Text

Rev 1 to Interim Deficiency Rept DER 83-42 Re Thermowells in Rcs.Initially Reported on 830629.Final Rept Expected by 840615.Proprietary C-E Rept Encl.Rept Withheld (Ref 10CFR2.790)
	ML20090L302
Person / Time
Site:	Palo Verde
Issue date:	01/18/1984
From:	Van Brunt E; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Bishop T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20090L275	List: ML20090L288; ML20090L302; ML20090L339;
References
	FOIA-84-212 ANPP-28613-BSK, DER-83-42, NUDOCS 8405250281
	Download: ML20090L302 (9)
	v • d • e

P

,l 0 -}'

Arizona Public Service Company r

[

PO. SON 21446 PHOENIK. ARIZONA 95036

('

January 18, 1984 ANPP-28613-RSK/KCP h t Eco V-I" l

U. 5. Nuclear Regulatory Commission ykqg I.

Region V Creekside Oska Office Park i

1450 Maria Lane - Suite 210 Waladt Creek, CA 94596-5368 j

Attention: Mr. T. W. Bishop, Director Division of Re41 dent i

Reactor Projects and Engineering Programs Subject InteriaReport-Revision 1-DER'33-421 A 50.55(e) Potentially Report;able Condition Relating to Thernovells in the Reactor Coolant System d

Pile:

84-019-026; D.4.33.2 1

Ruference A) Telephone Conversation tatween P. Johnson and J. Roedel l

on June 29, 19P.3 i

B) ANPP-27398, dated July 25, 1983 (Interia Report)

C) ANPP-27852, dated September 21, 1983 (Time Extension)

D) ANPP-28320, dated November 30, 1983 (Time Extension)

E) ANPP-28575, dated January 9,1984 '(Time Extension)

Dear Sir The NRC was notified of a potentially reportable deficiency in Reference (A). An Interia Report was submitted in Reference (B), and Time Extensions were requested in References (C), (D) and (E). At that time, it was estimated that a determination of reportability would be made by l

January 24, 1984 t

Due to the extensive investigation and evaluation required, a revised Interia Report is attached. It is now expected that this information will be finalized by June 15, 1984 at which time a complete report will i

be submitted.

i i

Very truly yours, Qf M.

e405250 31 840423 E. E. Van Brunt, Jr.

POR FO!A APS Vice President, Nuclear SEPNA8E84-212 PDR ANPP Prcject Director i

EEVB/KCPspt j [

Attachment

(

C E Doc. No. CEN-265(v)-P.,.,

Proprietary Copies 01 j

ect See Page Two i

l-

INTERIM REPORT - REVISION 1 - DER 83-42 ARIZONA PUBLIC SERVICE (APS)

PVNGS UNIT 1 I.

Potential Problem During hot functional testing, it was discovered that thernowells 01JRCA-TW-122CA and 01JRCC-TW-112CC were not maintaining the pressure boundary in the Reactor Coolant System (RCS), and were esitting steaa through their respective temperature elements, tag numbers 01JRCA-TE-122CA and 01JRCC-TE-112CC. Preliminary investigation revealed penetration cracks on the thernovells' internal wall surface. Some damage to temperature elements was also observed. Subsequent inspection revealed that three (3) additional thernovells, 01JRCA-TW-112CA, 01JRCD-TW-112CD and 01JRCE-TW-111Y, had also failed. The subject thernovells were supplied by Combustion Enginecring (C-E).

II.

Approach To and Status of Proposed Resolution i

l' C-E has performed an inspection, followed by testing and analysis, of the thernovell deficiencies as outlined in the C-E Interim " Report on Palo Verde Unit 1 Resistance Temperature Detector Thernovell",

j attached. The C-E analysis attributed the principle failure mechanism to flow induced vibration fatigue. In some cases, shearing of the thernowells was also due to impact from heavy objects in the flow stream.

2 The C-E Interim Report provides a detailed description of the thernovell

, damage, the inspections, testing and analysis of the original thernovell design, and the safety and generic implications of the deficiency. The C-E Interim Report also discusses the design modifications to the thernowells, and the tests and analysis that were performed to verify the adequecy of the redesigned thernovells. Planned corrective action includes the following A.

C-E has committed to replace the originally supplied thernovells in Units 1, 2 and 3 with redesigned thernovells.

Bechtel will issue DCP's ISM-RC-101, 2SM-RC-101, and 3CM-RC-101 to replace thernowells identified by the following tag numbers:

UNIT 1 UNIT 2 UNIT 3 IJRCA-TW-112CA 2JRCA-TW-112CA 3JRCA-TW-112CA IJRCB-TW-112CB 2JRCB-TW-112CB 3JRCB-TW-112CB IJRCC-TW-112CC 2JRCC-TW-112CC 3JRCC-TW-112CC IJRCD-TW-112CD 2JRCD-TW-112CD 3JRCD-N-112CD 1JRCE-TW-111X 2JRCE-TW-111X 3JRCE-TW-111X 1JRCE-TW-111Y 2JRCE-TW-111Y 3JRCE-TW-111Y IJRCA-TW-112HA 2JRCA-TW-112HA 3JRCA-TW-112HA IJRCB-TW-112HE 2JRCB-TW-112HB 3HRCB-TW-112HB IJRCC-TW-112HC 2JRCC-TW-112HC 3JRCC-TW-112HC IJRCD-TW-112HD 2JRCD-TW-112HD 3JRCD-N-112HD IJRCA-TW-115 2JRCA-TW-115 3JRCA-TW-115 IJRCA-TW-121X 2JRCA-TW-121X 3JRCA-TW-121X ta 5800A/1503A

,, ~ - -,

-,w

..--,-e-w-

-Y--

m--n

,-4-m,

--,,e

--,.----_m

_ _ = _ _ - __--

t 4

l INTERIM REPORT - REVISION 1 - DER 83-42 Page Two UNIT 1 UNIT 2 UNIT 3 1JRCE-TW-121Y 2JRCE-TW-121Y 3JRCE-TW-121Y i

1JRCA-TW-122CA 2JRCA-TW-122CA 3JRCA-TW-122CA I

IJRCB-TW-122CB 2JRCB-TW-122CB 3JRCB-TW-122CB t

IJRCC-TW-122CC 2JECC-TW-122CC 3JRCC-TW-122CC 1JRCD-TW-122CD 2JRCD-TW-122CD 3JRCD-TW-122CD i

1JRCA-TW-122HA 2JRCA-TW-122HA 3JRCA-TW-122HA IJRCB-TW-122HB 2JRCB-TW-122HB 3JRCB-TW-122HB IJRCC-TW-122HC 2JRCC-TW-122HC 3JRCC-TW-122HC l

IJRCD-TW-122HD 2JRCD-TW-122HD 3JRCD-TW-1229D IJRCB-TW-125 2JRCB-TW-125 3JRCB-TW-125 i

B.

NCR's SJ-2201, SM-2185 and SM-2249 will be dispositioned according to the respective DCP's.

C.

Combustion Engineering will revise drawings, manuals and qualification documents to reflect the redesigned thernovells.

D.

A copy of this report will be sent to Combustion Engineering for l

their review and disposition under the requirements of 10CFR21.

l E.

The redesigned thernowells will receive additional, final testing during startup testing of PVNCS Unit 1, in accordance with Section 6.0, " Tests and Analysis (Design Verification)", of the attached C-E Interim Report. The C-E Interim Report will be finalized, and submitted as an attachment to the APS Final Report, upon completion of the final testing and subsequent analysis of the redesigned thernovells. This activity should be completed by June 1, 1984 Projected Completion of Corrective Action and Submittal of the Final I

III.

Report Evaluation of this condition and submittal of the Final Report is forecast to be completed by June 15, 1984.

IV.

Attachments A.

C-E Letter V-CE-19590 B.

C-E Interim Report, C-E Doc. No. CEN-265(V)-P, Proprietary.

s

-3.,,

,p y-,,.-

-,,-,w%,-y m,,,w%,w--,,,.---,wwaw--,erv-es--+wr-wew-

e--

---=- - - - '

Mr. T. W. Bishop DER 83-42 Page Two C E Doc. No. CEN-265(v)-P Proprietary Copies I

cc:

Richard DeYoung, Director

2 Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.

3 G. C. Andognini J. A. Roedel D. B. Fasnacht A. C. 'au ers m

B. S. Kaplan W. E. Ide J. Vorees J. R. bynum D. D. Green P. P. Klute A. C. Gehr

4 W. J. Stubblefield i5 W. G. Bingham i6 R. L. Patterson f7 R. W. Welcher

8 R. M. Grant

9 D. R. Hawkinson

10 L. E. Vorderbrueggen ill G. A. Flore111

12 S. R. Frost J. Self D. Canady Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GA 30339 Mr. E. Licicra, Project Manager

13 through #37 U.S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, Maryland 20814 Filer DER 83-42

38

Non proprietary copy attached g

.e..-

.m.w -

e.

,,,, - - - - - - -. - ~, ~. -. _ _

\\

54 Power Systems T;i 203/6881911 C:meustion Engineering. Inc.

T;tu 99297 1000 Prospect HsII Road Windsor, Connecticut o6095

" q POWER L::s SYSTEMS January 13, 1983 V-CE-19590 Mr. E. E. Van Brunt, Jr.

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

Subject:

10CFR50.55(e)ReportonRTDThernowells

Dear Mr. Van Brunt:

Enclosed for your submittal to the Nuclear Regulatory Comission is the interim 10CFR50.55(e)rrportontheresistancetemperaturedetector thernowells, along with the proprietary affidavit. Copies 1 thr(RTD) 25 of the ough proprietary report are intended for submittal te the NRC. Copies 26 through 43 are provided for APS use.

In addition 15 copies of the non-proprietary version are also enclosed. This report is an " interim" report and is considered conplete to date. Upon conpletion of the remaining tests and analysis of data a final. report will be submitted for your comments and subsequent submission to the f;RC.

Very truly yo s,'

C. Fergus Project!!anager CF/TJC: tor Enclosure cc: ftessrs:

G. C. Andugnini w/ Copy 44 J. Vorees W. H. Wilson W. G. Binghan w/ Copy 45 R. H. Holm J. W. Dilk G. A. Butterworth S. N. Hager D. B. Amerine w/ Copy 46 W. L. HacDonald J. R. Bynum E. Gouvier

. * *,. O AFFIDAVIT PURSUANT TO 10 CFR 2.790 Combustion Engineering, Inc.

)

State of Connecticut

)

County of Hartford

)

SS.:

I, A. E. Scherer, depose ind say that I am the Director, Nuclear Licensing, of Combustion Engineering, Inc., duly authorized to make this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below.

I am submitting this affidavit in conformance with the provisions of 10 CFR 2.790 of the Commission's regulations and in conjunction with the construction permit of Arizona Public Service for withholding this infornation.

The information for which proprietary treatment is sought is contained in the following document:

CEN-265(V)-PReportonPaloVerdeUnit1ResistanceTemperatureDetector Thermowells.

This document has been appropriately designated as proprietary.

I have personal knowledge of the criteria and procedures utilized by Combustion Engineering in designating information as a trade secret, privileged or as confidential commercial or financial information.

Pursuant to the provisions of paragraph (b) (4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in deternining whether the information sought to be withheld fron pubile disclosure, included in the above referenced document, should be withheld.

e-

.me,e w -

1.

The information sought to be withheld from public disclosure are Combustion Engineering design and test results of high response thermowells, which is owned and has been held in confidence by Combustion Engineering.

2.

The information consists of test data or other similar data concerning a process, method or component, the application of which results in a substantial competitive advantage to Combustion Engineering.

3.

The information is of a type customarily held in confidence by l

Combustion Engineering and not customarily disclosed to the public. Combustion Engineering has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The details of the aforementioned system were provided to the Nuclear Regulatory Commission via letter DP-537 from F.M. Stern to Frank Schroeder dated necember 2, 1974 This system was applied in determining that the subject document herein are proprietary.

4.

The information is being transmitted to the Conmission in confidence under the provisions of 10 CFR 2.790 with the understanding that it is to be received in confidence by the Comission.

5.

The information, to the best of my knowledge and belief, is not available in public sources, and any disclosure to third parties has been nade pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.

6.

Public disclosure of the information is likely to cause substantial harm to the competitive position of Combustion Engineering because:

a.

A similar product is manufactured and sold by major pressurized water reactor competitors of Combustion Engineering.

b.

Development of this information by C-E required thousands of manhours of effort and tens of thousands of dollars. To the best of my knowledge and belief a competitor would have to undergo similar expense in generating equivalent information.

c.

In order to acquire such information, a competitor would also require considerable time and inconvenience related to the design and testing of high response thermowells.

d.

The information required significant effort and expense to obtain the licensing approvals necessary for application of the information.

Avoidance of this expense would decrease a competitor's cost in applying the information and marketing the product to which the information is applicable.

. t.' The information consists of design information and testing results of high response thermowells, the application of which provides a competitive economic advantage.

The availability of such information to competitors would, enable them to modify their product to better compete with Combustion Engineering, take marketing or other actions to improve their product's position or impair the position of Combustion Engineering's product, and avoid developing similar data and analyses in support of their processes, methods or apparatus, f.

In pricing Combustion Engineering's products and services, significant research, development, engineering, analytical, manufacturing, licensing, quality assurance and other costs and expenses must be included.

The ability of Combustion Engineering's competitors to utilize such information

.* +=

m-6

++a*

~

without similar expenditure of resources may. enable them to sell at prices reflecting significantly lower costs, g.

Use of the information by competitors in the international marketplace would increase their ability to market nuclear steam supply systems by reducing the costs associated with their technology development.

In addition, disclosure would have an adverse economic impact on Combustion Engineering's potential for obtaining or maintaining foreign licensees.

Further the deponent sayeth not.

AML 1. E. f erer Director Nuclear Licensing Sworn to before me this10 ay of G DGCL^b c IQ khew ku

'atut)

Notary Public U

M'l s *.t. ifrg;y, ggyzy a g,,

J.* 76 F 'T*.WT';t'i g-c.

v -

-- 5 g, p...

i e

e a.

.,y

+wa e.v 4-

TELIS ll t,',',y Arizona Public Service Company 4

Po sos tices

PMotNix. AmizoNA eso3e g

,3 7,) 3 g.g January 16, 1984:;2(;;;;p. :*.

ANPP-28627-BSK/TRB U. S. Nuclear Regulatory Commission g

U Region V Creekside Oaks Of fice Park i

1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop. Director Division of Resident Reactor Projects and Engineering Programs

Subject:

Time Extension For Report - DER 83-61 A 50.55(e) Potentially Reportable Deficiency Relating To Unit 1 LPS1 Pumps Tailed to Start and Do Not Produce the Required Head.

File: 84-019-026; D.4.33.2

Reference:

(A) Telephone conversation between P. Johnson and R. Tucker on September 14, 1983.

(

(B) ANPP-28001 dated, October 13, 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 January 26, 1984 Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by February 23,1984, at which time a complete report will be submitted.

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

I Very truly ours nu L CU._L <

E. E. Van Brunt, Jr.

APS Vice President, Nuclear Ah7P Project Director EEVB/UtB:db cc:

See Page Two

(

- o 4 b b65ui%

ad

s J

Mr. T. W. Bishop DER 83-61 Page Two a

c"c 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. Fa snacht A. C. Rogers B. S. Raplan W. E. Ide J. Vorees J. R. Bynum P. P. Klute A. C. Gehr W. J. Stubblefield W. C. Bingham R. L. Patterson R. W. Welcher

[

H. Foster D. R. Hawkinson L. E. Vorderbrueggen G. A. Flore111 S. R. Frost J. Self D. Canady Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, CA 30339 L-

f/&

.c,

?.C.9'.'El.

rx

~

Arizona Public Service Company no som riens. e ossix.mzosa mas g

g January 9, 1984 Id IfJ J '

ANPP-28575-BSK/KCP U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Rishop, Director Division of Resident Reactor Projects and Engineering Programs

Subject:

Time Extension For Report - DER 83-42 A 50.55(e) Potentially Reportable Deficiency Relating To Thermove11s In The Reactor Coolant System.

File: 84-019-026; D.4.33.2 Psferences (A) Telephone conversation between P. Johnson and J. Roedel on June 29, 1983 (M) ANPP-27398, dated July 25,1983(Interin Report) 1(-

(C) ANFF-27852, dated september 21,.1983 (Time Extension)

(D) ANPP-28320, dated November 30, 1983 (Time Extension)

Dear Sir The NRC was notified of a potentially reportable deficiency in Reference ( A), an Interia Report was transmitted by Reference (B), and Time Extensions were requested in References (C) and (D). At that time, it was estimated that a Pinal Report would be available by January 5, 1984 Due to the extensive investigation and evaluation required, it is now expected that this information will be finalised by January 24, 1984, at which time a complete report will be submitted.

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

Very truly yours

((C[

CLLL._

% 1 E. E. Van Brunt, Jr.

' p- '1_b APS Vice President Nuclear Projects Management

~

ANFP Project Director

(

EEVS/KCParu ect See Page Two 4

e Mr. T. W. Bishop DgR 83-42 Page Two ect Richard DeYoung. Director Of fice of Inspection and Enforcement U. 5. Nuclear Regulatory Commission Washington, D. C. 20555 T. C. Woods, Jr.

J. A. Roedel D. B. Fasnacht A. C. Rogers

5. S. Kaplan W. E. Ide J. Vorees J. R. Bynum D. D. Creen F. P. Klute A. C. Gehr W. J. Stubblefield W. C. Bingham R. L. Patterson

(

R. W. Welcher H. Foster D. R. Hawkinson L. E. Vorderbrueggen C. A. Flore111 S. R. Frost J. Self D. Canady W. F. Quinn Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, CA 30339

7 <%dd 0) s.

s MCDh o

' n,a Arizona Public Service Company i

[

Po somens. Pwoems,amizo 4 eeon ED JA'! 12 N It 2' January 5, 1984 ANPP-28559-SSK/N'...

U. S. Nucles-Regulatory Cassieston Region V Creekside Oake Office Park 1450 Maria Lane - Suite 210 usinut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop. Director Division of Reeldent j

Reactor Projects and Engineering Progrees

Subject:

Ties Entenelon For Report - DER 83-40 A 50.55(e) Potentially Reportable Deficiency Relating To Unit 1 LPSI And CS Pump Notors Mave Defective Welds And Are Leaking 011.

File: 84-019-026: D.4.33.2 Raferences (A) Telephone conversation between A. D'Angelo and R. Tucker on June 29, 1983.

(3) ANPP-27396, dated July 25, 1983(Interia Report) r k'

(C) ANPP-27962, dated October 5,1983 (Time Entension)

(D) ANPF-28363, dated December 6,1983 (Time Estension)

Dear Stra The NRC was notified of a potentially reportable deficiency in 1

Reference (A), an Interie Repor:: was transmitted by Reference (B), and and Time Entensions were requested in References (C) and (D) At that time, it was entiested that a Final Report would be available by January 6, 1984.

Due to the entensive investigation and evaluation required, it is now espected that this information will be finalised by February 6,1984, at which time a complete report will be submitted.

There 10 no new information or chs.nge to the Interim Report at this time.,

Very truly yours.

(

4 L4 l o n E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects Management ANPP Project Director REVS /TRBaru ces See Page Two

.5 %ttpoobS-

//,/ 0

e a

1r Mr. T. W. Bishop DER 8F40 Page 1tso cc:

Richard DeYoung Director Of fice of Inspection and Inforcement U. S. Nuclear Regulatory Counteston Washington, D. C. 20555 T. C. Woods, Jr.

C. C. Andoenint J. A. Roedel D. S. Faenacht A. C. Rogers B. S. Raplan W. E. Ide J. Voroes J. R. Bynum D. D. Green P. P. Klute A. C. Gehr W. J. Stubblefield W. C. Bingham R. L. Patterson

(

R. W. Welcher N. Foster D. R. Me dinson L. E. Vorderbrueggen C. A. Florelli S. R. Frost J. Self D. Canady Secords Center Institute of Nuclear Power Operatione 1100 circle 7S Parkway, Suite 1500 Atlanta, CA 30339

(

m.

W M g/gy.yr g~

l

.4.=%^-

lLf e

y, _,.,.,,

Arizona Public Service Company O( '

PHOENIX. ARIZONA 85036 j~' jf" ;*

l ' *-

, p.o. sox U666 January 3, 1984 N

ANPP-28537-BSK/KCP U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director Division of Resident Reactor Projects and Engineering Programs

Subject:

FinalReport-D$R83-39]

A 50.55(e) Reportable Conditi'on Relating to Fejectable Indications en C-E Supplied Unit 1 Reactor Coolant Pump 1A File: 84-019-026; D.4.33.2

(.

Reference:

A) Telephone Conversation between A. D'Angelo and R. Tucker on July 1, 1983 B) ANPP-27471,' dated ' July 1,1983 (Interim Report)

C) ANPP-28119, dated October. 27, 1983 (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 yoursg) s s -

r s

LLA.

%LL E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects Management ANPP Project Director EEVB/KCP:pt Attachment

' cc:

See Page Two s

L,

4 e

j di

\\f4Gl%W$

v 3 gs

(,

\\s

^

-.. i'

.,n.--

-. -,.~

-.,,,-,_.--.---,--.,-.,,n-,.~.

4

)

o.

Mr. T. W. Bishop DER 83-39 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 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 S. R. Frost J. Self P Canady Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, GA 30339 G

e-e

'V FINAL REPORT - DER 83-39 I

DEFICIENCY EVALUATION 50.55(e)

ARIZONA PUBLIC SERVICE (APS)

PVNGS UNIT'1 I.

Description of Deficiency 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/DERCEPOLA, two linear indications were found. The indications exist in the circumferential weld of the pump casing.

One of the RT indications found measures three (3) inches long; the second measures three fourths (3/4) inches long. Both exist within a length of six (6) inches. Subsequent examinations have shown that these indications are approximately three and two tenths (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 five and five eights (5-5/8) inches thick. The linear indications are acceptable to the ASME Section III RT acceptance criteria. A Fracture Mechanics Analysis has been performed by C-E on the casing using conservative parameters. The analysis assumed: 1) The indications have a through wall dimension of three fourths (3/4); 2) The indication is a sharp crack extending around the entire circumference of the casing. This analysis showed the casing to be acceptable even under upset conditions.

II.

Analysis of Safety Implications Based on the analysis performed of the RT indications in the RCP 1A pump casing, C-E has determined that the integrity of the primary system boundry has not been diminished and that the casing with the assumed j

l flaw is structurally adequate for the forty year design life of the component. Thus, if left uncorrected, the subject condition would not adversely affect the safety of operations of the plant during the lifetime of the plant. Consequently, this condition is evaluated as l

not reportable under the requirements of 10CFR50.55(e) or 10CFR Part 21.

III.

Corrective Action 1.

C-E has conducted a 100% review of the welds for all Reactor Coolant Pump casings for PVNGS Units 1, 2 and 3 and has found no other rejectable indications. Thus, the above condition is an isolated case.

2.

Although the Fracture Mechanics Analysis has shown the casing on RCP IA/IMRCEPOIA to be acceptable, C-E has committed to implement the following actions:

l l

A.

Rework of the pump case in order to satisfy the Section III RT Acceptance Criteria.

1 l

~ - - - - - - -. - - - - -

m

i Final Report - DER 83-39

'.f Page Two Rework of the RT linear indications consists of grinding out a cavity of a size sufficient to remove the indications which were not acceptable under Section III RT criteria. An extensive analysis performed by C-E determined that such a cavity is acceptable on either the ID or the OD of the pump case. Therefore, the cavity can be allowed to remain in the

" ground out" condition. If an ID repair is made, cladding must be added to provide corrosion protection.

The following items were considered in the analysis for determining the acceptablility of the cavity:

Minimum Wall Thickness The required minimum wall thickness of the pump casing in order to satisfy the internal pressure consideration is 1.783 inches. The resulting minimum wall for both OD and ID cavity exceeds this requirement.

Stresses in the Cavity Area In the existing stress report, stress intensities for envelope combinations of load cases for design normal upset and emergency condition and for the faulted conditions are developed and are available for the cavity area. Stress multiplication factors developed from hand and finite element solutions for a sphere with a thin spot have been established.

Multiplying the Stress Report stress intensities by these factors in the vicinity of the repair cavity and comparing the results to ASME Section III requirements leads to a conclusion of adequacy. Thus, there are no changes to the Stress Report conclusions.

A revision to the Stress Report is to be developed in order to obtain Code approval of the modified design. The actual cavity size is to be used in establishing the stress multiplying factors for the revisions to the Ctress Report.

I Design Transients None of the load scenarios nor design transients have been modified or dieinished for the analysis. Consequently, there are no operating restrictions of any kind being imposed on the modified design.

4

...-7.

--._,..,.,_..-m..--w.%,_

._....,_m..-.--.-y,._,_,

Final Report - DER 83-39

{

Page Three Section XI - Examination i

As a result of the rework of the RT linear indications, a UT examination in accordance with Section XI must be performed.

The outside cavity dimensions would have to include a base area of adequate size to allow for an examination of the weld root in accordance with ASME Section XI.

An inside cavity would have no effect on a UT examination from the outside surface.

Therefore, the inside surface would not need to be prepared to accommodate the UT requirement.

Based on C-E's evaluation and recommendations, the RT linear indications are being reworked until they satisfy the Section III RT Acceptance Criteria by grinding out a cavity on the inside of the pump case. After chipping and blending of the cavity is completed, an inconel clad overlay will be added for corrosion protection.

t B.

Local hydro and NDE tests will be performed on the pump. The f

hydrostatic test of the casing will be done locally by the use of hydro-dams installed in the suction and discharge nozzles.

A cover will be fitted on the casing seal housing area, and a portable pump will be used for applying the required hydrostatic test pressure.

C.

NCR SM-2025 will be dispositioned as " Repair".

3.

The present status of the rework on the RT linear indications on RCP IA/IMRCEPOIA is as follows:

A.

Excavation of the IA pump casing in the area of the RT linear indication has been completed. The area of the ID cavity has been magnetic particle inspected and re-radiographed, both with l

acceptable results meeting Section III acceptance criteria.

Hydrostatic testing of the pump to Section III criteria has been completed. The pump, RCP IA/IMRCEPOIA, has been "N" l

stamped in accordance wiuth ASME Code Section III.

B.

The revised Stress Report has been reviewed and accepted.

(Bechtel log number N001-602-367.)

i C.

Cladding of the pump cavity with inconel was completed and examination performed in accordance with Section XI l

requirements.

1 UT Examination of the cavity satisfied the requirements of Section XI.

G

---w--

- - - - ~ - - - - -

.wr-c- -,

-v-,

v,w

--we,swaenm-an -w m,,-wm,a e--mr-,

w,

,---.-------,-n

Y htt_u2'

.\\

,5 Arizona Public Service Company P.o. box 21666. PHOENIX. ARIZONA 85036 December 30, 1983

~

ANPP-28514-KCP/BSK U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director, Division of Resident, Reactor Projects and Engineering Programs

Subject:

FinalReport-BEi}3f55]

A 50.55(e) Report Relating to Missing Thermal Liner in Safety Injectio'n System Line File:

83-019-026; D.4.33.2

(.

Reference:

A) Telephone Conversation between P. Narbut and R. Tucker on August 1, 1983 B) ANPP-27604 dated August 22, 1983 (Interim Report)

C) ANPP-28211 dated November 9, 1983 (Time Extension)

Dear Sir:

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

Very truly yours

{

C1LL.

ALLL E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects Management ANPP Project Director EEVB/KCP/ sis Attachment cc:

See Page Two 1

- C Ll< !

.i n

, r.,

b I

h Mr. T. W. Bishop DER 83-55 Page Two cc:-

Richard DeYoung, Director Copies 1 through 25 of CE Office of Inspection and Enforcement Doc. No. CEN-264(V)-P (proprietary)

U. S. Nuclear Regulatory Commission are enclosed for the NRC office Washington, D. C. 20555 in Washington, D.C.

T. G. Woods, Jr.

G. C. Andogr.ini 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. C. bingham R. L. Patterson

('

R. W. Welcher

.R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiorelli S. R. Frost J. Self,

D. Canad'y Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, GA 30339 S

FINAL REPORT - DER 83-55 DEFICIENCY EVALUATION 50.55(e)

ARIZONA PUBLIC SERVICE COMPANY (APS) m PVNGS UNIT 1 I.- Description of Deficiency After hot functional testing of Unit 1, a visual inspection of the Reactor Coolant Pump 1-RCE-P01-1A and associated piping was performed.

It was revealed that the thermal liner, for the 14" safety injection nozzle installed in line SI-A207-BCCA-14" had broken loose and was missing. Further investigation determined that the liner was wedged between the outer shell and the flow baffle of the reactor vessel. The liner was retrieved from the reactor vessel by Combustion Engineering (C-E) and shipped to C-E's Chattanooga facility for inspection and problem resolution. The results of this inspection and related analyses are contained in the attached C-E report entit1=d " Report on Palo Verde Unit 1 Safety Injection Nozzle Thermal Liner", (Document No. CEN-264(V)-P).

II.

Analysis of Safety Implications The analysis of safety implications is provided in Sections 3.0,

" Inspections and Examinations", and 4.0, " Problem Definition", of

(

the " Report on Palo Verde ' Unit 1 Safety Injection Nozzle Thermal Liner", attached.

III. Corrective Action C-E recommended that the three (3) remaining thermal liners for Unit I be removed, and the explansion grooves blended into the nozzle wall ar a.

The thermal liners, four (4) per unit, for Units 2 and 3, will alzo be removed, and the explansion grooves will be blended to preclude stress risers in the safety injection nozzles.

Bechtel is implementing the required corrective actions, via the following design change packages, before fuel load for the respective units.

ISM-RC-102 2SM-RC-102 3CM-RC-102 In addition, SAR Chan'ge Notice No. 1131 will be issued prior to Unit 1 fuel load to identify the deletion of the thermal liners from the safety injection nozzles. This SAR change will reflect the deviation from the standard System 80 design as described in CESSAR Section 5.4.3.

~

fe V

1 s

AFFIDAVIT PURSUANT TO 10 CFR 2.790 Combustion Engineering, Inc.

)

State of Connecticut

)

County of Hartford

)

SS.:

I, A. E. Scherer, depose and say that I am the Director, Nuclear Licensing, of Combustion Engineering, Inc., duly authorized to make this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below.

I am submitting this affidavit in conformance with the provisions of 10 CFR 2.790 of the Commission's regulations and in conjunction with the application of Arizona Public Service for withholding this information.

The information for which proprietary treatment is sought is contained in the following document:

CEN-264(V)-P, " Report on Palo Verde Unit 1 Safety Injection Nozzle Thermal Liner".

This document has been appropriately designated as proprietary.

I have personal knowledge of the criteria and procedures utilized by Combustion Engineering in designating information as a trade secret, privileged or as confidential commercial or financial information.

Pursuant to the provisions of paragraph (b) (4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the inforwation sought to be withheld fron public disclosure, included in the above referenced document, should be withheld.

j 1.

The information sought to be withheld from public disclosure is the methodology related to the determination of usage factors and design features of reactor coolant system components, which is owned and has been held in confidence by Combustion Engineering.

2.

The information consists of test data or other similar data concerning a process, method or component, the application of which results in a substantial competitive advantage to Combustion Engineering.

3.

The information is of a type customarily held in confidence by Combustion Engineering and not customarily disclosed to the public. Combustion Engineering has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The details of the aforementioned system were provided to the Nuclear Regulatory Commission via letter DP-537 from F.M. Stern to Frank Schroeder dated December 2, 1974. This system was applied in determining that the subject document herein are proprietary.

4.

The information is being transmitted to the Commission in confidence under the provisions of 10 CFR 2.790 with the understanding that it is to be received in confidence by the Commission.

5.

The information, to the best of my knowledge and belief, is not available in public sources, and any disclosure to third parties has been made pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.

6.

Public disclosure of the information is likely to cause substantial harm to the competitive position of Combustion Engineering because:

l l

m

l'.

\\

4 s

a.

A similar product is manufactured and sold by major pressurized 7

water reactor competitors of Combustion Engineering.

b.

Development of this information by C-E required thousands of manhours of effort and tens of thousands of dollars. To the best of my knowledge and belief a competitor would have to undargo similar expense in generating equivalent information.

c.

In order to acquire such information, a competitor would also require considerable time and inconvenience related to the development of methodology to determine usage factors and design features of reactor coolant system components.

d.

The information required significant effort and expense to' obtain the licensing approvals necessary for application of the information.

Avoidance of this expense would decrease a competitor's cost in applying the information and marketing the product to which the' information is applicable, e.

The information consists of methodology related to the determination of usage factors and design features of reactor coolant system components, the application of which provides a competitive economic advantage.

The availability of such information to competitors would enable them to modify their product to better compete with Combustion Engineering, take marketing or other actions to improve their product's position or impair the position of Combustion Engineering's product, and avoid developing similar data and analyses in support of their processes, methods or apparatus.

f.

In pricing Combustion Engineering's products and services, significant research, development, engineering, analytical, manufacturing, licensing, quality assurance and other costs and expenses must be included.

The ability of Combustion Engineering's competitors to utilize such information

(

without similar expenditure of resources may enable them to sell at prices reflecting significantly lower costs.

g.

Use of the information by competitors in the international mark'etplace would increase their ability to market nuclear steam supply systens by reducing the costs associated with their technology development.

Ir.

addition, disclosure would have an adverse economic impact on Combustion Engineering's potential for obtaining or maintaining foreign licensees, Further the deponent sayeth not.

_s -

> >1M A. E. SeMErer Director Nuclear Licensing

(

Sworn to before me this D@ day of DEC, \\991 h

Oh

==y = a y, p,

1 l

l l

.=

f.

- Aps -

5, litCEiva

{c.

r':

f, Arizona Public Service Compan)

PHOENIX. ARI2oNA 8503,6 "7j k"{ {g 4

P.O BOX 21666 e e.

(

s l

December 19, 1983 ANPP-28461-BSK/MtIE.J;p.,

U. S. Nuclear Regulatory Commission Regioa V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention:

Mr. T. W. Bishop, Director Division of Resident Reactor Projects and Engineering Programs

Subject:

Time Extension for Report - DER 83-54 A 50.55(e) Potentially Reportable Condition Relating To Washers Found In Unit 1 Sterm Generator #1 and #2.

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

(A) Telephone Conversation between P. Narbut and R. Tucker on August 2' 1983 (B) ANPP-27603, dated August 22,1983 (Interim Report)

(C) ANPP-28009, dated October 13, 1983 (Time 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 Extension was requested by Reference (C). At that time, it was estimated that a Final Report would be available by December 15, 1983.

Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by January 18, 1984, at which time a c'omplete report will be submitted.

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

Ve*y truly yours j

CC C

L.

CLL MLL I E. E. Van Brunt, Jr.

APS Vice President i Nuclear Projects Management ANPP Project Director EEVBJr/KCP:ru cc: See Page 2 b6 I / Lo #f 6 /6

1.

/

Mr. T. W. Bishop i

'/

DER 83-54 k _,

Page 2 s

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. Voree s 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 N..

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

ne

~ eww y-

-se

~

-m m

,---r

c

\\

l

\\ 1)

M 3

5.

t-MCwED wc

~

DEC 081963 33 DEC 19 PM I: 50 g

Docket Nos.: 50-528 EM 50-529 and 50-530 APPLICANT: Arizona Public Sonice Company FACILITY:

Palo Verde. Units 1, 2 and 3 BUBJECT:

SLM %RY OF VISIT TO CE PUMP TEST FACILITY IN NEWINGTON, NBd HAMPSHIRE I

I On November 14-16,1983, the staff visited the CE pune test facility at Newington, New Hampshire. The purpose of the visit was to observe the test program that was in progress for resolving the problems encountered with the Palo Verde RCS pumps. Enclosure 1 provides a sismiary of the visit and includes the staff, applicant and CE participants.

P^'ais%th I ' Sil'8 l

Emanuel A. Licitra. Project Manager Licensing Branch No. 3 Division of Licensing

Enclosure:

As stated DISTRIBUTION Document Control (50-528/529/530) cc:. See next page NRC PDR L PDR TERA NSIC PRC System LBf3 Reading JLee MLicitra GWKnighton Timovak Attorney, OELD ELJordan:IE JMTaylor:IE h

4agional Admiristrator, Regien #e,

< -q e

(,e' l

.-.DL:LBf f

3 oment

.N

......./f../. 2......

/

l sunname>..E..Ali.c.i t.ra : '........................

...J...../.7../ 83

[

.../..g /f./.83 nave >

mc roau sis imon wacu ano OFFICIAL RECORD COPY use r. mi-m ew

, =,.... =,.. _ _.. _ - _. -. _ _ _. _. _... - -.... _. -. _ _. _ _ _, _ _... _ _.. _, _ - - _ _.

m

~

o Palo Verde Mr. E. E. Van Brunt, Jr.

Vice President - Nuclear Projects Arizona Public Service Company P. O. Box 21666 Phoenix, Arizona 85036 i

Arthur C. Gehr, Esq.

Kenneth Berlin, Esq.

Snell & Wilmer Winston & Strawn 3100 Valley Center Suite 500 Phoenix, Arizona 85073 2550 M Street, NW Washington, DC 20037 Mr. Charles S. Pierson l

Assistant Attorney General Ms. Lynne Bernabei l

200 State Capitol Government Accountability Project 1700 West Washington of the Institute for Policy Phoenix, Arizona 85007 Studies 1901 Que Street, NW Charles R. Kocher, Esq. Assistant Counsel Washington, DC 20009 James A. Boeletto, Esq.

Southern California Edison Company P. O. Box 800 Rosemead, California 91770 Ms. Margaret Walker Deputy Director of Energy Programs Economic Planning and Development Office 1700 West Washington Phoenik,' Arizona 85007 Mr. Rand L. Greenfield Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 l

Resident Inspector Palo Verde /NPS U.S. Nuclear Regulatory Comis:; ion P. O. Box 21324 Phoenix, Arizona 85001 Ms. Patricia Lee Hourihan 6413 S. 26th Street l

Phoenix, Arizona 85040 Regional Administrator - Region Y U. S. Nuclear Regulatory Comission 1450 Maria Lane Suite 210 i

Walnut Creek, California 94596

~

??.

z-5:r?

4 C', - l

.f%

(

? '3 s

I

~

[

NUCLEAR REGULATORY COMMISSION 7,

WBASHINGToN. o. c. 20055 are a !se MEMDRANDUM FOR: Vincent S. Noonan, Chief i

Ecuipment Qualification Branch Division of Engineering FROM:

Jerry E. Jackson Equipment Qualification Branch Division of Engineering

SUBJECT:

TRIP REPORT - REVIEW 0F CE-KSB TESTING OF MODIFIED PALO VERDE REACTOR COOLANT PUMP AT THE NEWINGTON, NH TEST FACILITY During the period of November 14-16, 1983 J. Jackson (NRR/EQB) and W. McNeill (Region IV) visited the Newington, New Hampshire test and manufacturing facility of Combustion Engineering, Inc. (CE) to review the manufacturing of the CE-KS8 reactor coolant pump (RCP) and the current testing of the modified CE-KS8 Palo Verde RCP.

W. McNeill's report will address the Ifegion IV findings regarding this trip, however the following facts, events and conclusions regarding the Palo Verde RCP problem and the current testing of the modified pump are worth noting at this time.

General 1.

' Phase-3 of the RCP test program did not occur during our visit to the site as previously scheduled. This delay was due to an accelero-meter which had failed and its replacement had to be shipped from Switzerland.

^

2.

We reviewed the RCP test facility with the engineer in charge, John Leavitt.

Charles White, manager of manufacturing at the Newington site showed us through the facility where the pumps are manufactured. We were able to see some of the Palo Verde RCP parts, both those which had failed during hot functional testing and the parts being modified for return to Palo Verde. Vincent Krecicki, Assistant Project Manager for the Arizona Nuclear Power l

Project also accompanied us to provide information on the Palo Verde RCP problem. We also reviewed the details of the changes being made to the RCP and the reason for these changes with Frazier Colon, manager of engineering at CE-KS8 Pump Company, Inc.

at Newington.

e 3.

We were told that flow resistance changes only slightly with the core in, therefore problems encountered during hot functional testing without the core are approximately the same as could be experienced during normal operation at Palo Verde [3% difference in flow].

Contact:

J. Jackson, NRR Ext. 27930 rn, o o A c e i fh Q

Jsk' lV 1 ) U

~_

~ ~~'

Z Z EZ.~.T' ~ ' E'.

4.

CE feels that the problem with broilen impeller vane segments is not related to loose and/or broken diffuser and suction pipe retaining i

cap screws or diffuser vane cavitation.

It is felt that these are two distinct and separate problems.

5.

The first pump or prototype was tested for 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months with approximately 50 or 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months of this time at runout (maximum flow). The time at maximum flow during the Palo Verde hot functional testing could have exceeded the test time on the prototype. When the sodified RCP's are installed in Palo Verde-1 the hot functional testing will not be repeated, the plans are to only functionally test the pump. This test will be approximately 160 hours0.00185 days 0.0444 hours 2.645503e-4 weeks 6.088e-5 months to reach an infinite number of fatigue cycles on the diffuser and suction pipe bolts. Also the i

decision has been made not to subject the modified pumps to the normal 50-hour performance test prior to shipping to Palo Verde.

In fact, parts of two of the modified pumps have already been t

shipped to Palo Verde. Also the decision has been made not to 3,

match impe11ers with diffusers in the future, as was previously done.

The reason given being that a mis-matched impeller and diffuser was tested in Phase 1 of the current tests relating to the Palo Verde RCP problem.

6.

In the past, three different vendors have supplied impeller castings 1) Schmidt and Clemens, 2) Fisher, and 3) Atlas.

The impe11ers used in Palo Verde previously, those which experienced impeller vane failure, were made by Atlas. The

~ impeller used in the current verification test program was provided by Schmidt and Clemens. The impe11ars being shipped back to Palo Verde are also Schmidt arid Clemens.

7.

Dr. E. Makay is the outside consultant being used for design change recommendations. The details for the major change recommended by Dr. Makay (changing diffuser to impeller gap from 25 to 6%) is given in the proceeding from the July 1983 symposium, " Power Plant Feed Pumps - Stzte of the Art", EPRI l

CS-3158 Ccatract WS81-211.

I 8.

During the course of our meeting we have asked for available information, pseferably documents, which would allow us to determine if 1) the RCP failure mechanisms had properly been i

determined and understood and 2) what tests were being performed to determine if the design changes being made would adequately solve the problem.

We were looking for final or preliminary reports on the KS8 'model tests, Phase 1 and 2 test results and reports on the cause of the impeller failure..Also we expected to see test procedures for one or all of the test phases, as well a complete picture the instrumentation used prior to the Palo Verde failures and in the present four phase test program. None of this information was provided as documents, final or preliminary. However all these issues were discussed in some j

detail and much valuable information was received.

,e4 w m.-*

-w-

= e em-e aeeq e o

e

-m--.--,,

,v,,,'.l

,, n J-n--,,_-e-,;

,:-,:D--,,----_.

,,.-----.,--+-------r

3 Pump Modifications The pump design changes were reviewed on the drawings with F. Colon and V. Krocicki. The major modifications were:

1)

Diffuser o

Radial gap between diffuser and impeller increased from 2% to 6% (material removed from diffuser vane to accomplish this) e o

Number of diffuser bolts increased from 16 to 29, with length increased from 65 mm to 110 mm.

o Increased thickness of diffuser clamping rings, changed segment size to go from 4 bolt pattern to 2 bolt pattern (increased number of segments from 4 to 14)

.[-

o Increased bolt torque from 130 ft.-lbs. to 260 ft.-lbs.

This increased the bolted joint clamping force by a factor of three.

2)

Suction Pipe i

o Suction pipe to diffuser joint changed to delete tapered fit and assure positive bolting surface.

c o

Four tapered pins were added to the joint o

Clamping ring added o

Number of bolts increased from 16 to 24, with length increased from 65 mm to 70 mm o

Increased torque from 110 ft.-lbs. to 155 ft.-lbs.

o Deleted sealing rings at bottom of the suction pipe.

3)

Impeller o

Filed trailing edge of impeller vanes to bring head curve back l

up to design (trailing edge did not fail in hot functional testing) o Increased quality control and NDE requirements to assure leading edge of the impeller actually meets design.

l 2

Pump Test Facility The pump test facility was designed and built to performance test l

centrifugal pumps of vertical, single stage, single suction design in l

accordance with the requirements of ASME Performance Test Codes. The l

6 n

~

.g.

facility is capable of testing pumps of this design driven by electric motors with a voltage of 13.2 KV and power ratings as lam as 11,931 kilowatts (16,000 horsepower), flow capacities of up to 185,000 gpa, I

operating temperatures up to 650 F and pressures up to 2500 psia.

l The primary loop consists of horizontal runs of 36 inch diameter carbon steel, stainless steel strip clad pipe approximately 70 feet in length jointed by a trifurcated return elbow. The two outside branches incor-parate butterfly valves for flow control while the center branch con-tains a throttling crifice that establishes minimum 1.oop resistance.

In order to cover the complete performance range, more than one orifice plate is required. The present test program for the Pale Verde pump uses one orifice plate and therefore can vary flows from 95% to 135%

of design and from 140% to 150% of design.

I Flow through the loop is measured by means of a calibrated 36 inch by 25 inch universal venturi tube. Piezometers and temperature sensors are located at various positions around the loop to measure pressure and temperature. The fluid in the loop is deaerated, deionized water.

l All of the test parameters measured are logged through an integrated computer system. This system provides*for logging test data continuously on a magnetic tape for processing at a later time, as well as recording selectable parameters on multipoint or multipen chart recorders for l

instantaneous analysis. This alminates the necessity of hand written i

data log sheets. A log will be maintained correlating events to test t,unning time.

Cooling systems provide temperature control of the primary loop water and cooling water for the pump and motor. A portion of the primary loop water is circulated through a water to air heat exchanger. The minimum primary loop water temperature that can be obtained is a function of heat load and environmental conditions.

l The closed cooling water system temperature is controlled by an evaporative cooler. Again, the minimum temperature is dependent upon heat load and environmental conditions. A closed system provides for control of a wider temperature range and water quality.

A charging system is provided to control the primary loop pressure and provide water for seal injection. A water heater provides temperature control of the seal injection system.

i Instrumentation i

The following instrumentation was standard for the 50 hour5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months production testing of a RCP prior to the Palo Verde pump failure.

1.

Pump shaft orbit indications 2.

Upper bearing housing frame vibration, in three directions, velocity probe integrated displacement meter.

e.

l l.

.g l' -

3.

Three seal pressures 4.

Five seal temperatures

~

5.

Three bearing temperatures 6.

One oil temperature 7.

Pressure differential across the pump 8.

Test loop pressure and temperature downsteam of the venture 9.

Loop flow indication l

In order to better understand what was occurring inside the pump the l

test loop pump casing was modified to install additional instrumentation l

for the four phase testing of the modified Palo Verde RCP. The baseline Palo Verde RCP was to be run from 95% to 135% and 140% to 150% of design flow and then the modified pump hydraulic components for Palo Verde would be installed and the same flew range covered again.

It is our understanding that during hot functional testing Palo Verde pumps were operated up to 146% of design flow'. However, with the core installed the flow rate would be reduced by approximately 3%. Therefore single pump operation would be at 143% of design flow.

The following additional instrumentation was added to the RCP test facility for this study.

i 1.

One displacement probe will be mounted in the pump casing at the area of the suction pipe piston rings in line with the pump discharge to monitor suction pipe movement.

2.'

Two pressure transducers will be mounted in the pump casing suction and discharge safe ends at the pressure tap locations to monitor pressure pulsations.

3.

Three accelerometers will be mounted in the diffuser at the split located 180' from the discharge. One on the five vane half,,and two on the six vane half. These will monitor radial, tangential, and vertical vibration of the diffuser halves. A biaxial and a vertical accelerometer will be mounted on the outside of the pump casing to monitor pump vibration. The difference between the two measurements will be the diffuser movement.

4.

Five ring segment bolts will be strain gaged to monitor bolt i

loadings. The bolt on each side of the diffuser split at discharge and at 180* along with the bolt near the diffuser key on the six vane half. Each bolt will have a thermocouple mounted to it and above it in the water to measure transient thermal conditions.

J 5.

Four thermocouples will be mounted on the top of the pump casing flange outside the pressure boundary to monitor thermal distribution of this surface.

l T.

I x

?

6-Failure Mechanisms The supporting information for understanding of the failure mechanisms appears to come from:

1)

CE and CE-KS8 internal pump experience and knowledge 2)

The German KS8 model testing of the Palo Verde pump configuration 3)

Information provided by Dr. Makay, the consultant 4)

Preliminary results of Phase 1 and 2 testing.

j None of this information was available to us in the form of documents, preliminary or final. However, we saw a preliminary KSB report on the model testing which was in German, some curves from a paper by Dr. Makay and some of the preliminary bolt stress level results from Phase 1 and 2 testing. The following information was provided to us during the course of our discussion of the problem.

O At the higher flow rates there is a mis-match between the impeller blade flow and diffuser vane, since the impeller and diffuser are sized for the design flow point. As the gap between the diffuser and impeller is increased there is more distance for this flow to adjust.

There is indiction that this mis-match is the cause of cavitation on the leading edge of the diffuser vanes. Also as the impeller blades pass a diffuser vane hydraulic forces.are imparted to the vane.

The larger the gap between the passing impeller blade and the diffuser vane the smaller are the turces which are passed. These forces can b.e seen at the blade passing frequency and were actually seen at that frequency in the preliminary results from Phase 1 and 2 testing. The primary blade passing frequency can be calculated as follows:

f = 2(Pump RPM) (Number of Impeller Blades) 60 f = 2(1190)(6) 60 f = 238 Hz Although the final results from Phase 1 and 2 testing where the 2%

diffuser gap was used were not available, higher strain and vibration at the high bolt stress area opposite the pump discharge was seen.

Also the test engineer saw visual signs of cavitation on the diffuser vane Irading edges. The highest delta strain at a frequency of 238 Hz was seen in bolt number nine in the six vane diffuser. This bolt

, is located 180* from the pump discharge.

We were told that the results of the KSB model test also showed cavitation to occur on the leading edge of the diffuser vanes at 2%

gap, but not at the 6% gap. The cavitation was determined visually using fiber optics. The model testing also confinned the areas of high bolt stress.

~.

5

.p p

i '.

7 The KS8 model strain gage testing of the impeller blades showed that the stress in the areas of impeller blades which had failed during the Palo Verde hot functional testing to be well within design limits.

Extensive investigations were then made of the impeller castings.

These investigations lead KS8 to believe that the failures were due to possible thin areas in the impeller blades as well as material imper-factions in these areas.

Methods Which Will Be Used To Assure Changes To The Pump Are Adequate The following results from the four phase test program will be used to assure the cf.anges which have been made to the pump are adequate to solve the proble::i.

1.

Delta strains on the diffuser bolts should be lower in Phase 3 and 4 testing than in Phase 1 and 2.

?.

2.

Accelerometer data should in.'.cate less vibration in the diffuser flange during Phase 3 and 4 tasting.

3.

Pressure pulsation data should show reduced pulsations during Phase 3 and 4 testing.

4.

Visual inspection of the RCP should show, a)

No cavitation marks in the modified pump b)

Contact surfaces, diffuser to pump casing, suction pipe joint and diffuser clamp segments, should anot show signs of wear or movement after Phase 3 and 4 testing.

c)

The bolt torque values should remain high after Phase 3 and 4 testing.

Combustion Engineering also feels that the KSB model testing which verified Dr. Makay's curve for radial hydraulic forces and the fiber optic investigation of the cavitation phenomenon support the fact i

that the diffuser changes are adequate. They feel that the KSB strain gage tests of the impeller blades and the detailed inspections of the impeller castings support the fact that changes in manufacturing and Q/A are adequate to solve the impeller problem.

Conclusion l

From what the staff observed during this trip it appears that CE and CE-KSB have taken adequate measures to determine the RCP failure mech-anisms and have provided for proper testing of the design changes in order to determine if future failures of the RCP are likely. However, it must be strongly emphasized that documented details and results from the testing and analysis are not now available to the staff for their detailed review. The staff will continue to follow the progress of the se uO m-w-wwi.,.e.-

e w

-e--w

~w---,-isv-w w

e-

---ii-w

- - - w v--

wwi----

w w

- - - - +

--*wv=we--w-me.---++<--v

+-iin

--e-*---- -

--v-=='=s----==-

F

.e

.g.

resolution of the Palo Verde RCP problem. However, we will reserve our conclusions until the results of the testing and final resolution by the applicant are made available.

erry E. Jackson Equipment Qualification Branch Division of Engineering cc:

R. Vollmer D. Eisenhut R. Mattson T. Spets J. P. Knight T. Novak G. Knighton V. Noonan R. Bosnak U. Potapovs, Region IV P. Boehnert, ACRS G. Bagchi J. Jackson E. Licitra W. McNeill, Region IV es s.

W J

.,8-,

-,,,,,, -- a. e, m e

-, - ~ ~

lE i..

RECBVEu

.)

Arizona Public Service Compa57 P O. SOX 21666

PHOENIA. ARI2ONA 85036 i

IM3 DEC I4

' December 6,d9.h:33 a

ANPP-28363-BSK/KCP hEGIO!wy..

U. S. Nuclesr Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director, Division of Resident, I

Reactor Projects and Engineering Programs

Subject:

Time Extension for Report - DER 83-40 A 50.55(e) Potentially Reportable Condition Relating To Unit 1 LPSI and CS Pump Motors Have Defective Welds And Are Leaking 011.

Pile: 83-019-026; D.4.33.2 Ref erence:.i) Telephone Conversation between A. D'Angelo and R. Tucker on June 29, 1983.

3 (B) ANPP-27396, dated July 25, 1983 (Interim Report)

(C) ANPP-27962, dated October 5,1983 (Time Extension)

Dear. Sir:

The NRC was notified of a potentially reportable deficiency in Reference (A), an Interia Report was transmitted by Reference (B), and a Time Extension was requested by Reference (C). At that time, it was estimated that a Pinal Report would be available by December 6, 1983.

Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by January 6,1984, at which time a complete report will be submitted.

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

l Very truly yours, h.b On

%' M E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects Management ANPP Project Director

/

EEVBJr/KCP:ru ec: See Page 2 wero%w

Q Mr. T. W. Bishop DER 83-40 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. Fascacht 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. Fiore111 S. R. Frost J. Self D. Canady Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 P

l

..__.-..,~.--e-we m

p..

~.

,.--.-_..___.y

V.

14016

.f D'g UNIT ED STATES

[

NUCLEAR REGULATORY COMMISSION

-7

'. g h

.i CASHINGTON, C. C. 205S5 s...*

s 9

NOV 3 01%

MEMORANDUM FOR: Thomas M. Novak, Assistant Director for Licensing, DL

f.,

GeorgeW.Knighton, Chief,LicensingBranchNo.3,DL[

THRU:

FROM:

E. A. Licitra, Project Manager, Licensing Branch No. 3 DL

SUBJECT:

UPDATED STATUS ON PALO VERDE RCS PUMPS AND RELATED MATTERS On November 16, 1983, Chuck Ferguson, CE provided a telephone update on the status of the efforts for resolving the anonalies found at Palo Verde Unit I following hot functional testing. Also participating on the call were George Davis, CE and Bill Quinn, APS. The status is an update of the status provided at the October 12, 1983 meeting and is sucinarized as follows.

RCS Pumps Testing of the full scale prototype pump with the original design (baseline) has been completed at the CE Newington facility. Data is currently being processed and evaluated. Preliminary indications are that higher strains and accelerations occur in the area that is 180* from the discharae side of the pump. Also, the strains and accelerations do increase with increased flow br ken oi 100se bolts. So,mNe;ggsambled for design modifications,%tfan Af~er the pump was di there were no rates.

t

. M M tis 78 M h W M, 4 4IA M : Te F W ih M W dtf N M r

M T?

The prototype pump has been modified to incorporate the design changes (e larger gap size, more and longer bolts, cut-back of the diffuser vapes an IE backfiling of the impeller vanes) and testing of the pump was schedg3ed toi "d fi N

M start by 11/17/83 (actually started 11/19/83).

z<

E

-o Modifications to the Unit 1 pump internals is nearing completio on the Unit 2 parts is in progress. To expedite the work, surface trachini hole drilling and rcugh cutting are being performed at both Newington and w in a shop in Cleveland. Final machining is being done at Newington. Ship-ment of the modified Unit 1 parts to the Palo Verde site should be completed by 11/28/83.

Thermal Sleeves The four thermal sleeves from the cold legs have been removed from Unit I and the expansion groove has been ground out of three locations. Grinding of the last location is in progress.

NT070 Mb h /9

o i [

p o

Thermowells The vortex shedding testing of the modified themowell design at the Windsor facility has been completed. Data reduction is in progress. Additional testing of the design will be performed at the Newington pump facility while testing the modified pump design.

Modifications to Palo Verde Unit 1, to incorporate the modified thermowell design, are 801 complete.

CEA Shroud Assemblies Hydraulic testing and most of the mechanical testing of the model shroud components have been completed and the data are currently being reduced. An additional model test to induce crackino is scheduled to start shcrtly.

In addition, the Unit I shroud assembly had been shipped to Newington and testing of this was assembly to start shortly to compare results to those obtained via -

component testing.

After all the testing is complete, the results will be reviewed with APS to determine what should be done to correct the cracking problems encountered during hot functional testing at Unit 1.

Identification of the mods is tentatively scheduled for around the end of November 1983.

E. A. Licitra, Project Manager Licensing Branch No. 3 Division of' Licensing cc:

H. Denton D. Eisenhut R. Purple R. Vollmer R. Mattson T. Spels H. Thompson J. Funches F. Miraglia J. Knight V. Noonan R. Bosnak

8. Liaw G. Bagchi J. Jackson

5. Hou D. Tereo D. Sellers L. Dewey T. Bishop T. Young

% P. Narbut S. Fiore111 J. Weidenhamer

=

- -.. -.3

w n

'l EECEIVED 1()

(

f t:rc

.U g'

I,-

' y Arizona Public Service Company

\\

P O. boa 21666. PHOENIX, ARIZONA 85036 i

Nove$hbN9fy ID 59 s,_

.ANPP-28313-BSK/KCP REGIS! Mil!F s

U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5 M8

Attention: 'Mr.iT. W. Bishop, Director, Division of Resident, keactor Projects and Engineering Programs

,. Sobject:

Ilse Extens1An for Report -Ou 83-49

-s f

.A 50.55(e) Potentially Retortitle Condition Relating To

' Diffuser Bolts Broken / Loc'e In Reactor Coolant Pump File: 83-019-026; D.4.33.2

Reference:

- ( A) Telephone Conversation between P. Narbut and R. Tucker on July 15, 1983.

(S) ANPP-27593, dated August.19,1983'(.Interin Report)

Dear Sir:

The NRC was nottfled 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 November 29, 1983.

Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized.by January 27, 1984, at which' time a complete report will be submitted.

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

Very truly yours Ch oC l

E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects Management ANPP Project Director EEVBJr/KCParu l

cc: See Page 2 9

k h

aYOfb d4 As o

7

4 J

/

4, o

1 J

Mr. T. W. Bishop e'

DER 83-49 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 C'

D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiore111 S. R. Frost J. Self D. Canady Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 y_.,

y__7 m

,,_y

lM ji. I10 y

~

nsCem

'e(' ~

Arizona Public Service Company P.o. Box 21666 e PHOENIX, ARIZONA 85036 Novd@eM69-919E D ST:

,ANPP-28314-BSK/KCP REG!0mH U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director, Division of Resident, Reactor Projects and Engineering Programs

Subject:

Time Extension for Report @, @ f4 A 50.55(e) Potentially Reportable Condition Relating To Reactor Coolant Pump Has Broken Impeller Blade.

File: 83-019-026; D.4.33.2

Reference:

(A) Telephone Conversation between T. Young and R. Tucker on (B) 9kedAugust 19, 1983 (Interim Report)

Dear Sir:

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

At that time, it was estimated that a Final Report would be available by November 29, 1983.

Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by January 27, 1984, at which time a complete report will be submitted.

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

Very truly yours Ct_LA _

6 t.L(

l E. E. Van Brunt, Jr.

l APS Vice President, l

Nuclear Projects Management ANPP Project Director 1

l EEVBJr/KCP:ru cc: See Page 2 l

~

/ o/ B frdtG,

~

O A/

i

Mr. T. W. Bishop f

DER 83-50 i

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 C-G. A. Fiore111 L. E. Vorderbrueggen S. R. Frost J. Self D. Canady Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 l

Atlanta, Georgia 30339 l

l i

i

I

.c ~

Arizona Public Service Company 0

P.o. Box 21666 e PHOENIX, ARIZONA 85036 November 9, 1983

ANPP-28211-BSK/KCP U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director, Division of Resident, Reactor Projects and Engineering Programs

Subject:

Time Extension for Report - DER 83-55 A 50.55(e) Potentially Reportable Condition Relating To Missing Thermal Liner in Safety Injection System Line.

File: 83-019-026; D.4.33.2 Ref erence: ( A) Telephone Conversation between P. Narbut and R. Tucker on August 1, 1983 (B) ANPP-27604, dated August 22, 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 November 9, 1983.

Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by January 26, 1984, at l

which time a complete report will be submitted.

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

Very truly ours

(

h l

E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects Management ANPP Project Director EEV5Jr/KCP:ru

'8*

29 0 Wd 81l.04CC9 OWN MS O o w.

n

-n

- u ]Il

(,_,D DL D (5 ' -

-dd dd

=

~.

Mr. T. W. Bishop DER 8}-55 Page 2 cc:

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

C. 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. Eingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson

[

L. E. Vorderbrueggen G. A. Fiore111 s

S. R. Frost J. Self D. Canady Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 l

l d'

-*--w

.m

,e M Ms

a l>

~

3.,

p

(...

Arizona Public Service Company P O. SOX 21666

PHOENIX. ARIZONA 85036 October 27, 1983 ANPP-28119-BSK/RQT U. S. Nuclear Reguintory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director, Division of Resident, Reactor Projects and Engineering Programs

Subject:

Time Extension for Report - DER 83-39 A 50.55(e) Potentially Reportable Condition Relating To Rejectable Indications on C-E Supplied Unit 1 Reactor Coolant Pump 1A File: 83-019-026; D.4.33.2

Reference:

(A) Telephone Conversation between A. D'Angelo and R. Tucker on July 1, 1983 (B) ANPP-27471, dated August 1,1983 (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 October 27, 1983.

Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by December 30,1983, at which time a complete report will be submitted.

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

(

Very truly y s,

r

(

CM m LLL E. E. Van Brunt, Jr.

APS Vice President.

Nuclear Projects Management ANPP Project Director EEVBJr/RQTaru cc: See Attached Page 2

4

'/ '

Mr. T. W. Bishop

(

DER 33-39 Fase 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. Flore111 S. R. Frost J. Self D. Canady Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite.1500 Atlanta, Georgia 30339 l

I l

I

~

l 25{

p:n ?S l.y 1

Arizona Public Service Company

/.)y. g8

,81 P.o. Box 21666

PHOENIX. ARI2oNA 85036 October 26, 1983 53;fy" ANPP-28093-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. T. W. Bishop Director, Division of Resident, Reactor Projects and Engineering Programs

Subject:

Time Extension for Report

,ast SF57 A 50.55(e) Potentially Reportable Condition Relating To Cracks In The Control Element Assembly Shroud File: 83-019-026; D.'. 33.2

Reference:

(A) Telephone Conversation between P. Johnson and R. Tucker on July 29, 1983 (B) ANPP-27598, dated August 29,1983 (Interim Report)

Dear Sir:

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

At that time, it was estimated that a Final Report would be available by October 27, 1983.

Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by March 9, 1984, at which time a complete report will be submitted.

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

Vary truly yours,

~

P S.

au b

E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects Management ANPP Project Director l

REVBJr/RQTaru f

I cc: See Attached Page 2 On

%)((0/()bff JJ$

=

D

']?!/ra.

o Arizona Public Service Compailf? m y! [/*

/,

P.o. sox 21666

PHOENIX. ARIZONA 85036

~

October 24, 1983 ANPP-28073-BSK/RQT U. S. Nuclear Regulatory Conmission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director, Division of Resident, Reactor Projects and Engineering Programs

Subject:

Interim Report ~. DER 83-62 A 50.55(e) Potentially Reportable Deficiency Relating to Core Support Barrel Snubbers Have Loose Or Missing Cap Screw Retainer Pins.

File:

83-019-026; D.4.33.2

Reference:

Telephone Conversation between P.'Narbut and R. Tucker on September 19, 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 February 28, 1984, at which time a complete report will be submitted.

Very truly yours, CLU,_

qLL E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects Management ANPP Project Director EEVB/RQTaru Attachment i

cc See Page 'Aro C-0 1/0705 &

M

, n-g Mr. T. W. Bishop DER 83-62 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 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. Fiore111 S. R. Frost J. Self D. Canady Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 i

i l

l*

l l

ww r-y--c-w--wgy++,p6 4

.en..WD

--w.

. ~,, - - -

x.,

,,,m.

e a

o

(

\\.

INTERIM REPORT - DER 83-62

~ ' '

POTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNIT 1 1.

Potential Problem Post hot functional testing inspection of the inside of Unit 1 Reactor Vessel revealed that core support barrel snubbers had loose or missing cap screw retainer pins. The snubber locations were identified as O degree azimuth 50 degree azimuth and 180 degree azimuth.

II.

Approach To and Status of Proposed Resolution Bechtel engineering is corrsponding with C-E to provide reportability :nd 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 February 28, 1984.

l I

2V Arizona Public Service Company PO. Box 21666 e PHOENIX. ARIZONA 85036 October 13, 1983 ANPP-28001-RQT/BSK U.S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director, Division of Resident, Reactor Projects and Engineering Programs

Subject:

Interim Report -tG M 'S F61 A 50.55(e) Potentially Reportable Deficiency Relating to Unit 1 LPSI Pumps Pailed To Start And Don't Produce The Required Head File.: 33-019-026, D.4.33.2 Ref erence: Telephone Conversation between P. Johnson and R. Tucker on September 14, 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 gfinalizea-by January 26, 1984, at which time a complete report will be

. submitted.

~*

Very truly yours, N'

E R

A LQ <

E. E. Van Brunt, Jr.

~

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

)hOh{0~h --

u

ANPP-28001

,[

U. S. Nuclear Regulatory Commission

\\

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

.-,._,.,,,,_,..-,_-.,_-.v.-.-_.--

l y

INTERIM REPORT - DER 83-61 POTENTIAL REPORTABLE DEFICIENCY r

ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNIT 1 i

I.

Potential Problem LPSI pump 'B' (INSIBP01) has failed to start on three different occasions and has been disassembled and inspected under Ingersol-Rand supervision on each occasion. Project DER 83-21 was previously issued and dispositioned in regard to this condition.

DER 83-61 was initiated as a result of NCR SM-2156 which documents that LPSI pump

'B' has again failed to start as required by the operability requirements specified in the perchase specification.

NCR SM-2756 documents that during Preoperational Test 91PE-1SI-8 the Low Pressure Safety Injection (LPSI) Pump, IMSIAP01, had actual Total Head of 315 ft. compared to the required 335 ft.

NCR SM-2757 documents that during Preoperational Test 91PE-1SIO8 the Low Pressure Safety Injection (LPSI) Pump, IMSIBP01, had an actual Total Head of 297.7 f t. compared to the required 335 f t.

II.

Approach To and Status of Proposed Resolution Bechtel engineering has received correspondence from C-E

,(V-C' -18979) providing disposition and technical justification for n

corrective action concerning Unit 1 LPSI pumps. However, recent testing on Unit 2 revealed LPSI pump "A" has experienced similar re-starting problems as Unit 1 LPSI pump "B".

Based on this new condition, DER 83-61 will be revised and an extension of time is requested for investigation of the LPSI pump problem.

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 January 26, 1984.

.ma.mm-.

1 Arizona Public Service Company a

Po sox 21666 e PHOENIX. ARI2oNA 85036 October 13, 1983 ANPP-28009-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. T. W. Bishop, Director, Division of Resident, Reactor Projects and Engtneering Programs

Subject:

Time Extension for Report DER 83 A 50.55(e) Potentially Reportable Condition Relating To Washers Found In Unit 1 Steam Generator #1 And #2 File 83-019-026; D.4.33.2 Ref erence: (A) Telephone Conversation between P. Narbut and R. Tucker on August 2, 1983 (B) ANPP-27603, dated August 22, 1983 (Interin 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 Pinal Report would be available by October 13, 1983.

Due to the extensive investigation and evaluation required, it is now atxpected that this information will be finalized by December 15,1983, at which time a complete report will be suhaitted.

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

Very truly yours,

\\

i

? 2.kte%E&_

E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects Management ANPP Project Director EEVBJr/RQTien ce: See Attached Page 2 q7, l'aj ( -

2 M]

f5

.lj

/

,, l f

(!

o b

e Mr. D. M. Sternberg

('

DER 83-54 1

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

ML20090L302

Text

Subject:

Dear Mr. Van Brunt:

Subject:

Reference:

Dear Sir:

Subject:

Subject:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Dear Sir:

Enclosure:

SUBJECT:

Contact:

Subject:

Dear. Sir:

SUBJECT:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Reference:

Dear Sir:

Subject:

Dear Sir:

Subject:

Dear Sir:

Navigation menu

Search