ML17296B044 (20)

Text

REGULATOR INFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION NBR e 8011120373 DOC ~ DATE P'0/10/31 NOTARIZED ~ NO FACIL:STN 50 528 Palo Verde Nuclear Stat{onr Unit lr Ar izona Publ ) 0 STN 50-529 Palo Verde Nuclear Stationg Unit 2~ Arizona'ubli 05000529 AUTH ~ NAME AUTHOR AFFILIATION 'lp VAN BRUNT<K,K, Ar i zona Public Ser vice Co. e~l RECIP,NAME RECIPIENT AFFILIATION

~ ST Region Sg San Francisco~

'PKNCEREG Reactor Construction L E'ngineer

SUBJECT:

Final deficiency rept re Borg-lerner motor>>operated gate valve failure to close under operating conditions, Caused by inadequate guiding of valve gate. Valves will be reworked by 810101 Unit 3 valve design change planned,

~

OISTRI SOT I ON COOS: SO I VS COPIES RECEIVES:I TR Deficiency ENCI. Q SIZE:

T I TLK: Construction Repo t (10CFR50.

r 55K~)

NOTES:Standardized Plant. 05000528'5000529 Standardized Plant ~

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LtTTR ENCL ID CODE/NAME LTTR KNCLT, ACTION; A/D LICENSNG 00 1 1 MIRAGLIAgF,. 05 '1 1 LEEgJ ~ 06 KERRIGANg J, 07 1 1 INTERNAL: AD/RC I/IK 17 1 1 AEOD 18 1 ASLBP/J ~ HARD 1 D/DIR HUM FAC15 1 KDO 8 STAFF 19 1 1 EQUIP QUAL. BR i 1 1 HYD/GKO BR 22 1 1 IHK 09 1 LIC QUAL BR 12 1 1 MPA 20 1 NRC PDR 02 1 OELD 21 1 1 RKV 13 1 1 QA BR 14 1 1 R G 01 1 1 RUTHERFORDT'JOIE 1 1 STANDRDS DEV ?1 1 1 NSIC'6 EXTERNAL; ACRS 08 16 16 1

LPDR 1 1 gpss 18 $ 80 TOTAL NUMBER OF COPIES REQUIRED: LTTR 39 ENCL 39

4 4

• II l

I I

a e Q m ~OZarmxm P. O BOX 2I666 PHOENIX'RIZONA 65036 October 31, 1980 ANPP-16653-BSK/JAR U. S. Nuclear Regulatory Commission P1 Region V CA Walnut Creek Plaza Suite 202 ~Z rOPl 1990 North California Boulevard n>~-" C-Q Ill Walnut Creek, California 94596 Vct~

Attention: Mr. G. S. Spencer, Chief gMO Reactor Construction and C7 Engineering Support Branch 'e CA

Subject:

A 50.55(e) Reportable Condition Relating to Borg-Warner Motor Operated Gate Valve Failure to Close Under Operating Conditions Final Report File: 80-019-026

Reference:

Telephone Conversation between J. Eckhardt and B. S. Kaplan on October 1, 1980 (DER 80-30)

Dear Sir:

Attached, is our final written report of the reportable deficiency, under 10CFR50.55(e), referenced above.

Very truly your Z C.4~I~

E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects ANPP Project Director EEVBJr/BSK:skc Attachment

o j

%= 9 C~

f

,)

R li=+

<~ W C- CP fQ

h ~

U. S. Nuclear Regulatory Commission Attention: Mr. G. S. Spencer, Chief ANPP-16653-BSK/JAR October 31, 1980 Page 2 Victor-Stello; Jr., Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Washington, D. C. 20555 A. C. Gehr Snell 6 Wilmer R. L. Robb D. B. Fasnacht W. E. Ide A. C. Rogers J. M. Allen J.. A. Brand W. H. Wilson W. G. Bingham W. J. Stubblefield J. E. Bashore R. W. Welcher.

D. R. Hawkinson

'I l

,(

I

FINAL REPORT REPORTABLE DEFICIENCY 50.55(e)

ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNITS 81 and //2 I. Descri tion of Deficienc During testing at Duke Power, a Borg-Warner 3", 1500//,

motor operated gate valve failed to completely close when actuated under operating conditions of 2,485 psig at 650 F with a flow rate of 220,000 pounds per hour of steam.

Extensive testing by Duke Power in conjunction with Borg-Warner, Nuclear Valve Division, determined the potential failure to be inadequate guiding of the valve gate.

Borg-Warner has filed a 10CFR Part 21 Notification Report with the NRC. Reference attached letter V-CE-10009, dated March 14, 1980.

II. Anal sis of Safet Im lications This condition is considered reportable based on the following considerations:

~ If not detected and corrected, the valves could possibly malfunction as indicated above.

~ The supplier has determined that modification is required and is taking the necessary actions to facilitate rework of the valves.

III. Corrective Action The valves delivered to the jobsite will be reworked by Borg-Warner in cooperation with Combustion Engineering and Bechtel construction forces. The rework is forecast to be completed by January 1, 1981. Reference attached letter V-CE-11058, dated September be documented on Bechtel,NCR P-A-1643.

ll, 1980. Rework will The Bechtel Tag Numbers are 1-J-SIA-HV604, 2-J-SIA-HV604, 1-J-SIB-HV609, and 2-J-SIB-HV609. Unit 3 valves will have the design change incorporated prior to shipment.

~ t"

~ l l

I I

I/

C-E Power Systems Tel. 203/688-191 1 Combustion engineering. Inc. Telex 99297 1000 Prospect Hill Road, Windsor. ConneclIcut 06095

,~t. ~ POWER

[.'~l.;..~ SYSTEMS March 14, 1980 V-CE-10009 Mr. E. E. Van Brunt, Jr.

Arizona Nuclear Power Project P. 0. Box 21666 Phoenix, Arizona 85036

Subject:

Val'ves, Mtotor Operated Gate, 10CFR21 Notification

Dear Mr. Van Brunt:

Enclosed is a Borg;Warner-NVD letter to C-E dated February 28, 1980, wh1ch forwarded a NVD notification letter to Region V of NRC. The NVD notification (copy enclosed) identifies a valve non-conformance which was found during a valve operability test at Duke Power. NVD has identified four (4)- valves at Palo Verde which may have a similar problem; SI-604 and SI609.

These valves are under investigation by NVD. We have requested Borg-Warner to provide us a schedule for .completion of their review. I'will advise you further when additional information is received from NVD.

I Very truly yours, ittFPr ~ lour

~ aO C. Ferguson j

Pro ect. Manager 'N] q'Bg CF/es Enclosures Rrr Rrlrs cc: 'essrs:

F. W. Hartley - w/e W. H. Wilson W. G. Bingham - w/e R. H. Holm W. L. MacDonald G. A. Butterworth IL'CI A. D. Guglietti - w/e S. N. Mager SIR R III'OIRI

~ ~

gage 1 of 4 nuclear Yalve Division

'I 8org 'LVarner Cor poraiion Tspp Tyrone Ave.. Van t4rrys. caiifoinia 91409 ~ Tefephone: 2i3 Wc'-4000

~ Q-80-'

. ].faiiing'harass: P.O. Boar 2i85. V~n Marys. Car'reran ~ ~ TÃsf fr i0 49S. i yea bruary 28, 1980 Combustion Engineering, 'Inc.

1000 Prospect Hill Road Windsor, Connecticut 06095 Attention: W. Pilipski, Engineering

Subject:

Copy of NRC Notificat'ion Letter frori NVD

Reference:

Telecon - W. Pilipski, C.E. - H.R. Wheaton, NVD 2/28/80 Dear Wa) t; Per the reference telecon, I afn enclosing a copy of NVD's Noti-fication letter to Region V of the NRC. The NRC was at NVD during the week of 2/11/80 and were given a thorough run down on the prob-lem. Their visit was a regular1y scheduled audit of our facility.

Hr. D.E. Whitesell of the Arlington Texas Office reviewed our actions to-date on this item and was satisfied that all the proper steps had been taken by NVD at this time.

If I can be of any further assistance, please do not hesitate to call.

Respectfully, BORG WrARNER CORPORATION Nuclear Valve Division)

N~~g c(

W.R. Wheaton Director, Quality Assurance HRW/jeh cc: C. Yerrrnersch, NVD Enclosure

l I

/f 1 tl I

I

~ ~.

o i(ucfo-.r Yalve Division Borg 'rgarner Cor porarion

~ ~

t rrliL, <<II III Page

~

2.of 4

~

SOP V ~

~'

~ 0 ~

'A"'. ill

~

~ iv ~

E"viprnenr 75pp Tyrcne Ave., van t$ vys. Caliiornia 914C9 ~ Te/ephone: 213 781-c000 L'.ailing Address: P.O. Bcx 2)85, Van r'vys, Cafifornia ~ RVX 910.<95-1726 g-80-041/MRW I

February 12;,1980 Robert H. Engelken, Director Region V Office of Inspection and Enforcement U.S. Nuclear Regulatory Corrmission.

1990 No. California Blvd, Suite 202 Malnut Creek, California 94596

Subject:

Notification Under Rules of 10CFR21

Reference:

Telecon Feb. 7, 1980 D. Sternberg, HRC and M. R. Wheaton, NYD-BM Dear Hr. Engelken; The attached report serves as formal written notification supple-menting the reference telecon of Feb. 7, 1980, as required by 10CFR21.

This report is filed on the basis of one known safety related applica-tion by Duke Power Company. Other customers noted in the report have been asked to evaluate their applications of similar valves and deter-mine their individual situatiqns.

If additional information is required, do not hesitate to contact the undersigned at your convenience.

Respectfully, Nuclear Valve Division BORG MARNER CORPORATION c'da~

M.R. Wheaton Director, equality Assurance.

MPM/jeh 213/781-4000 Ext 267/268 cc: C.A. Dotter, President E Gen. Hgr, NYD R.M. Fritch, Yice'resident, Engr and geA.

'l

'l

,l

( j

'l I

I t

~

Attachment to Y-PCE-1761

~ ~

~ J Page 3 of 4 Nuclear Valve Divfston Boti;-\Vafner Coi poiaiion HOTlFlCATIOH REi.opT a ~~

PROh &a'B Equipmoat M

/

'ssoo fiona ve., van wvq s. Caiifornia s i ao9 to b'.ucfcar Pogufatory Cornmtsston PART HUt',BER-

- Various N/R Ho.

PART NAME Gate Valve, 3" CUSTOMER Various HNtUFACTURER Nuclear Yalve Div. PROJECT Various Borg-Warner Corp. DATE DEFECT DISCOVERED Jan. 16, 1980 .(Approx.)

DESCRIPTIOtt OF ttOttCOhFOR'QNCE, AtQLYSIS OF CONDITION, AND CORPECTIYE ACTION (ATTACH SUPPORTIttG DATA) ..

Duke Power Co., as part of an operability test program, established a test loop at their Yarshal Steam Generating Station (non-nuclear) near Charlotte, t$ orth Carolina. Installed in that test loop was HVD P/H 74380, a 3", 1500'otor-operated gate valve. During November of 1979 NVD was notified that the subject valve had failed to completely close when actuated under operating conditions.

The operating conditions were 2485 psi 9 650'F with a flow rate of 220,000 lbs per hour of steam, which is equivalent to a velocity of approx. 40 ft/sec. Under these conditions the valve closed to about 10~ of full closure.

Extensive testing and evaluation was conducted by Duke Power Co. in conjunction with NYD to determine the exact cause of the nonconformance so that a proper corrective action could be accomplished. By approxinately, Jan. 16, 1979, it was confirred that the basic cause of the failure was inadequate guiding, of the valve gate.

Continued on Page 2 tlUANTITY AND LOCATION OF ALL SIMILAR ITEMS DELIYERED WITHIN THE U.S'.A. THAT COttTAIH THE SAME HOttCOttFOR'uANCE Refer to Page 2 Nc~~Z 6J Director, equal ity Assurance Date FORM 'HO. 400-144

V'

Page 4 of 4

."ton

';". REPORT TO U.S. NUCLEAR REGULATORY.COt'HISSION

..'3l Page 2 - Continued.

'; .vr:- ation of the gate guides was accor,",plished by NVD and the valve y Duke Power Co. verifyi'ng the adequacy of the corrective action;re-'ested:

tlVD understands that Duke Power Co. had made the HRC in their region aware of the situation and on Feb. 7, 1980, the HRC in Region V was notified by telephone by HVD of the situation. This formal notification report is, issved to complete NVD's obligation under 10CFR21 with'espect to similar valves delivered by NVD. ttVD has determined that a total of thirty-four (34) valves of similar design have been delivered. The pertinent data on those valves is listed below. The four (4) Custorr"rs involved have been notified and asked to.evaluate

'substantial if the installations of these valves at their sites safety hazard. HYD is prepared to respond in a time-represent a ly fashion to whatever action the Cvstomers deem necessary.

It should be noted that the valves involved are not all subject to .the severe

. operating environment encovntered in the Duke testing and that under less

'severe conditions of pressure,'temp. and flow could be expected to perform satisfactorily.

The valves listed below have been identified by HVD as having a potential eneric problem related to the Duke test failure described above. All four

4) Customers involved have been notified by telecon as of 2/ll/80.

(1) Customer: Ccmbvstion Engineering Site: Palo Yerde NVD P/N:= 77910 (}ty: Four (4)

C.E. Tag No's 'I604 and SI609 Val ve AP: ~90..psi Tenp: 350 F

'2) Customer: T.Y.A. Site:. Bellefonte P/N: 79190 sty: Sixteen (16)

'low:

NYD TYA Tag No: 3BW0456-KC-30 Ya1 ve b,P: 2500 psi

, Temp: 650' 100 GPH (Approx. 4.54 ft/sec) .

(3) Cvstomer: Bechtel Site: Arkansas Nuclear One-Unit2 HVD P/N: 75460 sty: Two (2)

Bechtel Tag Ho's: 3ACA-GT-lG-2CY4698-1-PL 3ACA-GT-5)-2CV4697-2-PL Yal ve 4P: 2485 psi Temp: 658' (4) Customer: Duke Power Co.

NVD P/H: 74380-1 Duke Tag Ho: 9J-239

'ty:Site:

Yalve bP:

Catawba Six (6) 2485psi 680' Temp:

Duke Power Co.

' '. Site: HcGuire HYD P/N: '74380 sty: Six (6)

'Duke Tag Ho:,9J-221 'alve bP: 2485 psi Temp: 680'. F

~l l

l i

~

~ ~

C-E Power Systems Tel. 203/688.t9t t Combustion Engineering. In~ Telex 99297 1000 Prospect Hill Road Windsor. Connecticut 06095 SYSTEMS September 11, 1980 V-CE-11058 Mr. E. E. Van Brunt, Jr.

Arizona Nuclear Power Project P. 0. Box 21666 Phoenix; Arizona 85036

Subject:

Motor Operated Gate Valves

Reference:

V-CE-10009 dated March 14, 1980

Dear Mr. Van Brunt:

The referenced letter advised of a potential problem with some Borg Warner valves. Please be advised that the valves (SI-604 and SI-609) will require site rework. This work will be done by Borg Warner at their expense. The extent of Bechtel involvement will be addressed by our Site Office once the rework procedure has been approved by C-E. We expect that this work will be completed by the end of the year.

Very truly yours, Pt-~

C. Ferguson NF5 CZZ ~

C$

Project Manager E~" 3 6'~"

CF/MFB/es

~R'ONha lr:. VpH cc: Messrs:

F. W.

W. H.

Hartley Wilson i O'AW 2 ni'=

~

S W. G. Bingham 1 R. H. Holm W. L. MacDonald Cl ~

t G. A. Butterworth I

~. jrPS S. N. Mager

.'2frc5'4)

~C ~

~~:.,~.

A7i~L Ek~ C'/r~

CC g. $ 74~/XT>~4 cc v. rypM~

~ ~

l, k I I

,