ML20108A228

Response to Late Filed Contentions of W Eddleman & Conservation Council of North Carolina Based on Cv Vo Affidavit.Contentions WB-1-2 & 41C-414H Should Be Rejected. Certificate of Svc Encl

ML20108A228
Person / Time
Site:	Harris
Issue date:	11/13/1984
From:	Oneill J CAROLINA POWER & LIGHT CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To:	Atomic Safety and Licensing Board Panel
References
CON-#484-120 OL, NUDOCS 8411140504
Download: ML20108A228 (200)

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'84 f5714 A11:13 November.13, 1984 13; ~l UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD-In'the Matter of )

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CAROLINA POWER & LIGHT- ) Docket No. 50-400 OL COMPANY and NORTH CAROLINA )

EASTERN MUNICIPAL POWER AGENCY)

)

(Shearon Harris Nuclear )

Power Plant) )

APPLICANTS' RESPONSE TO LATE-FILED CONTENTIONS OF WELLS EDDLEMAN AND CONSERVATION COUNCIL OF NORTH CAROLINA BASED ON THE AFFIDAVIT OF MR. CHAN VAN VO i

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, TABLE OF CONTENTS Page I. Introduction............................................ 1 II. Background on the Van TA) Affidavit...................... 3 III. Standards Governing Late-Filed Contentions.............. 5 IV. Application of the Standards........................... 11 A. The Eddleman Late-Filed Contentions Are Overly Broad.................................. 11 '

B. The Van Vo Affidavit Has Been Demon-strated To Be Factually Inaccurate And Unreliable and Cannot Serve As The Basis For A Contention........................ 13 C. Mr. Eddleman And CCNC Have Failed To Sustain Their Burden In Addressing The Five Lateness Factors......................... 17 Factor (1): Good Cause For Failure to' File on Time...................................... 17 Factors (ii) and (iv): The Availability of Other Means Whereby Petitioner's Interest Will Be Protected; and the Extent to Which Petitioner's Interest Will Be Represented by Existing Parties........... 19 Factor (iii): The Extent to Which the Petitioner's Participation May Reasonably Be Expected to Assist in Developing a Sound Record...................................... 20 Factor (v): The Extent to Which the Petitioner's Participation Will Br,Aden the Issues or Delay the Proceeding................ 23 D. The Late-Filed Contentions Fail to State Litigable Issues With The Requisite Basis and Specificity............................. 24-CCNC WB-1; Eddleman 41C, 41D and 41E (Pipe Hanger Material Traceability)..................... 25

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.CCNC WB-2 (Steam-Generator Feed Water Pump 1A-NNS)........................................... 29 -

Eddleman 41F (QA Concerns Not.Cocumented ,

. Properly)........... 4 ............................ 30 Eddleman 41G (Employee Harassment)................ 32 Eddleman 41H (Construction Inspection Independence)..................................... 34 V . C o nc lu s i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 6 Exhibits Exhibit A - Affidavit of Mr. Chan Van Vo, dated 10/6/84 Exhibit B - Eddleman Proposed Contentions 41C through 41H dated 10/25/84 (typed-version of handwritten original)

Exhibit C - Conservation Council's Late Filed Contentions Based on the Affidavit of Chan Van Vo -- 10/30/84 Exhibit D - Complaint of Mr. Chan Van Vo to the Administrator, Wage and Hour Division, Employment Standard Administration, U.S. Department of Labor, dated 8/28/84 Exhibit E - Letter from James C. Stewart, Area' Director, Wage and Haur Division, Employment Standards Administration, U.S. Department of Labor to Mr. Chan Van Vo, dated 10/12/84 Exhibit F - Affidavit of A. Parks Cobb, Jr., dated 11/9/84, with Attachments 1 and 2 Exhibit G - Government Accountability Project Press Release, dated 10/22/84 Exhibit H - Shearon Harris Nuclear Power Plant Work Procedure WP-110 (Rev. 9) (with Appendix J attached)

Exhibit I - " Nuclear Power Plant Construction Management -- Proposed: Proportional of Integral Derivative Controller Construction," prepared by Chan Van Vo (undated)

Exhibit J - Harris Plant Deficiency and Disposition Report (DDR) 1775, dated 7/25/83 Exhibit K - Harris Plant Deficiency Notice on Steam Generator Feedwater Pump 1A-NNS, dated 7/30/82

November 13, 1984

. UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION-BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

CAROLINA POWER & LIGHT ) Docket No. 50-400 OL COMPANY and NORTH CAROLINA )

EASTERN MUNICIPAL POWER AGENCY)

)

(Shearon Harris Nuclear )

Power Plant) )

APPLICANTS' RESPONSE TO LATE-FILED CONTENTIONS OF WELLS EDDLEMAN AND CONSERVATION COUNCIL OF NORTH CAROLINA BASED ON THE AFFIDAVIT OF MR. CHAN VAN VO I. Introduction During the course of the hearings held on safety conten-tions in the above captioned proceeding, on October 25, 1984, Mr. Wells Eddleman distributed to the parties present and the Board six proposed new contentions (proposed Eddleman 41C through 41H) based on the allegations contained in an Affidavit of Mr. Chan Van Vo, dated October 6, 1984 (hereinafter the " Van l

Vo Affidavit", attached hereto as Exhibit A).1/ Mr. Eddleman l offered the proposed contentions as late-filed contentions and l l l

I 1/ A typed version of the handwritten proposed Eddleman con-tentions is attached hereto as Exhibit B.

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addressedi on the' record, the five lateness' factors set forth-in 10 C.F.R. 9 2.714(a)'. Tr. 5730-45. At due hearing held on ,

October 30, 1984,~ counsel for the Conservation Council of North

- Carolina ("CCNC") distributed two late-filed contentions (CCNC I

WB-1 and WB-2). CCNC' adopted the earlier oral statement.of Mr.

Eddleman as-its position on the five lateness. factors. (A copy of the CCNC pleading which proffered the two proposed conten-tions is attached hereto as Exhibit'C.) Pursuant to the sched-ule established by the Board for reply (Tr. 5750), Applicants Carolina Power & Light' Company ("CP&L"),and North Carolina t

Eastern Municipal Power Agency hereby respond in opposition to the admission of the late-filed contentions.

Applicants oppose admission of all of the late-filed con-tentions because:

(1) Each of the six proposed Eddleman contentions is overly-broad in its scope -- the far-reaching allega-tions are not supported by the specific concerns raised in the Van Ve Affidavit.

. (2) The reliability of the Van Vo Affidavit has been se-riously questioned and cannot serve'as the basis of a contention.

(3) Both Mr. Eddleman and CCNC have failed to demonstrate good cause for raising these new issues at this late i date and have failed to demonstrate that application

, of the five lateness factors weigh in favor of admis-sion of the late contentions.

(4) Even assuming arguendo that the statements in the Van Vo Affidavit are factually correct, in the case of each proposed contention Mr. Eddleman and CCNC have failed to plead a litigable issue with adequate basis and specificity. Particularly, in this regard, many of the statements in the Van Vo Affidavit allege deficiencies in procedures that were in effect over

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one year ago.and that have been subsequently revised

~and any identified defects inLwork were corrected; to -

-litigate such issues would beEto litigate issues only ,

of historical interest. .

II. Background on the Van Vo Affidavit The Board has previously considered the Van Vo Affidavit in this proceeding in some detail (Tr. 5315-63),. having accept-ed the Van Vo Affidavit as a limited appearance statement.

Tr. 5316. Furthermore, the Board ruled that the allegations in the Van Vo Affidavit were not relevant to Eddleman-Conten-tion 41. Tr. 5571-72. During the hearing, counsel-for Appli-cants provided background with regard to the Van Vo Affidavit.

The Affidavit was received by Applicant CP&L, in mid-October in response to an. inquiry initiated by CP&L's Corporate Quality Assurance Department (" Corporate QA") under the Harris Plant Quality Check Program to obtain more information from Mr. Van Vo on the quality concerns he raised in a complaint to the De-partment of Labor. Tr. 5320. The Van Vo Affidavit was public-ly released at a press conference called by the Government Ac-countability Project on October 22, 1984. Tr. 5360.

The allegations set forth in the Van Vo Affidavit first came to light as a result of a complaint dated August 28, 1984, from Mr. Van Vo to the Department of Labor charging CP&L with a l

violation of the employee protection provisions of the Energy Reorganization Act (a copy of the complaint is attached hereto i

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as Exhibit D). Mr. Van Vo alleged inter alia that he had "been subject to repeated harassment, intimidation, pressure and ,

'other discrimination because ofi[his] actions in perf'orming-

[his]Lassigned duties'which included the identification and documentation of design and construction deficiencies." See Exhibit D at 2. On October 12, 1984, the Department of Labor issued its findings and concluded that it could net substanti-ate Mr. Van Vo's allegations.2/

As indicated by counsel for Applicants during the. hearing (Tr. 5322), an additional investigation of the quality concerns raised by Mr. Van Vo was initiated by the CP&L's Corporate QA.

Further, an independent consu :nt, "r.. A. Parks Cobb, Jr., a Senior. Manager at Duke Power Company, was retained to perform part of the Quality Assurance investigation. The results of Mr. Cobb's investigation are set forth in a report (the "Cobb-Report") dated October 31, 1984 (attached to the Affidavit of A. Parks Cobb, Jr. --

Exhibit F hereto). Mr. Cobb has consid-erable training and experience to qualify him to perform such an investigation. See Affidavit of A. Parks Cobb, Jr., at 11 1, 2; Attachment 1. Mr. Cobb's independent investigation was also unable to substantiate the allegations set forth in the Van Vo Affidavit. Indeed, Mr. Cobb's report describes a 2/ A copy of the letter setting-forth the findings of the De-partment of Labor is attached hereto as Exhibit E.

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number of inaccuracies that are found in the Van Vo Affidavit.

Nevertheless, Corporate QA will issue a separate' report on the ,

-technical concerns raised in the Van Vo Affidavit. I'n addi-tion, the NRC's Office of Inspection and Enforcement and Office of Investigation are conducting their own independent investi--

gations. Tr.'5333.

III. Standards Governing Late-Filed Contentions The Commission'c' Rules of Practice, at 10 C.F'.R. S'2.714, require that a petitioner set forth the basis for each conten-tion with reasonable specificity. This standard requires that a contention state a cognizable issue with particularity, Alabama Power Company (Joseph M. Farley Nuclear Plant, Units 1 4

and 2), ALAB-182, 7 A.E.C. 210, 216-17 (1974), and that a peti-tioner provide a " reason" for its concern. Houston Lighting i

and Power Company (Allens Creek Nuclear Generating Station, Unit 1), ALAB-590, 11 N.R.C. 542, 548 (1980).

As a general proposition, a Licensing Board should not address the merits of a contention in determining admissibili-ty. Id. However, a contention and its basis may be scruti-nized to determine if a litigable issue has been pleaded. Two purposes of the basis with specificity requirement are "to help assure at the pleading stage that the hearing process is not improperly invoked," and "to assure that the proposed issues are proper for adjudication in that particular proceeding."

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Philadelphia Electric Company (Peach Bottom Atomic Power -Sta-tion, Units 2 Land 3), ALAB-216, 8 A.E.C. 13, 20-21 (1974). In ,

this regard, a contention must be material to those f'indings-which precede licensing, as set forth in 10 C.F.R. 6 50.57.

See Public Service Company of New Hampshire (Seabrook Station, Units 1 and 2),. LBP-82-106, 16 N.R.C. 1649, 1654-55 (1982).3/

With respect to the specific issues raised by CCNC and Mr.

Eddleman regarding QA/QC of certain aspects of construction, we note that error-free construction is not a precondition for an operating license under either the Atomic Energy Act or the Commission's regulations. What is required instead is a find-ing of reasonable assurance that the plant, as built, can and will be operated without endangering the public health and safety. 42 U.S.C. 55 2133(d), 2232(a); 10 C.F.R.

S 50.57(a)(3)(i); Pacific Gas and Electric Company (Diablo Can-yon Nuclear Power Plant, Units 1 and 2), ALAB-756, 18 N.R.C.

1340, 1345 (1983); Union Electric Company (Callaway Plant, Unit 3/ Not only must the contention be relevant to the Board's ultimate findings, but it must provide a foundation sufficient to warrant further exploration. Philadelphia Electric Company (Peach Bottom Atomic Station, Units 2 & 3), 8 A.E.C. 13, 21 (1974); Duquesne Light Company (Beaver Valley Power Station, Unit No. 1), ALAB-109, 6 A.E.C. 243, 246 (1973). See also Seabrook Station, supra, LBP-82-106, 16 N.R.C. 1649, 1655 (cit-ing Consumers Power Company (Midland Plant, Units 1 and 2),

CLI-74-5, 7 A.E.C. 19, 32 n.27 (1974), rev'd sub nom.,

Aeschliman v. NRC, 547 F.2d 622 (D.C. Cir. 1976), rev'd sub nom., Vermont Yankee Nuclear Corp. v. NRDC, 435 U.S. 519, 553-54 (1978)), for the proposition that a contention must be sufficient to require reasonable minds to inquire further.

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1),fALAB-740, 18 N.R.C. 343, 346 (1983), reconsideration denied, ALAB-750, 18 N.R.'C. 1205 (1983), as modidied, ,

ALAB-750A, 18 N.R.C. 1218-(1983). Accordingly, .a ' QA/QC conten-tion in an operating license proceeding is not' litigable unless it would cast doubt on this finding.

Contentions may also be scrutinized to eliminate those that are based on factual inaccuracies or misrepresentations.

This scrutiny is readily distinguishable from the proscription in Allens Creek, ALAB-590, supra. Allens Creek prohibited Li-censing Boards from rebutting a source or reference proffered in support of a contention, but it did not prohibit rejecting a contention when such source material is ficticious or misrepre-sented. See Philadelphia Electric Company (Limerick Generating Station, Units 1 & 2), LBP-82-43A, 15 N.R.C. 1423, 1504-05 (1982), in which the Licensing' Board rejected a contention be-cause of factual inaccuracies in the allegations; Duke Power Company (Catawba Nuclear Station, Units 1 & 2), LBP-82-107A, 16 N.R.C. 1791, 1804 (1982), in which a Licensing Board rejected a contention because it seriously mischaracterized the draft en-vironmental statement; Carolina Power & Light Company,.et al.

(Shearon Harris Nuclear Power Plant, Units 1 & 2), LBP-82-119A, 16 N.R.C. 2069, 2076 (1982), in which this Licensing Board re-jected contentions which inaccurately described the applicants' proposals. Here, the sole asserted basis for the late conten-tions is an affidavit containing the allegations of a single

Ct-CP&Ljemployee, whose employment was terminated some nine months

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ago -- which allegations independent investigations of the De- ,

.partment of Labor and CP&L's Corporate QA found to be' unsubstantiated. Under these circumstances, Applicants submit -

that inquiry into the accuracy of the statements found in the Van Vo. Affidavit is permissible because it is akin to de-

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termining if a reference cited as basis even exists, and not into whether the contentions have merit.

In addition to the normal pleading requirements, 10 C.F.R. 5 2.714 sets out five factors that must be balanced in admit-ting a late-filed contention, and a contention is untimely if it is filed later than fifteen days prior to the 10 C.F.R. 5 2.751a special prehearing conference. 10 C.F.R. 5 2.714(b);

Duke Power Company (Catawba Nuclear Station, Units 1.and 2),

CLI-83-19, 17 N.R.C.' 1041, 1043 n.2 (1983). The five factors are:

i) Good cause, if any, for failure to file on-time.

ii) The availability of other means whereby the petitioner's interest will be protected.

iii) The extent to which the petitioner's par-ticipation may reasonably be expected to assist in developing a sound record.

iv) The extent to which the petitioner's inter-est will be represented by existing par-ties.

v) The extent to which the petitioner's par-ticipation will broaden the issues or delay the proceedings.

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. 1 10'C.'F.R. 9:2.714(a)(1)'(i)-(v)'.

In Catawba, supra, CLI-83-19, the. Commission enunciated <

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. 1 two fundamental principles underlying,the five-factors analy-sis: First, a petitioner has the obligation of uncovering information in publicly available documentary. material; and second, there is a substantial public-interestLin efficient and expeditious administrative proceedings. Id. at 1048 (citing.

WSTE-TV, Inc. v. FCC,-566 F.2d 333, 337 (D.C. Cir. 1977)). The Commission also adopted a three-part test for determining whether good cause exists. Good cause exists if a contention:

1. is wholly dependent upon the content of a particular document;

2. could not be advanced with. any degree of specificity (if at all) in advance of the public availability of that document; and

3. is tendered with the requisite degree of-1 promptness once the document comes into ex-istence and is accessible for public exami-nation.

i Id. at 1043-44. Although this test addresses documentary mate-j rial, it should apply equally to any other source allegedly l

providing new information.

4 Unlike the assessment of basis in determining the admissi-bility of a contention, assessment of the five lateness factors entails a determination of the merits of the claims made.

, Florida Power & Light Company (St. Lucie Plant, Unit No. 2),

CL1-78-12, 7 N.R.C. 939, 948-49 (1978). In St. Lucie, the Com-mission stated:

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In considering untimely petitions licensing boards are required to assess . . . whether -

the petitioner has "made a substantial ,

showing of good cause for failure to file on time." In doing so, Boards must neces- ,

sarily. consider the merits of claims going '

to that issue.

Id. The Commission therefore upheld the consideration of affi-davits.4/

Similarly, in Long Island Lighting Company (Shoreham Nu-clear Power Station, Unit 1), LBP-83-30,.17 N.R.C. 1132, 1141-42 (1983), a Licensing Board considered affidavits and held an on-the-record conference in assessing the lateness fac-tors. With respect to factor (iii), the Board held: "the ex-tent to which petitioner's participation may reasonably be ex-pected to assist in developing a sound record is only meaningful when the proposed participation is on a significant,

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triable issue;" and with respect to factor (v), the Board held, "the extent to which petitioner's participation will broaden the issues or delay a proceeding is properly balanced against the significance of the issue."5/ Id. at 1143.6/

4/ This ruling parallels the customary practice of consid-ering affidavits for and against motions to reopen a record.

See, e.g., Diablo Canyon, supra, ALAB-756, 18 N.R.C. 1340, in which the Appeal Board considered affidavits on a motion to re-open the record'on quality assurance. Furthermore, because of the importance of QA, the Appeal Board held a hearing on the motion and permitted cross examination of the affiants. Id. at 1343. The hearing revealed that intervenors were misrepre-senting an employee's statement about a contractor's QA pro-gram. Id. at 1347-48.

! 5/ "If significance and triability of the issue were not in-

herently part of the overall balancing test for late-filed t

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_IV.

Application Of The Standards, -

A. THE EDDLEMAN LATE-FILED. CONTENTIONS ARE OVE'RLY BROAD The six late-filed contentions proposed by Mr. Eddleman are so expansively worded that Applicants.can only speculate

-how Mr. Eddleman purports to relate specific referenced para-graphs in the Van Vo Affidavit to the broad sweeping allega-tions of the inadequacies of Applicants' Construction QA pro-gram. Indeed, Mr. Eddleman admitted as much in response to a question by the Board Chairman during his discussions of the new contentions:

[T]he reason I drafted these conten-tions relatively broadly was that I' don't know how much might be lurking out there. . . . I didn't want to be hung to a contention that just says specifically what Mr. Van Vo says. . . .

(Continued) contentions, the illogical result would be'that the signifi-cance of an issue could not weigh the balance in favor of ad-mitting a late-filed contention before the close of the record, but could weigh in favor of admitting the same contention filed

even later, after the close of the record." LBP-83-30, 17 N.R.C. at 1143-44.

6/ See also Detroit Edison Company (Enrico Fermi Atomic Power Plant, Unit 2, LDP-82-96, 16 N.R.C. 1408, 1429-35, aff'd, ALAB-707, 16 N.R.C. 1760, 1766 n.5 (1982). In this case, the Licensing Board resolved an untimely petition by making find-ings of fact with reference to a transcript of a public hear-ing. The transcript had been attached to applicants' answer to the petition. The Board criticized the petitioner for failing to offer factual support for its assertions and based its re-jection of the petition in part on the " clear evidence" sub-mitted by applicants. Id. at 1432-33.

i So thatLis why I Idrafted it that'way.

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l But, : basically,. what .I :mn saying is now I -

think the kind of. scoping of the~ contention .,

depends a good bit on the schedule,. it . ,

depends-I.think'in part on.the response of the Applicants-and the Staff.

Say,cfor example, the Staff says yes we think.you'ought to hear a specific part:

of this or one of them, than that would be a-different situation.

And, likewise,-I can't predict what the: Applicants-are going to do, but I think that is open. I am-just trying to address in a sort of general way.

Tr. 5739-5740. By his own admission, Jir. Eddleman's approach was to attempt to draft the broadest statements that he could possibly attempt to support with the allegations in the Van Vo Affidavit and then see "how much might be lurking out there."

Such an approach to drafting contentions is clearly

impermissible. .

In contrast, the two contentions proposed by CCNC, while t

objectionable on other grounds, do put Applicants on notice specifically as to the allegations that CCNC would desire to litigate. Compare CCNC WB-1 with Eddleman 41C, 41D and 41E.

In dealing with the eight proposed contentions in this re-sponse, we have combined CCNC WB-1 and Eddleman 41C, 41D and 41E as constituting essentially the same allegation with regard to material traceability of pipe hangers. Thereafter, we will treat CCNC WB-2 and Eddleman 41F, 41G and 41H separately. How-ever, as a threshold objection, Applicants submit that all.six

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of Mr. Eddleman's proposed contentions must-be rejected because of the overly-broad statements, lacking clarity and precision, ,:

which fail to put Applicants on-notice without consid'erable speculation as to specifically what issues Mr. Eddleman would seek to litigate.7/

B. THE VAN-VO AFFIDAVIT HAS BEEN DEMONSTRATED TO BE FACTUALLY INACCURATE AND UNRELIABLE AND CANNOT SERVE AS THE BASIS FOR A CONTENTION A threshold question that must be addressed is whether the-statement of Mr. Van Vo'should, without any other substantiation, serve as the basis for late-filed contentions.

The first public statement regarding Mr. Van Vo's alleged safety concerns was disclosed during a press conference orches-trated by the local representative of the Government. Account-ability Project on the eve of continuation of safety hearings.

The tactics of the Government Accountability Project in raising last minute " safety concerns" regarding nuclear projects that are close to completion based on the statements of so-called whistle-blowers is well-known. Indeed, Mr. Van Vo's attorney, Mr. Guild, was present for part of the management capability hearings in September (where QA/QC programs were discussed t

7/ See Kansas Gas and Electric Company (Wolf Creek Generating Station, Unit No. 1), ALAB-279, 1 N.R.C. 559, 576-77 (1975).

("It should not be necessary to speculate about what a pleading is supposed to mean.")

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during the testimony of Applicants' witnesses) and Mr. Guild apparently advised counsel for CCNC concerning certain lines of ,

questioning. Tr. 5358-59. At that time, having prev'iously filed the' Department of Labor complaint on behalf of Mr. Van Vo, Mr. Guild certainly was aware of Mr. Van Vo's allegations.

What information Mr. Guild then shared with Mr. Eddleman and Mr. Runkle, we do not know. What is clear, however, is that at least Mr. Guild waited until the safety hearings to publicly announce Mr. Van Vo's safety concerns. (Exhibit G is a copy of the press. release provided by the Mr. Guild at the October 22, 1984 news conference.) We certainly question the fairness to Applicants of such transparent tactics.

More importantly, it is clear that the "new" information revealed in the Van Vo Affidavit cannot be substantiated and, at a minimum represents a distorted and inaccurate character-ization of events that occurred over a year ago. The Depart-ment of Labor was not able to substantiate Mr. Van Vo's claims.

See Exhibit E. An independent investigation initiated by CP&L's Corporate QA places the Van Vo allegations in an entire-ly different light. The report of the investigation of Mr. A.

Parks Cobb, Jr. makes a number of important findings, including:

1. Mr. Van Vo's allegations of harassment were i no more than frequent counseling sessions  !

for poor job performance, which began for- I mally in March 1983. Mr. Van Vo denied poor performance on his part and rather blamed his supervisors -- even in r

. 1 ' I 9 3 interviews with senior CP&L management.

Cobb. Report at.3-8.

2. Mr. Van Vo's; allegations.of technical prob ,

lems with the steam generator feedwater

- pump and lines'and his allegations of-mate-rial traceability' problems with pipe hang-ers resulted from his relatively minor and isolated exposure to two complex situations about.which he drew incorrect conclusions.

Cobb Report at.4, 12-15.

3. In any event, Mr. Van Vo displayed his lack' of familiarity with Harris Plant systems by characterizing the steam generator feedwater pump and piping.as " Safety Cate-gory 4, Seismic Category 1," upon which "the integrity of rector temperature and

-pressure control is dependent" and there-fore " nuclear safety significant." Van Vo-

, Affidavit at 1 5. .In fact, both.the pump and piping are non-safety related. Cobb Report at 14, 16; see discussion of CCNC WB-2 infra.

4. Mr. Van Vo supports his allegations regard-ing material traceability with an instance where he found a Purchase Order ("PO") had been " voided." Van Vo Affidavit at 11 18-20. It simply turns out that the docu-mentation.was difficult to find and Mr. Van ~

Vo assumed that it had been destroyed. An-other engineer was assigned to review the problem identified by Mr. Van Vo and traced the material in question to another specif-

! ic purchase order. This situation was

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later investigated by Dr. Elleman's Nuclear-Safety Review Panel and found not to be a safety concern. Cobb Report at 17.

, 5. While Mr. Van Vo ends his monologue regard-ing material traceability for pipe hangers with a rhetorical question regarding the 300 pipe hangers that had successfully pas-sed inspection prior to changes in proce-dure to provide for material verification (Van Vo Affidavit at 1 13), Revision 9 to WP-110 (referenced by Mr. Van Vo) provided that all of the hangers that had been pre-viously installed and inspected under the

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1 old Phase II program were to be reinspected 1 to' ensure the desired . level of ' quality ,- - -

including material-traceability. Cobb:Re- ,

- port at 15; see WP-110'(attached hereto as: ,

Exhibit H).

6. . While Mr. Van Vo alleges lthat he previously had brought: safety concerns to. management-attention.(Van Vo Affidavit at 1 1, 24),

rather his interviewsiwith senior manage-ment were directed to his proposals for reorganizing the Harris Project.with Mr.

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sponsibility. Cobb Report at 5-10; see also " Nuclear Power Plant Construction Man-'

agement ---Proposed: Proportional of Inte--

gral Derivative Controller Construction" prepapred by Chan Van Vo'(Exhibit I hereto)'.

, The Cobb Report directly refutes the principal allegations in the Van Vo Affidavit, which is proffered as the sole basis f these late-filed contentions. As we discussed in the pre-ceding section on the applicable law, the Board may rely on af-fidavits to inquire into the accuracy of the information prof-1 fered as the basis for contentions. In so doing, the Board is

j. not. weighing the merits of the contentions themselves. Fur-thermore, while the Department of Labor did not detail its i

findings, it did conduct its own independent investigation and could not substantiate Mr. Van Vo's allegations. Thus, Appli-l cants submit that the Van Vo Affidavit must be considered

, unreliable and cannot be used as the basis of a new contention.

To accept such unsubstantiated allegations as fact and require Applicants to invest the substantial time and expense of' dis-covery and litigation at this stage of the proceeding would be i

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an abuse of the administrative process.8f;

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C. MR. EDDLEMAN AND CCNC-HAVE FAILED TO SUSTAI.N.THEIR-BURDEN 'IN ADDRESSING 'lHE FIVE LATENESS FACTORS

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When an untimely motion to admit new contentions-is filed on the eve of closing the record, " petitioner's burden on the Section 2.714(a) factors is.a heavy one." Houston Lighting and Power Company (Allens. Creek Nuclear. Generating Station, Unit 1), ALAB-671, 15'N.R.C. 508,.'511 (l'9'82). -Such-.is,the' case-at hand, since the Harris safety hearings are scheduled for com-pletion this week.

i l Factor (1): Good Cause For Failure to File on Time Mr. Eddleman asserts as good cause for the lateness of his-

[ contentions the fact that the Van Vo Affidavit was not avail-I able to him until October 22, 1984 and did not even exist until October 6, 1984. Yet Mr. Eddleman admitted that he and Mr.

8/ Of course, if the NRC's independent investigations were to j substantiate Mr. Van Vo's claims, this issue would be cast in.a different posture. Applicants are confident that the results of the NRC's inquiries will be the same as the independent in-vestigation performed by Mr. Cobb. At a minimum, it would be premature to give any credance to the allegations in the Van Vo Affidavit -- in light of the information presented here to the

! contrary and in light of the ongoing NRC investigations --

until such reports by the NRC investigatory arms were complet-

ed. Applicants, however, submit.that the-Board could at this time reject all eight contentions for no other reason than the unreliability of the Van Vo Affidavit -- without reaching the

, equally compelling arguments infra with respect to the five factors or the lack of basis and specificity.

l l _17 l

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Runkle knew at least~of the_ substance of Mr.. Van 1Vo's allega- ,

tions in? September and waited until.. late October'to present ,

'The' inter-

-this new information to-the Board. Tr -5578; 5736.

-venors have an obligation to do more than wait for the informa-tion to fall into their laps.

More importantly,' information putting the intervenors on

. notice of-a potential: concern regarding material traceability of pipe hangers (CCNC WB-1; Eddleman 41C, 41D and 41E) was. pub-licly available in the form of NRC Inspection and Enforcement

.("I&E") inspection reports that were available over a' year ago.

Similarly the questions of nonconformance reporting ~(Eddleman 41F) and Construction Inspection independence ~(Eddleman 41H) were also raised in I&E inspection reports over a year ago.9/

Therefore, the issued raised by these six contentions are not

" wholly dependent upon" the content of the Van Vo Affidavit and could have been advanced with even a greater degree of specif-icity over a year ago based on concerns raised in I&E in-spection reports.10/ Thus for these six contentions, Mr.

, .jb/ The specific inspection reports are identified in Section.

IV.D infra, in discussing the lack of basis and specificity for the individual contentions.

i 10/ As will be discussed infra, the concerns raised in these i I&E inspection reports have since been resolved to the satis-i faction of I&E. The information in the Van Vo Affidavit is stale and often inaccurate; on.the other hand, information that

relates to at least the substance of certain of his concerns was publicly available in late 1983.

18-l l

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Eddleman and'CCNC-haveffailed-to meetutwo parts offthe' 7three-part test!for. determining good.cause~'as set forth'in ,

ICatawba, supra,.CLI-83i 19, at.l'043-44.

Factors-(ii) and (iv): .The Availability'of other'Means F Whereby Petitioner's Interest 1W111.Be Protected; and

~the Extent to Which' Petitioner's Interest Will1Be Represented by Existing Parties Mr. Eddleman,-joined by CCNC,. argue that'there are no-l other means by which their-interests may be affected:

I certainly can't depend on the'Appli -

cants' i.iestigation. I.think the StaffLis

! basically adverse.to hearing these things, t

and cannot be counted on to-protect my in-terest, and.does say will be protected; it l_ is not may be or likely to be, i

i So, I-think that is pretty-straight I, forward. In other words,.if I want to pro-tect my interest on this, I have to go ahead and file contentions.

Tr. 5737. Accepting such an argument would always resolve fac-tors (ii) and (iv) in favor of late contentions. Furthermore, the argument is circular and seeks to avoid the affirmative l~ showing that the intervenors are required to make.

! While the Board should not simply assume that the Staff

! will represent the intervenors' interests, Washington Public l Power Supply System (WPPSS Nuclear Project No. 3), ALAB-747, 18 t

i N.R.C. 1167, 1174-75 (1983), this case is different. The NRC l 1s actively investigating the allegations recounted in the Van

! Vo Affidavit. In_ light of this activity, it is reasonable to i- conclude that the Staff will represent the intervenors' l

I I

li

, . ,f .

8

. j

, l

.l interest in conducting an independent investigation.11/

Factor (iii): The Extent to Which the Peitioner.'s Participation May Reasonably Be Expected to Assist in Developing a' Sound Record With respect to this factor, Mr. Eddleman offered the fol-lowing argument:

At the risk of sounding like a broken record, the Board and parties know I think that I almost always say about this, if you don't have a record on a subjecti you don't have a sound record. . . .

I have some knowledge of welding and that sort of thing. I am able, I think, to conduct examinations. Since he (Van Vo]

would be my witness, it doesn't depend much on my ability to cross, it just depends on my ability to put him on. . . .

Anyway, he has a counsel who knows something about this sort of thing and is experienced in NRC proceedings, and I think would be able to assist him in that regard.

And my participation then would be ba-sically just to get him in here and make him available to bring out his information, and I am willing to do anything I can to assist in that, but I think the main thing is just to get it on the record.

Tr. 5743-44. This statement totally fails to satisfy the in-tervenors' burden of persuasion. The Appeal Board has stressed the importance of this factor, stating:

11/ Factors (ii) and (iv) are given less weight than the other factors. South Carolina Electric & Gas Company (Virgil C. Sum-mer Nuclear Station, Unit 1), ALAB-642, 13 N.R.C. 881, 895 (1981); Detroit Edison Company (Enrico Fermi Atomic Power Plant, Unit 2), ALAB-707, 16 N.R.C. 1760, 1767 (1982).

r op c svl r1 .i L a . !h-t,3 .

y 1 W .; p; r j

>^

e When a petitioner addresses-this criterion .

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~-

it should' set out with as much particulari- r-y' t / -

sty as-possible-the pre'ise c issues it plans ' ;-* ,.

(I to cover, identify its prosp'ective witness , s i es, and summarize their,orboosed testimony. s , l ' l s i +  ;

4 ,

.WPPSS No. 3, supra, ALAB-747, 18 ' N '.' R . C . at 1177 :(citing 3 3 J-

')

Mississippi Power & Light Company?(Grand Gulf., Nuclear S.tation, '

i t

N ,

Units 1 and 2), ALAB-704, 16 N.R.C. _ 1725, 1730 (1982);> South

. Y \ ,

Carolina Electric & Gas Companyf(Virgil C. Summer Nuclear Sta- , /

I s

-tion, Unit 1), ALAB-642, 13 N.R.C. 881, 894 (1981);< Detroit- /

t Edison Company (Greenwood Energy Center,; Units 2 and 3), t

\

ALAB-476, 7 N.R.C. 759, 764 (1978); Lbng~IIsland Lighting s

Company (Shoreham Nuclear Power Station,NUnit 1), ALAB-743, 18 i-N.R.C. 387, 399-400 (1983)). In ALAB-747, the petitioner had ft T described its experience in NRC proceedings and identified a witness, but the Appeal Board found such statements;." manifestly inadequate." WPPS Ne. 3, supra, 18 N.R.C. at 1177.

Mr. Eddleman's offer regarding this f' actor is considerably less than that which the Appeal Board found inadequate in ALAB-747.1_2/ Indeed, Mr. Eddleman has never met Mr. Van Vo.

There is certainly no assurance that Mr. Van Vo we11d be avail-able for a hearing on any contention raised by his Affidavit at some later date, much less any assurance that he would be 12/ Mr. Runkle's failure independently to make a showing of CCNC's plans to assist in the development of a sound record, is a default by CCNC in meeting its burden and must weigh heavily against CCNC in balancing the five factors.

~

i t .

4 available for! depositions priornto: suchna -hearing. Mr.

Eddleman's offer /"to'get him'in here and make him avail'able to-

~

6 ,

n bring out-hisiinformation" falls considerably short o'ffthe ef-

' fort required to assist in1 developing a. sound record.

Further,pApplicantsLaubmit that the. record that Mr.

ri .

g EddlemanLand Mr. Runkle have assisted in developing-during the

~

f last three weeks of. hearings on safety 71ssues speaks:for;itself h+ - and is the best evidence in controverting the intervenors' ar-guments in support of the third factor. While Mr. Eddleman' suggests that' developing a' sound record on his proposed conten -

tions here~"doesn't depend much on.my ability to cross,' it just~

depends on my ability to put him [ Van Vo] on," Applicants re-mind the Board of the' state ~of the record with respect to the case presented by Mr. Eddleman's witness, Mr. Stokes. See Tr.

6037 et seg. The record on this issue can best.be character-ized as one of complete disarray. See-Tr. 6049.

i Mr. Eddleman has often complained about his' work load; but it is certainly one of his choosing. We note that Mr. Eddleman has a significant number of emergency planning contentions al- .

ready admitted. Experience to date in this proceeding, as the Board itself has acknowledged, strongly suggests that Mr.

Eddleman is over extended already and is clearly not in a posi-tion to assist in a meaningful way in developing a sound record

{ on additional QA/QC contentions. See Tr. 6280. Thus, the third factor weighs strongly against the intervenors here in admitting any late-filed contentions.

f

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

Factor (v): The Extent to Which the Petitioner's Participation Will Broaden the Issues or Delay the -

Proceeding ,

As he must, Mr. Eddleman concedes that admission'of the late-filed contentions'will broaden the issues:

I think it does broaden the issues, but I think because the issues are impor-tant, and because Mr.. Van Vo has direct ex-perience of much of this, and says he be-

-lieves there is more, to the extent we might get into further digging in it, that that shouldn't be a factor against these but rather should be a factor for them be-cause they are so important.

As to delaying the proceeding other-wise - what I am saying is, I am prepared to go forward with this in a couple of weeks, which is pretty'much within the hearing schedule we have now.

'If it goes more than that, I think we have some leeway in that nine month slip in the fuel load date that was just announced, I believe,. yesterday.

Tr. 5741-42. Not only does Mr. Eddleman admit that it will broaden the issues, he proposed "further digging."

Mr. Eddleman appears to believe that a delay in the pro-posed fuel load date for the Harris Plant sanctions any delay in the proceeding. The fifth factor refers to a delay of the proceeding, not to delay of the operation of the facility.

Enrico Fermi, supra, ALAB-707, 16 N.R.C. 1760, 1766. In Fermi, the Licensing Board rejected an argument that there was no delay because fuel loading was not scheduled for a year. Ad-mission of new contentions on the eve of closing the record on l

I cus' safety issues,necessarily will extend the proceeding signif-i icantly. Mr. Eddleman's. assertions that he is prepared.to go ,

forward:on.his new proposed contentions in.a couple o'f weeks is totally unrealistic. At this late Jdate, the introduction and-litigation of new contentions threatens a substantial and un--

reasonable delay in the proceeding.

Accordingly, all.five factors militate against, admitting

- the intervenors' late-filed contentions.

D. THE LATE-FILED CONTENTIONS FAIL TO STATE LITIGABLE-ISSUES WITH THE REQUISITE BASIS AND SPECIFICITY Even if the Board were to reject Applicants' position regarding the unreliability of the Van Vo Affidavit and were to weigh the five lateness factors in the intervenors' favor, an analysis of each proposed late contention clearly demonstrates that the intervenors have failed to state a litigable issue with adequate basis and specificity. The intervenors have i failed to advance a thesis that would link the isolated inci-dents described by Mr. Van Vo -- upon which the proposed con-tentions are solely based -- with the finding that the Harris

! Plant, as built, can and will be operated without endangering public health and safety. Indeed, Mr. Van Vo describes, in f part, his supporting role in determining the quality of pipe hanger installations, noting that deficiencies were found but that procedures were modified to ensure quality construction --

i-l i

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including verification:of materials used in.the pipe hanger in-

stallations. 'Mr. Van Vo' draws a number'of unsupportab'le con- ,

p ;clusions; many of .his : statements, .however, confirm th'at .the

' quality inspection, program worked.and that errors'in construc-

[

7

.. tion are detected. The intervenors-have utterly failed to l address the' program that presently exists at-~.the' Harris Plant for pipe hanger quality inspections, for nonconformance re-

. porting,_for Construction Inspection-independence.and:for I -

1- ensuring worker concerns will be dealt with.

l . CCNC WB-1; Eddleman 41C, 41D and 41E~(Pipe Hanger Material =

j Traceability)-

CCNC-WB-1 asserts that_the QA program at the Harris Plant is deficient in that " nuclear safety material traceability doc-umentation was falsified and other QA documents-relating to 4

j safety were falsified or destroyed." See Exhibit C. Eddleman i

41C repeats the same allegation. - Eddleman 41D is a variation

j. on this same theme, refering to " inadequate or nonexistent doc-i

umentation of material used in safety related equipment."

l Eddleman 41E alleges " wholesale discarding of documents." See l Exhibit B.

i All but.five paragraphs (if 5, 10, 11, 12 & 25) of th? Van Vo Affidavit are cited by Mr. Eddleman in support of Eddleman j 41C, 41D and 41E.- CCNC simply cites to the Van Vo Affidavit for basis. Yet Mr. Eddleman ,s admitted he really does not i

know what the statements in tne Van Vo Affidavit mean other

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-D than what they appear _.to say. Tr.'5351-54.13/:- It; appears that the'intervenors are principally-relying on statements by Mr. ,

. Van Vo about " Speed Letters" that'were allegedly' disc'arded (which discussed'the problem relatingLto the Steam Generator Feed Water Pump) and the saga of the voided Purchase Order ~as basis for these four contentions. See Van Vo~ Affidavit at 11 9, 18-20, 26.

With-respect to_use_of " Speed Letters" to document'QA

. problems, the only instance cited by Mr. Van Tha relates to the Steam Generator Feed Water Pump and piping-which fare-non-nuclear safety and do not require QA documentation under 10 C.F.R. Part 50, Appendix B. .Mr. Cobb could not substantiate any use of " Speed Letters" in lieu of the proper forms to re-port nonconformances. Cobb Report at 16-17. In any event, new procedures have been established to ensure consistency in non-conformance reporting. See discussion of Eddleman 41F infra.

The only specific instance of alleged " false _documenta-tion" of pipe hanger material was the voided Purchase Order --

P.O. #21022. Van Vo Affidavit at 1 20. DDR 1775 (Deficiency and Disposition Report) referenced by Mr. Van Vo does refer to l

13/ Mr. Eddleman even attempts to clarify one statement in the l Van Vo Affidavit by reference to a telephone conversation with Van Vo's counsel -- therebyfoffering hearsay speculation as {

basis. See note at Eddleman 41E.

l l

a. voided P.O. #21022. (DDR 1775'is attached hereto as Exhibit As explained in the disposition of the DDR,'the material J ) '. ,!

.which referenced P.O. #21022-was actually received on'another l Purchase Order (P.O. #19019). P.O. #21022 was administratively created to account for material stored in the fabrication shop.

The material in question was released by the fabrication shop by reference to the " storage" P.O. #21022. The Purchase' Order was subsequently voided in error. However, the material was still traceable to the origint P.O. #19019. See DDR 1775 (Exhibit J) at Page 2 of 17. As noted in the Cobb Report, an-other engineer was able to determine this information after Mr.

Van Vo had jumped to the conclusion that QA documents were being falsified or destroyed. Cobb Report at 18.

What the Van Vo Affidavit itself demonstrates is that quality problems with material verification of pipe hangers were being identified and properly reported on nonconformance reports. Van Vo Affidavit at V 20. When concerns were identi-fled, a stop work order was issued; work and QA procedures were "substantially changed, including particularly WP-110, and TP-34, which provided for hanger installation and inspection."

Id. at V 22. Mr. Van Vo states that CP&L noted "that hanger documentation should be checked to insure 'that the surplus hanger number / purchase order number is legitimate.'" Id. Mr.

Van Vo describes a situation which CP&L was at the time taking strong efforts to resolve.

While'Mr.-Van _Vo expresses a concern aboutlthe 300 out of' l

'18,000 seismic _ pipe; hangers-that had alreadyfsuccessfully pas- ,

sed inspection prior lto the'issuanc'e of the revised p'rocedures,

~

all hangers were reinspected. Cobb. Report at 15-16. -Thus the (Van Vo-Affidavit itself=does not support the broad sweeping al-

~

. legations of QA/QC deficiencies found.in these'four conten-tions.

Furthermore, I&E Inspection Reports, asLearly as 1981 re-

' ported ~ concerns regarding verification of material in. pipe hangers.14/ Thus the general issue of pipe hanger material control could have been raised much earlier. More recent I&E Inspection Reports detail the implementation of the revised-procedures, which the intervenors have failed to address.15/

Accordingly, these contentions fail to state lit 1' gable

~

issues with the requisite basis and specificity and must be re-jected.

14/ See I&E Inspection Report 50-400, 401, 402, 403/81-19 dated-October 2, 1981 (in which CP&L was' cited for material substitutions in pipe hangers without documentation); I&E In-spection Report 50-400, 401/83-22 dated August 3, 1983 (in which CP&L was cited for installation of incorrect material in

~

a pipe hanger); I&E Inspection Report 50-400, 401/83-25 dated October 19, 1983 (in which CP&L was cited for failure to pro-vide documentation for material substitution).

15/ See I&E Inspection Report 50-400/84-25 dated August 22, 1984, and I&E Inspection Report 50-400/84-35 dated October 22, 1984 (which reported on the inspection of CP&L's pipe hanger installation program, closed-out previously noted deficiencies, reviewed the efficacy of revised procedures and found no viola-tions or deviations).

, . _ , - , , .- ~ . _ , , , . . . ~ , - , _ . . ,-.,-.._,t,%. ...m,- ,--._..---_.w-~~,r.,wewynm,.~m.-m-,,,-.c.,w..r. , .mm,

O CCNC-WB-2 (Steam Generator Feed Water-Pump 1A-NNS)

This Contention alleges the piping line to $he discharge ,

nozzle to Steam Generator Feed Water Pump 1A-NNS was ' improperly installed thus causing improper stresses to the pump. CCNC as-

.serts "[t]he safety significance of this improper installation is that the integrity of the reactor temperature and pressure control is dependent upon the effective function of these pumps, valves, lines, etc." See Exhibit C.

CCNC WB-2 fails to raise a litigable safety issue. Steam Generator Feed Water Pump 1A-NNS and the suction and discharge lines thereto (as the designation "NNS" implies) are non-nuclear safety equipment and non-seismic category equip-ment, which perform no safety' function. Harris FSAR Table 3.2.1-1 (at page 3.2.1-39); Cobb Report at 14, 17; Tr. 5325-27; 5365-66.

Furthermore, even if the allegations in the Van Vo Affida-vit regarding the piping line to the Staam Generator Feed Water Pump were correct and even if the pump were safety-related, the contention would not raise a litigable issue absent evidence that the alleged misalignment had not been or was not being in-vestigated and corrected.16/ As demonstrated by the Cobb 16/ As was discussed ir.Section III, supra, error free con-struction is not a precondition for an operating license. A contention regarding construction activities must by its terms call into question a finding of reasonable assurance that the plant, as built, can and will be operated without endangering public health and safety. ,

Report at 14, Harris Plant quality inspection picked up the misalignment as a nonconformance. In fact, a Dediciency Notice .

(Exhibit K hereto) was written on the problem with th'e pump piping on July 30, 1982. Mr. Van Vo claims to have discovered this problem in mid-August 1982. Thus there is clearly no basis for a contention that would assert that the alleged im-proper installation went undetected or that Plant personnel ig-nored ligitimate safety concerns raised by Mr. Van Vo.

CCNC WB-2 must be rejected for failing to state a litigable contention.

Eddleman 41F (QA Concerns Not Documented Properly)

This contention broadly alleges that "QA concerns [are]

not documented properly at Harris "

. . . . Mr. Eddleman cites to twelve paragraphs from the Van Vo Affidavit for basis. See Exhibit B.

This contention is so broadly worded, Applicants must re-sort to speculation to determine what the principal concern is alleged to be. For that reason alone, it should be dismissed.

See Section IV.A supra.

The first paragraph from the Van Vo Affidavit referenced in Eddleman 41F is V 26 (which is also underlined), where Mr.

Van Vo alleges CP&L employs a " confusing and ineffective array of different documenting systems for controlling noncon-formances such as DR's, DDR's, NCR's and such commonly used t >

e -

a,

~-,

^

uncontrolled paperwork as Memos and ' Speed ~ Letters.'"12/.

Applicants assume that this statementL summarizes' the principal ,

' concern being raised by Eddleman 41F.

-In 1&E Inspection Report 50-400/83-25 and-50-401/83 ~ dated October 19, :1983, " Inspector Follow-up Item 83-25-14" reads:

Another~o'ffshoot of the_ multiple quality control type 1 organizations at Harris is the number of'different forms _and methods to document conditions-adverse to quality.

Although having many.fonus is in itself not

a problem, the potential to lose tracking control of identification and correction increases greatly with increased forms.

The use of the DR, DDR, NCR and-punchlis'ts for documenting the same type of problems can eventually-lead to missing items and inconsistent handling of problems.

In I&E. Inspection Report 50-400/84-22, dated August 14, 1984, Inspector Follow-up. Item 83-25-14 is " closed": ,

Multiple Formats for Identification of Sim-ilar Problems. The inspector confirmed that CP&L procedure CQA-3, R3, has been issued to require a single NCR form for the Harris project. All disciplines must therefore report nonconformances on the.

same form.

Thus, it is clear from I&E Inspection Report 50-400/83-25, that this issue could have been raised over a year ago. See Section IV.C supra. Further, the concern identified in Eddleman 41F 12/ Mr. Cobb was unable to substantiate the allegation that 4

speed letters are utilized in place of prescribed quality as-surance documentation at the Harris Plant. Cobb Report at 17.

I

m __ --.

I o

has been resolved. Mr. Eddleman fails to address the present.

system'and procedures at'the Harris Plant for reporting ,

nonconformances. The information in the Van Vo Affid'avit is stale, based on his experiences of a year ago and longer. For this' reason, litigation of this issue-would have no present

. meaning. Contention 41F must be rejected for-failing to state a litigable issue.

Eddleman 41G (Emplovee' Harassment)

This contention alleges "a pattern of harassment, intimi-dation, and failure to respond positively to employees bringing forward QA/QC concerns at the Harris Plant . . . ." Mr.

1 Eddleman jumps to the conclusion that "[t]his prevents concerns from being brought forward and dealt with properly . . . ."

See Exhibit B. .

The only specific allegation of alleged harassment or in-timidation is Mr. Van Vo's own description of being counseled and being placed on probation. Mr. Van Vo suggests that the reason for such dissatisfaction with his performance was be-cause of his raising safety concerns (as opposed to his inade-quate job performance). Accepted at face value, this allega-tion neither establishes a pattern nor provides a causal link with the safety of the plant as built. Further, Mr. Van Vo was neither a CI nor QA inspector.lg/ As detailed in the Cobb Ig/ Mr. Eddleman questioned the subpoenaed CI concrete in-spectors regarding any intimidation or harassment. They cate-(Continued Next Page) 1

.i

r __

t Report, there was good reason for counseling.

.Yet, Mr. Van Vo's Affidavit on its face does not support ,

the allegation'that employees were discouraged from c'oming for-ward with safety concerns or any other concerns, even to senior management. Mr. Van Vo was able to make appointments to see the Plant General Manager, the Senior Vice-President for Con-struction and the Executive Vice-President.19/ His own actions certainly do not reflect intimidation.

Finally, since the time Van Vo was terminated, CP&L has instituted a Quality Check Program further to encourage employees to come forward with safety concerns. This program was discussed in some detail during the management capability proceedings. Tr. 2697-2713; 3004-06. Mr. Eddleman simply ig-nores this program in his sweeping allegations. Indeed, the Van Vo Affidavit itself is being investigated as part of the Quality Check Program. See Cobb Affidavit.

Thus, even the allegations in the Van Vo Affidavit fail to support or provide any basis for proposed Eddleman 41G. It must be rejected.

j (Continued) gorically denied being aware of such pressure or harassment.

Tr. 6247.

l 19/ At the hearings held on management capability, Mr. McDuffie, Senior Vice-President for Construction, discussed his own accessibility to employees. Tr. 3064-59. ,

l

g.- ,

~- -

a I

-/

Eddleman 41H (Construction ~ Inspection Independence)

This contention' asserts that CP&L fails "to'give suffi-- ,

cient" independence to Construction Inspection (CI) an'd other-QA personnel ~to perform their duties without pressure or harassment . .. . ." See Exhibit.B. It is supported by a.brief-paragraph in the Van Vo Affidavit.which utterly lacks any spe-cificity. Van Vo Affidavit at 1 25.

As early as 1977,cI&E identified the need-to ensure in-l-

spection personnel would have-suffi'cient independence from cost

.and scheduling responsibilities to avoid compromise of ' quality. -

l I&E Inspection. Report 50-400, 401, 402,~403/77-3,~ dated I

l November 2, 1977. In 1979 the organization of Harris site in-spection personnel was again reviewed in detail by I&E, The inspector noted that CP&L is responsible for. managing construc-tion activities performed by the constructor, Daniel Construc-tion Company, and for verifying (auditing, inspecting, and testing) the quality of construction. At that time.the CP&L Construction Inspection Unit reported directly to the Senior Resident Engineer and was an autonomous organization, separate from the CP&L construction engineering unit disciplines. The CP&L site QA Unit monitored both Daniel and the CI Unit and re-l.

ported to the Engineering and Construction QA Manager -- inde-pendent of site construction management. The inspector found

" sufficient independence from cost and scheduling has been es-tablished for the CP&L Construction Inspection organization to t

I' l

1 O

avoid compromise of quality." I&E Inspection Report 50-400, 401/79-15 and_50-402, 403/79-14 dated September 5, 1979. ,

In 1983 this same organization created concerns 'for an NRC inspector, who noted that having the responsibility for both engineering and quality control' activities reporting to the Se-nior Resident Engineer "can create a conflict of interest."

I&E Inspection Report 50-400, 401/83-25 dated October 19, 1983 (Inspector Follow-up Item 83-25-12).

In I&E Inspection Report 50-400/84-22 dated August 14, 1984, this Inspector Follow-up Item was closed:

Potential for Inadequate QC In-spection. The inspector verified that the Construction Inspection (CI) group has been positioned directly under the Project Gen-eral Manager as of October 10, 1983, there-by eliminating the CI group from reporting to engineering. This change allows more freedom for independent QC inspections.

Two points must be made. Fi rst, the concern was raised in considerably greater detail and much earlier than the Van Vo Affidavit. See Section IV.B., supra. Second, the NRC's con-cern was addressed by an organizational change whereby the CI group reported directly to the Project General Manager rather than the Senior Resident Engineer.20/ This change was effec-tive some months before Mr. Van Vo was terminated although it 20/ Even more recently, Mr. Roland Parsons was named Project General Manager of Completion Assurance with the CI Group con-tinuing to report directly to him. This change moves in the direction of providing even greater independence for the CI Group. See Tr. 5754.

I L -_ -

] ,

a is not noted by Van Vo. In any event, Mr. Eddleman has failed )

to address the CI organization as it presently exists. ,

Contention 41H has no basis and must be rejected'.

V. Conclusion For all of the above reasons, proposed contentions CCNC WB-1 and WB-2 and Eddleman 41C through 41H should be rejected.

-RQspectfully submitf:ed, Thdmas A. Baxter, P.C.

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/ / l John H. O'Neill, Jr., P.C. I)

S W, PITTMAN, POTTS & TROWMIDGE O M Street, N.W.

Washington, D.C. 20036 (202) 822-1148

. Richard E. Jones Samantha Francis Flynn CAROLINA POWER & LIGHT COMPANY P.O. Box 1551 Raleigh, North Carolina 27602 (919) 836-7707 Counsel for Applicants Dated: November 13, 1984 e

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AFFIDAVIT My name is Chan Van Vo. I am also known as Van Vo Davis. I am giving this statement to Robert Guild, Attorney-at-Law, of Charleston, south Carolina, who has identified himself.to me as a representative of the Government Accountability Project. I was employed for almost five years by Carolina Power & Light company in the construction of the

, Shearon Harris Nuclear Power Plant near Raleigh, North, ,

Carolina, most recently in the position of Engineer where I 4

was responsible for ensuring that the installation of pipe and pipe-hangers was in accordance with , approved plans, i

specifications, codes, procedures and schedules. Although I i

j am not opposed to nuclear power, my experience with CP&L ,

causes me to have serious doubts about CP&L's commitment to

! nuclear safety and about the as-built quality of construction at the Shearon Herris Nuclear Power Plant. On many occasions I have brought safety concerns and construction deficiencies to the attention of my supervisors only to face lack of j interest and hostilityr and in one case only to find my f documentation of a serious safety concern discarded in my supervisor's trash can the next day. I have taken these concerns up my chain of command to senior management at CP&L i on several occasions only to be told that 'this is not Vietnam, here at CP&L you are only a soldier who must follow orders.' This lack of interest in my safety concerns was followed by a pattern of harassment, intimidation, pressure to resign, and ultimately my terminatibn. I have filed a I

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complaint against CP&L with the U.S. Department of Labor for violation of the Employee Protection Provisions of The Energy Reorganization Act because of the Company's discrimination against me for raising safety concerns. I was only trying to .

do my job to the best of my ability according to my pro-fossional engineering. training. I believed that the Quality Assurance regulations of the Nuclear Regulatory Commission, 10 CFR Part 50, Appendix B, and the Company's written i policies and procedures meant what they said. However', I have learned thac CP&L has very little interest in seeing that the Shearon Harris Nuclear Power Plant is built "by the book." Workers at the site are expected *to "look the other way" when they see safety violations or risk losing their jobs. I hope that my concerns will be fully investigated 'and that effective action will be taken to ensure that the public

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l health and safety is protected ,before the Harris plant is allowed to operate.

2. I was born in south Vietnam and became a U.s.

citizen after I came to this country in 1975. I hold a degree in Math, Science and Physics from the French College

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and a Bachelor of Science degree in Mechanical Engineering with a specialty in Fluid Mechanics from Phutho Higher Technical University, Saigon, South Vietnam. In order to l

supplement my education for engineering certification in this country, I have taken courses in civil and mechanical engineering from Fayetteville ' Technical Institute and International Correspondence schools. I am currently an MBA candidate at Campbell University, Buies creek, North I

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carolina, where I am concentrating in Production Management.

I expect to receive my degree in May 1985. I am an Associate member of the American Society of Mechanical Engineers.

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3. I was first employed by CP&L at the Harris site on "

April 10, 1979, as an Engineering Aide I, in the Mechanical Department under E.M. "Ed" McLean, where I was responsible l for preparing requisitions for site material procurement and for performing inspections of mechanical installations, in all

parts of the plant. On October 10, 1979, I was promoted to Engineering Technician II where I was assigned responsibil-ities for piping and pipe-hangers. Afte,r I finished the ICS j program for equivalence with a 4 year degree in mechanical

! engineering and based on my " outstanding" performance, I was 1

promoted to Associate Engineer, effective october 4,1980'.

In this position I performed material take-offs, prepared purchase specifications and material purchase orders for piping; and was in charge of field s.upport for radwaste piping in the Waste Processing Building. In April, 1982, I

was transferred to work for the Lead Manger Engineer, A.C.

"Alex" Fuller, where I was responsible for providing technical support to the hanger crafts including the preparation and interpretation of design documents and work procedures, investigation of field problems, preparation of field changes such as Field Change Requests / Permanent Waivers l

(FCR/PW), and the resolution of nonconformances.

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Alex Fuller and his immediate superior, Resident Mechanical Engineer E.E. "Ed" Willett, particularly demonstrated a lack of commitment to nuclear safety and a general lack of knowledge and competence to perform their ,

important engineering and management responsibilities. The Resident Engineering Unit carries responsibility for all site engineering functions at the Harris Plant, under the direc-tion of a CP&L employee, the Senior Resident Engineer, a position held by'A. Lucas until his removal for poor performance in early 1983. Under Lucas were the various engineering disciplines and the Construction Inspection (CI) organizations. Ed Willett took over the* Mechanical Engineering group in 1980. He originally supervised activities in the piping, hangers, equipment and heating-ventilatien-air conditioning (HVAC) areas; until equipment installation and HVAC were taken away from him in early 1983, and hanger work was taken away in october,1983, because of mounting problems and growing recognition of willett's lack of ability to effectively manage his work. Willett brought in his friend, Alex Fuller, to supervise the hanger program in late 1981, despite Fuller's lack of qualifications for this work. Fuller's training was in civil engineering and t

his only-previous work experience was in dam construction 1

with CP&L. As problems mounted in the hanger area, Al Rager was brought in over Alex Fuller. This did not help at all since Rager lacked any engineering experience. Rager has I

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e since been placed in charge of the Construction Inspection program. This recent move will do nothing to improve the Quality Assurance program at the Harris Plant.

5. In mid-August 1982 I was performing my normal duties e

checking the installation of pipe-hangers in the Turbine Building. While doing so I observed several pipefitters attempting to fit a 24" carbon steel piping line to the discharge nozzle of Steam Generator Feed Water Pump 1A-NNS.

This piping system is of large diameter pipe through which feedwater is pumped back from the turbine condensor to the steam generator which is located inside the Reactor Building containment. The system, including the piping and associated valves and pumps, is classified as Secondary System, Safety Category 4, Seismic Category 1. The integrity of reactor temperature and pressure control is dependent upon the I 88.A h. .u es

. 81 M e s ra u.....,

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F % s c N a rss....4 Ng ies M,t,t.

P,s M..w /.w N are, therefore, nuclear safety significant. The 24" carbon steel pipe in question extended on a horizontal run in the direction of the length of the Turbine Ruilding until it reached a position above the discharge nozzle of the pump in question where it dropped vertically toward the pump. Since the pipe-to-pump flange connection was the last remaining fit-up to be made in the pipe run, I was particularly concerned that proper alignment of the pipe to the flange 'was main-tained in order to assure that no improper stresses were imparted to the pump.

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To assure proper fit-up, I identifled the fitters' Foreman and requested that he ask. his General Foreman, Danny McGhee, to request Millwright assistance in fitting this connection. Millwrights are responsible for the installation of mechanical equipment such as this SGFW pump. The Foreman 5

did as I requested, but reported back that McGhee had said go ahead without the Millwrights. I returned to my office where.

i I called Piping Engineer D.M. Dasburg to whom I related the

problem. .

7 Several days later I encountered the same crew of pipefitters in the Turbine Building in the process of actually fitting up this pipe to the pump nozzle. The fitters had rigged a horizontal "come-along" from the pipe to a nearby beam and were " cold pulling" the pipe using extreme force which I would estimate at several thousand pounds in j order to force fit the connection. When I encountered them e

they had almost completed the entire weld. No Millwright was present, nor did I observe any Quali.ty control, Construction i Inspector, or supervisory authority present to witness the

" cold pull" fit-up of this pipe.

8. About one week later I observed two Millwrights, a Mr. Strickland, Company No. 50-185 and Mr. Bass, Company No.

50-105, performing an alignment test on the subject Feedwater Pump. One of them said to me, "Mr. Chan they really screwed up this pump!" The Millwrights were measuring the pump shaf t alignment using an instrument. called a " Dial Indicator" which measures in thousands of an inch. Procedure calls for an alignment tolerance of +/ .005. The Millwrights reported to

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me the results of alignment measurements over a three-day period under hot and cold temperature conditions. Their notes reflected a severe misalignment measurement of as much ,

as + .10 8 " , . 07 8 " under hot . conditions; and + .108",

.075" under cold conditions!

9. On August 25, 1982, I explained this problem to my Supervisor, Alex ruller. I asked him how I should document 4

and report this safety deficiency; and whether I should inform Resident Mechanical Engineer Ed Willett. Fuller told me to document the problem on a " Speed Letter" which he said he would route to Willett. " Speed Letters" are commonly used at the Harris site for not only routine internal communica-tion, but also in place of prescribed Quality Assurance documentation. Use of " Speed Letters" is not prescribed in any procedures for the documentation of construction l

deficiencies, nor are " Speed Letters" controlled documents which are normally part of the Nuclear Plant's permanent quality records. I documented the cold pulling misalignment j of the steam Generator Feedwater Pump as I was instructed in such a " Speed Letter" to Alex ruller, "

Subject:

Loads Imposed on the Steam Generator Feed Pump 1A-NNS," which I

i detailed my observations and attached a diagram showing the i Dial Indicator alignment readings and~the Millwrights' names i

and Company numbers. I closed my message: "Please inve s tiga te . " The very next day I happened to find my " Speed l Letter" with attached diagram discarded in Fuller's trash can!

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10. ,

The following day I spoke with R.T. "Roy"' Settle, a Daniel construction employee who serves as Equipment Installation supervisor. I told him of the problem and showed him my discarded " Speed Letter". Roy said that he had

-l told Ed Willett o'f the problem three times. He quoted Willett as cursing him and adding: "I don' t want to hear any more about that problem. If something happens I will fire you first!"

11. Several months later on October 14, 1982', I observed Millwrights re-checking the alignment of the subject pump.

They gave me a note reflecting the results of their Dial Indicator readings: + .098", .075". I showed this note to Alex ruller. He said nothing. The following day I showed it t

to Ed Willett. He said tell Daren Dsaburg the Piping i

Engineer. I already had. I gave a copy of the note to Dasburg.

12. Since I first raised my concern regarding the cold pulling of this pipe and its effect on the feedwater pump, I became aware of increasing pressure from Fuller and Willett.

4 I sought a transfer out from under Fuller and Willett

thinking that a change in supervision would ease this 4 retaliation. Willett refused to approve my transfer request.

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I pursued my concern regarding the mishandling of the pump deficiency and my request for transfer to avoid the mistreatment. Both Senior Resident Engineer A. Lucas and Harris Project Manager Parsons showed no interest and offered no help. They sent me back to Willett.

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In November or December 1982 I went to see CP6L Vice President, M.A. McDuffle. I told him that I was just trying -

I to serve my. company. I explained to him all about my report

of the pump deficiency. I showed-him my " Speed Letter" and diagram and the Millwrights' notes; I told him of Roy settle's comments. He showed no reaction and as ed no questions. I told him of the retaliation and pressure from Fuller and Willett. He told me that I was a good man, that

,the Company needed me. He said he would h.elp and,that I should go back and request a transfer. I did as'he told me; but my transfer was refused. Mr. McDuf fie did not help me, nor did he investigate my safety concern.s. e'

14. In March, Alex Fuller increased the level of

] pressure on me and threatened me with termination of my job.

He subjected me to " formal counseling" regarding my job i

performance, including a requirement that I impove my

" understanding and explanation of problems." After I requested Project Manager Parsons' help in allowing me to i

rebut Fuller's allegations, Fuller and Willett backed down and dropped their charges.

15. In April, 1983, I went to see Vice President

! McDuffie again for help. This time he sent me back without i

any action or help. Mr. McDu f fie said, "This is the U.S.

This is CP&L, not Vietnam. Here Ed Willett is your Lieutenant and you are only a soldier'. You must obey orders." During the Spring the pressure from Fuller continued to increase. I was assigned more and more works hangers in the diesel generator building, the turbine

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. ;. l building', the reactor building, the auxiliary building and the waste processing buliding. Much more work than my fair share.

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16. In June, 1983, the NRC began to identif'y serious problems in the hanger installation program at Harris. In a June 10, 1983, exit meeting with site management, NRC Senior '

Mechanical / Welding Engineer J.W. York noted problems in the hanger inspection area with particular regard to missed deficiencias and material control problems. Several weeks later Alex Fuller assigned me to work with the QA Surveillance-Group under the direction o,f QA Engineer " Buck" Williams. Our task was to begin an evaluation of the adequacy of the existing pipe hanger installation program.

Fuller instructed me to select, at random, about 50 hanger packages for review, with particular emphasis on material substitutions, use of surplus materials, and identification of Construction Material Requisitions (CMR's) that did not match the hanger materials actually installed. These areas represented significant problems which the NRC had observed and which indicated the potential need for costly and time consuming reinspection and rework.

17. At Buck Williams' request I pulled 50 hanger ,-

packages for seismic hangers on safety-related systems which were supposed to be Phase 11 completer installed, inspected, and found acceptable for turn over to operations with only the' final Phase III stress analysis yet to be performed. Of these, the QA Surveillance Group inspected 12 at random. In

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the course of this review numerous serious deficiencies were noted which had not been identified, documented'or eErrected  ;

althoughthesehangershadallreceivedfinalapproval[byCI l and CP&L QA/QC. / '

18. By " Speed Letter" of July 18, 1983, I ' transmitted to -

Alex Fuller and Ed Willett my completed " Hanger Phase II ,

verification Checklists" for these sample hanger packages.

Fuller was very angry that such a large number of deficiencies had been identified, and he blamed me for ,

documenting all of these problems. In particular he focused 'aI v i

on the proolem of material traceability which we had .I identified on many of these hangers. For example on pipe hanger A-2-236-1-CC-H-105, 4. " Speed Letter" of 4/25/80 indicates that a 1" x 10" x 10" plate was obtained from Purchase Order 21022 and installed as per drawing. Po 21022 was cited na the source for material in nany of the hange{,s we examined. I exnlained to ruller that ? had ra * *e rn k a d--

uito rv wscn va inEpector Jay vincent and another man on the Surveillance team. We could find no documentation of'this PO in the CA records vault. In the Purchasing Department, Robert Babb informed us that the Purchasing Log showed that Po 21022 had been voided and that no materials had ever been received through that order! We could not determine where <

these hanger materials had come from or document that such materials were of acceptable quality for nuclear safety application.

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19. , Later that af ternoon Fuller called me into his office.

He called me "a liar" and said that he had found documentation for P0 21022 in the warehouse. He accused me of not doing my job properly. I asked him to wait for the bI issuance of the Deficiency and Disposition Report (DDR) by the OA surveillance Group which would confirm my report of material traceability problems and, in particular, the apparent falsification of documentation involved in the repeated use of void Po 21022 to supply traceability for hanger materials of unknown origin. I returned to my work.

20. DDR 1775 was issued by Buck Williams on July 26, 1983, documenting the QA Sueveillance findings, as well as my report to Fuller and Willett regarding the void PO. That DDR states that "PO 4 21022 was volded and no documentation exists that material was received." It also states: "A further investigation of PO 4 21022 revealed that material '

from this PO was used on pipe hanger 1-CC-M-1242, 1-RH-H-183, and numerous other pipe hangers not listed here, although Po ,

1. 21022 was voided . . .

DDRs 1776, 1784, 1795 and i

Nonconformance Report (NCR) QA-255 .lso document problems we found in the hanger verification.

21. In respopse to my report to ruller and Willett of QA failures, Willett issued a Memo July 29, 1983 "

Subject:

Shearon Harris Nuclear Power Plant - Compliance. with Project QA Programs and Procedures", which emphasized that compliance with QA procedures is " mandatory" and provided examples of

" Do ' s a nd Don ' t 's " .

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on August 1, 1983, Assistant Project General Manager P.F. Foscolo responded to our. Phase II hanger surveillance and the NRC concerns by providing for significant changes in I the hanger program. A stop work order'had been issued on July 29, 1983, halting all work and inspection on seismic hangers. Phases I and II were eliminated; work and QA procedures were substantially changed, including particularly WP-110, and TP-34, which provided for hanger installation and inspection. In particular, CP&L noted that hanger documentation should be checked to insure "that the surplus hangers number / purchase order number is legitimate". At that time only about 300 of the 18,000 seismic pipe hangers had successfully passed inspection. I remain concerned about the use of false documentation on such safety grade materials.

Has any effort been made to investigate the cause or extent of this problem at the Harris Plant? *

23. On August 22, 1983,klexFullerpresentedmewitha Memo signed by himself and Ed Willett reflecting their decision to place me on probation due to what was described as a decline in my performance "over the past year and one

_ , half". Of course, Fuller himself had promoted me to Engineer less than a year earlier!

I believe that this action was in retaliation for my expression of safety concerns. I refused to acknowledge Fuller's false charges, and, ins,tead I wrote:

"I do not agree with this statement", on the memo.

Ironically one of the actions required of me over the next 6 months was: "

. . . problems that are detected must be reported accurately and timely.". CPfrL management

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_, e demonstr'ated time and time again that they wanted us to look the other way when we encountered deficiencies. " Problems " _

were the last thing they wanted reported.

24.

In the Fall of 1983 I met with CP&L Executive Vice President E.E. Utley in Raleigh. I carried with me all my documentation of safety concerns and deficiencies, including those described here. I explained these concerns to Mr.

Utley and the responses to them by my supervision. He showed little interest in anything I said or any document I showed him.

He did not ask questions regarding my concerns or my treatment.

He said I was a " good man" a,nd that I should go back to work. He promised to help. He did not.

I performed (p';.]j.j.

all work assigned to me over the next 6 months, and have -

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)1 *1g retained documentation of my satisfactory performance under increasing pressure and intimidation by my supervisor, Alex Fuller. All my requests for tr'ansfer were refused.

At the end of 6 months, I was called before Messers Foscolo, Rager, Ferguson and Fuller who told me that if I did not resign I would be terminated. They urged me to make it easier on myself by resigning; and said I would have a hard time getting another nuclear industry job if I did not resign. I told them I had done nothing wrong and would not resign.

That afternoon, February 29, 1984, Fuller escorted me like a prisoner out the gate without even a chance to exchange farewells with my colleagues and friends.

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25. ,I have very serious concerns regarding the breakdown j 1

of Quality Assurance at the Shearon Harris Nuclear Power Plant. There is a great deal of pressure on the Construction i Inspection (CI) organization which lacks the freedom and independence from cost and scheduling considerations to ef fectively perform their OA duties of identifying and documenting deficiencies. As an Engineer I was always aware of the conflict between production and quality. Both CI and Construction Engineering reported to the Senior Resident Engineer.

26. CP&L and its prime contractor Daniel employ a confusing and ineffective array of different documenting

( systems for controlling nonconformances such as DR 's, DDR's, NCR's FCR/PW's and such commonly used uncontrolled paperwork as Memos and " Speed Letters". Few of us were trained in which procedures were to be used when. Mostly we wrote things down informally. I doubt that the QA vault contains even a fraction of the deficiencies in safety systems which have been identified. In order to ensure that I communicated effectively in my work - particularly since English is my second~ language - I made it a practice to retain full documentation of work in my areas. I have " Speed Letters" reflecting numerous deficiencies which I am sure have been discarded by CP&L. I also have retained copies of many l quality documents which I believe have not been properly i

controlled by CP&L.

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• e I hope that someone will seriously investigate my safety concerns. I know that many other present and former Harris employees, including craft and other engineers, share my concerns.

However, they are not eager to share my experience !

in order to voice those concerns, since they have every reason to fear the same kind of retaliation that I have experienced.

I hope that this statement of mine will make it easier for the others to speak more freely.

I am willing to assist in identifying and correcting quality assurance and workmanship problems in any manner necessary to ensure that the Shearon Harris Nuclear Power Plant does not harm the public.

CHAN VAN VO Sworn to and subscribed before me this the day of ()d _

, 1984.

/2/J b NO pWY PUBCIC My Commission expires: F 7 ((

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1 10/25/84 WE Contentions (based on Chan Van Vo affidavit made public 10/22/84)

(& NRC regulations / requirements) l 41C -

CP&L Quality Assurance procedures and records violate NRC requirements because falsificahion of Nuclear Safety ,

Material traceability records has occurred and there-is inadequate assurance it-is not continuing (or undetected so far in Harris Plant Q7. records)' . This violates 10 CFR 50 Appendix B Criteria, e.g. #'s 17, 6, 1, 2, 7, & 15, 16, 8, 9. Fbr initial basis, Refer, e.g. to Chan Van Vo affidavit (available to me as of 10/22/84), e.g. paragraphs 18, 17, 16, 3, 4, 22, 23, 24.

41-D The Harris plant is in violation of the material traceability requirements of 10 CFR 50 Appendix B Criteria 8, 4, 6, 7, 1, 2 , 15, 16 & 17, because of inadequate or nonexistent documentatio'n of material used in safety related equipment, e.g. as stated or described in Chan Van Vo affidavit (dated 10/06/84, first available to me 10-22-84) 1's 20, 16, 17, 3, 4, 13, 18, 19, 22, 24 & 26.

41-E There has been a breakdown in Harris QA/QC programs for safety-related pipe hanger recordkeeping, installations,

and inspections, violating all 17 requirements of 10 CFR 50 i

Appendix B. Basis is as described in Chan Van Vo affidavit t

(1st available to me 10/22/84) ~ 1s 17, 18, 1, 3, 4, 14, 15, 16, 19, 20, 21-(past noncompliances not corrected *), 22, 23, 24 &

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I 26) .This also includes the wholesale discarding of documents including pipe hanger documentation or packages,* to.Mr. Chan van Vo's belief.

• These amplifications of CVV affidavit conveyed to me by his counsel by phone - 8 pm 10/24/84.

41-F: QA concerns not documented properly at Harris in violation of 10 CFR 50 APP. B Criteria 6, 7, 8, 17, 1, 2 , 3, 10, 11, 13, 14, 15, 16 & 17. See Chan Van Vo affidavit of 10-6-84 at is 26, 9, 10, 13, 15, 16, 17, 18, 20, 19, 22, 24.

These violations mean that the safety & quality of Harris safety - related systems cannot be established i

41-G. There exists a pattern of harassment, intimidation, &

failure to respond positively to employees bringing forward QA/QC concerns at the Harris plant (see, e.g. Chan Van Vo e

affidavit of 10-06-84 e.g. Ts 26, 25, 24, 23, 19, 15, 14, 13,

! 12, 11, 10, 9, 6, 4, 3, & l. This prevents concerns from being brought forward & dealt with properly in compliance w/10 CFR 50 1 App B e.g. criteria 15, 16, 14, 1, 2, & 3 i

41-H CP&L's failure to give sufficient independence to Construction Inspection (CI) & other QA personnel toWfTrm their duties without pressure or harassment, prevents proper 4

QA/QC on the plant, particularly all parts / systems / items I

inspected by CI when it did not have sufficient independence of cost / schedule concerns, and other parts / systems inspected by QA/QC personnel w/o the independence required to comply w/10 CFR 50 App B. See e.g. Chan Van Vo affid. 1 25, 26, & as cited I

in 41E & G above

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C CONSERVATION COUNCIL'S LATE FILED CONTENTIONS BASED ON THE AFFIDAVIT OF CHAN VAN VO-October 30, 1984 WB-1 The Quality Assurance program at Shearon Harris is deficient in that the nuclear safety material traceability documentation was falsified ar.1 other QA documents relating to safety were falsified or destroyed. This is in violation of 10 CFR 50, Appendix B, Criteria II (the QA program "shall be documented by written policies. . .and shall be . carried out. . .") (emphasis added), Criteria VI, Criteria VII, and Criteria VIII. Basis is provided for this contention by the affidavit of Chan Van Vo and other related documentation, as well as other similar material from'other current or former workers at the Harris Plant.

WB-2 The piping line to the discharge nozzle to the Steam Generator Feed Water Yump 1A-NNS was improperly installed thus causing improper stresses to the pump (see Chan Van Vo Affidavit, page 5 g seq., for details). The safety significance of this improper installation is that the integrity of the reactor. temperature and press.ce control is dependent upon the effective function of these pumps, valves, lines, etc.

_ The five factors applying to late-filed contentions was supplied upon oral arguments by Wells Eddleman and John Runkle, Counsel for the Conservation Council, during the hearings on safety issues, October 25, 1984.

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514 YO2k 1cl . Pr, cue (9/9) 86+-54 7/

• etteville, N*C 28303

, A u'sb 2e .19e+ l ADMIN 7STRA TOR,,.

l hlage and Hour Division, i Emplo ment Standa>d. Adminislmilon.

u. s . D t m eset o 2oo Con.efil.ufion.Are f La.bor W W -

Wa.s/sigic+r/ D.C. Boato SUB0~ECT: Cont.plainb of discrinslua$ ion. agalust Ca> olina Power $ bykt Co. under 29 cra.

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Pa>-t 24 Dear 5'ir oe Mada+n. ;

I believe t'/ rad Iha ve bee +e. discrinsoled ayk by m ;6ruter emplayer, Qu afina. Pow 4byId C bec~g ,

se of my ac2'< an.s u, t< expressmp conceens-

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and clocumen.L*+tg consi.ru.ct&on, of 1/re defacie+z.cles Strearo>r Ha.rris As 1Re Nuclea5 desig/%we Plan.t where I worXe& as a., Consteuc11o+t, Fie/cl.

Englueer ati t'lte MecJ<a.w&L Depart.mant unile, ny ternt.inafio+1. a.h c u.t /Te b . 29, i9e+ . I /rav.e. k refusecl. eos1.p/c4merth for wIsicis. I a.m eju.aflf'eet by many &clea.>.- a.n.d. o1/reu 9~irms because of C PdL's discriminafor,tj 'freabbren*b . I on.& leartre, f of my,eq/sts unden we emp/c,yee piotec%n.

proviston.s of s'/se. ENEAG>' h?ECMA MIEA MON ~ AC7 a. net

k oa>-t+tsent j of La ber /?ega.la1Lons kviflebt.iI'te las 4l'tEk& dags.

I re9a.est fbad, yau. o+-der CP4L 6o pro vide.

me- redie,C {ce ifels discrlin.' nation. htcfading.

pro viding. sne. bacz pa of.lw&- cwnifo h/e redief. y , compensatlan.

M T have been e+st.pl.ogecl, by CPd L a,b t.l1e.

Shea.ren. } 'vris Nu~ .clea> Powe, P/axt un. des

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< con.sl> ucL'on. a.h New Hill. , No~ rthe %fina aluce.

Apri$ /0,197.9 . I have been prosst.obed froset Engineering Ai.de. f.o EsagZueering 7eoh.u)cinn .2C, '

Assoclefe Englueep , aud. fr*nafG Enginees.- Lv ocho6au, t98u where I was a.ssig n ad. f.o woeK w';

Alex f~a.//er , Peine*~f Engbreer - Hangees . Ikawe, been, eubyect to lepeafed. ha.ra ssment, c'nlim *da2 pressu.>-e an.d oZises ct'Z ecelsuinnflcn berame eg"m acfions secA,A Min, p/re erformin

&lenfi Eca14citu<g Y .

an.da.ssynad docu m.enk d~iles An w -

of desyn, au.d cen.sleuction. def<:clencies .

For excun l CoinmiesEc>ple s. Asled de

, la Ju~ ne , /983 , The A&ctn fey ots.

an.c Mi . Falles- asstyxed metoficlexci.e& foi- aus- area-iQcb ide hastgent few fu.,1/1e>- defsc.Lesecied a.long avif4 f4e Gn/>*L Assanmce Sa>reselance. G . Anes. I easmNA-% ori 4<., Tu. 'clencA ru)/.eu.-@' toldz mewhici.< e-L.a ais2,-

was l.arge Aanstum.ber a s u no ay"t hour.

h.ow to perfor m m.y job . Ahhough.14e Guaq Assu>-ance reporte supported. 9 (4<. ding &, .T um

^ placed on. six suose71sa P,e ba.ficn about #

A ust 2:

t9es, A~ s fa pes-formance. having

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• eet belew the'a.ccep le.-

/we2 foe die cfasSCf?dca1Ec3 t.

af E11(.aer ove> f.Ae pasb geas- M one Aaff. #

I pe>-formed. su.y 4ofin wAZ.&. ci<- prohdian an.d. was not b< formed af ay poorperformance. .

I was repea led.G presscered. to resign a*rd mis

-finalg 'le+>uina.fecc o. boa.b Feb. 29,,19e+ .

z repeaf.eaq-L4lscom.platuea 1o my ee>.lo-a a.e su,fadin CP$L aboah d2scsz'mino 4'en in c. Suele

[ neasu1gement, w4o prornisect to hee,o me .g7h' ey sen.6 me. he.cg/ -lo war 16 wi/hou.6 any heep. No one ab D. o .CP4L As)tsuis,atzart%med.

l. dzsc< nre to +in ofing . file6ig/<h

-t4ls

. comp a l ..

I hase t>-ted. t.o get .Aafp may people. anot

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, Governures A Ag.encles . Afe;ne. of -tirem J1are inform

>>1a of my +Zgals to /sle Mts cosaptain.t . zn Pfaro4 , /984 711e E>np/opment Seca,ZG GassemissEas of Moef/r Caroll' net. A'apresess.la&*ve to&L este 1/ ret CPt L was aNowecL. -/c fes-m.Zsrefe, are ass.aa- r these Direwerstances . Z~t > l'784 %a.sd'een Afrid a>rd ab 771e l/.S. Departenent c/ 74.h , LaAov ofr 4- i e:

/bs.A.efp/s.ZMgto>t Ar.- M/a.~s D.c . Atifro ug4 .Z exp'/al>seet. stig ccsnp laint I was .seut awag ca.ch tOsre. WI/bcut IreAf er En/cr>>sa1*cs1.- aboub n<4 rG/1.ls ic /<.*Le.

l th i s c o i n p fa ht. h .

l I haua app ied. l for and. bee >< Larsred. clown '

.)o' r kra Nuclea, and Mas, hGc/eae. pbs . foe whicl< .y>r.etu.e 4 cyea /Zf* eel. be~ue of CP4 f 's c4*x ?Zise.brafic>t. T a u <. a$E$d wt.eu<ployecf.

Abou.b' & 3/i /9 8 4. , I IN a s th l ci n 14 of b c t.-

A?efrasexb2ve o.f 7'Jre GoverstAMest.t Accoon / Aid e e. Protsef *m Pro visdans V Proyect of //re. eylog//terss<nce. Ou's, of /A e La.w assd of / row fo f<.Ye t

Coylain &.

I a.s M for yew- he Ap Ere in.ves?.i'ga.6*ng 3 corvtplaZ>12 au.a. pro vie /2n m e. a q A a. M e

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mA 39 fo~ t/u.'.s c:4'scrimi fion . .i w/ H b e.

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t u t.

sypo-b of' >ng comp a/nc i Sz>rces-eQ, CNA N VA N VC

( Als c kn' own as VAN yo ogp?*s_,,)

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

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+

.U.S.D pfriment of Labor fme!o>mo :: s?#6darcs Adm;nistration Wage and Nour Omnion

( ,,

P. O. Box 27486

( J Raleigh, N. C. 27611 ,

DATE: October 12, 1984 Telephone No. 919-755-4190 Reofy to the A!!ention of: Wage-Hour Mr. Chan Van Vo Chan Van Vo vs. CFL 514 York Road i Tayetteville, N.C. 28303 Deer Mr. Van Vo: -

f This letter is to notify you of the results of our compliance action in the chove case. A previous letter from this office advised you that your complaint

ras received on September 13, 1984, and enclosed a copy of Regulations, 29 CFR

. Part 24 and a copy of the pertinent section of the Energy Reorganization Act.

, Our initial efforts to conciliate the matter revealed that the parties would not

, at that time reach a mutually agreeable settlement. An investigation was then f

conducted. Our investigation did not verify that discrimination was a factor in the actions comprising your complaint. Conversely, it is our conclusion that your ellegations are unprovable for the following reasons:

In order to have a valid complaint the following factors must be met.

1. You must be employed by an employer subject to the Energy l ,

Reorganization Act.

2. You must have been discharged or otherwise discriminated against with respect to compensation, terms, conditions, or privileges of employment. _

i

3. Finally, the alleged discrimination arose because the employ a participated in a Nuclear Regulatory Commission Proceeding '

Under the Energy Reorganisation Act of 1974.

W2 could not suberantiate ites 3 cited above.

Employer's records and interviews with supervisory employees reveal that you were placed on six months probation in August 1983, because of unsatisfactory work performance. You were terminated in February 1984, because your work performance had not improved.

This letter will notify you that if you wish to appeal the above findings you have a right to a formal hearing on the record. To exercise this right you must, within

'five (5) days of receipt of this letter, file your request for a hearing by tele-gram to:

The Chief Administrative Law Judge U. S. Department of Labor Suite 700, Vanguard Building Illi -- 20th Street, NW Washington, D. C. 20036 ls w- - _ ---- ---- w---w--,-,-----.--~,w

2. * .

.5 Page 2 Chan Van Vo 514 York Road Fayectaville N.C. 28303 Unless a telegram request is received by the Chief Administrative Law Judge vitihin the five-day period, this notice of determination'will become the final order of the Secretary of Labor dismissing your complaint. By copy of this letter 1 as advising Carolina Power & Light Company of the detemination in this case sud the right to a hearing. A copy of this letter has also been sent to the chief Administrative Law Judge with your complaint. If you decide to re-quest a hearing it will be necessary to send copies of the telegram to Carolina-Power & light Company and to me at U. S. Department of Labor, Wage and Hour Division. P. O. Be.f 27486, Raleigh, N. c. 27611. After I receive the copy of your request, appropriate preparations for the hearing can be made. If you have any questions do not hesitate to call me.

It should be made clear to all parties that the role of the Department of Labor is not to represent the parties in any hearing. The Department would be neutral in such a hearing which is simply part of the fact-development process, and only allows the parties an opportunity to preaant evidence for the record. If thera l is a hearing, an Order of the secreta ~y shall be based upon the records made at 3 said hearing, and shall either provine appropriate relief or deny the complaint.

Sincerely,

. St Area Director cc: Ms. Margaret Glass, Associate General Counsel carolina Power & Light Company P. O. Box 1551 Raleigh, N. C. 27602

Nuclear Regulatory Countission .

101 Marietta Street

! Suite 3100 Atlanta, Georgia 30303 i

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- . _ - - - _ - - - , + , _ , . - . _ . - . . . . . _ , - - - , - - . . - , - - - _ . - . _ _ _ - . . - - _ . _ - . _ _ _ _ _ . - - . - . _ . - _ _ _ _ - - . - - - --

i

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD r

In the Matter of )

)

)

. CAROLINA POWER & LIGHT COMPANY ) Docket No. 50-400 OL and NORTH CAROLINA EASTERN )

MUNICIPAL POWER AGENCY , )

)

(Shearon Harris Nuclear Power Plant)

AFFIDAVIT OF A. PARKS COBB, JR.

County of Mecklenbura ss.

State of Ncrth Carolina )

A. Parks Cobb, Jr., being duly sworn according to law, de-poses and says as follows:

1. My name is A. Parks Cobb, Jr. and my business address is Duke Power Company, 422 South Church Street, Charlotte,

North Carolina 28242. I am Manager, Project Management Divi-l sion, of the Design Engineering Department at Duke Power Compa-

ny. The Project Management Division irr ~sponsible for (1) en-gineering project management of all company in-house projects in which the Design Engineering Department has a role, (2) man-agement and technical services activities for outside clients through the MATS (Management and Technical Services Program)

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

and. '(3) departmental support in scheduling, budget and cost control, computer. aided drafting', and computer applications and

.- production support. Previously,-I was Manager, MATS, which is a section within the Project Management Division of the Design Engineering Department which is responsible for business devel-opment and project management activities associated with

-providing Duke's services to outside clients. I have worked for Duke Power Company for eleven years and, in total, have over twenty years of professional experience in engineering, I

project management, and research and development. A detailed statement of my professional qualifications and experience are provided in a resume which is included as Attachment 1 hereto.

2. In October of 1983, I was retained by Carolina Power &

Light Company ("CP&L") as a consultant to provide outside, third-party review of activities performed by a review panel, headed by Dr. T. S. E11eman, CP&L Vice President, Nuclear Safe-ty, which was assigned to solicit and evaluate potential technical i concerns raised by quality inspectors at the Shearon Harris Nuclear Power Plant construction site. This activity consisted of re-viewing the collection and disposition of technical concerns,

reviewing qualifications of the review panel members themselves

! and providing a final report of findings to CP&L management.'

As part of this program, CP&L requested that I review and com-ment on their newly fonned Quality Check Program. In per-forming this activity, I reviewed in detail CP&L's i

a a

2

documentation which describes the operation of the Quality Check Program and selected Quality Check interview forms and logs being maintained at the Shearon Harris Nuclear Power Plant

' Site. I brought to this task my experience at Duke in serving as chairman of a Duke task. force assigned to investigate tech-nical concerns of welding inspectors at the Catawba Nuclear Station Construction Site.

3. On October 15, 1984, Mr. H. R. Banks, Manager, CP&L Corporate QA Department requested my assistance in reviewing, investigating and addressing concerns raised in an Affidavit they had received from a former employee, Mr. Chan Van Vo.

In performing this activity, I first reviewed the Affidavit and identified items in the Affidavit I considered to be signi-ficant issues. I recommended to Mr. Banks that I focus my attention on concerns raised in the Affidavit related to manage-ment responsiveness, particularly those raised in paragraphs #12,

1. 13, #15, #23, and #24. I also recommended a course of action on other issues. For the issues I was to focus on, I recommended an approach utilizing personal interviews with management personnel identified by Mr. Chan Van Vo as well as any other CP&L personnel likely to have knowledge relating to the inquiry. Mr Banks con-curred with this approach.

h 3

I conducted interviews, and the information obtained from those interviews and my findings are documented in a report to CP&L which is provided as Attachment 2 hereto. This report contains my specific findings relative to.the assigned paragraphs and additional information regarding other issues raised in the Affidavit which was obtained during these interviews.

A. Parks Cobb, Jr.

Sworn to allg ubscribed before me this e/ # day of November, 1984.

//Shb Notary Public ks/YwW/

~ ~

My Commission Expires: My Commission Expires November 4,1987  :

i i

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Attachment 1

• RESUME ALTON PARKS COBB, 3R.

FORMAL EDUCATION: University of Alabama - Huntsville: 1966-72 (33 hrs toward M.S. in Engineering Mechanics)

North Carolina State University: BSME 1964 Rocky Mount (NC) Senior High School: Diploma 1960 ADDITIONAL TRAINING: TECHNICAL Miscellaneous Technical Seminars (structural mechanics, analog compu-tation, vibration analysis) (Boeing)

M.2cellaneous Computer Program' Usage Seminars (SUPERPIPE, ASTRA, N ASTRAN, STRUDL) (Boeing, Duke)

Seismic Design of Nuclear Power Plant Facilities (University of Pittsburgh)

Time Series Analysis for Noise and Vibration (Structural Dynamics Research Corporation and Time Data)

SUPERVISORY /MANAGEMEN1 Dynamics of Motivational Management (Success Motivation Institute)

Supervisory Training (Duke)

Effective Project Management (Center for Professional Advancement)

Management Development (Duke)

Effective Interviewing (The Psychological Ccrporation)

Boomerang II - A Management Training Program in EEO (Duke)

Persuasive Communications Seminar (Technologies)

Effective Management (Harbridge House)

Advanced Management Development (Duke)

PROFESSIONAL INVOLVEM ENT: Registered Professional Engineer - NC 6817, SC 5951 Member - ASML WORK EXPERIENCE:  ;

l FROM TO TITLE PROGRAM COMPANY l 10/S4 Present Manager, Project Management Division Duke Power PMD Design Engineering Department l

In charge of Project Management Division of the Design Engineering Department which is responsible for (1) engineering project management of all company in-hcuse projects in which the Design Engineering Department has a role - principally design in support of new and operating electricity generating facilities of nuclear, fossil, and hydroelectric types, (2) management and technical services activities for outside clients through the MATS program, and, (3) departmental support in scheduling, budget and cost control, computer-aided draf ting (C AD), and computer applications and production support related to department usage of corporate mainframe computers and personal computers.

1 .

Resume - A P Cobb, Jr Page'2 WORK

-EXPERIENCE: . (continued)

- FROM TO TITLE PROGRAM COMPANY 9/8'2 10/84 Manager / Management and .

Duke Power Section Head Technical Services (MATS)

In charge of nesv section in the Project Management Division of the Design Enginaring Department which is responsible for business development and project management associated with providing Duke's services to outtide clients.

6/81 9/82 Principal Engineer / Nuclear and Conventional Duke Power

. Section Head (6/81) Power Plant Design In charge of civil engineering section responsible for design support for all operating stations,

. including nuclear, fossil, hydro, and combustion turbine. Section work included periodic 2

and emergency inspection and maintenance, upgrade, and addition to operating plants. Engi-neering scope included safety and non-safety related design in the areas of structural steel and concrete structures, pipe and equipment support / restraints, ash basins, and spillway structures. Served as chairman of a task force to investigate technical concerns of welding inspectors at Catawba Nuclear Station construction site. Provided testimony in support of this activity at Atomic Safety and Licensing Board (ASLB) hearings for an operating license for Unit 1.

i 4/80 6/81 Senior Engineer / Nuclear Power Duke Power Group Head Plant Design j In charge of McGuire stress analysis and support restramt design group which was responsible for initial piping analysis and pipe, equipment, and ductwork support / restraint design for McGuire Nuclear Station, Units I and 2. Group Head duties included management of in-house engineering work performed by approximately eighty (80) Duke personnel and two hundred and forty (240) contract personnel, most of whom were engineers. Personnel were located i

in Construction Site offices (Group headquarters) and Charlotte area office. Duties also included management of out-of-house consultant-performed piping analysis analysis and restraint design of approximately seventy (70) personnel (EDS Nuclear). Group completed work to support McGuire Unit I fuel load in 1/81, including closeout of major USNRC Bulletins 79-02 and 79-14.

12/78 4/80 Senior Engineer / Nuclear Power Duke Power Group Head (11/79) Plant Design i

In charge of group responsible for computerized analysis of all designated piping outside containment for Project 81 Nuclear Stations (Cherokee Units 1, 2, and 3; Perkins Units

, 1, 2, and 3) encompassing ASME Class 2 and 3 and ANSI B31.1 piping. Duties included i organization of group, establishing training programs, recruiting new employee engineers, l technicians, and draf tsmen, and recruiting temporary (job shop) engineering personnel.

l l.

l l

l Resume - A P Cobb, Jr. .

Page 3 '

I WORK '

EXPERIENCE: (continued)

FROM TO. TITLE PROGRAM COMPANY 7/76 5/79 Design Engineer (8/76) Nuclear Power Duke Power Plant Design In charge of group responsible for managing consultant contracts for performance of ' computer-ized piping analysis of designated piping inside and outside containment for McGuire and Catawba Nuclear Stations, including Nuclear Steam Supply System (NSSS) contractor analysis of Reactor Coolant Loop piping and consultant contractor analysis of piping. In charge of group responsible for special stress and vibration and analyses for all current projects, including analysis and criteria definition for welded attachments to piping, mechanical equip-ment anchor bolt analysis, containment piping penetration analysis, analysis and test develop-ment program for pipe whip energy absorbers, development and implementation of in-house program for vibration testing of non-rigid valves, and performance of troubleshooting test and analysis for mechanical equipment in operating plants.

, 9/73 7/76 Assistant Nuclear Power Duke Power Design Engineer Plant Design In charge of group responsible for resolution of anchor installation problems with mechanical equipment, responsible for seismic design criteria development for mechanical equipment, and responsible for mechanical troubleshooting of vibration problems in operating plants.

I 6/64 9/73 Senior Engineer (4/73) Aerospace & The Boeing Engineer (2/70) Military Company Associate Engineer (6/64)

Performed structural dynamic, load, and stress analyses on a variety of contracted and company-sponsored projects. Projects included Saturn V recoverable booster study, Improved HAWK missile, Saturn V Integration, Multiple Artillary Rocket System (MARS), Lunar Roving i Vehicle (proposal and development contract), Saturn V - Shuttle Impact Study, and U.S.

Army Corps of Engineers Safeguard Program. Other duties included detailed involvement in development and use of large scale computer programs for performing structural analyses using finite element and matrix methods, implementation of computer graphics in digital

- ~ computer solutions to time history dynamic analysis problems, and development of scale

[. model testing of water impact dynamics of spent rocket boosters.

I

Attachment 2 REPORT OF RESULTS OF INTERVIEWS CONDUCTED WITH CP&L PERSONNEL RELATED TO SELECTED ASPECTS OF AN AFFIDAVIT SUBMITTED BY FORMER CP&L EMPLOYEE CHAN VAN VO Prepared by:

A F Cobb','Jr.

Manager, Project Management Division Design Engineering Department Duke Power Company October 31, 1984 Revised November 9, 1984

i l

TABLE OF CONTENTS 4

Section Subject Page 1.0 Overview 1 2.0 ' Background 1 3.0 Paragraph #12 Items 4 4.0 Paragraph #13 Items 5 5.0 Paragraph #14 Items 6 6.0 Paragraph #15 Items 7 7.0 Paragraph #23 Items 9 8.0 Paragraph #24 Items 10 9.0 Events Related to Steam Generator 12

, Feedwater Pump Pipino Installation 10.0 Events Related to Phase II Hanger Program 14 11.0 Isolated Incorrect Statements in the Affidavit 16 l

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

1.0 Overview This report documents results of discussions held with CP&L personnel related to statements contained in an Affidavit submitted by Chan Van Vo, a former CP&L employee in the construction organization at the Shearon i

Harris Nuclear Power Plant (SHNPP). -The discussions pertained to the statements made in Paragraphs #12,13,14,15, 23, and 24, which address CP&L management responsiveness to alleged safety concerns by Chan Van Vo.

The purpose of the discussions with CP&L personnel was to ascertain facts related to CP&L involvement in the events cited in these paragraphs.

Parties cited as contacts made by Chan Van Vo were interviewed, and others were interviewed who might have been in a position to confirm or 4 contradict events recalled by those primary contacts. Personnel cited as contacts by Chan Van Vo and who were interviewed were Alex Fuller, Ed Willett, R M Parsons, M A McDuffie, and E E Utley. Others interviewed were John Ferguson, Dr. T S Elleman, and Darren Dasburg,

2.0 Background

Statements cited in Paragraphs #12, 13, 14, 15, 23, and 24 of the Affidavit were part_of_a-sequence of events that occurred during Chan Van Vo's employment at SHNPP. Discussion with personnel involved, especially Alex Fuller and Ed Willett, provided a description of events related to Chan Van Vo's employment. This sequence of events is important to place statements made in the Affidavit in perspective.

4 1

1. Chan Van Vo was initially employed as an aide at SHNPP and was later promoted to technician.

l

2. Sometime later, in October 1980, Chan Van Vo was promoted to entry level' engineer status after completing correspondence school training.

3. As an engineer, Chan Van Vo worked in_the piping area under Ed Willett.

4. While working in the piping area, Chan Van Vo developed a history of problems associated with his work. There does not appear to be specific documentation available; however, Ed Willett was aware of problems, both in his individual performance and with his interface with others. Because it was-not clear as to the source of the problem, it was deemed appropriate to move Chan Van Vo to another area of work and provide an opportunity for a fresh start.

5. In April 1982, Chan Van Vo was assigned to work under Alex l

Fuller in the area of pipe hangers. At the same time, Ed Willett contacted John Ferguson (CP&L Employee Relations) and arranged for Chan Van Vo to talk with Mr. Ferguson regarding concerns about his employment situation.

l 6. -Chan Van Vo was promoted in October 1982 to the second level engineer classification at CP&L. This promotion was generally 2 ,

. 0 l

I in accordance with CP&L's promotion policy whereby an entry  :

level engineer is promoted at the end o f- two years if performance is satisfactory.

7. Counseling for performance problems in Chan Van Vo's work under Alex Fuller began formally in March 1983. This counseling was received in a resentful hostile manner by Chan Van Vo, who denied any unsatisfactory performance even though he was presented with documented examples.

8. Counseling continued until August 1983, at which time Chan Van Vo was placed on probation and provided again with a clear statement of areas of his performance that were unsatisfactory.

9. Counseling continued from August 1983 until February 1984 without noticeable improvement in performance in the areas cited when Chan Van Vo was placed on probation.

10. In late February 1984, a final. counseling session was held and Chan Van Vo was infonned that progress on items requiring l improvement in performance had not been satisfactory. He was i given an opportunity to resign in order to prevent having a job termination on his record. He refused to resign and was tenninated on that same day. He was escorted to the gate on that day in accordance with standard procedure.

3 l

. Technical items- cited in the Affidavit which relate to the fitup of.

l piping to a steam generator feedwater pump and related to the Phase .II l

, hanger program occurred .during . the time frame that Chan Van Vo worked under - Alex Fuller's supervision in the hanger area and was receiving counseling for unsatisfactory perfonnance. Both the steam generator feedwater pump piping and the Phase II hanger program situations were complex and covered a sub tantial span of time (months). Chan Van Vo became involved in these situations either due to actions of his own or by virtue of assignment and worked on isolated aspects of each. He collected an isolated sample of data, drew his own conclusions, and may have pursued some actions on his own as he was prone to do. Since both situations were already being attended to by assigned CP&L personnel who had knowledge of the entire situations, Chan Van Vo's information provided little help and nothing new and was likely not given special attention. As can be ascertained from information later in this report, j individuals who he supposedly contacted and provided specific information i

regarding these two situations have no recollection of any-such contacts.

To aid in understanding of events that actually transpired related to steam generator feedwater pump piping and the Phase II hanger program, individuals interviewed provided an overview which is documented later in j this report. /

1

} 3.0 Paragraph #12 Items ,

i I

In Paragraph #12 of the Affidavit, Chan Van Vo made reference to

" increasing pressure from Fuller and Willett." He stated that he sought

~

a transfer which was refused by Willett. Based on the time frame he is L

I 4

- .- _. = . __

referring to, this was the ' time frame during which ~ counseling for performance problems unrelated to ' the steam generator feedwater pump piping was taking place. He requested a transfer and the transfer was approved by all levels of supervision. He was interviewed once or twice for assignment to other areas, but other organizations were not interested. Willett had no other areas under his supervision available in which to transfer Chan Van Vo and, in fact, needed his assistance in i

the hanger area due to the magnitude of the hanger work. Chan Van Vo did not contact R M Parsons directly with respect to his request for transfer or concerns with Fuller and Willett. Although he saw him frequently, i

Parsons recalls only two contacts with Chan Van Vo, one related to organizational information which he provided and one contact made in' the field where statements were made about the installability of diesel generator piping and pipe supports.

4 l 4.0 Paragraph #13 Items 1

i

! Chan Van Vo relates incidents associated with a discussion he held with M A McDuffie in 1982. According to McDuffie, he talked with Chan Van Vo i sometime in 1982, the exact date of which was not recorded. He recalls the discussion because Chan Van Vo requested to come talk with him on a Saturday morning, and McDuffie was particularly impressed that an employee would take his own time in the attempt to provide information l which might improve the work situation at SHNPP. In that discussion, l which lasted for a considerable time, Chan Van Vo complained about his i

work situation and expressed concern about not being fully utilized and i

work in general being done in an inefficient and costly manner. There 5~

,.p k

+

. .j-.

was'no. suggestion or discussion from Chan Van'Vo indicating that work was being performed incorrectly from a technical point of view ch that fitems g were .being ' completed in; an improper manner. He prodaced a rjumber of-organization charts that he had personally prepared and explained how.he

. felt the site should be organized; and in so doing. . he could be more  !

l fully utilized. There was no mention of safety concerns- during this .,

conversation. McDuffie expressed to Chan Van Vo the need to demonstrate

g. m ,,

to his supervision that he .was capable of- handling additional or higher quality work and he would be given, additional assignments. During the course of this conversation, Chan Van Vo criticized almost everyone above him in the managinent chain, but this criticism focused -on their 'i administrative capability and not their technical capability. As followup to this discussion, p!th Chan Van Vo, McDuffie talked to = R M .

i .

'}

q Parsons by telephone and satisfied himself that personnel at the site

,' were providing an' audiecce to Chan Van Vo regarding his concerns with his job and that action that they deemed appro"priate was being taken. No '

further followup was considered necessary

or was made.

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I 5.0 Paragraoh #14 Items .

f

/ '

ej.

, f ,

. .r: .' y , ',r . * .

In Paragraph #14, Chan Van Vo alleges that in M[rch 1983 (assumed 1983),

j r e

~ f. /

AlexFullerincreasedpressureonhimandthreath/ed'himwithtermination 1 ,.' ,

and subjected him to fonnal counseling regarding job performance. He? -

( ,

noted that this counseling required that he improve his understanding'and explanation of problems. This information coincides with the point in i time at which fonnal counseling due to unsatisfsctory job performancejid l in fact start. This counseling is documented thoroughly .and spellsiout l C, l 6 e<

a ,, . - . -

/

.w,-...-.-.L,----.

a specifically the job performance-related concerns supervision had with l Chan Van Vo. In Paragraph #14, Chan Van Vo noted that he- requested assistance from R M Parsons; however, to the contrary, Parsons has no recollection of any contact from Chan Van Vo related to concerns about this counseling. There were no instructions provided from Parsons to Fuller and Willett to alter their course of counseling with Chan Van Vo.

Parsons confirmed that he stayed aware of the counseling that was being ccnducted as he did with counseling of any person in the construction organization.

6.0 Paragraph #15 Items

In Paragraph #15, Chan Van Vo refers to a second visit to M A McDuffie.

McDuffie confirms that a second visit was held sometime in 1983, but events suggest this visit was held later than April. At this meeting, Chan Van Yo laid out a plan he had developed for the as-built program for piping and hangers at SHNPP. He provided a hand written document to McDuffie which consisted of a compilation of his ideas, along with information he had collected from sources at the site. Since this was the second proposition he had made to McDuffie regarding substantial reorganization of the operation at SHNPP, McDuffie was less interested and the conversation took less time. At no time in this conversation did Chan Van Vo raise concerns regarding the technical competence of work at the site or safety concerns in general. Mr. McDuffie has no recollection j of making the quoted statement in the Affidavit which is attributed to him regarding Chan Van Vo being a soldier and Ed Willett being his lieutenant and that he should obey orders. As followup, McDuffie sent 7

4

. the document provided to him by Chan Van Vo to R M Parsons via informal

note for review and requested that they discuss the. information with Chan

~ Yan Vo. The date on this note and McDuffie's recollection of when it was.

sent relative to the conversation he held with Chan Van Vo suggests that the meeting with Chan Van Vo actually was held in May or June 1983. .The note to Parsons containing the package of information was dated in July.

The response to McDuffie by Parsons indicates that discussionLwas held

. with Chan Van Vo by Ed Willett and Alex Fuller and that the package 'of informatio'n was reviewed in detail. Willett and Fuller pointed out that a number of items contained in that proposal were in fact included in the current hanger program at the site. Other items were not included and were not deemed appropriate to include. Parsons' response 'to McDuffie was dated in late July 1983 and a copy can be obtained from Parsons.

Chan Van Vo makes reference to pressure.from Alex Fuller in the spring of 1983 and alleges that he was assigned more and more work and that this was more than his fair share. As noted earlier, in the spring of 1983, Chan Van Vo did receive formal counseling which started in March 1983 because of poor performance. The areas of poor performance were clearly cited in counseling documentation in March 1983.

~

Subsequent counseling sessions monitored progress in areas cited as unsatisfactory. Fuller states that Chan Van Vo's assignment was changed during this period because work in this group was reorganized under lead personnel. Because he was experiencing performance problems, Fuller worked more closely with Chan Van Vo than others and utilized him in several activities in the attempt to find one he could handle satisfactorily. Assignment of Chan 8

~

Van Vo to the QA surveillance activity was one such attempt by Fuller.

Chan Van Vo's assignments did not constitute a disproportionate amount of  ;

work compared to others in the group, according to Fuller.

7.0~ Paragraph #23 Items f

~

In Paragraph #23, Chan Van Vo states that he received a memo signed by Alex Fuller and Ed Willett in August 1983 that stated he was on probation

due to performance problems of the past year and one-half. He . makes ,

3 reference to being promoted by Fuller less than a year earlier and notes that he believes that this probationary action was'in retaliation for his-expression of safety concerns. In October 1982, Chan Van Vo was promoted from entry level engineer to the next level. In March 1983, formal

counseling on performance problems actually started. In August 1983, Chan Van Vo was placed on probation, and the basis for this probation is i well documented. This was as a result of his failure to respond to unsatisfactory performance in areas documented earlier. Documentation f related specifically to performance problems observed while working under Alex Fuller. Chan Van Vo was promoted based on CP&L's system which allows promotion from entry level engineer to the next level in two years tf performance is at least satisfactory. At the time of the promotion, Fuller had concerns about Chan Van Vo's performance but they were not

' significant enough to block l

the promotion or to initiate formal counseling. By March 1983, the concerns reached a level to justify formal counseling and docut.:entation. Chan Van Vo objected to the documentation that perfonnance was unsatisfactory and refused to. sign the 9

l

l counseling memo. There was no information to suggest that CP&L demonstrated that they wanted personnel to look the other way when they 1

-encountered deficiencies as alleged in Paragraph #23.

8.0 Paragraph #24 Items In Paragraph #24, Chan Van Vo refers to a meeting with' E E Utley in the fall of 1983. He refers to documentation of safety concerns and deficiencies which he carried with him and alleges that he explained these concerns to Mr. Utley, including the responses he received from his supervision. He goes on to state that Mr. Utley. did not ask questions regarding these concerns' and that he promised to help him and did not.

Contrary to the statements in the Affidavit, Chan Van Vo met with E E Utley on July 1983 as documented on Mr. Utley's calendar. He brought with him a package of information two to three inches thick. His discussion with Utley consisted of expressing his concern with the way CP&L was managing the job with respect to pipe hangers. He noted that he j had reviewed - his concerns with his management, with personnel at the site, and with M A McDuffie and that they had not accepted his proposal 1

for the way the job should be conducted and he was concerned about that.

He noted that he felt that he had a much better understanding of how this work'should be conducted than they did and had a thorough knowledge of his particular job. There was no expression of concerns related to 1 safety. In fact, the conversation did not at all involve the package of information that he had brought with him, although he left that information with Mr. Utley. Mr. Utley made no specific promises to Chan Van Vo other than to give his input consideration. 1 10

As- followup to this meeting, E E Utley sent the package of information

-left with him by - Chan Van Vo to . Dr. T S Elleman, Vice President' of I l

Corporate Nuclear Safety, for his evaluation for potential safety  ;

concerns. At about this same time, Dr. E11eman had been made Chairman of a-review panel to investigate potential concerns by personnel at SHNPP.

MF. Utley received no input from Chan Van Vo indicating that there were

^

technical concerns contained in this package. Discussion with Dr.

E11eman indicates that he reviewed the package and was unable to determine what Chan Van Vo was attempting to comunicate. The package contained a collection of site procedures, non-conformance reports, and 1 as he recalls, possibly some speed letters. There was no documentation as to what the compilation of information was intending to comunicate.~

Dr. Elleman contacted Chan Van Vo by telephone and had a long and somewhat disjointed conversation. Chan Van Vo's main concerns expressed to Dr. Elleman related to his own job stability and the fairness of his supervision and the fact that people were not listening to his ideas about how the job should be conducted. Dr. Elleman tried to obtain

specific concerns from him. After a lengthy conversation, Dr. Elleman obtained information from Chan Van Vo regarding concerns he had on the following items

il l 1) Q-1.ist nut and bolt control (P0-40924)

2) Purchase orders for steel plates (P0-21022, P0-21021)

3) Vibration of installed air compressor l

The first two of these items were converted to Review Panel Concern C-23, which was addressed by the Review Panel and resolved. The third item was i

11 l

E -

l

~

converted to Review Panel Concern.C-24, which the Review Panel addressed and resolved. In none of the'se cases did infomation provided by Chan

[ . Van Vo constitute new information that had not been obtained previously I by means of' programs in place at SHNPP and solution paths had e'ither been

. already taken or were _in process. '

After the Review Panel completed its work on these items, Dr. Elleman.

made repeated attempts to get back in contact with .Chan Van Vo to relate the resolution of these items to him. . After repeated attempts, he made contact and explained the' resolutions. _ Chan Van Vo indicated that i

he was satisfied and had no further concerns with these items. At that

time, Dr. Elleman inquired as to the basis of information Chan Van Vo had 1

provided to E E Utley. Chan Van Vo related to Dr. Elleman that this information was brought to Mr. Utley to prove to him that Chan Van Vo was a capable performer and was doing his job satisfactorily. Following the completion of the Review Panel . work, Dr. Elleman did not retain the package of infomation passed to him by Mr. Utley.

r 9.0 Events Related To Steam Generator Feedwater Pump Piping Installation 1

j Based on discussions primarily with Willett and Dasburg, the situation that existed with regard to installation of the steam generator feedwater pump piping was as 'follows. Nomal practice generally requires installation of piping such that the final closure weld does not occur at a piece of equipment such as a pump. Nomally, piping is installed i beginning with the connection at the pump and installed moving away from the pump, and a closure weld with other piping is made somewhere at a t

+

12

. distance remote from the equipment. The purpose of this' is to ensure that-any loading that may be necessarily applied to align the piping for the final-closure weld is not transmitted to the nozzle of the equipment.

In this particular case, craft personnel had requested approval to make the final closure weld at the pump. Because CP&L had concerns : about potential loading on the . pump, -approval was granted with restrictions which' included ensuring that hangers close by the pump were installed and

.would rigidly hold the pipe in place after it was aligned to the -pump, and secondly, that movement of the pump be monitored carefully to ensure

^

that the welding process itself did not create pipe movement which would provide loading on the pump. Actual construction of this particular

, closure weld was conducted utilizing continuous monitoring of pump _

movement by millwrights using dial indicators. During the process of

welding, movement of the pump was monitored and if it moved in one

-particular direction, this could be corrected by welding on the opposite j side of the piping and create a compensating movement. This iterative technique of welding, providing compensation for movement, would- allow the welding to proceed in a manner not to create unacceptable pump loading and/or misalignment when welding was completed. During the course of this iterative technique, the two millwrights who had been

! monitoring movement were out of work one day, and two substitute millwrights were utilized. Craft personnel' were reluctant to proceed with substitute millwrights, but decided to do so anyway in the interest of time. During the day when substitute millwrights were used, the iterative technique was continued and it was believed that no adverse i l

lo alignment was created. On the day that followed, when the two original millwrights returned to work and made readings with dial indicators, i

13 i

there was indication that adverse movement had in fact occurred and, because welding was virtually completed at that time, the misalignment could not be corrected by further iterative welding on one side or another. At this point, CI (Construction Inspection) Inspector Ed Williams wrote a non-safety nonconformance because the alignment was unsatisfactory. There were several Options considered to correct or compensate for the unacceptable alignment. Two options considered were breaking the joint and rewelding or adjusting the motor installation position to compensate for the misalignment. Considerable amount of time passed while these options were being evaluated and work priorities in

" the field shifted such that the situation was not at tiiat time resolved and had not as of the interview date been resolved. In the time that has passed since the welding to the pump, the pump vendor has visited the site and has observed that the barrel is out of round, which may now necessitate breaking the weld and rewelding. The nonconformance that was written at the time the misalignment was observed is apparently still open and will have to be resolved before the item can be considered closed. Based on the above sequence of events, it appears that CP&L was both knowledgeable and in control of events that occurred to the degree that could be reasonably expected. Although the pump welding did produce

, an unacceptable alignment, the program for inspection picked up the misalignment as a nonconformance. This particular event does not relate to safety since both the pump and piping in question are non-safety related.

14

_ I I

10.0 Events Related to Phase II Hanger Program Early in the program for installation of the pipe hangers, CP&L utilized a two phase hanger program. Phase I consisted of -partial erection of hangers whereby some portion of the hangers was not installed or.was left in an. adjustable state to facilitate piping erection. The Phase II program was intended to complete the installation of partially installed hangers and to complete all necessary inspections. When the Phase II program was started, CP&L' performed a number of routine checks to-ensure that final inspections under Phase II were accomplishing . the Lintended purpose. Most of these checks proved the opposite, and it was clear that they were not achieving the level of quality desired and required. The QA surveillance in which Chan Van Vo was involved was one such exercise initiated by CP&L that demonstrated to CP&L management that they were not

~

achieving the desired level of quality in Phase II. This particular

, ' surveillance was one of the final events before CP&L stopped the-inspection program and redesigned the entire hanger erection and t

inspection program. The program was redesigned to utilize a one step process whereby total hanger installation and inspection was performed at t' l one time, as opposed to the original Phase I and Phase II approach.

Results of the particular QA surveillance activity to which Chan Van Vo j i was assigned produced several nonconformance reports. These and others were written based on findings of surveillance activities. Istop work

! order referred to by Chan Van Vo was a stop work on inspection until a formal and detailed checklist could be developed to ensure that hanger inspections would achieve the level of quality required by CP&L's QA j program. All of the hangers that had been installed and inspected under l

l 15

~

the old Phase II program were reinspected under the new program to ensure

~

that the desired level. of quality was achieved. Since restart of the program, which occurred approximately December 1, 1983, the hanger program at SHNPP has. proceeded satisfactorily according to Parsons.

11.0 Isolated Incorrect Statements in the Affidavit 1

, Based on interviews with CP&L personnel and review of the Affidavit in

, general, there appear to be several incorrect statements in the Affidavit. Information related to these is provided below.

Affidavit Paragraph # Information 6 Contrary to Ch'an Van Vo's claim that he contacted ~

D M Dasburg regarding the steam generator feedwatcr pump piping, Dasburg has no recollection of ever being i

contacted by Chan Van Vo regarding concerns he had with

! this piping installation.

9 Alex Fuller has no recollection of ever being contacted by Chan Van Vo regarding concerns he had with the steam

generator feedwater pump piping installation. Fuller has no recollection of receiving a speed letter or throwing a speed letter in the trash can. Fuller acknowledges that he may have been contacted on the item and, if so, would have in turn contacted the l

l 16

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

i F .

responsible piping engineer, who would likely have confimed that they were aware of the situation regarding the installation of this piping and had it under control. Having received this feedback, he would likely have discarded any information he had received such as a speed letter. Again, he has no recollection' of being contacted at all by Chan Van Vo, either verbally or by speed letter regarding steam generator feedwater pump piping installation.

}

9 Chan Van Vo refers to his concern with steam generator feedwater pump piping as a safety deficiency. CP&L engineering should be able to confirm that neither the piping nor the pump are safety related items at SHNPP.

9 Chan Van Vo alleges that speed letters are utilized in place of prescribed quality assurance documentation.

There is no information to support this allegation.

R M Parsons and others interviewed confirmed that speed -

letters are used to transmit information from one party to another, and occasionally the information contained on the speed letter is converted to a nonconformance if deemed appropriate. The speed letter itself is not considered sufficient documentation for nonconformances and is not used for that.

17

_--_- -______ __-_ _____ __________________a

8 19- Fuller denies ever calling Chan Van Vo a liar as alleged. Fuller confirmed that another engineer in his group was assigned to research the concern with PO-21022, that documentation associated with this P0 (Purchase Order) was found, and there was no residual safety problem. The particular PO had been used in a manner different from a normal P0 which did make the information in question difficult to find. This was one of the P0 numbers provided to Dr. Elleman and was addressed in Review Panel Concern C-23.

21 Based on conversation with Ed Willett, Willett's memo of July 29, 1983 was stimulated by input received from INP0 (Institute of Nuclear Power Operations) and not by input received by Chan Van Vo. Willett, in fact, did not receive information from Chan Van Vo as a result of his QA surveillance activity, and the memo was unrelated to information eminating from the QA

surveillance in which Chan Van Vo was involved, i

l

{

l 18

[~

I..

For Immediate Release October 22, 1984 SAFETY OF SHEARON HARRIS NUCLEAR POWER PLANT f

TO ' BE INVESTIGATED e

An investigation into worker allegations of Quality Assurance deficiencies at the Shearon Harris Nuclear Power Plant was announced today by representatives of the Washington D.C.-based Government Accountability Project (GAP) and local citizens' organizations con-cerned about safety at the nuclear plant. The plant is now under construction about 17 miles south of Raleigh. The Nuclear Regulatory 4

Commission's Atomic Safety and Licensing Board is conducting hearings on CP&L's request to operate.the plant.

GAP lawyer Bob Guild released the sworn statement of former CP&L l Engineer Chan Van Vo detailing concerns of safety deficiencies at Shearon Harris.

i "Mr. Van Vo's experienes reflects a callous disregard by high CP&L management for nuclear safety. Like many nuclear workers, Chan Van V,o faced harassment and retaliation instead of gratitude for identifying Quality Assurance problems. Such retaliation is not only unlawful, but its. greatest harm is that is simply hid.es known safety ,

defects," said Guild.

l Former Harris Engineer Chan Van Vo's Affidavit details: -

- falsification of nuclear safety material traceability docu- i mentation

- breakdown in the Quality Assurance / Quality Control programs for safety related pipe-hanger installations and inspections:

l l - violation of Nuclear Regulatory Commission requirements for i

Protecting freedom of Quality Assurance functions from project cost and scheduling pressure s

_ . u. ._ _ _ _ _...~ _ _ . _ _ _.-... _ _ . _._. _ _ . _ _ _ .. _ . _ _ _ ._. _ _. . _

1 .

4

- destruction of Quality Assurance documents including his own

- documentation of safety concerns. i i

" Based on our review of the NRC record and the experience of I workers including Chan Van Vo we see strong evidence of programmatic breakdown in the Quality Assurance system at the Shearon Harris Nuclear Power Plant," Guild concluded.

Attorney John Runkle, who represents the Conservation Council of North Carolina as intervenors in the NRC's licensing hearings stated:

"We welcome this investigation by GAP. We will ask the NRC Licensing Board to fully consider Chan Van Vo's testimony. Only last month CP&L executives E.E. Utley and M.A. McDuffie assured the Licensing Board that worker safety concerns are encouraged and all are fully investigated. Mr. Van Vo's experience directly contradicts s

this CP&L testimony."

The Government Accountability Project is a public interest organi-i zation which supports "whistleblowers" in the nuclear industry who -

l have raised concerns regarding nuclear power plant construction i

l quality.

!* For more information call Bob Guild at 803/254-8132 or 803/252-1419. or Betsy Levitas at 828-3403 0

+

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is 1.0 SCOPE 1.1 This procedure describes the steps to be followed for the installatien of =

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Stainless Steel 2.4 WP-48, Temporary Construction Leads Suppceted From Permanent I Plant Equipment 2.5 he-102, Installation of Piping ,

2.3 "?-03, Gene al Welf n; ? :-:edur e .'..- O rt::- 3 t e e'. ?ledm enu 2.7 3!?-07, General Welding Procedure f:c Stainless Stie! Weldments

.. 3 CAR 2155-G-301 Flow Diagram - Reactor Coolant System 2.9 TP-04 Calibration of Controlled Tools 2.10 WP-103, ? otective Coatings -Service Level! Emcedded Sted Plate, Service LevelII Steel Surfaces and Salance-of-?lant Steel Surfaces 2 .11 SD/C-A-1013, Identification of Sergen Paterson Hanger Parts 2.12 SD/C-A-1019, Neutral Axis of Odd-Shaped Struc al 3! ambers 2.13 WP-25, Field Enginearing 2.14 3t?-05, Permanent Starking of Site '.!aterial and Components 2.15 WP-139, Pipe Hanger Work Package Prepara: ion 2.16 WP-140, QA Records Review (Seismic Pipe Hangers and Suppcets for i

i Seismically Analyzed ?!pe) i i

2.17 CAR 2155-G-10~S01, Field installation Tolerances *:: Pipe Hangers l

7014 MO. !?77 2 e- -- .

CON 3TRUCT!Cri P.;CCEDURES MANUAL SM *

• _"2. "*",". o

• • _ _ _ . ,l i u A eeM , :

WGRK FROCE;URE IFS!.M.LATION OF SEI5MIC ?!?N HANGERS AND ' " * "

g  ;

SU?? ORTS FOR SI!SMICAI.LY AN.C.YZID' ?!?! '

CESCRf*T!ON 8 e. 6 ee is I

3.0 GENERAL l

3.1 Introduction i t

Unle:s otnerwise noted. the tolerances in the icilowing sections may be j used for construction of a oice hanger. However, to exceed these tolerances, a Field Mod (Exhibit 1) must te obtained from the Hanger Engineer. These Mods will allow work and inspections to proceed to completion. The tolerances described herein may also be applied to the Mod requirements.

3.2 Location Tolerances

1. Hangers shall be installed within11/2" of the design location

'elevati:n and column line offsets). Mcwever, !! the pipe is act i

installed. the box f sme henp snculd :e left tacked to the

. l.

ecced ad u.e pge s ia. u 4e.< wetcs snouac ce large enouga to ensure safety).

2. Manger memoers should not be installed within 4" of an adjacent pipe or structure.

3. Hangers should not be located within 15" of a pipe (butt) weld !!

19 the hanger supports Class 1 or 2 pipe.

4. Mangers shall not be installed on a pipe elbow, fitting, butt weld, or ID tag.

3.2 Geomet.v Dieranc +

1. Geometry may vary;!/2" fr:m design. However, this :!srance shall not be used to reduce the clearance requirements around the pipe.

2. Slopes and angles may vary from des!gn provided the location and '

geometry dimensions are maintained.

3. Sway supports must be within; 3' of the design requirements.

4.

The neutral axis of structural members shall be used as reference lines for geometric configurations (see SD/C-A-1019).

5. Strut lengths must be within 1/2" of design.

l 6. Filler plate sizes shall de - 1/2", -0" from the Bill of Material

! requirem ents.

1 I

l l

'O W so i??3 e _-_ _ -

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CCNS 9UOT1GN NCCECUP.E5 .WNUAL -

w.iio As Azerove.!

WORK PROC 'w -

~ CISTA1.1.1TIQ9 CF 3:~.P.CC P!?E EAAG_35 AND ' 3"I '"

..JR, 3U??OR'f5 TOR SEIS}!IAI.LY .CALTZED ?!?! 9 l ** ,

oESC !PTION -

3.4 Steel Attachment Tolersnees

1. Mangers are to be attached with!a 1/2" of the embed centerline (s).

2. Hingr3 rs ts be attached vi2fn ,L'2" cf a case plate scrised work point.

3. Hangers should attach to the ecerect embed type which is detailed on the hanger sketch. If the embed in the field !s designated as a Dubose plate, reduced tolerances will be necessary and should be provided via a Manger Stod.

4. Hangers must attach within V2" of the centerline of a structural steel member (existing steel) and may move 1/2" along the axis

, cf f.e ste.:com! s eel memcer. In Se 0:.-tain.- ent building the  ;

I :entirline if t's **.-:ct ral steel ember s'u!! t e usumed to be -I on the azimuth required by design.

5. Attachments to ste!p plates with threaded studs must be g9 surrounded by acceptable studs. See F!gures 1 and 2. A threaded stud !s not accepta:le if it is disengaged b'/ mera than 1/3" or if there is a weld within U2" of the stud.

If otherwise cotain a Hanger 31od from the Hanger Engineer if possible.

8 Figu:e 1:

All four mus:

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be acceptable. 8 0 ii.gure 2:

All s:.x zud:

O O p '

be a::ep;able. ' g b

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SW CON 3TRUCTION PRCCEOURE5 MANUAL.

US!.C.L IION 07 5:15EC d?I F.MGI3.5 is  !' !.UTo"t AslE$:ve'a WORK PROCECURE stypop, S yog sgIsMIC.i.LLY c.ALY I] ?:?I 9 DESCRIPTION

• • 0 "

3.5 Sox Frame Mangers i

1. Clearances  !

Clearances around the pipe in a box frame hanger must be achieved. However, the pipe can not be cold pulled (forced out of its relaxed position) in order to do so. If the clearance is specified as 1/16" by design, then the clearances must meet the criteria tald out in Appendix I. For one-way restraints, the Hanger Engineer must issue a 5tod to detail the clearance requirements. The pipe and the hanger shall be visually square with respect to the other; however, shims used to obtain acceptable clearances shall meet the skewness requirements of.

Ap;endin I.

2. Ws

1. Shims shall be installed in accordance with the Fleid >!od around the pipe !! cicarances are not acceptable.

2. Shims called for by the design sketch may be deleted by a

• Field Stod if the pipe clearances are acceptable. R9 i

3. Shim material must be A-36 or A-569 carbon steel. If otherwise, a Field Stod must be obtained from the Hanger Ecgineer.

4. Shim plates and hanger .smters ~.ust :e in :c.nact an:1 free of. lubricant. Sh!m surf aces shall n:t be sandtlasted.

3. The shim should overhang the hanger member appruimately l' on both sides in order to protect the pipe from are strikes.

A maximum overhang of 2"is ;ermitted cn eitner or both sides. If a weld, valve, branch line, or other projection will not allow 1" clearance from the end of the shim, contact the Discipline 5!echan!:a1 Engineer for resolut!cn via a ?!ald Stod.

6. The centerlines of the shim and pipe shall :e aligned within the - 1/2" of each other.

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CONSTRUC9CN FRCCICURE5 MANU/.i. ..__.

=  ! (Q'c' x, Ajyy,g I'43IAEAIION OI 3EIWIC IIII ENOIII A"U WC5K PROCECURE SU?? ORTS TCR SI;WICA .:Y .GM.TII3 ?!?!

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9 OCSCR!PECN _ _ _ _

-- 'as* 9 9 13

7. The shim and shim weld details snall be provided on a Field I I

Mod.

• l

8. Weld leng*.h shall not exceed the 1er.gtn specified on 'he .

Mod. i 3.6 Catalog Parts  !

1. Combinations of WBA, sway support.s and/or pipe clamps must I conform with the requirements of Appendix A unless noted l otherwise.

2. All combinations must be aligned, in order to ensure the support

, does not bind and lock up. Part numbers 1000 and 1001 should be

~ ~ ~

fitied to :ther items usT.jihe had ;in'a.: the ac"*-C ""-

3. Catalog 7a- s - +y :e idern:ite :7 a :,e:g a;3: ,st ;ne -i- e .:::..:

providec in :ne 5.te Orawing (sO, C-A-t43i. .uso seit .sppency, .:..

4. Care should De exercised to ersure load pMs, bolts, nuts, washe-s, i R9 and pipe clamp nalves for different hangers /or parts are not indescriminately exchanged. An !r.spector shall verify material I

padas for ! cad ;!ns, bolt: end nuts prier to F!nal Acceptance.  !

(See Appendix C). f

5. If the load pin must be removed from the end attachment, a light lubricant and pur.ch should be used to faellitate rem:vs.t. Care fi m 4t be taken a peev.:n: :ne 1. or!0an .' rom contac:ing stair.iess ,

Itt el pipe.

S. The holes in the ears of the W3A or pipe clamps shall not be l

pound in order to reinsert the load pin. However, the ends of the i Icad pins may be !!ghtly f!1ed to remove r;;ushr:oming caused by forced installation. The shank of the load pin shall not te pound ,

for any reason.' Also, l!ght tapping may be used to remove or install the load pins. If the end attachment ears are damaged in j the process, the end attachment must be replaced. Cotter pins i i

must be spread in opposite directions to prevent the load pin from i i

slipping out.  !

i

renw Mc :?rs C _ . . . _ . . -_

CON $rRUCTION KCCE00RE.3 MANUAL W42 M*17 u p h ,g

. .- WORx 2RCOEC;;RE ISSIMI ATION OE SEISMIC ?I?? 'IMIG7RS MO ' " * "

i 5; P?0E*S FOR SI:5M:0!J. .Y .WM.Y:3.0 ?!?!

• m ci!$CRIPT!ON _ 13 of is l l

. 7. Bearings should be tightly engaged between the ears of the WBA i i e i or pipe clamp. Any gaps should not exceed the clearances  ;

s;eci!!ad in Ap;endix 3. C:nue: the Hanger 2 ;ineer !! its clearance cannot be reduced w!!h spacer washers per Appendix G.

3. When installing the struts, care must be taken to ensure that the f, pipe is not forced out of its relaxed position (this is caued cold 1 pull). I

, i

9. Tightening of bolts, studs, threaded rod, and U-bolts shan be in accordance with Appendix F. Nuts should be fully engaged on the threads and should not bear against the bolt shanks. li I

3. L.strue

w.3 far tig .:ening to;:s and T;*.s in appucations :that g :hr.r. ;!;a :'im;;, "-5:;*:, :hr:r.d:d ::d : ;; rt, 2nd :;rin;c snoulc ce ootained from tne Hanger Engineer.

u. T: shorten er lang han stru: a=amblies (:ut:!de : cut in 39 adjustment), the Hanger Engineer must provide detaued instruc !:ns to the craft via a ?! eld .',1:d.

~

12. For telescoping struts, there mus; be 1/4" =!nimum engagement 4 ,

between the strut and the shank prior to welding. (A 1/4" hole ,

may have to be druled 1/4" minimum from the end of the barrel to verify shank engagement.) The shank and p!;e strut mus: be ,

aligned. The weld s::e Oe: ween :ne shanx and :::!n; shau -a provi'ed cn a .!cd even if ..;;4d :herw!;e en :he 3ergan .Sa: arson f sketch. i 3.7 General Guidelines l

1. Lift Points I Installed pipe hangers shan not be used as lift ;o!nts for loads  !

other than the ones approved by WP-43. The welding of [

temporary attachments to hangers sha11 de in accordance with ,

.i!P-08. Au welded temporary attachments will be removed from 2

the hanger pr!ce to any inspections.  !

i f

e

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

'OAM No. I?'9 3 __

SE CONSTRUCT!CN PRCdECUES MANUAL - ~5$ElY AsYoorevec l WCRK PR"*"*~"Un'

~ '

Si;??ORIS FOR SESMIC.C.I.Y .GA*.YZID ?!?I k- ) -

I CESCRIPTION - ,I** 11 a' t9  !)

2 Ploe Cleanliness j

]

The external surface of all stainless steel piping shall te cicaned-I of all contaminants (P.eference WP-112) prior to :ne olacing of a >

.s pipe clamp around the ;iipror-surecunding the pipe witn a window  !

hanger. Contact the Piping Superintendent or his designee if I cleanliness has not been attained.

3. Hangers Near Penetrations. Sleeves or Ecuioment Pipes are usually designed to run through the center of the sleeves in the walls and floors. Box frame hangers adjacent to these sleeves, penetrations, or equipment shall not be erected until the

} pipe !s installed hed-pcint to hard-po!nt.

4. Tamoc ar Pi:a sue:c-ts -

.. Tsmpctry hr. gars : hall:a stact&d :s suppert thi pipe LT accordance with WP-102 Section 4.2.5.7. These supports should ..ot be removed nor should permanent suppcets be reworked if the work would compromise the required R9 spacings for the pipe supports.

2. Temporary hangers shall also be erected in I!au of permanent hangers when necessary to support RFTs. They shali not be erected (insofar as practicable) in the same i

location 2.3 the permanent suppc. . Thase :empcrar/

hangers will be tagged and may caly be removed after the permanent supports have been installed. A Werk Directive I is necessary for this effort.

5. Coating Recuirements Per WP-108, all steel going into the containment building shall be 4

coated to Service LevelI requirements; all stock steel going into areas outside the containment building shall be coated to Service Leve1II requirements. Prior to coating, hangers shall be hard marked for hanger and material identifications; stock stee! shall be hard marked for material identification.

F'J::M NC.:*7S 9

_ _ _ = . - --

TP CONSTROCT:CN >RCCECUR S' NANU;L ... '

'a N 1U' 155 ff.I . C ,..,,,,

es2Nroved WORK PMCCEOURE g,;ppag.'.CION ;3 yhg gg;33;e OFg3EISMIC y jyA,y;g3 FI?E 777g F.ANGIA31.: 9 OESCRI2T:CN **** 12 e8 13

6. Material Markint  !

All steel for future installations shall be hard marked in ,

accordance with MP-05 for mater'al identif!:stier. TMs shell re witnessed by a QC Inspector. If markings wul be removed or

• i covered by a construction activity prior to a final QC signcff, the i l-marking shall:e transferred and witnessed by the QC Inspector. j.

There shall be no unmarked steel in the fleid surplus room. l

7. '

Snubber Substitutes Since snubbers can't be installed untu just prior to Hot Functional testing, a snubber substitute such as non-Q angle should be i stalled : ; reserve 2e space tet veen be hr.ger structure and i

e the pipe. The specer s mid :2 ;rnted red :: :dantify !! as a i

eini,0. .cf .i crac curv. gg

8. Access Interferences If the hanger creates an access Interference in a doorway, aisle, or stairwell, etc., er if an interference prevents the hanger from performing its design function, the hanger should not be installed I and the Hanger Engineer should be contacted.

9. Stainless Steel Straos Stainless steel straps sha11 not be Installed with the pipe hangers t

een if sped!'ec ay design. ,1cds or design re <isions are a

necti3 8. 7 to dell *.3 this l'.e.T. f.*0m *he 3!2 tf '!1*.3ri215. . I

10. Stiffener Plates '

Stiffener plates may be coped ce trimmed as necessary in ceder i for the item to be fitted between the !!anges of W-shapes.

11. Welded Pice Attachments (WP A) I Although the installation of WPA's is in accordance with other l i

procedures, it should be verified that all parts of the WPA are installed as designed. Box frame hange s that interface with the WPA should not be installed untu the WPA is welded Out. ,

12. Valve Hanzers  !

Valve hangers snould not be !nstalled untu after the valve has  ;

I been welded out. I 4

4 y ,- - -

r EM NC. !?79 3 _ _ _ _____

q'.- #-a CONSTRUCTION P;CCECURIS MAi4UA' -

\ *:.c.a m n :a ,,

,?-110 As 1.coreved WORK PROCCURE . I 3 0F 3ED.IC WI MEM E

• 9 SU7? ORTS 70R SEISMICAI.t.I AN.C.YZED ?I?E DESCRioT!CN **S

• 13

13

13. Voided Hangers i

A Work Directive shall se issued with vo!ded hangers to havo l them removed from the field. C: and QC must verif;. tne warx l was accompushed and sign the W;rk O! ective.

14. Soring Hangers and Fire Protection Hangers All spring hangers and nonseismic fire protection hangers were within the scope of WP-109 (InstaHation of Nonseismic Han;ers).

As a result, fitup gaps were not recorded, hanger geometry and locations were not checked, and structural welds were not inspected by QC. Spring hangers on seismicauy analyzed pipe per

?.svision 7 and 3 argen-Paters:n : ire pectaction hangers per. i Revision 3 are witnin tne scope of WP-!!0. Altnougn tne insoector  !

cannot go back and check fitup gaps or other in-process inspectior.s. the inspectors can verify geometry and location and '

perform a final visualinspection of the welds. For hold points which cannot be met due to instaUation prior to t.'.is procedure, t'o

~

the inspector can so note on the Traveler and/or SWDR.

15. llaterial Recuisitionimr

1. Hangers may be requisitioned from the warehouse ustrg the hanger numbers found en the hanger sketches. The material snall consist of all pieces received f: the current cra.t!ng

{

revision and,if necessary, tacse items taken from seisitic surplus stock. For hangers utuizing snubbers, the warshouse wul withhold the sr abber and snubber extension if a separate requisitica is made for : pee!!!c parts needed. The

. parts being withheld can be requLQ!oned at a later date. At the time of requisitioning, the requisitioner should use the I

hanger sketch to invent:ry the materials for the hanger.

2. Hanger material shan be placed in a clean, dry area designated by the area superintendent and/or hanger supt.

3. Au material superseded by later drawing revisions shall be -

removed from the (! eld. Usable surplus material should be

- e , - w . - -

m 1 9-FoT^i No. :779 3 . __

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CONSTRUCTION PROCECUR S MANUAL '

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. . WORK PROCEDURE 35 mm 07 SI:5E DI MCAS M * . .

St!?? ORTS FOR SIISMICALLY <WALY ID ?!?!

OEscRIPTICN  %

\L .fk ^ t 8 i returned to the warehouse in a timely mariner. This sh'ould s- , l avoid work-area congestion and m!suse of matarial.

4. Scrap matarial shall be sant ta the deggEated scrap .

s

~

location..~

.  ?;

3.3 Exhibit Instructions, .(

Changes to tne content of Work Directives, Travelers, and Hanger Stods must be initialed and dated. Signoff blocks on a Work Directive or the Traveler for a Hanger Stod should be dated on or af ter the change date.

1. Field Stods (Exhibit 1) f

1. Field Stods shall be written and Issued by the-Resident -

Hanger Engineer or his des: pee. ,'

~

2.

$!:di!!: .tions to hangers en C1 u *. lines mt s be Umitad to Jt corrections in draf ting errors, drawing clarifications, wald - ,

symbols, and dimensional changes within the tolerances of Reference 2.17.

3.

The field med Is comprised of two, copies, one of which 39 remains in the field for hangee installation, and the original which is routed to the work package group for assignment of ,

Fa!# and routing to Document Control. (The Fa!# is a ;j sequential tracking number).

~

4. If NDElequireme.it hold;oints 'or welding ;rocedures are I

affected oy the issuance of a Stod, the hanger package '

should be routed to Welding Engineering and QC 6elding for the required changes to the SWDR.

5. The field copy of the Stod shall se considered active for ten -

calendar days. If a centrolled (blue) copy has not been Inserted in the hanger package within ten calendar days, all ,

work on the hanger shall step until a controlled copy is ,-

received.

6. Each Stod shall also have a unique number which shall

consist of the Rangeg Des!p rpvision, at for Stod, and an ascending number starting wid.T 1 lex. 2/ A $11). This

.e numerical sequence starts over when a new desip revision is received. _

I,

7. New design revisi ns shall supercede the previous design revisions and allifods written against that revision.

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CONSMUCUCN PRCC; CURES MANUA' ST _

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WCRX PROCECURg!NSTALL.CION OF SII!MIO PI?E F.A.NGIR$ AND ' " ' " " _s StIPPORTS FOR SEISMICALLY ANALYZID FI?:. ,' i3 *, ea OESCRIPTON * "

8. Mods which affect an already active Mod shall not be issued until the active Mod has been voided. Voiding os .Iods shall  !

be accomplished as follows. The vcidad Mod sh::.11 ca i rwmoved from the hanger package and routed to document control for distribution af ter the drawing has been stamped void, initialed, and dated by the Hanger Engineer.

2. HIC Sticker (Exhibit 2) -

The HIC sticker shall be located and completed by the Field Engineers.

3. Traveler (Exhibit 3) - - - - . _ - - . - - . - - . -

1. The Traveler shall :e !nitiated Dy the Hanger Engineer in order to control the in-process instsJlation and inspectier.s of the pipe hanger.

2. Work Directives, DCN's PW's. FCR's, and Hanger Mods should be referenced in the applicable blocks at the top of the Traveler. Mod numbers (i.e.,2S1 M1) are listed under the

' l RCI heading. If any of these documents are voided, the

{ 39 entry should be lined through, initialed and dated by the Hanger Engineer. Superceded documents do not need to be crossed out.

3. Engineered plate thickness determinations should te listed l af ter 7/22/81 by the Hanger or Area Engineer.-

4. The phase of construction - Pre!!minary or Final should be appropriately denoted. Completion of either phase shall be to the latest design revision and/or Mod (Examples 2/A M1 or ISI.M4).

5. For the PRELDt! NARY phase of construction, the FIT-CP and WELDOCT signoff blocks shall de initialed and dated by the foreman, the CI block init!aled and dated by tne Hanger Engineer, and the QC block initiated and dated by the Welding Engineer. The QC :Icek may be marked N/A -

Initialed and dated by the Hanger Engineer.

l l

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No Nc.1779 a l CONSTRUCTION FRCCEDURES MANUAL SliNP? ho n2 ~ ~ i. ~-]

= '*n 1. i.,,,...,.2

.gogg oRCCEOURE INSTALLATION OF SEIS'GC ?!?! EANGERS AND **~

SUPPORTS FOR SEISMIC.M.LY ANALYZED Pl?E CSSCRIPT!CN 'see is .* 13

6. For the Final phase of construction and inspection, the FIT-UP AND WELDOUT blocks may be initialed and dated by the foreman. The CI and QC blec!c shall be i .itialad and dated by CI and QC inspectors respectively. The CI and QC signoffs are for final acceptance of the hanger,.however the actual inspectica records are on TP-34 and the SWDR ,

respectively. .

7. Upon receipt of a new design which does not affect the as-built configuration and location of the hanger, signoff blocks I, shall be N/A'd, initialed and dated and the Hanger Engineer  !

shall make an entry f:r that revision and nots "as-ouilt on

! the traveler.

3. If he new revision does affect work,' the work package is re-issued to the field for completion to that later revision. i A9 s

, 4. Material Verification Exhibit 4) l

The Material Verificativn sheet snall be completed by the Hanger -

Engineer per the instructions provided in Appendix J.  !

5. Work Directives (Exhibit 5)

1. ' Work D!re ,tives shall be issued to detail construction ,

activities. Jhis includes ary wor'< which wjl1 void out a previous inspection.

2. Work Directives shall be initiated, signed and dated by the Hanger Engineer.

3. Work Directive Numbers shall be sequential starting with one. The number shall be assigned by the Hanger Work ,

Package Group. .

4. Signoff blocks shall be completed by the appropriate persons unless N/A'd by the Hanger Engineer.

4.0 PROCEDURE '

l. The Fleid Engineers shallidentify interferences and provide control points for hangee installation and inspection as requesteG The control -

points are laid out in accordance with Aeference 2.13 and are easily  ;

1 N.

I I

l

i-

$ pcAd No.17:s_e 3D*?D '.T'"t  :*

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CON $mVCT10N.FRCCEOURE3 MANUAL 2 i,,.n._...,

WORK PRCCECURE Ci3T.CT*0ii 07 3EI3MIC ?!?I E.CiGERS A:C 9 DESCMiPTICN ?m 17 e# 13 identified by the orange sticker (Exhibit 2). These activities are referred to as the HIC -Hanger Installation Checkout - Program *n WP-

'39. I

2. The Hanger Engineer should estaclish that the hanger is not on hold for construction, engineering er quality reasons prior to generating the work package. The work package should consist of but not beJmited to the Hanger Design drawing, SWDR, and Traveler (Exhibit 3). In addition a Work Directive (Exhibit 5) detailing work instructions to the craft and inspectors shall be included. After the work package is made.up in accordance with Reference 2.15 and its established that the hanger is ready for c:n.scruction, it is issued to the Hanger Superintendes.: for l i. nallati:n. i

3. The Hanger Engineer or Superintendent shall requisition the. material - -

from the warehou:c. The mater!al shall be tacked up per Ref arence 2.1 and the Hanger Engineer called for a preliminary examination. R9

4. The Resident Hanger Engineer er his designee shall issue Mads (Exhibit

1) for any problems encountered.

5. The Hanger Engineer shall then examine the hanger for completeness (including trunnion material where applicable) and correctness, and list the gap measurements (See Appendix K for criteria):n the SWDR.

6. The Craft Supert .tendent shall weld tne hanger cut per Reference 2.1 and call for a preliminary examinatica sy Welding Engineering.

7. The Welding Engineer shall examine welds for quality and si::e as requested. -

8. The Hanger Engineer shall verify material and complete Exhioit 4 prior to the finalinspections.

~

9. CI and QC shallinspect following the weldout of the hanger.

10. The Craft Superintendent shall return the week package to the Hanger Engineer following the installation and inspection of the hanger.

11. The Hanger Engineer shall review the Q documents per Reference 2.16 and transmit them to QA Records Review Group after the hanger has ,

been completed and inspected and an as-built of the hanger has been incer;;&lted into the design drawing.

n i N Nc.!? c 3

_= -

CCT<STRUCDC ! F.*.CCICURES MANUAL SNP {c,y)N* gtevu

^

• • ~

WCRK ? ROC ~ ~*nUR'e INSTEMION OF SII2!C ?I?I MIRS .G 9 S1;??0RTS 70R SII5:D AI.LT ANEY IO ?!?I .,

ciscmpnoN * *se -' * ,8

12. The Hanger Engineer shall put a CWRA in the work package when l required. I 9 5.0 EXHISITS AND APPENDICES 5.1 Exhibit 1 - Field alodification (Rev. 0-W83) 33 5.2 Exhibit 2 - HIC Sticker (Rev. 0-11/93) i

. 5.3 Exhibit 3 - Seismic Hanger Installation and Inspection Traveler (Rev. 2-4/83) 5.4 Exhibit 4 - Slaterial Verification Form (Rev. 0-11/83) [ gg 5.5 Exhibit 5 - Work Directive (Rev.1-11/82)

a.o Exniba 5 - 3eismic I.csd Shee: lRev. 0-532) i

! 5.7 Accendix A - Catelci Part Combinations (Rev.1-Ll!931 I 5.8 Appendix 3 - Gap Tolerances r:-i. cad ? ins (Rev. 2-T'33T 5.9 Appendix C - Fastener Types (Rev. 2-11/33) l R9 5.10 Appendix D - Flow Chart (Rev 0-11/33) 5.11 Appendix E - Strut Identifications (Rev.1-lu33) 5.12 Appendix F - Tightening Criteria (Rev.1-11/S3) 5.13 Appendix G - Flat and Tapered Washer Reference Table (Rev.1-1230) 5.14 Appendix H -Installation Procedure Fcr Slain Steam B-Wa11 Supports (Rev.1-11/ 33) i 5.15 Appendix I - Clearance Tolerances (Rev. 0-11/33) l 5.16 Appendix J - 3!aterial Verification Prog am (Rev. h-11/33) 5.17 Appendix K - Gap 31easurement Criteria (Rev. 0-11/93)

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.' Rev.1 CAROLINA POWER & LIGHT COMPANY Appendix J l 12/83 SHEARON HARRIS NUCLEAR POWER PLANT WP-110 l

Sheet 1 of 3 MATERIAL VERIFICATION PROGRAM The following instructions are to be used by the Hanger Engineer to complete Parts 1-7 on Exhibit 4. ~'

Part 1 All material which was issued prior to 9-6-83 maintained identification via material control. To ensure the controls were implemented, the Hanger Engineer shall need to know what material was received and issued for

, construction. The Warehouse Engineer shall provide that information in Part 1 of Exhibit 4. He shall research receipt reccrd.: and !!st items and the drawing revisien for uhich the material ru 9:ce'.!ed. He shall sip trd da*.e c e entry.

Items Rev.

Examole: 1 2 7 3 .

Part 2 The Hanger Engineer shall verify the as-built steel is the as-received as-Issued material for the pipe hanger. He must perform a field check on the items listed in Pert I and compare the phy3ical ceramen.s, e;cep, leny.h. of the as-built steel to the Bill of Materials of the drawing revision for which the material wes supplied. In addition, the hanger material must: '

1. Be coated with red oxide primer (except in the Containment Building) g,

2. Be coated with flat white primer (only in the Containment Building) g,

3. Be coated with gloss white paint and stamped with the hanger number g,

4. Be an uncoated structural shape less than S"long g,

5. Be an uncoated plate which has an exposed area less than 3" from a weld -

6. Not be marked with another hanger number er PO number

7. Not have documentation in the package to indicate the material

. was supplied from surplus or stock.

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1 Rev.1 CAROLINA POWER & LIGHT COMPANY Appendix J 12/83 SHEARON HARRIS NUCLEAR POWER PLANT WP-110 Shest 2 of 3 MATERIAL VERIFICATION PROGRAM If the material has been determined to be the original Issue, the Hanger Engineer shalllist the item numbers in Prt 2 cf Exhibit 4.

Part 3 The Hanger Engineer shalllist those items in Part 3 of Exhibit 4 whose source of material,can be determined from Work Package documentation (i.e., Speed

, Letter, RCI or CMR). However the source must be legitimate with a

,, Certificate of Comformance from a qualified vendor. This is evidenced by a stamp "Sou ce Accepted" - en the C.'. 2. Speed Letter, er RCI.

Part 4 & 5 All materialissued after 9/6/83 will be stamped or etched for positive identification. The following will be the acceptance criteria for this material.

A-36 plate, channel, wide flange, and angle shall be stamped with

, the 36 symbol unless it is less than 3/1S" thick.

A-500 Grade B tube steel shall be stamped the 36 symbol.

10-guage and 16-guage shim stock will be stamped or etched with the material grade. (A-569 is acceptable.) FCR-H-1263 allows shim stock to be stamped (but not with the 36 symbol) even though it may be less than 3/16" thick.

. U bolts and threaded rod will be stamped or etched with the material grade.

. Stock pipe tubing for struts shall be etched with the material grade. -

Steel other than A-36 or A-500 Grade B shall be stamped with the purchase order number.

If the material is marked and is acceptable, the Hanger Engineer shalllist the item numbers under Part 4 or 5 as appropriate. . .

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4 1 2ev. 2 CAROLINA POWER & LIGHT CO.'.IPANY Appendix J 2/S4 SHEARON HARRIS NCCLEAR POWER PLANT WP-110 l I

Sheet 3 of 3 MATERIAL VERIFICATION PROGRAM Part 6 Catalog pa-ts shall be identified by the physical characteristics of the item or by the stamped catalog part number. The catalog part identity must be in accordance with The Bill of Materials. The Hanger Engineer shalllist these item numbers in Part 6 of Exhibit 4 and not under Parts 2,3,4,5, or 7.

Part 7 A sampling program is set up for structural shapes, plates, and shims which cannot be identified under part 2,3,4. or 5. The Hanger Engineer shalllist these items in Part 7 of E::hibit 4.

General Notes:

If more than one of an item is to be considered, each piece shall'b e listed in

' the appropriate section. For example, if there are two piece 7's and both pieces are stamped, Item 7 should be listed twice in Part 4. After the form is completed, the Hanger Engineer shall sign, date, and enter the drawing revision the items were checked against. A copy of the form shall be removed from the Work Package and returned to the office to determine the irut ,f 't? rr: p.'i g ,e or r r: d te ! 'tia*: Iny na'2r'a' ::sth; .

Welded pipe attachments (trunnions, lugs, etc.), anchor bolts and cinch anchored plates shall not be listed on Exhibit 4.

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cue. o -if<.e. .most .sericu.s pecMeus jGz.ced by .

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SECAUSE oF ITS PCTEN TIAL IMPACT oN PU8 LIC HEALTH AND SAFETY.

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, 1000 "C Sct2CI 1005 Reactor 7essel and Inter =als Systa= 5' 1045 Kaccre Nuclear Inst *mzant System

• 1050 Incore Nuclear Instru= ant System 1060 Az1a1 ?over Dist:thution Monitoring Systsu ,

1065 End Control System . Rod Position Indication System ' 1075 1080 Reactor Protection System 1090 Inst = sered Safety yestures Actuation (Controls) 1095 Matal I= pact Monitor 1=g System 1100 conta1= ment Isolation System

• i 1900 N555 Procesa Instru=entation Control System 2000 CORE C0012tG AND SL"?M!C STS-'Id.5 2005 Ranctor Coolant System l Esa-tor Coolant Pu=p and Motor .

! 2025

• 2030 Esactor Coolant Pump Vihrstion Monitor'ng' 2050 Pressuri=ar -

2060 Chemical and Volume Control System " 2'065 - ~3eron Ther:mi 1agene:M 15.*5ystem 2070 Con-sd - t spray System

• l 2075 I,Purgs Systes j 2080 E!sh Hand Safety Injection System 2085 low Eaad Safety Injection and RE1 i

2090 Pasette Safety Injection System l 2105 Gross failed Fuel Datection System ' 2110 Imactor Coolant Make-up 'Jacer 2115 Isactor Coolant Sampling System 2160 Process control System I 2175 Hydrogen Racombiner i 2000 STZ1M CTC.Z I 3005 < Steam Generator ) <5taan Generator 31owdova System !

• 3010 i 3015 V Staan Generator Chemical Addition System l 3020 V Wsin Steam i 3015 / Er::aation Steam 3030 Motstars Separator /Zaheater

3033 Steam Damp System 30.'0 w "

• ry Seus 3050 /7eedvatar .

feedwater Easter l 3055 3060 Easter Vents, Drains, and level Control 3065 A'* mry Feedvater b.,, 3067 A " 'dnry Condensate [ ..--...5'~ _m_......3........-_..:. . f. d ( . 47 f \ Condensata Systan '3070 3075 Condensate Polishing Oasisersiimar ifsta= . 3080 condensata Maka-sp System 31C0 Staan Cycle Sampli=g 3115 Staan Generator Wet Lay-up Systaa 3120 i+ " sry 3cilar Tual C1'. , 33:4 Instrument Installation , 4000 Ex" SI'!I , 4005 condenser 4010 Condenser vacuus System 40L5 Cir:ulating Water System 1 4020 Circulc ing Tatar Treat = ant System 4025 Cooling Towers System 4020 Cooling Towers Maka-up System 4035 Cooling Tower Slowdown System 4040 Traveling Screens & Screen Wash 4045 Esservoir 4047 Esservoir (Auz)

4055 Raservoir 31owdevn Systam

! 4060 Nor=al Servica Water System 4065 Z=argenc7 Servica Water System V' } Component Cooling Water System 4080 l ( 4082 4085 4086 Waeta Processing Building Component Cooling Water System ' Essential Chilled Watar.5ystem Neu-E.sser.tial Ch*"ad:.Dtirr 4ystan I 4115 Emergency Screen Wash ! 5000 ILZC"RICAL CCNTIISION AND DIS".t3t"" CN STS"".!2dS 4 5005 Turbine System Elecuydgaulic control System 5015 4 5020 Turbine-Generator lubs. 011 System i 5025 Gland Seal System 5030 Exhaust Hood Spray System l 5040 Generator System 5045 Generator Exetter System 5050 Generator Gas System 5060 Seal 011 System 5065 Genarment Isolatad Phase tus system 5070 Ioad Frognancy control System  !* 5095 Dissal Ganarstor System . $1C0 Diesel Fusi 011 System l 3105 Diesel lake Oil System 5110 Dissel Jackat Water System $11: Dise*1 Starting Air - 5133 250 E7 seitchyard System . 5145 Startup 2:a 1 '" c7 Tr==sf :nn: System 5135 Transformer Fire Protection System $165 6.9 E7 AC Distribution System 5170 4 K7 Ac Distribution System , / . 4 6 g . ., .. e -w----- , , - - , - . _ _ . , , , _ , _ , _ . _ _ _ _ _ , _ ._ . , . ,, _ _ _ , , , _ . - _ =. , . . e ,-. , _ _ ~ ( Ac ( , ,. g 5175 130 7 AC Dist:1Sution system

• 5135 208/120 % AC Dist:thution System 5195 Unists nptable AC System (2CP)

• 5196 Unistarruptibia AC System (Class II) 5205 Nor=al AC I.13ht1=g System 5210 Inergency AC I.1ght1=g system 5215 F.nargency DC I.ighting System 5220 250 7 DC Dist:1bn 1on System 5222 125 7 CC System A-5A (Class II) .

5224 48 7 DC Rasar reir Maka-up System , 5226 125 7 DC Security System  : .i 5245 125 7 DC System A (Non-Class II) , _ . . . 5230 Lightning Protection System 5255 Cathodic Procaction System -- 5250 site Grounding System 5265 Hast Tracing and Franze Protection Systsu 5270 Su11 ding 11 set:1c Unit !aatar System 60C0 I'r"!CIL"."C FI.22ry A2TD S2"! 575 TM5 6005 Process Computer /SPDS i 6008 Salancs- of Plant Process Inst =:manution Centrol System 6010 Main Control Board 6013 Annuciator Syste=s . 6016 Isolation Cabinets 1 6020 W "mry Control Board ' - 6020 PA System .- . .% . , . , ~-*

• 6035 PABX Systaa .

l Sound Powered Telephona system

6040 6055 Portabla Radios (?CC Licensad) 3 6060 Mic=ouavs System 6070 Mateorological and Environmental Systa=s

^ 6075 SaisuLe Monitoring System l 6080 Defensive Security Equipnann 6085 Security Computer System

6090 Personnel EmM 2 tion Cc=puter System 4

,6095 Card lander /Acessa Control System

• c100 Survam- s/ Alarm Assessmant System 6105 Intrusion Detection System

. 6110 !acurity Illt=sination System - g 6113 Security 7 enc 1=g and Gatas Special P_ pose Datectors l 6120  ! 61:3 Eny control and Har:baars (Securt:7, Radiation,  : sad Safety 1alated) 6150 securir7 C ==:.ication System i 6133 Instr =nsat Air System l 6140 Ser7:.ca Air 5 ut=n  ; 6130 Nienr.sn Seppir System

• I 6150 T-d: ;u 5:pp17 Snte=

l 6162 C=7sen Sopply system - l 6163 Carbon-Dioxida Supply System Site Fire Protsetion System j l 6175  ; 6180 Sita Fire catection system l l. i St".4 Is s . . _ , ..2._ '.. ( .. * (- h ( ' 6185 I=argency Diesel Generster CAR OCI Systas ', 6190 Air Comoressors Luba 011 Storage and Trsssfer Systas 6200 - - 6210 Savaga Treat = ant System 6215 Savaga Dra1=s Systa=s 6220 Storm Drains System 6225 011 Drains System 6220 Chemical Drains System , 6235 Radioactive ?lsor Drains System 6240 Radioactive Equipment Ur:1:s System i' ' 6242 Secondary System Drain System 6245- I4undr7 and Hot Showers System . 6260 Water Treat =ent System 6262 Upflow yilter 6265 Potable Water System 6270 Domineralized Water System 6272 Acid & Caustic Systam - 6235 Filter SacJerash Storsge and T.-snsfer System 6310 Wasta Neutrali=atien' 6840 Wasta Proesss Computer

6850 Sample System 7000 RAEWAS"?!

Process Radiation Moniteri=3 System (f y.- 7005 7045 Solid Wasta Processi q ystem 7055 0117 Wasta an'd Cc11aef.on -STaparster System 7060 Liquid Wasta Process'ing System 7062 Secondary Wasta Treat = sat System 7065 Baron Escovery System Gaseous Wasta Processing System 7070 7075 Indvasta Sampling System ' 4 709 5 tafueling Systes 71C0 New Fust System 7105 Spent Pual Systaa l j 7110 Spent Fual Pool Cooling System ' 1 7113 Spent Fuel Fool Cleanup System 7122 Spast fuel Cask Caccatami=ation and Spray 7125 Spent Fuel Cask l 7120 Spant Easin and Coneant: stas Storsga and Treat =nnt System j 7125 unsta Precassist; 2e42 tors ,. 7140 Wasta Processing Analog Cant =ol System 8CCO 5"?.Ct"""AZ AND C"4tm ST55.5 ) 8001 Site Plot Plan i 8002 Plant Model

• 8010 C :tsi=m=t S-stem Cantsmi=ated 5::ruge Sa11 ding i 8013 8020 Con n4 = nt Li=ar and 7enet:stion System  !

Security Build 1=g (y 8025 8045 8050 Grounds Maintenance /landscapfsg Containment Pressure Ra11af System l 1 l I arr. . _-._._.__.l............ . . _ . . _N ______________~~~._-. T 7 r_- ( y 53 C.

• 5055 3060 M::o n il Ec'!A*s C ::si:=s : 74cuu= 3:saker Sys:e=

~ or 8065 3 ridge C:2:ss , L < . 8070 Com u1 =ent ? sssuri:::10: S? s t as (~~1.T' -  ;- r 8085 Machi:a Shc?' 'a Sts:2::cm ' ** ' 8100 Ps:st:stic: ?:sasu:1:s:10: 8113 Che=ical Staruga'Zui'di=3 , EVAC Cc:: 1==== 3211d1:3 System , 8130 , 8152 Conni==iant Cooling ' 8160 Costs',-=== Radicactivity la= oval Sys:ss ,- 8165 Cc= pressed Gas Sts:sge - 3170 C: uis:ias: Purga Systas 8180 3cd Drive Cooling- Sfs:.as  ? 8:00 Spen: Tual Casir. Easdling Crane - 8:10 EVAC An

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8200 E7AC Cautral Iccm Area 8:31 EVAC Imergesc7 Se: rica W:e h:ske St::c:::e , 8 50 E7AC Se:rica 3uilding . r f 8260 EVAC Turbina 3u1141:3 7 8230 EVAC Wasta ?;ccessi g Su11di:g C / 8235 Mic::vave,3cdd"g _ 8291 Operatics.s Cffica , 8300 1A*d-dat:stiva Buildi 3 - 830L Racords Storage 7ault ' 8302 EVAC iA- d * *::stive Ind '>d's 8303 Plant Library . [( 8310 2"v*2:7 3cile Ecus e. . . 8330 An'd'd2ry 3uild1=g- .???- : - - . 8330 C : rol 3=cm A sa - 8340 Diesel 2nd'_d' g - 834 E7AC Diesel 3nd' dd"g 8343 EVAC Diesel ?ual 013. :s:sf a: Pu=p 8350 ?nal Easdli=3 2nd'A* g ' 835. E7AC Fuel **-d' d g 3uild1=g 8360 Servica 3"d'd*"g 8370 5:bina 3ad'd'*g 8371 h:51:a - Ea.21:h Physics 3uild1=3 8372 h:bi=a ic=c.5::c: 8380 h itheuse f,382 E7AC '4 :ahen.se J 4330 Waar.a ?::cessi q Euilding 8400 W:ar T:sa:=sst 3cildi 3  ! 9450 Pola: Cra:a Systas 1 8460 T-G Cast-7 C:::.a Systes 8470 T-G v:intenasca C.2=cpy Syst=2

• 8490 Chis:1=a 3tersga Shed 8500 Elevator Systa:s <

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.* l QA-7 SHEARON HARRIS NUCLEAR 70VER Pl. ANT h/,7I,4 RECEIVfNC INSPECTION REPORT Dato Race (ved 7. Z la -7 7 -

Quality Release No. N/4 a

. Item Nat.4 / Do scrip tion

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Shop Order Cade quantity Unit Quali ty As su rance Nt.atw r l Class (Pun ch.a su O rde r A L i . .. :n e o

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Seriet Heat or Other identitication Supplier or Manulacturer Ty e of Pren.ursment No. (Specify) ~~

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M C A- E eo C I N.':s.< rd , _ ,

Base PC and CN's ))//I Coatings and Preservativen ,

Project PC and CN's YEs~ Iiert cas stas.wc.. A) ; 4 M//f Base E. Spec. and Rev. e siccan t .ano Indica to r /d/ M Y56 Project E-Spec./Dws. and Rev. Lubricants _ _ b) { [

Storage Level O _ . Elec tric.11 In: ul a t ini. A) / d ,,

'Special. Handling / Inspections _ , /) C /0 6 User's Test ,, A) _

3 Physical Damage (0 o ld 6 **ta tc r ia l Ci r t t t it.. r. i on_ jfS '

g Identification anc Marntng '5 A r w anu f a c tu r in.; acc. n..en ta tion 189 l

O Cleanness S A7 P

• Dimensions rd 1  ;+s__ S*/7 7- {

Protcetive Covers and Seals M/A *Vorkmanship SM (

• Inspection of these Ltems not mandatory when Quality Releasu is r.welved with -,

shipment. -

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. Package Canary-Accounting Pink-RIR Packade (Tereporary)

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/ 2/20/79 3 g NAaRIS EUCl2AR POWIa P Fue 7 *d 87

/ Rev. 3 RECORDS REVIEW AND ACK.'CVLZDCEMIN1' Transmittal Letter No. O ! A. QA- M- 9 C / '?

Quality Release No. e e, r item Name/ Description Shop Order Code Quantity

~ Unit PO Nuc.be t- Iteis No. ~

Class Pt A ra Ol l' O & Oc.'

Serial Heat or other Identification Supplier or Manufacturer Mf4 Type of Procurement No. (Specify) c yC7&L PC a Trans fe r

.SEE REA Ar_k. S c4R eed res FRon a A-t P a Nsss Po Type of Documents Included A-E & NSSS PROCURED ITEMS 1 _ Document Index Sheet scords are Gm6ete .nd Accepted

._2 -_.. Quality Releases and Supplements 3 Deviation Notices ()o y , ,

M Reviewe r s Signature Oate

_ Manufacturer's Data Report (Code Form)

N L Material Test Reports _ ,

SITE PROCURID ITEMS C3 C Nacerial Certificates of Compliance Records are Complete nnel Accepted

.1, _ Milestone Reports

,,3, Welding Data GO~  ;

L -1 h'a s

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17 _ Identification (Nameplate rubbing)

REM E PT _ Heat Treatment Charts /P,ecords

, , , . . ,. . , , . , , _,q q p 17 , ,

_ Ultrasonic Examiriation Reports /

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la.D Magnetic Particle Examir$ation Reports

• • • ' - I# -

14 _ Liquid Penetrant Examination Reports ' ? < . ') -

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15 _ Radiographic Examination Reports 16 Radiograph Film ^-

17

_ Leak Test Repo rts ~

18 ~ Hydrostatic Test Reports -

w y cy%L [ c.; T M.

19 _ Valve Minimum Wall Thickness; Reports ~--

20  %

_ Oimenstonal Reports 21 _ Performance Test Reports 22 I

_ Setsutic Calculations or Test Reports 23 [tbd

_ Certification of Compliance to Seismic Requirements N" 24 _ Cleaning, Painting and Packaging Reports .7'I /Y' l' M' * -

OA RECORDS . -

27 Records Received and Filed .n QA p' Reco rd s 28 _

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SHEARON HARRIS NUCLEAR POWER PLANT an m e m a. ymst o.ma m L j 7 j:: _ j y) _J / /-2/o fE USED FOR CO6T CODE ITEM DESCRIPTION GTY. UNIT UNIT PAICE TOTAL PAICE j e .. . . < a

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1. ACORESS ORIGINAL.' & (2) COP!ES 2. ArrAcM catotNAL sit.t or t.Acaso ,

OF YOUR ITEMlZED INVOICE TO; I mveier wust swow irru =

Peden Steel -

TNE A80VE ACOMESS ATTENTION SHOWM ON PURCHASE ORCER, F.o. Drawer 26208 .AccouMTs PAYAELE ctPAnT9fNT. ' *4('gP,,A n ,Ac A M CRIGI

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2. 18 ea /M

3. 3/178 n place (AsI" '.-36) i=z5.'--o" 20 ea YA

4. 1/6 TK Place (ASTM-A-36) 6" x 8' o" 20 em 0-a.

5. 5/16 23: placa (ASTM-A-36) 6" x 8'-e= 20 es NO-u

6. f.Tk place (ASIN-A-36) 6" x 45-0" 20 em MOa

7. 1/2" n Place (AST3 M ) 6" x 8*-o** 20 es NA

8. 5/8" n Flata (ASTH-A-36) 6" x 8'-O" 20 es NA

9. 3/14" n place (ASTs-A-36) Sa a 8'-o" 20 ea NO-4

10. 1/?," TK Place (ASTH-a-3e) '8" x 8'-0" 20 - em O* .

11e 5/16" Place (Astm-4-3'6) 8" x 88-o" 20 es Nb

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certirisees of cearermance to Arzz4-M9 fer - .- .

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TDEAL ORDER B&T YART +/- 101.

, Ackaseledge receipt and acceptance 'of this -

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All = tion required by this purchase ,

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"Certificaties 2nquir====e==, dated 1/30/31.

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FO.-@! 1922 l#db-30 O -

b -S CAROLINA POWER & LIGHT COMPANY ## 0 SHEARON HARRIS NUCLEAR POWER PLANT 4A/ ~ '*7 -d/o

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CAROLINA POWER & LIGHT COMPANY g/r/- W-d/0-SHEARON HARRIS NUCLEAR POWER PLANT

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FIELD INSPECIION REPORT '

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. UNITED STATES OF AMERICA n,. ..

NUCLEAR-REGULATORY COMMISSION 'Udl[.['

• e4 ter 14 mi '.I, BEFORE THE ATOMIC ShFETY AND LICENSII'G BOARD Y ;~, : l 'i:AU

?Ril{cnW In the Matter of )

)

CAROLINA POWER & LIGHT' COMPANY ) Docket No. 50-400 OL and NORTH CAROLINA EASTERN )

MUNICIPAL POWER AGENCY )

)

(Shearon Harris Nuclear Power )

Plant) )

CERTIFICATE OF SERVICE I hereby certify that copies of " Applicants' Response to Late-Filed Contentions of Wells Eddleman and Conservation Coun-cil of North Carolina Based on the Affidavit of Mr. Chan Van Vo" were served this 13th day of November, 1984, by deposit in the U.S. mail, first class, postage prepaid, upon the parties listed on the attached Service List, except for those parties upon whom a copy was personally served at the hearings held in Apex, North Carolina. } .

- OY>9 Johd R. O'Peill, Jr. /

lh '

Dated: November 13, 1984 l

O

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of -) '

)

CAROLINA POWER & LIGHT COMPANY ) Docket No. 50-400 OL and NORTH CAROLINA EASTERN )

MUNICIPAL POWER AGENCY )

)

(Shearon Harris Nuclear Power )

Plant) )

SERVICE LIST James L. Kelley, Esquire John D. Runkle, Esqu. ire Atomic Safety and Licensing Board Conservation Council of U.S. Nuclear Regulatory Commission North Carolina Washington, D.C. 20555 307 Granville Road Chapel Hill, North Carolina 27514 Mr. Glenn O. Bright M. Travis Payne, Esquire Atomic Safety and Licensing Board Edelstein and Payne U.S. Nuclear Regulatory Commission P.O. Box 12607 Washington, D.C. 20555 Raleigh, North Carorina 27605 Dr. James H. Carpenter Dr. Richard D. Wilson Atomic Safety and Licensing Board 729 Hunter Street U.S. Nuclear Reguletory Commission Apex, North Carolina 27502 Washington, D.C. 20555 Charles A. Barth, Esquire Mr. Wells Eddleman Janice E. Moore, Esquire 718-A Iredell Street Office of Executive Legal Director Durham, North Carolina 27705 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docketing and Service Section Richard E. Jones, Esquire '

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Office of the Secretary Vice President and Senior Counsel U.S. Nuclear Regulatory Commission Carolina Power & Light Company j Washington, D.C. 20555 P.O. Box 1551 Raleigh, North Carolina 27602 Mr. Daniel F. Read, President Dr. Linda W. Little CHANGE Governor's Waste Management Board P.O. Box 2151 513 Albemarle Building Raleigh, North Carolina 27602 325 North Salisbury Street Raleigh, North Carolina 27611 l

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Bradley W. Jones, Esquire  ;

U.S. Nuclear Regulatory Commission Region II 101 Marrietta Street Atlanta, Georgia 30303 Steven F. Crockett, Esquire Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission .

Washington, D.C. 20555 Mr. Robert P.'Gruber Executive Director Public Staff - NCUC P.O. Box 991 Raleigh, North Carolina 27602 Administrative Judge Harry Foreman Box 395 Mayo University of Minnesota Minneapolis, Minnesota 55455 t

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