Text

Interim Deficiency Rept DER 83-49 Re Broken/Loose Diffuser Bolts in Reactor Coolant Pump.Initially Reported on 830715. Due to Extensive Investigation & Evaluation,Final Rept Will Be Submitted by 831129.Related Info Encl
	ML20090L339
Person / Time
Site:	Palo Verde
Issue date:	08/19/1983
From:	Van Brunt E; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Sternberg D; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20090L275	List: ML20090L288; ML20090L302; ML20090L339;
References
	FOIA-84-212 ANPP-27593-RQT, ANPP-27593-TQT, DER-83-49, NUDOCS 8405250289
	Download: ML20090L339 (7)
	v • d • e

... .

gg 1 o .

i RCa'rn j:: c ~

Arizona Public Service Company P.o. sox 21666

PHOENIX, ARIZONA 85036 ,l *] p r

^

August 19, 1983 E9' ANPP-27593-RQT/BSK HT::c,: .

U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projects Branch 1

Subject:

Interim Report - DER 83-49 A 50.55(e) Potentially Reportable Deficiency Relating to Diffuser Bolts Broken / Loose In Reactor Coolant Pump File: 83-019-026 D.4.33.2 References Telephone Conversation between P. Narbut and R. Tucker on July 15, 1983

Dear Sir:

The NRC was notified of a Potentially Reportable Deficiency in the referenced telephone conversation. At that time, it was estimated that a determination of reportability would be made within thirty (30) days.

Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by November 29, 1983, at which time a complete report will be submitted.

Very truly yours,

\

. CA AA. O P E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects Management ANPP Project Director EEVBJr/RQT ske Attachment cc: See Attached Page 2 8405250289 840423 PDR FO!A BERNA 8E84-212 PDR

.th ], $

U. S. Nuclear Regulatory Commission

. Attention: Mr. D. M. Sternberg, Chief ANPP-27593-RQT/BSK August 19, 1983 Page 2 cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.

G. C. Andognini J. A. Roedel D. B. Fasnacht A. C. Rogers B. S. Kaplan .

W. E. Ide J. Vorees J. R. Bynum

. P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen

, C. A. Fiore111 Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 J. G. Self S. R. Frost M

^ ... *

' INTERIM REPORT - DER 83-49 POTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNIT #1 I. Potential Problem Post inspection of Unit #1 Reactor Coolant Pump, Tag Number IMRCEP01A, revealed the following damage occurred during hot functional testing:

A.

Fifty percent (50%) of all diffuser bolts were loose.

B.

Three (3) diffuser bolts were broken and the pieces are missing.

C.

The diffuser and suction pipe areas were damaged.

II.

Approach To and Status Of Proposed Resolution Bechtel Engineering is corresponding with CE to provide

(-, reportability disposition and technical justification for corrective action.

III.

Projected Completion of Corrective Action and Submittal of the Final Report Evaluation of this condition and submittal of the Final Report is forecast to be completed by November 29, 1983.

p w.-

DAILY REPORT O EGION V ,

- .DATE Facility Notification Item or Event Regional Ahtion .

~

'b . b.,3 < ba,-;l& -lest h , , ,, W. t c. e 1 a ~B wa a ;m 4,l..,e19 4 Jose.i% iaL Lo m ulb)Hs

' k g og. q(,I wha h nou.d '((c. niloellor

}l

~ '

-to L oke. . nue c aa j ( C; tu.c , . v d it i m e,

! cd -flo -lk albg k evccJdue foice ' is i

SCAS pp r/ kC d ,

! l% L'ce n see_ w'ill pr ov e ,x

(

%J s s' *e (Qfor' t' Y}O .

i

, [ "((e

~

t ( e re ', orG tC 08 F ' ruk

~

be w p; nbb l -lo RV FORM 102 i

~, . . _ ~

8 . ....-

DAILY REPORT 8tEGION V .A* .

- DATE Facility Notification Item or Event Regional Action .

Q . .i. Ic L (b. er,il .

~M4 g (;r, ( Ca,d,..di<,. l .,.{m.ecIn o.:.. pg(

, s.,. -

P p ,.,_

t ' < c ~- t c 't b. becace ,l%< t s Mc 2Sig, -

h'*" F;'

'll15f63 A, h,m-ty G{c. x@, r.p Ih .

Dp 50-523 -

52%

D3D 5.]Pc h *') C" PsC '"5

-fc;[eJ , f.~ve ( is deen cJiled ,

h 6 ) p'iccc.e eb % bli

-,ss;, . n aque ard

% suc h p.p are cln~ege<l.

ll , p, r. p w as 66q ekn e.s.c,ololeci for py $3_g l .a a a_ _ '

ch y c. <; i. usco eI *t-ic cv e red.

~ hode bdL M+ 0 b bM I O*

.- b s u h d o c p, e v,av

$ a e241

- -A C no/k a b>k n ')lb b0 50*c S (c[. led in f(.c CE.- K66 'lesi

~

Gmp. 11 8 = gui<ecl woJ <hecd6s , ..

6d bee n dc. ul TAto w Je .

Q 1e p o,'!c* b M., ca pede d # ct l .- e (.?ses;

,de m 6/3/g3 .

r RV FORM 102

p ,m

). MN /. .

--* s j

MORNING REPORT - REGION Y DATE: 08/02/83 FACILITY NOTIFICATION TEM OR EVENT REGIONAL ACTION Arizona Public Telephone call POTENTIAL CONSTRUCTION DEFICIENCIES: Followup per MC 2512 Service Co. from licensee Palo Verde 8/1/83 . Unit 1 Turbine Driven Auxiliary Feed P 3 1,2,3 The nump shaft vibrates badly at 135 gpm minimum flow DN's 50-528 operation) causing the suction piping to vibrate severely.

50-529, 50-530 Additionally, the pump does not develop 1420 psig at a flow of 875 ppm as required by the hot functional test -

requirements. (DER 83-51)

. The Unit 1125 volt vital DC power bus distribution panel exoeriences 70 volt AC spikes at a 0.0007 second frequency. Discovered during testing. (DER 83-52)

. Unit 3 containment embedment plates failed to meet specification requirements. Two plates were discovered without anchor bolts installed. Nine plates, accepted by inspection, did not meet minimum thread engagement requirements for the anchor bolts. Approximately 300 other plates, not yet final accepted, also lacked anchor bolt thread engagement. (DER 83-53)

. Inspection of the Uni I steam generator primary sides revealed debris. SG2 ' !11 washers and one threaded '

plug. SG1,hagnewasher. (DER 83-54)

. The Unit I thermal sleeve for line SI-A207-DCCA-14 was visually detemined to be missing and is expected to be found in the reactor vessel. (DER 83-55)

. During the conduct of hot functional testing in Unit 1, the licensee declares that continual operational difficulties were experienced with the MSIV's by Anchor E Darling Comoany. Repeated failures required rework and L retest. (DER 83-56)

T The licensee will submit a written report in 30 days if the t above six items are detemined to be reportable.

N

w N

DEA DAILY REPORT ^ REGION V A -

DATE Facility Notification Item or Event Regional Action a,pks yn -se -

, twsu susrc> : ,ng 5%nw/*

44 .xc Mc = m awesu ,y,,

Dn. fo42E W Q egg QJ pm -

"- /%

_e-j' " =

O m,

~cm m

t Q-

" W.

c-e u -" ,. m

~ a

,7 a7".wq Me

&y 39Hm m W- u w -

pc g RV FORM 102

. o <..

- qq

.qk..,

i h 1 Arizona Public Service Company ejy Po. sox 21666 e PHOENIX. ARIZONA 65036 0

'I c/ ,

August 22, 1983 '

'//

ANPP-27604-BSK/RQT . /gg'D*/ /

U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projects Branch 1

Subject:

Interim Report TDER 83-55 A 50.55(e) Potentially Reportable Deficiency Relating to Thermal Liner In Safety Injection System Line Is Missing.

File: 83-019-026; D.4.33.2

Reference:

Telephone Conversation between P. Narbut and R. Tucker on August 1,1983.

Dear Sir:

The NRC was notified of a potentially reportable deficiency in the referenced telephone conversation. At that time, it was estimated that a determination of reportability would be made within thirty (30) days.

Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by November 9,1983, at which time a complete report will be submitted.

Very truly yours,

. . 4A- gfg_

E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects Management ANPP Project Director EEV8Jr./RQT:en Attachment cc: See Attached Page Two

(

h o'Wces u ~

A #9

. s t .

e

's U. S. Nuclear Regulatory Commission .

l Page Two cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.

G. C. Andognini J. A. Roedel D. B. Fasnacht A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees J. R. Bynum -

. P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant

( D. R. Hawkinson L. E. Vorderbrueggen

,G. A. Fiore111 S. R. Frost J. Self Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 6

s. <n * -

I ~ INTERIM REPORT - DER 83 ,

POIENTIAL REPORTABLE DEFICIENCY

- - l ARIZONA PUBLIC SERVICE C,0MPANY (APS)

PVNGS UNIT 1 I. P.otential Problem During visual inspection of piping, af ter disassembly of Unit 1 pump tag no.1-RCE-P01A, it was revealed that the thermal liner for line number SI-A207-BCCA-14 was missing. Preliminary determination is that the liner broke loose during hot function testing and was flushed into the Reactor Vessel.

II. Approach Tp and. Status Of _ Proposed _ Resolution

. Bechtel engineering is corresponding with C-E to provide reportability disposition and technical justification for corrective action.

III. Project.ed . Completion Of Corrective Action _and Submittel _of _The _ Final Report Evaluation of this condition and submittal of the Final Report is

- forecast to be completed by November 9, 1983.

9 6

o G

O 1

9 a

4 m , ,, - - , - - . . aw-n-- ----------w,, --r-.-+-g- - . - - - - , . - .,w--, -

e--- ,ew,-w--n-,--s-w- - -a-.,,nn-w.a w . --- - - - - - - -,,.e, - - - - - , w

i ,

'k$?o

f. ,

Arizona Public Service Company /?SJg P.o. box 21666 + PHOENIX, ARI2oNA 85036

/ ,

August 22, 1983 D&,(.. .

ANPP-27603-BSK/RQT "U/

U. S. Nuclear Regulatory Conunission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projects Branch 1

Subject:

Interim Report - DER 83-54 A 50.55(e) Potentially Reportable Deficiency Relating to Washers Found In Unit 1 Steam Generator #1 And #2

.. File: 83-019-026; D.4.33.2

Reference:

Telephone Conversation between P. Narbut and R. Tucker on August 2, 1983 .

Dear Sir:

The NRC was notified of a potentially reportable deficiency in the referenced telephone conversation. At that time, it was estimated that a determination of reportability would be made within thirty (30) days.

Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by October 13, 1983, at which time a complete report will be submitted.

Very truly yours,

b. b. O. YL Q

E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects Management ANPP Project Director EEVBJr./RQT:sn Attachment cc: See Attached Page Two Oo ogg 44 y

a 4 U. S. Nuclear Regulatory Commissica Page Two cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washingtonr D. C. 20555 T. G. Woods, Jr.

G. C. Andognini J. A. Roedel',

D. B. Fasnacht A. C. Rogers B. S. Kaplan W.'E. Ide s J. Vorees J. R. Bynum .

s

, P. P. Klute/D. D. Green '

A. C. Gehr W. J. Stubblefield W. G. Bingham -

R. L. Patterson R. W. Welcher R. M. Grant

(- D. R. Hawkinson L. E. Vorderbrue'ggen G.'A. Fiore111 S. R. Frost J. Self Records Center

. Institute of Nuclear Power Cperations

'1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 N

h I

(

\

\' .,

.__m__________ _ . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ . . _ _ . . _ .

r

. s' '

o i ~ IrrERIM REPORT - DER 83-54 POTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNIT I

1. Potenti_al Problem During initial inspection of Steam Generator #2, eleven (11) bevel washers and one plus were found inside the Steam Generator on the side next to the Reactor Vessel. One (1) washer was found in Steam Generator #1.

II. Aparoach .To and Status of P.ropose.d _Resq14 tion Bechtel engineering is corresponding with C-E to provide reportability disposition and technical justification for corrective action.

, III. Prolected Completion Of Cor_rtetive . Action and _Sybmittal of .The _F.inal Report Evaluation of this condition and submittal of the Final Report is forecast to be completed by October 13, 1983.

(

0 i

e g

4 ete:n.

,,,, :. , 'f. 7

, . , e.

, Arizona Public P o. 80X 21666 Service

PHOENIX. ARIZONA Company 85036 /503

D g ,, (()

b*

nj i: r.,

August 1,198SE7/Q,.,,

- , ANPP-27471-BSK/RQT * #

' U. S. Nuclear Regulatory C:snission Region V -

Creekside Oaks Office Park

,1450 Maria Lane - Suite 210 Walnut Creek, :CA 94596-5368 Attention: Mr.'D. M. Sternberg, Chief Reactor Projects Branch 1

Subject:

Interim Report , DER 83-39 A 50.55(e) Potentially Reportable Deficiency Relating to Rejectable Indications on CE Supplied linit 1 Reactor Coolant Pump 1A.

File: 83-019-026; D.4.33.2

Reference:

. Telephone Conversation between A. D'Angelo and R. Tucher on jplaty~ 1,1983. ~ *

Dear Sir:

The NRC was notified of a potentially reportable deficiency in th'e~

referenced telephone conversation. At that time, it was estimated that a determination of reportability would bc made within thirty (30) days.

Duc. to tihe extensive investigation and evaluation required, an Interim Report is ::ttached. It is now exppeted that-this information vill be finalized by October 27, 1963, at which time a complete report will be

. submitted.

Very truly yours, Cc. . T, no na

,E. E. Van Brunt, Jr.

APS V*ce President, Nuclear Projects Management ANPP, Project Director l EEV3Jr./RQT:rb -

l Enclosure l

cc: See Page Two.

o .,

' >o 8'1'2'crffg-

_ 2 . __ . . _ _ . . - Nfd__

E . . .._.... . . . . -. 1

- r ,

e U. S. Nuclear Regulatory Commission Page Two ec: Richard DeYoung, Director Office of Inspection and Enforcement

- U. S. Nucl. ear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.

G. C. Andognini J. A. Roe ~ del D. B. Fasnacht A. C. Rogers B. S. Kaplan~

W. E. Ide J. Vorees .

J. R. Bynum P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen

')

G. A. Fiorelli S. R. Frost J. Self Records Center Institute of Nuclear Power Operations .

1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 8/1/83 m

. -,n.-- , - ---- -r--,. , - , , , , . ,_, ,., -- .- ,,. p. ,,n ,,m- - -,--,e p, - - -., -y- y e , , - - -rn--

~

( ,f ',- .

INTERIM REPORT - D'ER 83-39 POTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC' SERVICE COMPANY (APS)

PVNGS UNIT 1

'I. POTENTIAL PROBLEM On a recent re-examination and comparison between the Preservice Examination Ultrasonic (UT) data and the construction Radiographs (RT) for the Combustion Engineering (C-E) furnished Reactor Coolant

~

Pump 1A/IMRCEPOIA, two linear indications were found. The indications exist in the circumferential weld of the pump casing.

One of the RT indications found measures 3 inches long; the second measures 3/4 inches long. Both exist within a length of 6 inches.

Subsequent examinations have shown that these indications are approximately 3.2 inches in from the outside diameter of the casing with no perceptible through wall dimension. The base metal of the casing in this area is 5-5/8 inches thick. The linear indications are acceptable to the ASME Section III UT acceptance criteria but do not meet the ASME Section III RT acceptance criteria. A Fracture Mechanics Analysis has been performed by C-E on the casing using e' conservative parameters. The analysis assumed: (1) the indications have a through wall dimension of 3/4 inches; and (2) the indication

(' is a sharp crack extending around the entire circumference of the casing.

II. APPROACH TO AND STATUS OF PROPOSED RESOLUTION Bechtel is continuing to correspond with CE on this matter to determine reportability.

III. PROJECTED COMPLETION OF CORRECTIVE ACTION AND SUBMITTAL OF THE FINAL REPORT Evaluation of this condition and submittal of the Final Report is Jforecast to be completed by October 27, 1983.

(.

1 Arizona Public Service Company % /C5 ,

PO. Box 21666

PHOENIX, ARIZONA 85036 hf ,

July 25, 1983 ;' . -

ANPP-27398-BSK/RQT U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projects Branch 1

Subject:

Interim Report - DER 83-42 A 50.55(e) Potentially Reportable Deficiency Relating to Thermowells in Reactor Coolant System

. File: 83-019-026; D.4.33.2

Reference:

Telephone Conversation between P. Johnson and J. Roedel on June 29, 1983

Dear Sir:

( The NRC was notified of a potentially reportable deficiency in the referenced telephone conversation. At that time, it was estimated that a determination of reportability would be made within thirty (30) days.

Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by September 21, 1983, at which time a complete report will be submitted. .

Very truly yours,

{

- Cl.,LL A I E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects Management ANPP Project Director EEVBJr./RQT:rb Enclosure cc: See Page Two D

I hb

U. S. Nuclear Regulatory Commission Page Two cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.

G. C. Andognini J. A. Roedel D. B. Fasnacht A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees J. R. Bynum P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen -

G. A. Fiorelli S. R. Frost J. Self Records Center Institute of Nuclear Power Operations ,

1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 9

3r

k,.,'

)

INTERIM REPORT - DER 83-42 POTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE CONTANY (APS)

PVNGS UNIT 1

1. Potential Problem During hot functional testing, it was discovered that thermowells 01JRCA-TW-122CA and 01JRCC-TW-112CC were not maintaining the pressure boundary in the Reactor Coolant System and were emitting steam through their respective temperature elements, tag numbers 01JRCA-TE-122CA and 01JRCC-TE-112CC. Preliminary investigation reveals penetration cracks on the thermowells internal wall surface. Some damage to temperature elements was also observed.

II. Approach To and Status of Proposed Resolution Bechtel engineering is corresponding with C-E to provide reportability disposition and technical justification for corrective action.

III. Projected Completion of Corrective Action and Submittal of the Final Report

( Evaluation of this condition and submittal of the Final Report is

.fo~ recast to be completed by September 21, 1983.

(

h l

.1::ct:,,,

7.f',nD

, , l Arizona Public Service Company j

.(- P.o. BOX 21666

PHOENIX, ARIZONA 85036 /[,}^ ,

17! 1: 12 July 25,1983 g;.fg* ,.

ANPP-27396-BSK/RQT -

U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. D. M. Sternberg, Chie f l Reactor Projects Branch 1

Subject:

Interim Report - DER 83-40 A 50.55(e) Potentially Reportable Deficiency Relating to LPSI And CS Pump Motors Leaking Oil And Have Defective Wells File: 83-019-026 D.4.33.2

Reference:

Telephone Conversation between A. D'Angelo and R. Tucker on June 29, 1983

Dear Sir:

The NRC was notified of a potentially reportable deficiency in the referenced telephone conversation.. At that time, it was estimated that a determination of reportability would be made within thirty (30) days.

Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be l finalized by October 6, 1983, at which time a complete report will be

( aubmitted.

Very truly yo rs,

. CU'.A Gd E. E. Van Brunt, Jr.

APS Vice President, l Nuclear Projects Management ANPP Project Director l

l EEVBJr./RQT:rb i Enclosure cc: See Page Two hou-563'r 4 y4

}

~

4' *.

l l

t l U. S. Nuclear Regulatory Countssion .}

Page Two */ i I

cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Connaission Washington, D. C. 20555 T. G. Woods, Jr.

G. C. Andognini J. A. Roedel D. B. Fasnacht A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees .

J. R. Bynum P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson '

R. W. Welcher R. M. Grant .}I D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiorelli S. R. Frost J. Self Records Center Institute of Nuclear Power Operations '

1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 D.

)

, ._ -. , . - .,,,.____,_-,_..y-_,___-. --,_, --,. _._,_, _,,.,.,.w - , , ,- ,,--,- w- , _ , - _ -

~

g- ..

~

INTERIM REPORT - DER 83-40 POTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNIT 1

1. Potential Problem The LPSI and CS Pump Motors "A" and "B" are discrepant as follows:

1. Lower bearing leaking oil.

2. Defective welds on the lower motor end brackets.

II. Approach To and Status Of Proposed Resolution Bechtel engineering is corresponding with C-E, to provide

, reportability disposition, and technical justification for corrective action.

III. Projected Completion of Corrective Action and Submittal of the Final Report

< Evaluation of this condition and submittal of the Final Report is forecast to be completed by October 6, 1983.

(

7 ,-- r - -,- , , , ,c,, - -- ew-- ,--- - . , - - -

%R " /. -;u i %

6 ~

9'/

2 4 fr3 '

DAILY REPORT EG10M V

FOR: EXECUTIVE DIRECTOR FOR OPER$TIONS DATE: o ) g/f 3 Regional Actit Facility Notification Iten or Event Follow-up per go,55~(e)e b h Arizona Public Telephone call from licensee fM ggggg P tG f ,

P m M & cc.i=sx5,c==7

. M" ' '"'" M A h rm.u s

e, -

M.

e a mW .

4 a1 Y ^*7nf44 A -

e _

f& h .

G Op.s e P

1 h1 - '

DAILY REPORT REGION V. P '

3 DATE

Facility Notification Item or Event Regional Actic, '

Y$f f all^' h 60 Sf(e);

pm y Lw.+ c

" "

7""*

gg,s 4 sp/n t w M rm

yngo4V W wg s acz%a eda s 4~y n xpsmw-mn a a aw w a asm w 2. YL. A w -fM 9 CP d W $ C-E 4 gggs

% LM + a9p

M S 4 WA 30 9 b RV FORM 102

o 4 b* ~ e a l' '

. Mf,EfGo j ,

Arizona Public Service Company P.o. Box 21666 e PHOENIX, ARIZONA 85036 '

\~ I- f*if .

- July 18, 1983 ~ 2a~ pjjf3. ,.e ANPP-27333-RQT/BSK U. S. Nuclear Regulatory Commission NGlC,'J' ; ..

l Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr.'D. M. Sternberg, Chief Reactor Projects Branch 1

Subject:

Time Extension for Report - DER 83-09 A 50.55(e) Potentially Reportable Deficiency Relating to Unit 1 i LPSI Pump "A" Suction Strainer Contains Foreign Material, And Pump "B" Strainer is Torn.

File: 83-019-026, D.4.33.2 l'

Reference:

(A) Telephone Conversation Between T. Young and G. Duckworth

! on February 16, 1983.

l (B) ANPP-23238 dated March 14, 1983 (Interim Report)

Dear Sir:

i (N._

The NRC was notified of a Potentially Reportable' Deficiency in Reference (A), and an Interim Report was transmitted by Reference (B). At that time, it was estimated that a' Final Report would be available by July 15, 1983.

l Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by September 21, 1983, at which time a complete l report will be submitted.

l l

There is no new information or change to the Interim Report at this time.

Very truly yours, CtA.t n u.A._

E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects Management ANPP Project Director

! EEVBJr/RQT:ru cc: See Page 2 M

' u .) O 60 fbv

~f (f

^

/

U. S. Nuclear Regulatory Commission Page 2 -

J cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Connaission Washington, D. C. 20555 T. G. Woods, Jr.

G. C. Andognini J. A. Roedel D. B. Fasnacht A.' C. Rogers B. S. Kaplan .

W. E. Ide J. Vorees '

J. R. Bynum P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant ,

D. R. Hawkinson L. E. Vorderbrueggen }

G. A. Fiorelli S. R. Frost Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 .-

!. Atlanta, Georgia 30339 w --- --- . -- , , . - - - - - , , ,r_ y.- ,, r.,,-- ,,w---,,,,r--

my,% ..r---, .w,w,, _ , - , - . . , - ., . - -

G _

"C i

Arizona Public Service Company P.O. Box 21666

PHOENIX. ARIZONA 85036 [ ('] " . :

. (l.l .:._..

May 11, 1983 ANPP-23731'-RQT/BSK U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projects Branch 1

Subject:

Time Extension For Report - DER 83-9 A 50.55(e) Potentially Reportable Deficiency Relating to Unit 1 LPSI Pump "A" Suction Strainer Contains Foreign Material, and Pump "B" Strainer is Torn File: 83-019-026; D.4.33.2

Reference:

(A) Telephone Conversation between T. Young' and G. Duckworth on February 16, 1983 (B) ANPP-23238, dated March 14, 1983 (Interim Report)

Dear Sir:

The NRC was notified of a potentially reportable deficiency in Reference (A), and an Interim Report was transmitted by Reference (B).

At that time, it was estimated that a Final Report would be available by May 12, 1983.

Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by July 15, 1983, at

,hich time a complete report will be submitted.

w There is no new information or' change to the Interim Report at this time.

Very truly our, b.E .k( m h u.t E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects Management ANPP Project Director EEVBJr/RQT:db cc: See Attached Page 2 Swtom .

_ . _ _ - ~ _ _

e __-w - - - - - - - - - - - - - -- ,--+ -- - - -- - ---

.. o ,

N Mr. D. M. Sternberg ,,

May 11, 1983 ANPP-23731-RQT/BSK Page 2 cc: Richard DeYoung , Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. C. Woods, Jr.

J. A. Roedel D. B. Fasnacht G. C. Andognini J. R. Bynum A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson _}

R. W. Welcher /

R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiorelli a

k e

e S

( -

E. ,

T *

%;,yg o Arizona Public Service Company P.o. sox 21666

PHOENIX, ARIZONA 85036 l* .] g . , , , ,

~

'O I!! !;. i May 6, 1983 ANPP-23692-RQT/BSK . , . .

n ;,, . -

U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projects Branch 1

Subject:

Deficiency Evaluation Report kk2l A 50.55(e) Evaluation Relating to

=, A LPSI Pump Was Operated In Violation Of Procedures Possibly Causing Damage File: 83-019-026; D.4.33.2

Reference:

Telephone Conversation between A. D'Angelo and R. Tucker on April 6, 1983

Dear Sir:

The ,NRC was notified of the subject Deficiency Evaluation in the referenced telephone conversation, with a determination of reportability to be made within thirty (30) days (May 5, 1983).

The deficiency has subsequently been determined to beMWe-(

under the requirements of 10CFR50.55(e), therefore no written report is required. Necessary documentation of the evaluation will be maintained

'in APS files.

Very truly your

< GA.A _ 9&

E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects Management ANPP Project Director EEVB/RQT:db i

Enclosure ec: See Page 2 l

Y ^ C_= % #m

~

'"JL)oht ~

, Sl1 l

y-. - - , - - --s - - - - v,

w--g

s J .

l . .6 l

I Mr. D. M. Sternberg } .

May 6, 1983 ANPP-23692-RQT/BSK Page 2 cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.

G. C. Andognini J. A. Roedel D. B. Fasnacht A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees J. R. Bynum D. D. Green P. P. Klute A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant

'D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiorelli

=,

smh-e'"

.+pgp w e s et=e=

~-

p

., 4 . l Arizona Public Service Company I, ,YEU 3

(' P.o. box 21666 . PHOENIX, ARIZONA 85036

~

~

Marc 18 F4,2 2983~ , l: p'c ANPP-23238-LQT/BSK U. S. Nuclear Regulatory Commission p.gg.. ,,.

Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projects Branch 1

Subject:

Interim Report - DER 83-9 A 50.55(e) Potentially Reportable Deficiency Relating to Unit 1 LPSI Pump "A" Suction Strainer Contains Foreign Material, And Pump "B" Strainer Is Torn

. File: 83-019-026 D.4.33.2

Reference:

(A) Telephone Conversation between T. Young and G. Duckworth on February 16, 1983

Dear Sir:

The NRC was notified of a pctentially reportable deficiency in the refere'nced telephone convertation. At that time, it was estimated that a determination of reportability would be made.within thirty.(30) days.

Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by May 12, 1983, at which time a complete report will be submitted.

Very truly yours,

)

(h L -L. C(.,LA \

j dLQ

]

l E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects Management ANPP Project Director EEVBJr/RQT:db Enclosure cc: Sea Attached Page 2 O h

/, F ,

- e

{ .'

U. S. Nuclear Regulatory Commission March 14, 1983 Attention: Mr. D. M. Sternberg, Chief ANPP-23238-RQT/BSK Page 2 -- f cc: Richard DeYoung, Director Office of Inspection and Enforcement "

U. S. Nuclear Regulatory Conmission Washington, D. C. 20555 T. G. Woods, Jr.

J. A. Roedel D. B. Fasnacht G. C. Andognini J. R. Bynum A. C. Rogers '

B. S. Kaplan W. E. Ide J. Vorees P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bingham .

R. L. Patterson R. W. Welcher R. M. Grant

)

/

D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiorelli B

e s

t O

e , - - - - - - ,. -e-, - r,, ---, -. . - - . - - - - - . . , , , ,-. .. . . ,, , , -

n- y

. , e..

. R~

6 INTERIM REPORT - DER 83-9

- , POTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNIT 1 I. POTENTIAL PROBLEM .

Startup Quality Assurance Stop Work Notice S-83-005 documents two (2) findings regarding the cleanliness level of the Low Pressure Safety Injection (LPSI) system as follows:

1. A substantial amount of foreign material (purge dam material, etc.) was discovered in the suction strainer for Low Pressure Safety Injection Pump (LPSI) IMSIAP01 after operation.

2. A torn suction strainer for Low Pressure Safety Injection Pump (LPSI) 1MSIBP01 was discovered. The torn strainer indicates

- that a foreign object may have entered the LPSI pump.

The reliability of the LPSI system is consequently indeterminate, and continued operation without corrective action could result in possible damage to the LPSI pumps.

II. APPROACH TO AND STATUS OF PROPOSED RESOLUTION

(' Damage to the suction strainer of LPSI Pump 1MSIBP01 has been evaluated and is currently being replaced with a better design.

Bechtel Engineering is performing an investigation to determine the cause of entry of foreign material into the LPSI system.

III. PROJECTED COMPL' ETION OF CORRECTIVE ACTION AND SUBMITTAL OF THE FINAL REPORT Evaluation of this condition and submittal of the Final Report is forecast to be completed by May 12, 1983.

'E e-

, ,$ ' ,

C / MI ! _

c

.qs

, gg -

7, .

G toss - -

'n s m essa a.

p nc samemcesnPmw sva. 3003 p.o. sox 2:ssa, . awocNix, anizoNA 8503s September 29, 1982 ANPP-21921-GHD/BSK U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projects Branch 1

..,a

Subject:

Final Report @ SERIS2 A 50.55(e) Repoft Relating to Unit 2 LPSI.and Containment Spray Pump Casing Hold-Down Bolts

- Under-Torqued File: 82-019-026; D.4.33.2

Reference:

(A) Telephone Conversation between J. Eckhardt and G. Duckworth on July 7, 1982 (B) ANPP-21557, dated August 5, 1982 (Interim Report)

Dear Sir:

Attac'hed is our final written report of the deficiency referenced above, which has been determined to be Not Reportable under the requirements of 10CFR50.55(e).

Very truly yours,

- 6.LL

qLLL E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects Management ANPP Project Director EEVBJr/GHD:db Attachment cc: See Attached Page 2

... . .a

,n ) -

~

450

a U. S. Nuclear Regulatory Commission September 29, 1982 Attention: Mr. D. M. Sternberg, Chief ANPP-21921-GHD/BSK Page 2 cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.

J. A. Roedel D. B. Fasnacht G. C. Andognini A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees

, J. A. Brand A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen

, 13. A. Fiorelli Lynne Bernabei, Esq.

Harmon & Weiss 1725 "I" Street, NW Suite 506 Washington, D. C. 20006 R. L. Greenfield Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 5

=

4 4

1. * ,.

i FINAL REPORT - DER 82-35 t.

y DEFICIENCY EVALUATION 50.55(e)

ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNIT 2

'I. DESCRIPTION OF DEFICIENCY Ingersoll-Rand's instruction manual specifies a 4,000 ft.-lbs torque value for the Low Pressure Safety Injection (LPSI) and Containment Spray Pumps hold down bolts. During the conduct of rework of the LPSI "B" Pump (087641) and Containment Spray "B" Pump (S/N 087645) per requirements of NCR NA-080, a hydraulic torque wrench (direct read-out) was utilized to remove the nuts, revealing that the break-away torque was 2,500 ft.-lbs. This DER was initiated to evaluate the condition, since the original application of tightening torque was done utilizing a field fabricated wrench, and may not have provided

, the necessary accuracy.

It is Engineering's position that the 2,500 ft.lb. torque value was

'o not an accurate measure of the original tightening torque. This

-position is based on the following_ findings:

1. Per references (1) and (2) the amount of torque required to start disassembly of an axially loaded fastener is called the break loose torque, and is less than the torque required to tighten.

In reference (2), Power and Engineered Products Company (PEPCO) performed tests to determine the tor,que required for disassembly of coated (lubricant) and uncoated bolts. For the lubricated bolts the break loose torque varied between fifty-three (53) and Sixty-five (65) percent of the original tightening torque.

Similarly, the uncoated samples varied between seventy-three (73) and seventy-eight (78) percent. The Ingersoll Rand Installation Manual (Reference 3) calls for the application of a lubrleant to

~the bolts to prevent galling.

2. Additionally, there is a drop in bolt tension versus time. This condition is known as relaxation resulting from the elastic re-covery which takes place when the torque wrench is removed.

(Torsional stresses go to zero). Secondly, creep and yielding in the bolt due to the high stress level at the root of the threads results in further relaxation over time. Therefore, the break loose torque is not an accurate method for measuring the original hold down torque. Dependent on many factors, the break loose may vary between fifty (50 ) and seventy-five (75) percent of the assembly torque. A 2,500 ft.-lb. or 62.5 percent dis-assembly torque for the LPSI pump casing bolts falls within this range.

4

.. Final Report - DER 82-35 6 - Page 2 -

t II. ANALYSIS OF SAFETY IMPLICATIONS APS and Bechtel Engineering have evaluated the torque value recorded during the rework of the LPSI "B" pump, and conclude that'this condition is not reportable under the requirements of 10CFR50.55(e). The observed value of break loose torque is indicative of an original hold down torque in compliance with the specification requirement.

III. CORRECTIVE ACTION A copy of this DER will be routed to the responsib3c field engineers to assure understanding of the methodology used in verifying fastener torque values. In the future, field personnel will verify a torque value by recording the additional tightening value rather than the break loose value.

, REFERENCES

1. " Helpful Hints for Fastener Design and Application", Russell, Burdsall, Ward Corporation.

2. " Report from G. P. Miller to J. Stravinkas", Power and Engineered

Products Company, Incorporated, June 21, 1982.

3. Instruction Manual for LPSI Pumps, Ingersoll-Rand Bechtel Log

. No. N001-9.02-1.

e M

- -~ , - - , -. -- - . . - ,e--w- y. - - ,- . 4e - . - - . - . - . . . - , - - -. , - - - - . - - - -, .-.r - - --.- . ----- - . - - - -

ene o

e, l',7:

O ~

~

STA. , P.o. Box 21666 =

PHOENIX. ARIZONA 85036 '

August 5, 1982 ANPP-21557-Ds DIE,SK,.

U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. T. W. Bishop, Chief Reactor Construction Projects Branch

Subject:

Interim Report - DER 82-35 A 50.55(e) Potentially Reportable Deficiency Relating to Unit, 2 LPSI and Containment Spray Pump Casing

. Hold-Down Bolts Under-Torqued.

File: 82-019-026 D.4.33.2

Reference:

Telephone Conversation between J. Eckhardt and G. Duckworth on July 7, 1982

Dear Sir:

The NRd was notified of a potentially reportable deficiency in the referenced telephone conversation. At that time, it was estimated that a determination of reportability would be made within thirty (30) days.

Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by September 30, 1982, at which time a complete report will be submitted.

Very truly yours,

\

! ( ( .

L trA.

>t q (AL g

l E. E. Van Brunt, Jr.

! APS Vice President Nuclear Projects ANPP Project Director EEVBJr/GHD:db Attachment ec: See Attached Page 2 i

O.

Wo 8/$6%E1-49 ._

't o

- U. S. Nuclear Regulatory Commission ANPP-21557-GHD/BSK Attention: Mr. T. W. Bishop, Chief August 5, 1982

~

cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 J. A. Roedel D. B. Fasnacht G. C. Andognini A. C. Rogers B. S. Kaplan W. E. Ide

. J. Vorees -

J. A. Brand ,

A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant

(- D. R. Hawkinson

11. E. Vorderbrueggen G. A. Fiorelli Lynne Bernabei, Esq.

Harmon & Weiss 1725'"I" Street, NW

. Suite 506 Washington, D. C. 20006 R. L. Greenfield Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 6

=

M

m

. . , s N *

., _ , ' s. , -

i INTERIN REPORT.- DER 82-35 l 1 POTENTIAL REPORTABLE DEFICIENCY

,IARIkONAPUBLICSERVICE' COMPANY (APS)

I. POTENTIAL ' PROBLEM ' s

.s.

t-Ingerspil LPand Instruction Manual specified 4,000 ft, lbs. torque for the Low Pressure Safety Injection (LPSI) and Containment Spray Pumps hold down bolts. ' Luing rework of the LPSI "B" Pump (087641) and Containment Spra'y "B" Pump (S/H 087645) per requirements of NCR NA-080, a hydnulic torque wrench (direct read-out) was utilized to remove the nuts, ' revealing that the break-away torque was 2,500 f t. lbs.

(l Subsequent to this discovery, research revealed that the original torque was applied utilizirgfa field fabricated wrench, torque wrench and multiplS r. During the. calibration process, the torque wrench was the l

only item calibrated. When torque was applied, the multiplier ratio was usM to determine the torque, applied. This application may not

~

have proYided the desired accuracy. '

V . / ' '

y , v.

II. APPROACM TO AND STATUS ~07 FROPOSED RESOLUTION x

s , .

)7

( ., s e Engineering is performing an analysis of this condition to determine:

\ -(1) . If the nut removaf torque' in an 'an urate measure of the original

)' tightening tordae'. ,

y(2) If the 2,500 ;f t. lbs,e torque' is sufficient to meet the operational 1,,

N . requirements 'of the pur:p and pump motor.

\.

y t

III. :PJ.0JECTED COMPLETIGN OF CORRECTIVE ACTION

. ly0 SUBMITTAL OF THE FINAL REPORT s

' Evaluation of thi.s< condition and submittal of the Final Report is

! Forecast to be congile'ted by September 30, 1982. - s 4

\ s '1 l

M\ n '

e ~

\

s 4

s c-

' N' \ A 6

\

, T s, 's .

r , s..

~

t [

L i e .~

,b

. y i m e - w- + r---e-,c-- em,-m-, u--v-*e ,--wee +=-- ty--r--+. - - --* -- ,-w, v.-... e - , - - .- . - - - -- - - - - - - - - . - - - - - - , - -

~

8//ZSO o ,a hl l'.EXI TD i N STA.

k FU""@ w=dH@2SmiFm@N>

P.o. sox 23666 - PHOENIX, ARIZONA 85036 May26,19EIU'4' --

ANPP-21044-GHD/BSK U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. T. W. Bishop, Chief Reactor Construction Projects Branch

'..... . m g

Subject:

Final Report - DER;81-521 A 50.55(e) Report Relating to Unit 1 Low Pressure

. Safety Injection Pumps and Containment Spray Pumps Have Potentially Loose Anti-Rotation Pins File: 82-019-026 D.4.33.2

Reference:

(A) Telephone Conversation between J. Eckhardt and G. Duckworth on December 30, 1981

(- (B) ANPP-20014, dated January 28, 1982 (Interim

- Report)

(C) ANPP-20486, dated March 19., 1982 (Time Extension)

(D) ANPP-20818, dated April 27, 1982 (Time Extension)

Dear Sir:

Attached, is our final written report of the deficiency referenced above, which has been determined to be Not Reportable under the requirements of 10CFR50.55(e).

Very truly yours k TS. m E. E. Van Brunt, Jr, quE APS Vice President Nuclear Projects ANPP Project Director EEVBJr/GHD:ake Attachment cc: See Attached Page 2 kesy3m +sa nin

. .t

.. U..S. Nuciscr Rigulctory Commissicn r Attsntion: Mr. T. W. Bishap,' Chief' ANPP-21044-GHD/BSK May 26,' 1982

_, Page 2 ec: Richard DeYoung, Director Office of Inspection and Enforcement U. S.' Nuclear Regulatory Commission Washington, D. C. 20555 J. A, Roet el D. B. Faenacht G. C.' Andogaini A. C. Rogers

, .B. S.'Kaplan

.W.'E. Ide

.J. Vorees J. A. Brand A., C. Gehr W.' J. Stubblefield -

. W. G. Bingham

.R. L. Patterson R. W. Welcher, R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiorelli f

Lynne Bernabei, Esq.

. Harmon & Weiss 1725 "I" Street, NW

^

Suite 506

.Washingten, D. C. 20006 R. L. Greenfield Assistant Attorney General.

Bataan Memorial Building Santa Fe, New' Mexico 87503 v

9 5

s.

~

FINAL REPORT - DER 81-52 DEFICIENCY EVALUATION 50.55(e)

\_ ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNITS 1 I. Description of Deficiency Combustion Engineering identified a low pressure safety injection pump failure at the Arkansas One plant. Sub-sequent Combustion Engineering correspondence requested Bechtel to check and reinstall any loose Anti-Rotation Pins in the low pressure safety injection and containment spray pumps manufactured by Ingersoll-Rand.

II. Analysis of Safety Inplications This condition is evaluated as Not Reportable based on the attached Combustion Engineering Letter V-CE-15903, dated February 10, 1982. Should this condition have remained undetected andn uncorrected, it would not represent a safety significant condition.

III. Corrective Action Nonconformance Report NA638 CLow Pressure Safety Injection Pump) will be dispositioned to secure the loose pins by tack welding in compliance with Combustion Engineering Letters V-CE-6180, dated March 15, 1980, and V-CE-6354, dated October 8, 1981.

Nonconformance Report NA639 (Containment Spray Pump) will be dispositioned as Use-As-Is, since the pins were found to be tight by Bechtel Field personnel.

The above pumps for Unit I were modified under Ingersoll-Rand supervision. The pump sets for Units 2 and 3 were modified by Ingersoll-Rand prior to delivery to the jobsite (see attached Letter leR to W. G. Bingham, dated April 16, i

1982).

l

~4 e nappe-- -e

., C-E Pawsr Systams Combustion Engin:ering. Inc.

Tel. 203/688-1911 Telax: 99297

'b2 Eb 16 y ;,4 hW

, J000 Prospsct Hill Rozd D i>0!. ( r . r-Windsor. Connscticut 06095

T'dr(AMi#,/v </ l/

T S $"j'5903 Resp.

-fC l Supv U Mr. W. G. Bingham ~83 Bechtel Power Corporation . DER 61-52 -BsK M 12400 East Imperial Highway g DBF /

Nomalk, California 90650 iRLR /

JAR '/

Subject:

ANFP Bechtel Job 10407 y -_ACR 6 Anti-rotation Pins LPSI CSPumps 8a WEI //

2 ttfd //

References:

A B/CE-E-37869, dated December 31, 1981 !% /dh /

B Bechtel Deficiency Evaluation Report No. 81-52 ,:00 -

EEVB , .Ir., / enc --

dated 12/17/81. n.t (C) CE letter V-CE-8313, dated 5/25/79 $j _

Y- I

Dear Mr. Bingham:

FILE

.t2-tol c/11 1 ens.

- Reference (A) fomarded Reference (B) to CE and asked for CE inpur. as to the reportability of the reported deficiency. CE does not consider the loose fitting " anti-rotation pin" situation to be a reportable deficiency item for the following reasons:

(

l. The pins are all to be checked for tightness at the site prior to pump operation. Any pins discovered to be loose are to be reinstalled in accordance with the procedure in Reference (C) above.

2. If a pin were to come loose it would remain captive in the region between the impeller arid diffuser. This event occured at Arkansas. Noise of the pin rattling between impeller and diffuser was detected and the cump shut down and disassembled. The pin which was originally about 1 " long by

" diameter had been reduced to the size of a pencil eraser.

3.. 'The pin is not designed to carry any loads, but is merely a device to properly locate the diffeser during pump assembly. The diffuser is secured in position, between the stuffing box extension and the suction ring, when the main casing bolting is torqued, thereby preventing its rotation.

If you have any questions, please contact us.

Ver tru ,ours, C. Fer n CF/CDB/rre cc: Messrs:

E. E. Van Brunt, Jr. R. H. Holm S. M. Mager F. W. Hartley W. L. MacDonald G. C. Andognini W. H. Wilson G. A. Butterworth D. B. Amerine

l ,

Attcchment to DER 81-52 1

- INGERSOLLRAND tm w eom=

NmobRand Company

'~

April 16, 1982 5533 Eam W Nd Mgh im ws. cA soo22m .

(213) 72:HM31 ru _ N-DDI Bechtel Power Corporation P.O. Box 60860 - Terminal Annex IPR 22 82 a a Los Angeles, CA 90060 y_ n a ..~ -

Attention: Mr. William Bingham _s- 't 5' N p an u s,. ---

F f et samman

~

ANPP-Palo Verde Nuclear Generating Station * * "

Subject:

Units 1,2 and 3 $ll' Model 8x20 WDF Low Pressure Safety Injection Pm ^

"'8 3 I-R Orders 001-36423/26/29 7't "

and -

Model 8x23 WDF Containment Spray Pumps E I-R Orders 001-36424/27/30 , g,,

_ tu.:: 1

g er.r.., f __

etet at i Gentlemen: num Sta g u v.

Q q ui 1 We respond to your recent request for clarification of t},e mu r change in the anti-rotation pin to pr2 vent the diffusor rd T V'*j f-'

rotating in the pump casing. #

(' On Unit #1 both sets of pumps were modified by captive welding the pin.under Ingersoll-Rand supervision.

On Units #2 and i3 the pump sets were shipped later and we wer able to incorporate a design change during manufacture so tha the pin is permanently secured and no field modification of t ase pumps is required. Z We hope this clarifies the situation. I very truly yours, INGERSOLL-RAN COMPANY Ted R. Kernkamp mm k W seeog a e e. ee

'o '

M A "F " # # C ' *~N-'% ' ' * ~ " - -

~}_

M. 'T~--'- *.~/9 "-' 38"

_] . m';T - , - - - .

_ _ _ _a

('

.9 52-( .., ammssa D' y @ a tamnow mmeman ammusw P. O. sox 2I666 PHOENIX, ARIZON A 85o36 March 19, 1982 ANPP-20486-GHD/BSK U. S. Nuclear Regulatory Commission -

Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. B. H. Faulkenberry, Chief Reactor Construction and Engineering Support Branch

Subject:

Time Extension for Report - DER 81-52 A 50.55(e) Potentially Reportable Deficiency Relating to Unit 1 Low Pressure Safety Injection Pumps and Containment Spray Pumps Have Potentially Loose Anti- /

Rotation Pins File: 82-019-026 D.4.33.2

Reference:

(A) Telephone Conversation between J. Eckhardt and G. Duckworth on December 30, 1981

( (B) ANPP-20014, dated January 28,1982 (Interim Report)

Dear Sir:

The NRC was notified of a potentially reportable deficiency in Reference (A) and an Interim Report was transmitted by Reference (B).

At that time, it was estimated that a Final Report would be available by March 23, 1982.

Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by April 30, 1982, 9 hen a complete report will be submitted.

1.iere is no new information or change to the Interim Report at this time. ,

,1 Mg f Very truly yo rs, ,

Q A (A, 5 g 5 8 [ E. E. Van Brunt, Jr.

" O APS Vice President 4 Nuclear Projects y ANPP Project Director E'

EEVBJr/GHD:ske g \

cc: See Attached Page 2

/ > ?

^

jhh ,G -bd' rr

h, . . ',

U. S. Nuclccr Regulct ry Consniccion Att ntions Mr. B. H. Fruiktnbarry, Chi 2f ANPP-20486-GHD/BSK

, -March Pa~ge 219,1982 cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 J. A. Roedel -

D. B. Fasnacht G. C. Andognini ,

F. W. Hartley J. M. Allen A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees J. A. Brand

. A. C. Gehr W. J. Stubblefield W. C. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson

( L. E. Vorderbrueggen

. R. L. Greenfield Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 Ms. Patricia Lee Hourihan 6413 South 26th Street Phoenix, Arizona 85040

~~_,[_. ,. _ . _ . . _ _,.,., .___. _ _ . _ - _ _ _ . . , , , , _ - _ - , _ _ , _ ,

s

. .?x, . -

F/N 930 ,

g g

.5 1,. -

g s 9.'

{

amamman

\ ,[: mm sumeerm co:cammy

/

r. s o

V gs x, P. O. BOX 26666 - PHOENIX. ARIZON A 85o36 . ?

April 27, 1982 y ANPP-20818-CHD/BSK U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. T. W. Bishop, Chief Reactor Construction and Engineering Support Branch

Subject:

Time Extension for Report - DER 81-52 A 50.55(e) Potentially Reportable Deficiency Relating to Unit 1 Low Pressure Safety Injection Pumps and Containment Spray Pumps Have Potentially Loose Anti-Rotation Pins File: 82-019-026 D.4.33.2

(,

Reference:

(A) Telephone Conversation between J. Eckhardt and G. Duckworth on December 30, 1981 (B) ANPP-20014, dated January 28, 1982 (Interim Report)

(C) ANPP-20486, dated March 19, l'982 (Extension)

Dear Sir:

The NRC was notified of a potentially reportable deficiency in Reference

'(A). An Interim Report was transmitted by Reference (B), and a time At that time, it was estimated extension was requested by Reference (C).

that a Final Report would be available by April 30, 1982.

Due to the extensive investigation and evaluation required, it is now expected that this information' will be finalized by May 28, 1982, when a complete report will be submitted.

There is no new information or change to the Interim Report at this time.

Very truly yours, 04%

E. E. Van Brunt, Jr.

APS Vice President k j

(

Nuclear Projects ANPP Project Director EEVBJr/GHD:ske cc: L See Attached Page 2 - ',T JL 6 F {2 - Ui

s,

\ "U. S. Nuclaf.r K;gulctory Commicsion e

'Ayt ntion: Mr. T. W. Bish:p, Chiaf 6' ANPP-20818-GHD/BSK April 27, 1982 l Page 2 ,

cc: RicharJ DeYoung, Director ,

Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 J. A. Roedel D. B. Fasnacht -

G. C. Andognini A. C. Rogers B. S. Kaplan W. E. Ide J. Votees J. A. Brand A. C. Gehr W. J. Stubblefield

W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant ~

D. R. Hawkinson L. E. Vorderbrueggen R. L. Greenfield A,ssistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 Ms. Patricia Lee Hourihan 6413 South 26th Street Phoenix, Arizona 85040

.. t

4 8//2308 1

Nd 5 Y P. O. B OX 216 6 6

PHOENIX, ARIZON A 85o36 January 28, 1982 l ANPP-20014-GHD/BSK l U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. B. H. Faulkenberry, Chief Reactor Construction and Engineering Support Branch

Subject:

Interim Report - DER 81-52 A 50.55(e) Potentially Reportable Deficiency Relating

to Unit 1 Low Pressure Safety Injection Pumps and Containment Spray Pumps Have Potentially Loose Anti-Rotation Pins File: 82-019-026 D.4.33.2

Reference:

Telephone Conversation between J. Eckhardt and G. Duckworth on December 30, 1981

Dear Sir:

The NRC was notified of a potentially reportable deficiency in the referenced telephone conversation. At that time, it was estimated that a determination of reportability would be made within thirty (30) .

days.

Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by March 23, 1982, at which time a complete report will be submitted.

Very truly .

.\ Clk E-E. E. Van Brunt, Jr.

hd'

..; ; APS Vice President Nuclear Projects ANPP Project Director EEVBJr/GHD:ske O ! dd ! ~ Ud 1.3.

(. Attachement cc: See Attached Page 2 4pJ>1446M '

4GS g,.,,

.. . U. 's. NuclGar R3gulctory Conniccion Attention: Mr. B. H. Eculkenbarry, Chief ANPP-20014-GHD/BSK January 28, 1982 e Page 2

(

cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 J. A. Roedel D. B. Fasnacht G. C. Andognini ,

F. W. Hartley J. M. Allen A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees J. A. Brand

' A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant f D. R. Hawkinson

( L. E. Vorderbrueggen

'R. L. Greenfield Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 Ms. Patricia Lee Hourihan ,

6413 South 26th Street Phoenix, Arizona 85040 O

e

e, INTERIM REPORT - DER 81-52

.. POTENTIAL REPORTABLE DEFICIENCY

~

\' ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNIT 1 I. Potential Problem ,

Combustion Engineering identified a Low Pressure Safety Injection Pump failure at the Arkansas One plant. Subsequent Combustion Engineering correspondence requested Bechtel to check and reinstall any loose Anti-Rotation Pins in the Low Pressure Safety Injection and Containment Spray Pumps manufactured by Ingersoll-Rand.

II. Approach To and Status Of Proposed Resolution Bechtel has requested assistance from Combustion Engineering in

, evaluating and dispositioning this item.

III. Projected Completion of Corrective Action and Submittal of the Final Report

[ Evaluation of this condition and submittal of the Final Report is forecast to be completed by March 23, 1982.

( .

O e

e O

ne

- - - m2 -e -_w,gp,,+ ,m,-

ML20090L339

Text

Subject:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

References:

Dear Mr. Bingham:

Subject:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Navigation menu

Search