ML20099H692

Affidavit of Cv Vo Re Improper Cold Pulling & Misalignment of Steam Generator Feedwater Pump & Util Mishandling of Efforts to Identify & Properly Correct Nonconformance. Certificate of Svc Encl.Related Correspondence

ML20099H692
Person / Time
Site:	Harris
Issue date:	11/21/1984
From:	Vo C GOVERNMENT ACCOUNTABILITY PROJECT
To:
References
CON-#484-313 OL, NUDOCS 8411280260
Download: ML20099H692 (11)

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RELATED 00Rff ESPONDENCE h-h AFFIDAVIT

• p My name is Chan Van Vo.

IamalsoknownasVanVoDav$y am giving this AIO-to Robert Guild Attorney-at-Law, of Charleston, South Carol 7oina, who statement 1)P.

has identified himself to me as a representative of the Government! Accountability Proj ect.

I have been asked to provide further information to the Atomic Safety and Licensing Board of the Nuclear Regulatory Commission about the significance of the improper cold pulling and misalignment of the Steam Generator Feed Water Pump; and CP&L's mishandling of my efforts to identify and properly correct this nonconformance.

2.

I repeat my professional opinion expressed in my October 6, 1984, Affidavit that the effective function of these pumps, valves and piping are nuclear safety significant. At the time I attempted to document the deficient fit-up of the Feed Water piping and the resultant stress-induced misalignment of the pump in August 1982 -- and during the entire course of construction of the Harris Plant until then-- the Feed Water system, its piping, pipes'upports, valves and pun.ps, were classified by the Architects / Engineers, Ebasco Services, Inc., by CP&L, and by their contractors as " Safety Class 4/ Seismic Class I,"

acknowledgement of its nuclear safety significance. This classification an applied to the Feed Water system in the Harris Turbine Building. Conformance to the Commission's 10 CFR Part 50, Appendix B, Quality Assurance Criteria such as detailed inspection and documentation were required for the Feed Water system.

3.

7 After several years of serious problems in the design, fabrication, installation, and inspection of piping and associated components in the Turbine l

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, Building at the Harris Plant, CP&L faced the prospect of performing extensive and costly rework including necessary inspections and documentation as required by the NRC's QA regulations.

Instead of seeing that the job was done right--

by the same standards that cven CP&L had committed to honor-- CP&L sought to circumvent quality standards and thereby " alleviate all concerns related to the additional inspection and documentation requirements for the supports in the Turbine Building," by attempting to "de-classify" the Feed Water and Main Steam systems inside the Turbine Building.

4.

In my opinion such attempts by CP&L Engineers Ed Willett and Alex Fuller to "de-classify" these important systems simply represent efforts to cover-up their own shoddy work; as did their responses to my attempt to document and correct the Feed Water Pump misalignment.

5.

Even the limited documentation available to me now supports my position.

j For Example, I attach as Exhibit 1 Work Directive No. 2836, dated 7/13/83, for Turbine Building Feed Water pipe support T-3-261-1-FW-H-11, which reflects this "de-classification" of the Feed Water hangers in the Turbine Building: ".

this hanger is considered non-seismic and will require no CI or QC involvement or acceptance." This Work Directive cites generic Field Change Request FCR-H-1145,

" Reclassification of MS & FW Supports in the Turbine Building." Revisions 0 and 1 reflect site approval by Ed Willett on 1/14/83 and Alex Fuller on 5/13/83, res-pectively. They are Exhibits 2 and 3 attached.

These generic FCRs rely on a November 12, 1982, Ebasco letter, EB-C-14332, 1

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. Exhibit 4, f or authority to " reclassify the mainsteam and feedwater pipe supports and the main steam piping, in the turbine building. These items are to be non-seismic, in accordance with letter EB-C-14332." No mention is made of the Feed Water piping lines themselves in the FCRs, since the Ebasco letter expressly excepts the Feed Water piping from de-classification: "Please note that the generic FCR should also cover the feedwater cupports in the Turbine Building. From the inspection and documentation aspects, these supports can be handled as B31.1 non-seismic, however, the lines will not be declassified to non-seismic." Thus, even long af ter my observation of the improper fit-up of the Feed Water pipe-to-pump connection, the Feed Water piping line remained Seismic Class I-requiring Quality Assurance program compliance. The Bergen-Patterson drawing for pipe-FW-H-11. Exhibit 5, dated S/27/83, continues to reflect " Safety Class 4/

support Seismic Class 1" for this hanger.

6.

1 continue to question the validity of CP&L's attempts to solve their problems of shoddy work at the Harris Plant through such "de-classification" of quality requirements. The nonconformance I observed was a violation of such quality requirements applicable at the time they were violated. My concerns should have been investigated and documented properly at the time by my management.

They were not.

Neither "de-classification" of defective work nor discarding employee complaints will make the Shearon Harris Nuclear Power Plant safe.

I only hope that this NRC Licensing Board will.

SWORN to and subscribed before me Chan Van Vo t h i s. ',,

day of November, 1984.

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EsAsco esRvicas INCORFORATED cuoSCO Two woria rraos ccier New Yort NY 10048 EB-C 14332 File: 5Q-H-2 5-S-11 Mr L I Loflin, Manager r_. 4==ering - Barris Plant Carolina Power sad Light Company F 0 Box 101 New Mill, North Carolina 27562.

SUBJECT:

SEEARON BARRIS NUCLEAR POWER PLANT ANALYSIS OF MAIN STEAM LDIES SMS2-144 TEROUGH 150

Reference:

CE-13476 We have reviewed your request for deletion of snubbers associated with the subject lines and wish to offer the following for your consideration.

The EB-B-241 correspondence provided a criteria for support loads which assure a satisfactory seismic design. The snubbers in question cannot be replaced with rigid restraints without thermelly overstressing the pipe during plant normal cperation.

It is noted that any snubbers located in the Turbine Building will be reviewed and deleted if the criteria for design of anchors at seismic /non-seismic inter-faces are not violated.

Regarding the subject lines, portions of the lines inside the Turbine Building do not have to be seismically designed. As discussed with your Mr G White, the most cfficient way to reflect this change is to have CF&L prepara a generic FCR which would request Ebasco to "de-classify" all MS lines / portions of lines inside the Turbir.e Buildin's to B31.1, abn-seismic lines.

Due to the large scope of these lines (auch broader than SMS2-143 through 150 as indicated in your letter) the disposition cf this change through a line and valve list would be too extensive.

In our opinion this generic FCR will alleviate all concerns related to the additional inspection and documentation requirements for the supports in the Turbine Building.

The only 1

exception to this generic approach are the major Main Stesa lines from the interface ancho: to the turbine stop valve (44" lines).

The declassification of these lines will be handled through a formal revit: ion to the line list and other design documents i

including the FSAR. This is highlighted in our reply to your CE 13502 letter.

Please note that the generic FCR should also cover the feedvater supports in the Turbine Building.

From the inspection and documentation aspects, these supports can be handled as 531.1, non-seienic, however, the lines will not be declassified to non-seismic.

This is due to the fact that the interface anchors were not designed fcr the seismic /non-seismic load criteria.

Please provide us with the aforementimed FCR as soon as possible.

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22 ANALYSIS OF MAIN STEAM LINES 5MS2-144 M OUGH 150.

If you have any questions, please call us.

Very truly yours, ia er R K Matzelle Froject Manager PF:amb cc:

L I Loflin J J Sheppard L E Martin J L Willis R M Parsons Sheldon D Smith G L Forahand N J N aa51 i

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UNITED STATES OF AMERICA NUCLFAR RK,UIATORY ColEISSION In the matter of CAROLI!;A POWER k LIGHT CO. Et al. )

Docket 50-400 Shearon Harris Nuclear Power Plant. Unit 1-

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CE!!TIFICATEOF SERVICE Signed and Notarized Chan Van Vo I hereby certify that copies of

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HAVE been served this day of "

198 by deposit in the US Mail, first-class postage prepaid, upon all parties whose names are listed below, except those whose nanes are marked with an asterisk, for when service was accomplished by co,v of unstened affidavit nailed out by John Runkle this date.

Any narty wishing a signed copy can obtain one on request fron ne.

Judges James Kelley, Glenn Bright and bar.ae Caynter (1 egy each)

Atomic Safety and Licensirg Board US Nuclear Regulatory Connission Washington DC 20555 George F. Trowbridge (attorney for Applicants)

Shaw, Pittman, Potts & Trowbridge 4 R uthanne G. Miller 1600 M St. NW ASLB Panel WashinEton, DC 20036 USNRC Washington DC 2055 5 YSpence W. Perry O{aI [ cst.sw" Office of the Executive Legal Director Attn Docke ts 50-400/k010 L.

l C d Washingt n DC 20740 Wa ngton DC 20555 Docketing and Service Section (3x)

-KDan Read CEA!LT/FLP

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Attn Docke ts 50-k00/h01 0 L.

Waleigh,9 07 Waveross NC 27606 Office of the Secretary USNRC afashington DC 20555 (oev.LindaW.Little Dr ernor's Waste Mst. Bd.

3 (E plan only) 513 Albemarle B1dg.

John Runkle S*. eve 90chlais 325 N. salisbu n St.

CCNC FEMA-Suite 700 M

307 Granville Rd 137.1 Peachtree St.NE 'aleigh, NC 27611 Chapel Hill Ne 2751h Atlanta nA 30309 B

9 radley W. Jones

-tTravi s Payne dRobert Gruber USNRC Region II Exec. Director 101 Marietta St.

Edelstein & Payne Public Staff Atlanta GA 30303 Blex 12601 Box 991 Raleigh NC 27605 Raleigh NC 27602 9 Richard Wilson, M.D.

Certified by h

729 Hunter St.

Apex NC 27502

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