ML20099H561

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Forwards Draft Affidavit of V Vo & Five Exhibits Which Show Feedwater Sys in Turbine Bldg Classed as Safety Class 4/ Seismic Class 1 at Time of Problem in Aug 1982,per 841115 Request.Certificate of Svc Encl
ML20099H561
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 11/25/1984
From: Runkle J
CONSERVATION COUNCIL OF NORTH CAROLINA
To: Bright G, Carpenter J, Kelley J
Atomic Safety and Licensing Board Panel
References
CON-#484-311 OL, NUDOCS 8411280200
Download: ML20099H561 (13)


Text

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_e THE CONSERVATION COUNCIL OF NORTH CAROLINX""

307 Grenville Road, Chapel Hill, N.C. 27514 '84 f$ 27 g g)

(919) 942 7935 or 9421080 (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

November 25.1984~iah.

ad A rg o James L. Kelley Glenn O. Bright Dr. James H. Carpenter Atomic Safety and Licensing Board Nuclear Regulatory Commission Washington, D.C. 20555 Re: Shearon Harris Nuclear Power Plant (Docket 50-400 OL)

Dear Sirs:

As requested at the hearing in Raleigh on November 15, I am supplying an affidavit in support of the Conservation Council's Contention WB-2 which addressed the " safety significance" of the feedwater pump and system.

As you will notice, the affidavit has not been signed by Mr. Van Vo.

This is a draft affidavit although it is my understanding from Mr. Van Vo's attorney, Mr. Guild, that Mr. Van Vo has lead and approved it. He is sending me a signed and verified original. I unfortunately will not be available next week as I have a hearing down in Jacksonville, NC. I have asked Mr.

Eddleman to send copies of the signed afildavit if it is sent to my office before I return.

Attached to the draf t affidavit are five exhibits which show that the feedwater system in the turbine building was classed as " Safety Class 4/ Seismic Class 1" at the time of the problem in August of 1982. Part of the sytem was latter "de-classified," although the feedwater piping itself has apparently not been. The af fidavit and exhibits supply adequate basis for the contention.

Thank you for allowing us the opportunity to submit this affidavit in support of our contention.

Sincerely, John Runkle General Counsel

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! cc. Service List l Robert Guild, Attorney for Chan Van Vo O

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CERTIFICATE OF SERVICE I hereby certify that copies of the Conservation Council's Affidavit of Chan Van Vo and Exhibits were served upon the following by deposit in the U. S. Mail, postage prepaid, or by hand delivery.

James L. Kelley Robert Gruber Atomic Safety and Licensing Board Public Staff, Utilities Commission US Nuclear Regulatory Commission PO Box 991 Washington, D.C. 20555- Raleigh, NC 27602 Glenn O. Bright Dr. Linda Little same address Governor's Waste Management Board 325 N. Salisbury St., Room 513 Dr. James H. Carpenter Raleigh, NC 27611 same address Thomas Baxter Docketing and Service (3 cc.) Shaw, Pittman, Potts & Trowbridge Office of the Secretary 1800 M Street, N.W.

US Nuclear Regulatory Commission Washington, D.C. 20036 Washington, D.C. 20555 Charles A. Barth Office of the Executive Legal Director US Nuclear Regulatory Commission a Washington, D.C. 20555 V

Daniel F. Read John Runkle PO Box 2151 Conservation Council of NC Raleigh, NC 27602 307 Granville Road Chapel Hill, NC 27514 M. Travis Payne PO Box 12643 g Raleigh, NC 27605 Thisisthe$3JthdayofNovember, 1984.

Dr. Richard D. Wilson 729 Hunter Street Apex, NC 27502 Wells Eddleman 718-A Iredell Street Durham, NC 27705 Bradley W. Jones '

US NRC--Region 11 101 Marrietta Street Atlanta, GA 30303 I i

Richard E. Jones l Vice President--CP&L PO Box 1551 i Raleigh, NC 27602 i

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DRAFT AFFIDAVIT My name is Chan Van Vo. I an also known as Van Vo Davis. I am giring this ctatement to Robert Guild, Attorney-at-Law, of Charleston, South Carolina, who 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 cnd Licensing Board of the Nuclear Regulatory Commission about the significance cf 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 l cf the pump in August 1982 - and during the entire course of construction of the Harris Plant until then-- the Feed Water system, its piping, pipesupports, valves and pumps, were classified by the Architects / Engineers Ebasco Services, Inc., by CP&L, and by their contractors as " Safety Class 4/ Seismic Class I,"

cn acknowledgement of its nuclear safety significance. This classification cpplied to the Feed Water system in the Harris Turbine Building. Conformance to the Coimaission's 10 CFR Part 50, Appendix B, Quality Assurance Criteria such i

cs detailed inspection and documentation were required for the Feed Water system.

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

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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 even CP&L had committed to honor-- CP&L sought to circumvent quality standards and thereby " alleviate all concerns related to the cdditional inspection and documentation requirements for the supports in the Turbine Building," by attempting to "de-classify" the Feed Water and Main Steam cystems 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 c ver-up their own shoddy work; as did their responses to my attempt to document cnd correct the Feed Water Pump misalignment.
5. Even the limited documentation available to me now supports my position.

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 h:nger is considered non-seismic and will require no CI or QC involvement or ccceptance." This Work Dircctive 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-p:ctively. They are Exhibits 2 and 3, attached.

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

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Exhibit 4. for authority to " reclassify the mainsteam and feedwater pipe supports and the usin steam piping, in the turbine building. These items are to be nor. 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 supports 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 after my observation of the improper fit-up of the Feed Water pipe-to- i l

pump connection, the Feed Water piping line remained Seismic Class I- requiring Quality Assursace program compliance. The Bergen- Patterson drawing for pipe-support FW-H-11. Exhibit 5. dated 5/27/83, continues to reflect " Safety Class 4/

Seismic Class I" for this hanger.

6. I 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 this day of November. 1984.

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usisco ssRvices INCORPORATED . c EuO Two woria nace Center New Yoru. N Y.10048 EB-C 14332 File: SQ-H-2 5-S-11 Mr L I Loflin, Manager Engineering - Harris Plant .

Carolina Power and Light Company P O Bdx 101 )

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Dear Mr Loflin:

SUBJECT:

SHEARON HARRIS NUCLEAR POWER PLANT ANALYSIS OF MAIN STEAM LINES SMS2-144 THROUGH 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 o satisfactory seismic design. The snubbers in question cannot be replaced with rigid restraints without thermally overstressing the pipe during plant normal h 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 CP&L prepare a generic FCR which would request Ebasco to "de-classify" all MS lines / portions of lines inside the Turbine Building to B31.1, non-seismic lines. Due to the large scope of these lines (such broader than 5MS2-143 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 conc.orns related to the additional inspection and documentation requirements for the supports in the Turbine Building. The only exception to this generic approach are the major Main Steam lines from the interface anchor to the turbine stop valve (44" lines). The declassification of these lines I will be handled through a formal revision to the line list and other design documents 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 B31.1, non-seismic, however, the lines will not be declassified l 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 aforementi>ned FCR as soon as possible.

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