ML20148P643

QA Program Insp Rept 99900080/80-02 on 801027-29.No Noncompliance Noted.Major Areas Inspected:Implementation of 10CFR50,App B & Followup on 10CFR50.55e Rept Re Weight Discrepancies in Valves for Sequoyah Units 1 & 2

ML20148P643
Person / Time
Site:	Sequoyah
Issue date:	11/21/1980
From:	Barnes I, Oller R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20148P640	List: ML20148P636 ML20148P643
References
REF-QA-99900080 NUDOCS 8101150395
Download: ML20148P643 (6)

Text

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O 10.5. NUCLEAR GGUUTORY COMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION IV Report No.. 99900080/80-02 Program No. 51300 Company: Copes Vulcan Incorporated Post Office Box '577 Lake City, Dennsylvania 16423 Inspection' Conducted: October 27-29, 1980 Inspector: I8% n-2<-Po f R. E. Oller, Contractor Inspector Date ComponentsSection II Vendor Inspection Branch Approved by: I8w // - t <- Fo I. Barnes, Chief .0 ate .

ComponentsSection II i Vendor Inspection Branch '

Summary

'l Inspection on October 27-29, 1980 (99900080/80-02) -

Areas Inscected: Implementation of 10 CFR 50, Appendix B, and other NRC  !

requirements with respect to followup on a 10 CFR 50.55(e) Report by TVA con- l cerning weight discrepancies in valves for Sequoyah Units 1 and 2. The inspection involved 14 inspector-hours on site.

Results: In the area inspected, no noncompliance items, deviations or unresolved items were identified.

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2 DETAILS SECTION A. Persons Contacted P; Peoples, President

• J. Baker, Vice President - Engineering

'J.-Clifford, Sales Engineer

• R.-Lawson, Director . Engineering N._Mattson, Manager - Contract. Engineering - Valves

• 0. Mays, Manager - Quality Control

• Attended the Exit Meeting.

B. Followuo on 10 CFR 50.55(e) Report by TVA. Concerning Two (2) Air Ooerated Cooes vulcan Valves Furnisned oy Westingnouse For secuoyan Units 1 and 2

1. Introduction On January 1, 1980, by telephone report and on February 11, 1980, by written report, the NRC was notified by Tennessee Valley Authority pursuant to 10 CFR 50.55(e) that two (2) air operated Copes Vulcan valves (Unit Tag No. 2-IA78 RE Location 9967 and 9985) were supplied by Westinghouse for Sequoyah Units 1 and 2. The valve weights were specified on the Copes Vulcan drawings as 240 pounds, whereas the actual weight was approximately 405 pounds. The erroneous valve weight could therefore have resulted in installed supports which could be inadequate to perform their required safety functions.

Corrective action was accomplished by rerun of the piping system load analysis using the correct valve weight.- The resulting new loads'were then applied in support calculations and the existing supports were found to be adequate.

A' prior NRC followup inspection of this-matter was performed by" '

the Vendor Inspection Branch in August, 1980. It was later deter-mined that additional information was needed concerning other CVI customer valve contracts specifications requirements for valve weight criteria and potential valve. weight aiscrepancies.

2. Objectives The objectives of this inspection were to ascertain whether or not valve weight criteria for other CVI customers were specified, and j whether or not CVI met- the requirements; also to determine if -1 potential valve weight discrepancies, similar to those for Westinghouse Sequoyah valves, could exist.

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3. Method of Accomolishment The prec'eding objectives were accomplished by:

a. Discussions with cognizant CVI personnel-,

b. Review of CVI's Nuclear Contract Log Book for the period of 1969 through October', 1980, to identify nuclear valve customer's con-tracts.

c. Review of- the following five'(5) nuclear valve purchase specifi-cations and related CVI valve-assembly drawings, to determine what requirements for valve weights, if any, were imposed on CVI, and what valve weights were supplied by CVI.

(1) CVI Contract No. 95327 (a) Soecification:

Bechtel Specification No. 7220-J-255(Q), Revision 0, dated 12/14/73, Design Specification For Purchase of Nuclear Service Valves For Midland Units 1 and 2.

(b) CVI Orawings For Midland 1 and 2 (1) No. B-170032, Revision 5, Model-0-100-60 Actuator, 1" Class 1500 Standard Valve Assembly, ASME Code Class 2. (Total dry weight is 200 lbs. Aoproximately).

(2) No. B-170031, Revision 5, Model 0-100-60 Actuator, 2" Class 150 ASME Standard Valve Assembly, ASME Code Class 3. (Total dry weight is 350 lbs. Approximately).

(2) CVI Contract No. 95225 (a) Specification Babcock & Wilcox Specification No. 08-114000001-06, for cor. tract 620-0017, dated 12-1-71, " Control Valves For Auxiliary System Service, North Anna Unit 3," Virginia Electric & Power Company.

(b) CVI Orawing For North Anna Unit 3 (1) NO. L-163986, Revision 4, Model D-100-60 Actuator, 1h" -1500 lb. ANSI standard val e, dated 3-12-73 ASME Class 3 (Total dry weight is 350 lbs. : 10%).

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(2) No. L-163988, Revision 6, dated 3-12-73, Model 0-100-100 Actuator, 2" -1500 lb., ANSI Standard  :

l Valve Assembly, ASME Class 2 (Total dry weight is {

390 lbs. ; 10%). 'l (3) No. L-163985,- Revision 3, dated 3-12-73, Model 0-100-60 Actuator, 2 " -150 lb. ANSI Standard l Valve Assembly, ASME Class 3 (Total dry weight 1 is 230 lbs. ! 10%).  ;

(3) CVI Contract No. 95096 j i

(a) Soecification 1 Stone & Webster Specification, revised 6-15-80, for Main Steam Atmospheric Oump Valves, Beaver Valley No. 1, Duquesne Light Company.

(b) CVI-Orawing For Beaver Vallay No. 1 No. B-145770, Revision 2, Model 0-100-160-3 Actuator, 6" - 600 lbs. ANSI Standard Valve Assembly, Tandem Trim. (Approximate total valve weight is 700 lbs. )

(4) CVI Contract No. 95325 (a) Soecification Combustion Engineering Specification No.13172-PE-703, Steam Dump and Turbine Bypass Valves, St. Lucie Unit No. 2.

(b) CVI Drawing For St. Lucie No. 2 , ,

No. B-166439, Revision 9, Model 0-100-160 Actuator, 10" ' lass 600, ANSI Standard Valve Assemoly, Tandem-Te ,pproximate total valve weight is 2000 lbs.)

(5) CVI Con, act No. 95358 (a) Soecification Stone & Webster No. 5H1-318, Revision 0, dated 2-12-75, for Air Operated Control Valves, ASME Section III, Class )

i 2 and 3, Shorenam Unit No. 1, Long Island Lighting i Comoany.

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b. CVI Drawings For Shoreham No. 1 '

(1). No. E-175701, Revision 2, Model D-100-60 Actuator, 3" Class 1500 Valve Assembly, ASME III, Class 3 (Dry weight for valve and actuator is 350 lbs.)

(2) No. E-174780, Revision 2, dated 6-4-76, Model D-100-160 Actuator, 8" Class 900 Valve Assembly, ASME Section III, Class 2. (Dry weight for valve and actuator is 1285 lbs.)

(3) No. E-175695, Revision 2, dated 6-4-76, Model D-100-160 Actuator, 4" Class 900-Valve Assembly, ASME Section III, Class 3 (Dry weight for valve and actuator is 575 lbs.)

3. Findings,

a. Within this area of the inspection, no noncompliance items, deviations or unresolved items were identified.

b. Other Findings - Comments As a result of review of records and discussions with cognizant CVI personnel, the following information was obtained:

(1) The five contract specifications reviewed were selected by first reviewing CVI's Nuclear Valve Contract Log Book for the period of 1969 through October, 1980. All Westinghouse Q) contracts were excluded, as the previous NRC inspection nad established that W was aware of the valve weight discrepancy condition and was pursuing the matter.

(2) The five specifications were' selected at random to be reviewed for evidence of valve weight requirements. In two cases, estimated valve weignts were required in the Bid Request document, but not in the awarded purchase specification. In another case, the valve specification contained valve data sheets whicn listed the approximate required valve weignts.

The other two specifications did not specify the valve weight requirements. The CVI Director - Engineering indicated that these requirements could have been received verbally or by documented means other than in the specification, and that these records were not retained.

(3) Review of the CVI valve assemoly drawings for valves furnisned in the above five contracts verified that, in all cases, CVI had furnished total calculated valve weignts and total valve centers of gravity to either accroximate or + 10% weignts, and thus had met their customer requirements.

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i (4) With regard to CVI nuclear valve customers other than W, Gilbert l Associates, and Flcrida Power & Light identified in the previous j NRC' Inspection Report No. 99900C80/80-01, the CVI Director - '

Engineering indicated that CVI had not received any requests

'for recalculated valve weights. He also indicated that.CVI had.not notified previous customers of the potential for valve weight discrepancies as W had not indicated that this condition was a reportable item. This matter was discussed in the exit meeting.

(5)- The results of this inspection indicate that the same CVI -l calculational techniques, which predicteo a significantly different weight from actual for the two TVA Sequoyah Unit 1 and 2 valves, were used for the five contracts covered  ;

by this inspection. It would thus appear, that a potential exists for discrepancies between actual CVI valve weights and the valves furnished to their customers, for all nuclear contracts shipped prior to the CVI and 'f discussion I of the condition early in 1980. I C. Exit Interview

1. The NRC inspector met with CVI management personnel denoted in para-graph A, at the conclusion of the inspection on Octooer 28, 1980. ,

2. The following subjects were discussed:

a. Area of inspection.

b. The inspection findings identified in the report.

3. The inspector indicated that CVI should consider the possible need for CVI to notify all of their previous customers of the potential ,

for valve weight discrepancies, excluding these customers who had contacted CVI on this matter' .

4 CVI's management questions related to clarification of the above

-matters.

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