ML20205T567

Informs That Gap 840621 Petition Containing 300 Allegations Was Returned by G Hernandez & Maintained at Ofc of Investigations

ML20205T567
Person / Time
Site:	Diablo Canyon
Issue date:	11/26/1984
From:	Meeks R NRC OFFICE OF INVESTIGATIONS (OI)
To:	NRC OFFICE OF INVESTIGATIONS (OI)
Shared Package
ML20204G686	List: ML20204G679 ML20205S937 ML20205T047 ML20205T121 ML20205T237 ML20205T567
References
FOIA-84-741, FOIA-84-742 NUDOCS 8704070325
Download: ML20205T567 (35)

Text

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[+ .\ NUCLEAR REGULATORY COMMISSION *

, OFFICE OF INVESTIGATIONS FIELD OFFICE. REGION V

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• e[ 1450 M ARIA L ANE. SUITE 210

• WALNUT CREEK. CALIFORNIA M5%

November 26, 1984 MEMORANDUM FOR: Diablo Canyon Miscellaneous File (FAC 1)

FROM: Ronald A. Meeks, Senior Investigator [M Office of Investigations Field Office, Region V SU8 JECT: GAP PETITION DATED JUNE 21, 1984 CONTAINING APPR0XIMATELY 300 ALLEGATIONS ON DIABLO CANYON

REFERENCE:

Memo from Ronald A. Meeks to Diablo Canyon  :

Miscellaneous File (FAC 1) dated September 12,  !

1984, same subject

, 1 As referenced above, Copy 2 of the subject petition, including 18 attach-ments, was returned by Gonzalo HERNANDEZ, Region V, and maintained in 0I:RV.

As a matter of record it' is being noted that on this date, this copy is being fpardedtoHanSCHIERLING,NRR.

'cc: Han Schierling, NRR j

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o June 12, 1984 MEMORANDUM TO: D'. G. Eisenhut, Director, Division of Licensing V FROM: T. W. -Bishop, Director, Division of Safety and Projects Region V

SUBJECT:

SAFETY RELATED BOLTING AT DIABLO CANYON UNIT 1 - REQUEST FOR TRANSFER OF LEAD RESPONSIBILITY - DOCKET No. 50-275 3

Based on the results of a Region V Special Inspection during the weeks of May 14-25, 1984 and information received on June 11, 1984 in the Region V Office (PG&E Letter No.: DCL-84-220), on safety related bolting problems at Diablo 4

Canyon, Unit 1, the Region requests that NRR assume lead responsibility for the evaluation and resolution of the enclose 8 information. Because of the possibility of a near term Conunission decision on a full power license for Diablo Canyon Unit 1, and because of the potential significance of this issue, s

the Region suggests that immediate action be taken.

As per a telephone discussion with Mr. J. Knight at 11:00 a.m. PST on June 1

11, 1984, you will find, enclosed, support information obtained from our onsite inspectors. Allegations 351, 861, 862, 864, 871, 873 and 885 are included in this package and are being specifically transmitted for your responsibility.

} ,

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'T. W. Bishop, Director Division of Reactor Safety and Projects Region V I

Enclosures:

As stated t cc w/ enclosures: G. Knighton, NRR pc< n[ 't-- L -

H. Schierling, NRR cc w/o enclosures: P. Johnson, RV R. Pate, RV l D. Kirsch, RV I

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is document lists (or directly references) each allegation or concern brought to the attention of NRC personnel. The purpose of this statement i sheet is to assure that all points raised by the alleger are covered.

If the problem statement is not clear as to who, what, where, when, or why regarding the issue, ,the, cosamentan~yTection will amplify the statement. The 1

cosamentary section will also be used if there is apparent conflicting information or if there is no or very little original information available . ,

which describes the concern (s). (This can occur if, for example, a line concern was received in an interview).

Probles Statements (use extra sheets as necessary)

Allegation # Verbatum Statement or Reference Y jftb

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j Date This Statement was Completed l7 j 'l l Tectinica'l ,Reviewek Signature I

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6-T2j W $Y-3 PI2:44 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE COMMISSION In the Matter of )

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PACIFIC GAS AND ELECTRIC CO. ) Docket No. 50-275 OL

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(Diablo Canyon Nuclear Power ) "

Plant, Unit 1) ) 'S'

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• PETITION PURSUANT TO 10 CFR 2.206 i

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THOMAS M. DEVINE,

. Legal Director GOVERNMENT ACCOUNTABILITY PROJECT 4

_e403040104-840503 INSTITUTE FOR POLICY STUDIES PCR ADOCK 050Cojy G

1901 Q Street, N.W.

washington, D.C. 20009 (202) 232-8550 DATED: May 3, 1984 .

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i (a) to determine through visual, destructive and non-

! destructive examination the scope and nature of deficiencies in the condition of Diablo Canyon resulting from alleged violations of regulatory or program quality assurance .

violations; and -

. (b) to determine the need for a comprehensive, third i party reinspection program of all safety-related construction

in Units 1 and 2, with full authority by the independent organiza-

tion to identify and impose corrective action on any noncon-forming condition that deviates from 10 CFR 50, Appendix B,

, the Final Safety Analysis Report ("FSAR") or plant specifica-j tions, through implementation of corrective action; 1

I (5) development of a full factual record on Pacific Gas and Electric's ("PG&E") character and competence to operate the Diablo Canyon nuclear power plant, including (a) a management audit by an independent organization,.

ud 1

(b) publication of a report by the NRC Office of Investigations ("oI") after completion of its investigation to j determine the causes of construction and design QA violations

at Diablo Canyon, including issues such as harassment and j retaliation, subordination of quality assurance to cost and i scheduling cencarns, destruction of records and false state-l ments, and deliberate violations of the Atomic Energy Act, and

{ (c) review of the record compiled in any pending 1 administrative hearings before the Department of Labor for j alleged retaliatory personnel actions in violation of 42 USC i 5851 at Diablo Canyon; l (6) Board Notification of transcripts of whistleblower i

interviews that began on April 3,1984, until completion of all l such interviews 1/ ,

! (7) investigation by the office of Inspector and Auditor l (" OI A") to determine --  ;

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(a) whether there have been misleading or material l false statements by the NRC staff to the Commission during the March 19, 26, 27 or April 13 briefings, or in supplemental Safety Evaluation Reports 55ER-21 (December 1983) or SSER-22 I (March 1984), and i

(b) the causes of the QA breakdown within the NRC staff l responsible for Diablo Canyon 1

l A/ In order to facilitate manageable review of the voluminous l transcripts, counsel will work with relevant witnesses to prepare i summaries of issues raised and supported during the interviews.

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The Mothers adopt and incorporate by reference all 519 l allegations and documentation in earlier February 2, March 1, .

March 23 and April 12, 1984 petitions to the Cossaission. Those disclosure are relevant bases for this petition and have not yet I been seriously reviewed, let alone resolved. This petition is j

1 further supported by NRC inspector Isa Yin's draft reports on

} Diablo Canyon. See Diablo Canyon Board Notification No.84-071 (April 3,1984) . Third, this petition is supported by the trans-cripts of witness interviews since April 3 which the commission I

has not yet released. Those transcripts include hundreds of specific, new allegations.

Finally, this petition is supported by the evidence summarized below. Since the Commission's April 13 decision to 4

1 I.

permit icw-power testing, counsel has received six additional

affidavits , including two from GAP investigation Richard Parks

?

j and ot.her affidavits from four current and former employees

! at the plant. 3/

1' j I. DESIGN QUALITY ASSURANCE BREARDOWN i

~

j Although QA deficiencies for large- and small-bore piping are common in the nuclear industry, Diablo Canyon suffered a compre-hensive QA breakdown in these areas. At the April 6, 1984, il j Advisory Committee on Reactor Safeguards ("ACRS") aceting, j Inspector Yin put the violations in perspective. "What makes it 1

unconsnon with Diablo Canyon is that, first, all areas cor.sist of deficiencies. . . " (Transcript of April 6, 1984 ACRS meeting, p.

1 i M Two witnesses submitted affidavits on condition that that con-fide.ntiality ing cl.aracteristics.

would be protected through deletion of any identify-In those cases ul. censored versions of their j

atttaments will be provided to the NRC staff or the Office of

] Investigations.

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1 .

1

To illustrate the scope of the problems, one of whistleblower i

Charles Stokes', allegations which Mr. Yin " fully substantiated" . ,

1 involved " thousands (more than thirty 21 s " binderafull)" of i

unreliable " Quick Fix" design changes. (Board Notification 84-

) 071, March 29, 1984 Yin draft, pp. 49,55). In light of the j

uncontrolled nature of the program, a sampling review by PG&E is unacceptable. Every ' Quick Fix" must be examined by an i

objective reviewer.

Every Quick Fix that is skipped or glossed

] over will represent a potentially dangerous questior. mark during cc merical operations.

i Finally, PG&E disqualified itself through misleading or I material falso statements to the commission a week and a half

{

1 prior to the April 13 licensing vote, on the same issues that ~

j were holding up the license. An April 30, 1984, affidavit from i

i

! whistleblower charles Stokes, enclosed as Exhibit 1, alleges j

17 misleading or material falso statements by licensee representa-i tives at an April 2,1984, public meeting on Mr. Yin's findings.

J Mr. Stokes' charges should be carefully considered due to his

strong credibility to date on factual issues. As Mr. Yin pointed i I

out on March 26, "Almost all of the Stokes allegations assigned ,

i to me for follow-up had been substantiated." (March 26 Yin  !

statement, p. 1) .

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) work could have been maintained throughout the company. However, J

i the Pullman version pervaded the attitude of the supervisors .,

involved." (M,., p. 8).

3. Case studies

{ Individual case studies highlight the results i

of the QA breakdown - ineffective corrective action and dormant hardware deficiencies that haven't been fixed.  !

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l'. Bolting --

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{ hree witnesses provided affidavits desc'ibing r alleged '.

violations for safety-related bolting throughout Diablo anyon. An April 18, 1984, affidavit from a confidential I

witness, enclosed as Exhibit 3, charges the following violations i

of American Institute of Steel Construction ("AISC") requirements --:

i p 4 (a) designdrawingsnotshecifyingelongatedholes; '

l y $4 L $(b) hole sizes outside of Code specifications; fAp4%$T=9(c) torquing method; l

/ f $. y 4 (d) bolt reuse; [and] ,

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(e) examples of ' packing' violating foreign material cifications.

i i (Exhibit 3, p. 10).

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To illustrate the effects of the QA violations, the former

! inspector reported his discovery of a Unit I pipe rack "where j

l six of the eight mounting / bolt holes were elongated to the point j ,

where the washers could not cover the holes . . . In some j

instances I found the crafts had stuffed the holes with short tions of soft tie-wire to serve as packing." (M., pp. 2-3 .

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The causes of the QA violations again were deficient '

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j procedures and management's attitude. The installation pro- I i

cedures, Engineering Specification - Diablo ("ESD"), that set the

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p. 6).

The result is that in late 1983, three years af ter NCR DC2-RM-002, significant procedure deficiencies remained. Mr. Lockert reports the following violations:

[1.] The tables provided for the description of acceptable washers had not been updated per the requirements of AISC, Sec. 5, Page 191, Para. 2(a).

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[2.] Acceptance criteria for High Strength bolts was not defined in ESD 243. Field Inspectors did not know, nor were they legally able to reject bolts that were defective per ASTM A-490, ASTM-

] 325, and ANSI B18.2 requirements.

[3.] Bolt Torque Tables in ESD 243 were still out of compliance with AISC Manual requirements as late as December '83. Discussions with Pullman Field OlO Engineers Dale Warren and Larry Werner indicated that although the tables had been recently updated, they still do not meet AISC Manual requirements.

(Exhibit 4, p. 6) . Similarly, training remained deficient. (Id. , p. 7 The bottom line is that literally at the nuts and bolts level, hardware remains deficient. Between July and December 1983, when he has terminated, Mr. Lockert identified the following recurring violations:

1. Unauthorized modifications to fillet welds O\\ that encroached on bolt or washer land areas.

~ 2. Oversize holes already QC accepted outside (j the tolerances of ESD 243 and AISC Manual.

3. Oversize holes in base plates packed with steel rods and wires without the benefit of an O\b approved Pullman procedure. (This work was performed to a memo from Mr. Torstrom in violation of 10 CFR 50 App B, criteria V and VI.)

4. Oversize welds beyond that allowed by AWS D1.1 and beyond that allowed by Pullman's ESD 243.

5. Defects in A-490 bolts had been found after the r bolts had been " dedicated" by Pullman's QA Receiving Department and sent to the field for installation.

l (Exhibit 4, p. 5).

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, affidavit, enclosed as Exhibit 6, This weld connects the " Safety Injection Accumulators" (core flood tanks) to one of the Reactor Coolant Cold leg (s) . This tank is required to be available during a " loss of coolant accident" to inject borated water into the core to ensure it is and remains in a safe,

' shutdown condition during an accident. This is .

because the borated water prevents the fission 1 process by absorbing the neutrons required for l

} fission. A failure of this line could " prevent l 1

an Engineered Safeguards Actuation System from 4

performing its design function (maintaining the i core shutdown)." A failure of this system would also violate the Accident Analysis of the Final Safety Analysis Review of the Plant, and every avenue should be pursued to assure this system boundary has'not been violated.

I i (Exhibit 6, p. 8).

Unfortunately, PG&E didn't take that approach. In theory, i this condition was resolved through a corrective action plan

approved by NRC Region V. See IE Report 50=275/83-26 (August 5, i

, 1983). In fact, the sampling program was not properly expanded (Exhibi 6, p. 5) and a relatively inaccessible weld such as RC-f

2-16 was missed.

Even more significant, PGEE knew better for this particular weld, despite the sampling deficiencies. In March or April of 1983, a whistleblower had identified the deficiency on-site.

i (March 23 supplement to pothers for Peace 2.206 petition,

Exhibit 12, p. 5) .

l These case studies raise the question of how many similar deficiencies remain doreant at Diablo Canyon. No one can answer with certainty. The breakdown in corrective action helps to j explain the quality indeterminate state of the plant.

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j III. NAC QUALITY ASSURANCE BEEAKDOWN i i

The ,au.re o, ..c-ap, roved correctyve actyon in the ..a7 tor

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eroded confidence. One whistleblower cancelled out of the tour due "to fears (of] my identity becoming known and my personal ,

safety on-the-job jeopardized. I feel the potential existed for compromising my confidentiality because the NRC was callous and awkward in handling the details for the tour." (Exhibit 2, p. 1).

l By contrast, the staff refused to permit another whistleblower to attend the plant tour, despite prior agreement. As the t

j witness explained, j- The NRC's position was that they had not spoken with me, and it had not been agreed to the night before so they couldn't let me go. Mr.

Parks informed me that other witnesses had I

decided to back out because of fears that their identities would be compromised. I agreed to

go in their place. I wasn't afraid, I would have

] been with NRC personnel and because I didn't work 1

there anymore, I could not have been retaliated

) against later. The NRC declined again and made no effort to even speak with me about my concerns.

I was astonished and angered.

(Exhibit 3, p. 5) .

] Region v has continued to exhibit bias since the April 13

decision on low-power testing. For example, on April 30 Region V official Thomas Bishop reported that "we did not see a widespread j problem" with intimidation and unfair dismissal of whistleblowers 1

i (Thomas Bayes, "Diablo Canyon Reactor Starts Up Amid Protests l and Industry Praise," The New York Times, April 30,19 84, p. 38) .

Mr. Bishop neglected to mention that those issues are under the

jurisdiction of the office of Investigations, which has just begun i its probe of alleged retaliation. Mr. Bishop's exoneration was premature, to put it mildly.

Mr. Bishop also failed to identify "an undermining of the quality ase arance program" from alleged intimidation and reprisals. In this instance, Mr. Bishop's reassurances have an

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it will become a threat to the public.

1 Respectfully submitted, l

- O 1, -

\ l ,a A Yss Thomas Devine Counsel for Mothers for Peace e

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' EM&T 3 i

AFFIDAVIT .

I

(

i My name is 1

4

, I am providing this i

statement freely and voluntarily, without any threats, induce-i ments or coercion to Richard Parks, who has identified himself to me as a volunteer investigator investigating alleged problems at the Diablo Canyon Power Plant.

i I am providing this statement to document my concerns over the improper installation of rupture restraints, pipe sup-t ports and equipment foundations.

j I volunteered to personally i identify these problems to the NRC representatives on the plant j

tour that took place on 4/11/84 My offer was declined.

I felt 1 it was necessary for me to accompany the tour to properly iden-

) -

tify the locations of the problems that I knew e.

xisted before I ter=inated my employment with Pullman Power Products in .

1 1981.

l I' i i

i I was employed at the Diablo Canyon Plant from approx-i

! imately 1978, until approximately 1

1 1979 with the G.F.

i Atkinson Company. My job status consisted of weld inspector. It was during that period that I functioned as an Inspector that I became in-j timately familiar with American Society for Testing and Materials (AST:1) and American Institute of Steel Construction (AISC) C relevant

to bolting requirements on structural joints and surfaces

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..- 4/18/84

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design drawing showed no enlongated holes. In all cases the per-sonnel .

advised that:

1. Work was performed by another contractor;

2. Not,to worry; .

3.

PG&E as is.

knew about it, it was old work and was accepted

, had to accept these statements as being gospel, main-ly because there 'was insufficient documentation in existence and available to dispute their claims.

i i

This type of problem was widespread throughout the plant.

I had discovered

! similar situations in Unit 1 Reactor Building and Unit 2 Reactor Building. In some instances I found 4

the crafts had stuffed the holes with short sections of soft tie-wire to serve as packing. I could not understand this practica.

k When I questiened what document provided the instructions for this practice, none could be provided. I consulted the pipefitters in-volved, my supervisor, PG&E inspectors and the engineers. Their reply was that "we had always done it this way, PG&E is aware of it and had accepted it as is."

i To me, this constituted covering up poor workmanship by virtue of oral procedure or at best by internal memo rather .

than'by approved procedures or AISC/ ASTM codes.

My persistance in persuing these examples of non-E ._ c = - - ~ ' - - - ~ ~~ ~ ~

(next)

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1 state that there would be a problem with my going and had agreed the night before with Mr. Devine (GAP Legal Director), to allow another witness to go.

5 At approximately 7:30 P.M. on 4/11/84, I arrived at the meeting site. Shortly after my arrival, Mr. Parks and Mr.

Schollenberger of the NRC were discussing my accompanying the tour.

i The MRC's position was that they had not spoken with me, and it had not been agreed to the night before so they couldn't let me go.

Mr. Parks infoEmed me that other witnesses had decided to back out because of fears that their identities would be compro-

! mised. I agreed to go in their place.

I wasn't afraid, I would

)

have been with KRC personnel and because I didn't work there any-more, I could not have been retaliated against later. The NRC declined again and made no effort <

to even speak with me about my concerns. I was astonished and angered.

I I

Mr. Parks advised me to prepare a brief statement cut-lining my concerns and that he would ensure the NRC would receive i it.

on 4/12/84, I presented a two page handwritten state-I ment to Mr. Parks while he was meeting with the NRC. In this statement I stressed that I wished to speak with the NRC Office of Investigations.

He asked me if I could wait around for a 1

while and he would see if he could get the NRC to talk with me.

{ Approximately 45 minutes later, Mr. Parks introduced me to three (next)

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[;. .4/18/84 Pcgo 7 . .

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with respect to a plane normal to the bolt axis.  !

' Bolted steel parts shall not be esparated by gaskets and shall fit solidly together after the bolts are tightened. Moles may be punched, subpunched and i reened, or drilled, as required by the applicable code or specification.

i Standard holes shall have a

{

diameter bolt diameter, nominally 1/16-in. in excess of the nominal i

Where shown in the design drawings and at other lo-cations approved by the designer oversize, short

! . slotted. and lon 1

mentary) may be ssed 'g slotted withholes high-strength (,see Table 7 in 5/8-in.

bolts Com-j diameter and longer in connections assembled as  :

follows:

1 I

1. Oversize holes may have nominal diameters up to: J/16-in lar l in diameter, 1/4-in ger thanthan larger boltsbolts 7/8-in.

1-inandinless  !

l dia-l meter, and er in diameter. 5/16-in. larger than bolts 1 1/8-in. great- i of friction-tvoe connections.They may be used in any or all plies 1 I

Hardened washers shall l be installed over oversize holes in an outer ply. '

1

2. Short slotted holes are nominally 1/16-in, i wider than the molt diameter and have a length which 1 does not exceed the oversize diameter provisions of j subsection 3 a 1 by more than 1/16-in. They may be l t used in any o(r)all plies of friction-tyos or bearina-i connections. The slots may be used without regar ggg, d to direction of loading in friction-type con-i i nections but shall be load in bearinz-type normal to the strection of the connections.

! Hardened washers j shall be outer ply, insta11ec over ,short slotted holes in an t

)

3. Lona slotted holes are nominally 1/16-in.

wider than the molt eiameter and have a length more j thantimes 2% allowedthe bolt in subsection diameter. 3(a)2 but not more than

The slots may be used i without regard to direction of loading in friction- )

o connections he load in bearina-type but shall connections. be normal to the atraction '

J 1 Long slotted holes may be used in only one of the connected parts of either a friction-type or bearina- l gge, connection at an indivisual raying surface.

i I

Where long slotted holes are used on an outer t a plate washer or continuous bar of at least 5/16 ply, in,

thickness with standard holes shall be provided. This

washer or har shall be of structural grade material,

! tut need not be hardened. If hardened washers are re-(next)

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does not produce a nut or bolt head rotation from snug tight greater than that permitted in Table 4.

If manual torque wrenches are used, nuts shall be in tightening motion when torque is measured.

When using calibrated wrenches to install several bolts in a single connection, the wrench shall be returned to " touch up" bolts previously tightened, which may have been loosened by the tightening of sub-sequent hits, until all are tightened to the prescrib-ed amount. .

(f) Reuse reused.

A490 bolts and galvanized A325 bolts shall not be '

the engineer Other A325 bolts may be reused if approved by responsible. I Recightening previously tightened bolts which may have been loosened by the tightening of adjacent bolts shall not be considered as a reuse.

6 INSPECTION *

(a) The Inspector shall determine that the re-quirements of Sections 2,3, and 5 of this Specifi-cation are met in :he work. When the calibrated wrench method of tightening is used, the Inspector shall have full opportunity to witness the calibration test prescribed in subsection 5(d).

(b) The Inspector shall observe the installation of bolts to determine that the selected procedure is properly used and shall determine that all bolts are tigTeened. Bolts installed by the turn-of-nut method may reach tensions substantially above the value given in Table 3, but this shall not be cause for rejection.

COMMENTARY C5 INSTA1.1.ATION Where long slotted holes are used, experimental evidence has shown that a plate washer or continuous bar of at least 5/16-in, thickness with standard holes is necessan to provide adequate bearing.

or bar shall be of structural grade materialThis but washer need not be hardened. However, if hardened washers are '

i required to satisfy Specification provisions, the hard-oned the piste washer shall washer or be bar.placed over the outer surface of l

The examples I could have identified to the NRC on the plaat cou. would have been code violations with respect to:

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we<- + r ac t n. gar f V: , . p,. q,cpq (,p p A v M lca q s/s p y & L:LH y J--

notified of such modifications.

b) Field Engineer Dale Warren issued the proper Washer criteria for myself without notification or acceptance by Pullman or PG&E QA Departments.

QA/Qr Manager Harold Karner, when notified of out of date Washer criteria in ESD 243, did not issue l

a Non Conformance Report nor update the present ESD 243.

pex > E!Y

-p[c) Pullman did not have the proper Torque Tables in effect three years after the writing of NCR DC2-80-RM-002.

10. Pullman did not train nor indoctrinate inspectors to the requirements of the AISC Manual for Bolting. (Ae-cidental reinspection of work accepted in late '82 or early '83 revealed hole sizes outside the tolerances of the AISC Manual.)

I

11. Defects in bolts were not reported per a NCR. I was unable to report the defects I iuut found in A-490 bolts because I was not allowed to consult the procure-ment documents needed to properly generate such a report.

Pullman Supe'rvisor, Russ Nelle specifically prevented me from referencing these documents by saying that I was out of my area. (see oct. 17 indicent of Lockert Letter addressed to Mark Padovan, USNRC dated 1/2/84.)

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ALLEMT20N REPORT Q*

dE . ALLEMTION: FACILITY:

Dokdo CetugM Ess: C e3% egg. g ag p g cy g g c, ,) rs g -sE h4-Coy'

- * - ~ ' ~ l oad.t. 4ev O s *5v d hvc su fit e DAT E :

. __.........._.: (e[7[By 72ME: .

2' o6 P. r PHONE: CONFIDEPITIALITY REQUESTED NO DO~ NO:

S) .

SUMMARY

OF INFORMATION:

%e ce k e.k ul dr esA- o t I nc Le n tch & .

cremda nw o< i ete Ohm nuaS , Meemo toiil 0ctit ba&

4

& 6/si/sy M nh o zio c, P. e to

h. t r- a ba .

a.s eu Elm 3 Ws p d e J s t,._ c e <x+wia.

eme u .

i l

1 Mst t PCCPantD ST DATE c . He < n ud.e n. s/,len i

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L N3w Lu ii c o l. J. Kn ct . wss wm O a.u o to ut a u G u s $ .c. , m co/e/a4 o ' ,

l d

arCVICTED SY * -

DATE*

s.He1a u rat co/,/en - - -

JA"" 6 13'-

OFFICIAL USE ONLY DO NOT DISCLOSE .'.

c.s eo ecC Cn . Y c r ^ M c.*a-6/I/s4

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ce ca 3 6 w< ew wa (*; ms-sem y _

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& ctes i - be % gh bcLeve.s h.k to /. g du s maJ-( beve sme po4 es W feud .

g.9 N g du +~ h L a - iaea me u pth a no-I c a cu. w cs -

beco m g subsh h q d ,

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Date f ROUTING AND TRANSMITTAL SUP

$0ff 4 ,

TO (Name. oNice symbef, room number, Initials Date

building, Agency / Post)

3. 7. P. k a , SM .

3.

• O 3.

4. - ,

5.

Action File . Note and Retum Approval For Clearance Per Conversation

, As Requested For Correction Prepare Reply ,

Circulate For Your Information See Me Comment Investigste Signature Coordination Justify REMARKS h b , C,]C- 8M b O h ,

w m rea t A R E . _ Pl a wu .

- hk- Qt (A A {, .

( .

DO NOT vee this form as a RECORD of approvels, concurrences, disposals, clearances, and similar actions FROM:(Name, org. symbol. Agency / Post) Room No.-Sids.

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, hsW \ k Phone so41-102 -

• OPTIONAL FORM 41 (Rev. 7-76) ..

eso Nser o. sea-s:s cats)-

rres YcD-11.ao's .

~ . .

M .

, , , , , , , , , , ;f7) sit ce

.f#d'0 ALLEGATION leepwowe sa o DATA FORM

'a* . e.

u 5 woctise as cuision towwwo'.

F MCEIVING OF FICE Doch en Number (if applicable)

,, recilitylle al involved: I N . =.1 ' & C,  ? ,*I C f. *,.. f t S ' 2

• in m . in n s. .,or b t r-L t. O I peM.esme GtNtfleCl C C & C, C, 1 % .,

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2. Functional Assets) Involved: onsite heelsh and safety (Cwr.a .pswep w be.t.it I _ operations offsite health and eefety I construction _

safeguards _

emergency prepstednese other tspecitrl

3. oeseription: 1(li131 lole irl R.lT-Ic 121n10Ii 14161 Islo li F l<l l I I

',"""" l (l 2.l) l lt lH PI A.lo l p lrlg.l lals (El lolFI lAl.ficl7 ll IMI AIrlrle.it IMtl I t'l 3l5 l l vli Ic_lw Ir le l uii tul(-l l J Ir-lt.1 Al 916I c1s.1 lui t Irl H olu l T1 I clo I dI 712.1 cl' Isl J

4. Source of Alleget on: seCufIfy guard (Chect .pgwopoete bes) -

ControClot empIoyes _

- ficensee employee. __ news medie .

NRC employee _

private citizen

_ organization especityl c,o v.!T.Qc,,.A ggr pLo y cT

[ osher isp. city %l2 44 EN2.

MM 0D YY

5. Date Allegation Received: o g O 2l{ 4 N DC  ;

6. Name of Individuel tri, i ..nis.. . ..dt..: n. .t l

Receiving Allegation:

\

7. Of fice: g ACTION OFFICE

. sosi;.e. ... s.. .. ..

- - O M I-

3. Action Of f~ce Conteet: . tr...i S. FTS Telephone Number; g 3 ,

3

10. Status: T/'

J Open. if followup actions eve pending or in progress l ICheck o* l Closed, it f ollowup actions are completed i MM DD YY

u. Dete cloud: 11.1 Document Nos. l l l

' ".*Itanni

• *io 50 c h.. . : w r.1 II IIIIII -

I I I I I I I I I I I I I I i~l Il l IIIIIIII IIIIIIIIIIiiiiIII

v. ., home..

o tt.. .

MAQ-hours Date o o 2 V

\

13. Alleget.on Num er:

l lR V -RL* . . .

. \e

\

Ti m O* t'el l !

c/ F:cL F eri c -

2116 Coipente/ C&nycn Rcid S i.n Lv:s 001opc. CA 97.301 Wes) 544.I102 - - - - . .

cliegatier. (1) In re'erence to ESD-238, per,ct:ce at D: Lb l a *. : :.

/ been to torque bolts on gasiet joints up to trice minimum ta c.:

J'

/ \

in accordance with Sections 2.4.3, beycnd

0. 4. .. I and 2.4.3.2.

titi ce this minimum tor que and engineering evaluation a s Fcr r eq.*: r ed a c:- Section 2.5. Howeve , Mr. O' Nei l l ' c c al cul at i c..

chew that incre+=:ng to twice ma nimum torque value can result :-

ec cess.2 ve teol t ctiess; i.e.. greater ths.n all owable cold stress in ESD-2 9. Section 2.5.2.1 (see attached cal cul ations) . This i.I l s g o t t o n includes that there is not correl ati cn between torc'. e

. a l te e s and ms::i mum hot ellowable stress in pppendi> C of E5D-2 2.

Alse. it i n cl uctes thet bolt tensicns me.y e::ceed allcwable st cs-cn gesFet ma t er i al (ESD-239. Section 2.5.2.1).

Allegation (2) Use of A307 materi al in Class C systems (which is

[ Cl ass 3 in B31. 7) has not been specified in PPP procedure and :s P not speci f i ed as allowed by ANSI B31.7. Mr. O'Neill questiene:

..' whether this los nonconf ormance. He was told that it was not,

.' tecause B31.7 allows uss of materi al s, and design based on ASME Section 8, and B71.0, r e sp ccti vel y. However, this was inccrrect because D71.' spec:f.ed stresses in accord with ASME Section G end meter.a: in accced tai th B31.7. He was told later thst A5ME Sactico O ellot.: tis. of A T J.*7. The all egaticn is that there ic r,.

cl ea; pe c:s.f ure or rpe-!f i c ati o. s f en- the. une t f ATO7 A l l e .;s. : : : - ' ' . '

. Et t - t v . ' 7s :me in e- d tightened flange 3 wi t t. n '.

j .g.\\ a n f s p;;Or e. . ? . cr.t r o i n , : n c. ] c. q 1 sc:

. -f an, DC. trspe.tci. T' ;

,, . al2egstion c. esti ons. FlDO 41 c.c.ge t c 1 t r.g . pr acs cer e accc :st at t 11 t .

enc i nt ci-i a :e wi th PPP 4.tel: t f documentation. This in:1udes

~

control for replscement Qsaiets used by stortup and test cres:.

n:Iejat.en 4) PPP ESD-2~E. Ce:t:on 2.1. 2 speci f :es that f cr

.t -crt t '.a t has nct M-d pee v i c.is e -i f 2 c eti on of mater

• i 2.1

• .F:m %!.t): that GA fie d 1 rs ert2 e n ;s :e.auired. This .

. . 21 : ts st.cn 3.cserts tbst th c-r e e cs .c conticir to essure that th -

{2 eld : ncpc-c ter could vei.Fv th7t

• hi. 2 r e.::;ui r emen t was satisf t...

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Q A 193 GR P/7)KZ crec_ da @ 6"df = 2,BCC P51

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b-b N P Giz % ecd tdg,a = 4o78 4  %=y = 48.02 k61 6im - iz.(65) 12.(.50) = 13.6 wie 3g9, wm u.c. dr,w. = 'ht = g6.04 ust '

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• FICtD THAtlGEG WCl40 NOT IN ACCORDANCE WITit 11TG TRAN CSI A!4.1GIED POCUMENTATICN4 1373 Rv84A073 OA/OC OF 5/22/84 NRR l'101 liiODLD l'thSONNI:1. IJICCl)llitAOED F Delft IDENTIFYING CHG NTG titan 1374 RV84A073 OUICK FIX OF 3/22/04 NRR OIIICV FIX OilOCCDINiC 100CD TO..JUGTIFY FDOR WORIHANSHIP P1TG TRAN OF 5/22/04 1375 RV04A073 WCLD SYNBOLS NRR Wl'8 D SYHiDR DF.AWINie!i tle.G PJOI Flior[68.Y DELINEAirp ON TIN: DCSIGN NTG TRAN Nil;GING

~; 1376 RVO4A473 WC1 DING /

OF 5/22/04

. NRR ORACTICES llur OF tauf f Cor4FOhMINii At.7 leOI.IG AG STilDG FOR HTG TRT.N

( OHit l ANf:C WITH ACHE CDDC 1377 RV04A073 OUICK Fik OF 5/22/04 NHR IMitCF FIX PROC # telWiC 18C00 TO Dl:GIlife ll VtDWAhC 41TG TRAN 087 5/02/04 i

• l RVa4/nes73 ANCalOR faut Tti/

4 NRR 1

i.Ot.T i No hilCllt Ni f. ell $ NOT OlsOf"!:lti Y CHitt DDT D IN CI)Nri;rll: g TS.TRAf4' . '

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• - RV84A073 It1FROFt'R 84hlt

• INST AL L ATION N.lf OH filllD 184 Allt llOtha.1 [D PfiOf f Hi Y.Fi l l, W.n TI- fi G'.'!sil li ConJt. f, NO T DC tlTG TRAN It4tlT(et LCD Ill[N I Af:1- FM48 WiiG Clli 184 hat f At40 OF 5/22/t4 b'N t h WII Ot O 10 Is bE OLATC **

j 2 RVO4A073 DRAWINGS / DOCON NRii

• CONil?Ot. .

AS 191911.1 AClllAL Dit4Wif FIEL D CONDI M>S flON IMI f 40l ILHilia. Nil r fiEFL ECT THE HTG TRAtt Y 3 y 3 RVI54AO73 OA/DC 4 NRR OF 5/22/04 k

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g fif LCIFICATIflNS FAMil.II.R WI TH CODES AND 1}io RVB4AO73 ANCilDR DOLTG/

t1TG TRAN h DOLTING NRA (8841 1 HILTI I Wil; A18Clioli OF S/22/04 D '

I< 44At l i. , .303T CtlT OtT FL LMiH.TsOt.1S NOT RrMOVED l'ftOH N10 TRAN I IN!ifALLCD 1.5 INCill !i AWAY WI THOUT OF 5/22/04 i)D DOCUMENTINGIJTW ANCif0R 1 7 (_OCATION OF OtD BOLT '

q RVD4A073 ANCHOft DOLTS / NiiR 5 I

DOLTING 4 L8tJI T 2 Suf f0RT LAVOllTS ARC DCING t1ADli WITHOUT NTG TRAN M

APFfiOVED COtJfiIfitfCT ION LRAWINGS OR FliOCEDINiCG .

OF 5/22/04 q

11 3 RVB4Au73 ANCHOR DOLTS / !if'l(INI ( Cil llANGlilititiRILIItJG HOLFS AND DfiY l' ACTING h

$ VACATFD HO 5 #48tR BOL TING f g 1:0 VACATED hot.CS IN Aux Dr.DG Cl.EVATION 85 MTG TRAte A

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RVD4A073 ANCalOR BOLTS /

BOLTING NRR OF "/22/04 (Q INNPOfsi 1.tll t il 0Rit t.f DATION INfil Al.1 IN TitC COH1 AIN'1ENT WAt t

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/0 Of 5 2'.'/04

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

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= .

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1397 RVS4AO73 DfiAWINGS/ DOCllrl NhH jl CONTEOL D il fit t Gl'NCFe4llut 8 Ul< Of t 1he N34Tli fiYfiTEN SIN POhI NTG Ti4AN 3i

'6HNt ilAG A NilI ist AlsillO HN WEl D AND HALF OF A Gil!N OF 5 / 2 2 /154 PlAIL. 4i T ill S COND I T I ON HO T CI N)WN DN AS - Bli t L T '

DhAWING 1398 ftVG4AO73 WELDINO/ NRR $

WING Pt. ATE ON SUPPOffT :Y,05ft (KiED l'AR T I AL PRACTICES l'ENElRATiuN WUtD NTO TRAN

• INGifAD OF FatLL l'ENETRATION WELDG OF 5/22/04 CONSTRl8CTION Di(AWINGS REOulRED

• 1399 RV84A073 RHR VALVES NRR 4 IfNIT 2 RHN CONTAINNENT SUNP 6ECIRCin ATION LINE TO NTG TRAN RHR PUMP IS SEAL WELDED WITH NO PENClfiATION OF 5/22/84 3 RV84A073 ANCHOR 90t_TS/ NRR BOLTING HILT 1 OulK BOL.TS WERE CUT OFF AND LEFT IN WALLS NIG $A4 ..

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ly ( RV84A073 ANCHOR DOLTS / NRR

! I k IsOLTING ANCHORG CUT OFF FLilSH WITil WALLS, tEFT IN HOLES, NT JF

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1402' Rv84AO73 ANCHOR BOLTS / N84R g EsOLTING W GROUTINO hu)CEDelhE DOES Nut LOAD THE CROUT 'NTO TRAN

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