ML20202B437

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Partially Withheld Affidavit of R Yockey Re 820714 Meeting Concerning Brown & Root Personnel Policies
ML20202B437
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 01/24/1984
From: Yockey R
BROWN & ROOT, INC. (SUBS. OF HALLIBURTON CO.)
To:
Shared Package
ML18052B537 List: ... further results
References
FOIA-85-59 NUDOCS 8607100301
Download: ML20202B437 (4)
v • d • e


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  • g d eQbts bp In Reply Refer To: . -

jff@ h Docket No. 50-445/80-15 g 50-446/80-15 d0 g /(

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. Texas Utilities Generating Company ATIN: Mr. R. J. Gary, Executive Vice President and General Manager l 2001 Bryan Tower Dallas, Texas 75201 Gentlemen:

This refers to the inspection activities performed by our Resident Inspector, Mr. R. C. Taylor, of activities authorised by NRC Construction Permits No.

CPPR-126 and 127 for the Co===neh= Peak Steam Riectric Station, Units No. I sad 2, and to the discussion of the findings by the inspector with members of your staff on June 17, 1980.

During the inspection, it was found that certain activities under your license appear to be in noncompliance with Part 50, Title 10, of the Code of Federal l

Regulations. The item of noncompliance and references to the pertinent requirements are identified in the enclosed Notice of Violation. Details of this item will be included in an inspection report to be issued in the near future and identified as Inspection Report No. 50-445/80-15; 50-446/80-15.

i This notice is sent to you pursuant to the provisions of Section 2.201 of the NRC's " Rules of Practice," Part 2, Title 10 Code of Federal Regulations.

Section 2.201 requires you to submit to this offica, within 30 days of your receipt of this notice, a written statement or explanation in reply includfast (1) corrective steps which have been taken by you, and the results achieved; (2) corrective steps which will be taken to avoid further noncompliance; and (3) the date when fall complianos will be achieved.

F0lA-85-59 oFFIC .. . W . .

daylor/nh WACrossman WC e le WEVege I 6/23/80 6/23/80 6/4$/85 5/z.3/80 oATE .. ..... , , ,. , ,,,,,,, ,, ,,,,, ,, ,, ,, ,,

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Texas Utilities Generating Company June 23, 1980 Should to discuss youthem havewith anyyou.

questions concerning this inspection, we will be pleased Sincerely, Original sieed by W . C. ': Li':.

U..C. Seidle, Chfaf Reactor Construction and Engineering Support Branch

Enclosure:

Appendix A, Notica of Violation ec: v/ enclosure Texas Utilities Generating Company ATTN: Mr. E. C. Schefdt, Projact Manager 2001 Bryan Tower Dallas, Tazas 75201 -

bec to Reproduction Unit bec to DAC:ADM for dist. 6AJYd for dist. /' W#

Ad/RCI IE Files Central Files PDR Standards Develop:nent LPDR ELD TIC NRR NSIC bec dist by RIV [9

Texas Dept. of Health Resources Mrs. Juanita Ellis Mr. Geoffrey M. Gay Richard W. Lowerre, Esq.

Mr. Richard Fouke g

9

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{

50-445/80-15 50-446/80-15 Appeadix A

) NOTICE OF VIOLATION Based on results of the NRC inspection conducted on June 6 and 9, 1980, it appears that certain of your activities were not conducted in full compliance with the conditions of your NRC Construction Permits No. CPPR-126 and 127 as indicated below:

E Failure to Establish Quality Assurance Program for Class 5 Pipe Support Systems i Appendix B, Criterion II states in part, "The applicant shall establish

! at the earliest practicable time, consistent with the schedule for

! accomplishing the activities, a quality assurance program which complies

with the requirements of this appendix. This program shall be documented

! by written policies, procedures, or instructions and shall be carried out l throughout plant life in accordance with those policies, procedures, or i

instructions. The applicant shall identify the structures, systems, and j components to be covered by the quality assurance program . . .."

FSAR, paragraph 3.2.2.3 defines Class 5 piping systems as those in the

'non-nuclear safety category wnose failure in a seismic event could result in a loss of capability of a safety-related function, FSAR, Table 17A-1

, (page 24) identifies the Chilled Water System as having supports in the i Class 5 category and by reference to Note 27, appearing on page 40 of the

, same table, indicates that certain portions of Appendix B apply.

}

) Contrary to the above:

I

! On or about June 9, 1980, the RRI identified several pipe supports for Chilled Water piping in the Auxiliary Building (common to both Units

! 1 and 2) that appeared to be essentially complete. Reference to applicable drawings established that these supports had been classified as Class 5 supports. Various inquiries by the RRI, coupled with a search of site quality assurance procedures and the applicable specification 2323-MS-46B,

) "Non-Nuclear Pipe Hangers and Supports," established that a cuality assurance program has not been established for these hangers as reauired by Appendix B and commitments of the FSAR. The licensee stated to the RRI that approximately 2500 other Class 5 hangers already installed are involved.

This is an infraction.

1 l

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July 31,1980 In Reply Refer To: -

RIV s '),

Docket No. 50-445/Rpt. 80-15 J 50-446/Rpt. 80-15 /)f ,3 /

~

Texas Utilities Generating Company ATTN: Mr. R. J. Gary, Executive Vice President and General Manager 2001 Bryan Tower '

Dallas, Texas 75201 Gentlemen:  %

This is in response to your letter dated July 17, 1980, which requested an extension of tne due date for your response to the Notice of Violation trans-mitted by our letter dated June 23, 1980.

As discussed with Mr. Fikar on July 23, 1980, the due date for your response is extended to August 20, 1980.

Sincerely, 1

Si

~

W. C. Seidle, Chief Reactor Construction and Engineering Support Branch becs w/ltr dtd 7/17/80 bec to Reproduction Unit for dist. bec dist. by RIV bec to DAC:ADM for dist.

AD/RCI Tex. Dept. of H. R. Central Files IE Files PDR ' f' Stancards Development p, 70 N LPDR l' ELD TIC NRR NSIC AE00

/nh dCossman* 'wp I Wy gr . . .. ....

om ).. . 7/31/80 7/31/80 ,

7/31/80 7 4./3 / . . . .

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  • TENAS UTILITIES GENERATING COMPANY 2001 BRYAN TOWER + DALLAS.TEXA8 76201 i .. i f. 7 ^f l ..., Ju1y 17, 1980

- " * - ~ ~ TXX-3165 l ..

f Mr. W. C. Seidle, Chief Reactor Construction and Engineering Support Branch U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement 611 Ryan Plaza Dr., Suite 1000 Docket Nos. 50-445/Rpt. 80-15 Arlington, Texas 76012 50-446/Rpt. 80-15 i

j COMANCHE PEAK STEAM ELECTRIC STATION 1981-83 2300 MW INSTALLATION NOTICE OF VIOLATION

, INSPECTION REPORT 80-15 DOCKET NOS. 50-445 & 50-446 FILE N0: 10130

Dear Mr. Seidle:

Our evaluation of the Notice of Violation identified in Inspection Report 80-15 is not yet complete.

We request an extension to August 20, 1980 to determine the scope of the problem and implement corrective action, as necessary.

Very truly yours, i R. J. Gary RJG:dk l

h 1 l

4 l

K.

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September 12, 1980 In Reply Refer To: . /.17 i RIV Docket No. 50-445/Rpt. 80 50-446/Rpt. 80-15 h- k' / f

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l' Texas Utilities Generating Company .

! ATTN: Mr. R. J. Gary, Executive Vice  ;

President and Geeeral Manager .

! 2001 Bryan Tower l Dallas, Texas 75201 ,

i Gentlemen:  !

Thank you for your letter of August l8,1980, in response to our letter- [

dated July 23, 1980, and the attached Notice of Violation. We have no - '

further questions at this time and we will review your coprective action 1 during a future _ inspection. i l  ;

Sincerely. .

4

] Original signed by W. F.. fefifih Chief '

Reactor Construction and '

Engineering Support Branch l

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1 TEXAS l'TILITIES GENERATING COMPANY +

2001 BRYAN TOWER DA1.LAS. TEXAS 76201 1 ,

i August 18, 1980

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...... TXX-3177 1 .

i t Mr. W. C. Seidle, Chief Reactor Construction and Engineering Support Branch U. S. Nuclear Regulatory Commission

  • Office of Inspection & Enforcement 4

611 Ryan Plaza Dr., Suite 1000 Docket Nos. 50-445/80-15 ~

Arlington, Texas 76012 50-446/80-15 -

COMANCHE PEAK STEAf1 ELECTRIC STATION 4

1981-83 2300 MW INSTALLATION

, RESPONSE TO NRC NOTICE OF VIOLATION '

I INSPECTION REPORT NO. 80-15 ..

DOCKET NOS. 50-445 & 50-446 j FILE NO
10130

Dear Mr. Seidle:

We have reviewed the reports dated June 23, and July 23, 1980 on the inspection conducted by Mr. R. G. Taylor, of activities authorized by NRC Construction Permits No. CPPR-126 and 127 for the Comanche Peak

facili ty. We have responded to the findings listed in Appendix A of

! those reports.

4 To aid in the understanding of our response, we have repeated the re-quirement and your findings followed by our corrective action.

We believe the attached information to be responsive to the Inspector's findings. If you have any questions, please advise. '

l Very truly yours, i

f R. J. Gary -

l Attachment

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Inspection Report No. 80-15 TXX-3177 h/

i Page 2 j Appendix A NOTICE OF VIOLATION (Dated June 23,1980)

Based on results of the NRC inspection conducted on June 6 and 9,1980, it appears that certain of your activities were not conducted in full compliance with the conditions of your NRC Construction Permits No. CPPR-126 and 127 as indicated below:

Failure to Establish Quality Assurance Program for Class 5 Pipe Support Systems Appendix B, Criterion II states in part, "The applicant shall establish at the ~ earliest practicable time, consistent with the schedule for accomplishing the activities, a quality assurance program which complies with the requirements of this appendix. This program shall be documented I

by written policies, procedures, or instructions and shall be carried out throughout plant life in accordance with those policies, procedures, or instructions. The applicant shall identify the structures, systems, and components to be covered by the quality assurance program . . . ."

FSAR, paragraph 3.2.2.3 defines Class 5 piping systems as those in the non-nuclear safety category whose failure in t seismic event could result in a loss of capability of a safety-related function. FSAR, Table 17A-1 4

(page 24) identifies the_ Chilled Water System as havina supports in the Class 5 catecory and by reference to Note 2_7 app a _ ear _irLg_on page_.40_ otthe

,same table, indicates _ that certain_ porti.ons of Appendix B apply.

Contrary to the above:

On or about June 9,1980, the RRI identified several pipe supports for

Chilled Water piping in the Auxiliary Building (comon to both Units 1 and 2) that appeared to be essentially complete. Reference to applicable drawings established that these supports had been classified as Class 5 supports. Various inquiries by the RRI, coupled with a search of site quality assurance procedures and the applicable specification 2323-MS-46B, "Non-Nuclear Pipe Hangers and Supports," established that a quality assurance program has not been established for these hangers as required by Appendix B and comitments of the FSAR. The licensee stated to the RRI that approximately 2500 other Class 5 hangers already installed are involved.

This is an infraction.

~

O Inspection Report !!o. 80-15 TXX-3177 Page 3 Corrective Step- Which Have Been Taken and Results Achieved The applicable fabrication and installation specifications have been re-viewed and now include specific provisions for Quality Assurance criteria

, to be applied to the design, fabrication and installation of Class 5 Hangers. Construction and Quality Control procedures to incorporate these provisions have been prepared and are' currently being implemented.

Corrective Steps Which Will Be Taken to Avoid Further Noncompliance The stated corrective action will preclude recurrence of the noncompliance.

Date of Full Comoliance Implementing procedures were established by July 25, 1980 and are currently being applied to ongoing fabrication and installation activities. Inspection of hangers previously installed will be accomplished as soon as practical, consistent with the project schedule for turnover to startup personnel.

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Inspection Report No. 80-15 ,

TXX-3177 l Page 4 i Appendix A NOTICE OF VIOLATION (DatedJuly 23,1980)

I Based on the results of an NRC inspection conducted during June 1980, it '

appears that certain of your activities were not conducted in full compliance '.

with conditions of your NRC Construction Permits No. CPPR-126 and 127 as indicated below:

Failure to Follow Construction Procedures Required by Drawings Appendix B, Criterion V states in part, " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings. The Comanche Peak Steam Electric Station Quality Assurance Plan implements this requirement by Section 5.0 which states in part, "The quality assurance actions described throughout this manual shall be delineated in documented instructions, procedures, drawings, specifications, check-lists or manuals, as appropriate."

Contrary to the above:

The NRC Resident Reactor Inspector identified several drawings during his inspection that state:

(1) "All tolerances in accordance with QCP #2A001 U.N.0."

(2) " Fab. Procedure is GH-101."

The P5.1 established that the above referenced documents were not available on the Comanche Peak site at the time of the fabrication of the components and, therefore, could not have been followed. One such drawing described an installed component support identified as SI-1-031-007-A42R and modified by Component Modification Card 12042R3.

This is a deficiency.

Inspection Report No. 80-15 TXX-3177 Page 5 Corrective Steps Which Have Been Taken and Results Achieved CPSES Engineering has determined that the notes referenced on the drawings apply only to shop fabrication by ITT Grinnell at their Warren, Ohio facility and are not applicable to fabrication at other facilities or at the CPSES Site. Fabrication or installation activities other than at Warren are controlled in accordance with approved fabrication or installa-tion procedures and to the dimensional data of the drawings and accept /

l re. ject criteria established by the fabrication and installation specifica-l tions.

To provide positive record of this situation, a change to the sit'e drawings is being prepared which will then be submitted to document holders of record per established CPSES procedures for Document Control.

Corrective Steps Uhich Will Be Taken to Avoid Further Noncompliance The stated corrective action will preclude further noncompliance.

Date of Full Comoliance The clarifying change to the component support drawings is scheduled for implementation by September 1, 1980.

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In Rsply Refer To M ' /' h Dockat No. 50-445/Rpt. 80-15 50-446/Rpt. 80 15 g0 g **f LO gfh W -

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) Texas Utilities Generating Cowany i

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ATTN: Mr. R. J. Gary, Executive Vice {

President and General Manager - l 2001 Bryan Tower n=11 == , Texas 75201 Gentlemen This refers to the inspection conducted by our Residsat Reactor Inspector, i Mr. R. G. Taylor, during June 1980, of activities authorised by hltC Construction Permits No. CPPR-126 and 127 for the Comanche Peak faci H ty, Units No. I and 2, and to the discussion of our findings with Mr. R. G. Tolson and other members of your staff at the conclusion of the inspection. 1 Areas ar== bad during the inspection and our findings are discussed in the  !

enclosed inspection report. Within these areas, the inspection consisted of selective awa=4== tion of procedures and representative records, interviews with personnel, and observations by the inspector. l During the inspection, it was found that cartain activities under your license appear to be in noncompliance with Part 50, Title 10, of the Code of Federal Ragulations. One apparent item of noncompliance, which is discussed in para-l graph 6 of the enclosed inspection report, was forwarded to you by our letter dated June 23, 1980. A second apparent item of noncogliance and references to the pertinent requirements are identified in the enclosed Notice of Violation and in paragraph 6 of the enclosed inspection report.

This notice is sent to you pursuant to the provisions of Section 2.201 of the NBC's '%1mm of Practice," Part 2, Title 10 Code of Federal Regulations.

Section 2.201 requires you to submit to.this office, within 30 days of your receipt of this notice, a written statement or esplanation in reply including:

(1) corrective steps which have been taken by you, and the results achieved; (2) corrective steps which will be takaa to avoid further noncompliance; and (3) the date when full compliance will be achieved.

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m 4f1 Texas Utilities Generating Company 2 One new unresolved item is identified in paragraph 6 of the anelased report.

In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2 Title 10, Code of Pederal Regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. If the report contains any information that you believe to be proprietary, it is .

necessary that you submit a written application to this office, within 20 daye l of the date of this letter, requesting that sech inforention be withheld from j public disclosure. The application asst include a full statement of the reasons '

why it is claimed that the inforestion is propriatary. The application should i be prepared so that any proprietary infbruntion identified is contained in an enclosure to the application, since the application without the enclosure will also be placed in the Public Document Room. If we do not hear from you in this regard within the specified period, the report will be placed in the Public Document Room.

Should you have any questions concerning this inspection, we will be pleased to discuss them with you.

Sincerely, Original sig.P by W. C. Seidle E C. saidle,rM af Reactor Construction and i Engineering Support Branch

Enclosures:

1. Appendix A, Notice of Violatten
2. IE Inspection Report No. 50-445/80-15 50-446/80-15 cci w/enet w ees Texas Utilities Generating Company ATIN: Mr. E C. Schmidt, Project Manager 2001 Bryan Tower Dallas, Texas 75201 bec to Reproduction /ML i t- g bec to DAC:ADM y for distribution F# '/ for distribution U 9 /41/

AD/RCI (Reinmuth)

'}&h Central Files IE Files PDR Standards Development LPDR ELD TIC NRR (9 Cys) 2_/ NSIC AEOD bcu dhu.ibuted by G e dN

,, Texas,Departmen,t,,of Health Resources ,

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50-445/80-15 50-446/80-15 APPENDIX A Notice of Violation Based on the results of an NRC inspection conducted during June 1980, it appears that certain of your activities were not conducted in full compliance with conditions of your NRC Construction Permits No. CPPR-126 and 127 as indicated below:

Failure to Follow Construction Procedures Required by Drawings Appendix B, Criterion V states in part, " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings. The Comanche Peak Steam Electric Station Quality Assurance Plan implements this requirement by Section 5.0 which states in part, "The quality assurance actions described throughout this manual shall be delineated in documented instructions, procedures', drawings, specifications, checklists or manuals, as appropriate."

Contrary to the above:

The NRC Resident Reactor Inspector identified several drawings during his inspection that state:

(1) "All tolerances in accordance with QCP #2A001 U.N.O."

(2) " Fab. Procedure is GH-101."

The RRI established that the above referenced documents were not available on the Comanche Peak site at the time of the fabrication of the components and, therefore, could not have been followed. One such drawing described an installed component support identified as SI-1-031-007-A42R and modified by Component Modification Card 12042R3. . obb ggt g 0g i

This is a deficiency. p/ gd :. N h 70 y%f pp yu s

?OO 9ts' . .

O U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION IV Report No. 50-445/80-15; 50-446/80-15 Docket No. 50-445; 50-446 Category A2 i

Licensee: Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Facility Name: Comanche Peak, Units 1 and 2 Inspection at: Comanche Peak Steam Electric Station, Glen Rose, Texas Inspection Conducted: June 1980 Inspector: . _ 7/24/[8 M . G. Taylor, Reside Reactor Inspector 'Dats v Projects Section Approved: . d

. A. Crossman, ChieQC/ Projects Section 'Date Inspection Summary:

Inspection During June 1980 (Report 50-445/80-15; 50-446/80-15)

Areas Inspected: Routine, announced inspection by the Resident Reactor Inspector (RRI) including general site tours; safety-related piping installation and welding; electrical cable installation; protection of major components; and safety-related pipe supports. The inspection involved ninety-nine inspector-hours by one NRC inspector.

Results: Of the five areas inspected, no items of noncompliance were identified in four areas. Two items of noncompliance (infraction - failure to establish quality assurance program for Class 5 pipe support systems - paragraph 6; and deficiency - failure to follow construction procedures required by drawings -

paragraph 6) were identified in one area.

Obh

DETAILS

1. Persons Contacted Principal Licensee Employees
  • J. T. Merritt, TUSI, Construction and Engineering Manager
  • D. N. Chapman, TUGCO, Quality Assurance Manager
  • R. G. Tolson, TUGCO, Site Quality Assurance Supervisor Othei Persons
  • D. C. Frankum, Brown & Root, Project Manager
  • W. E. Baker, Brown & Root, Project Welding Engineer The RRI also interviewed other licensee and Brown & Root employees during the inspection period including both craft labor and QA/QC personnel.
  • Denotes those persons with whom the RRI held on-site management meetings during the inspection period.
2. Site Tours The RRI toured the safety-related plant areas several times weekly during the inspection period to observe the general progress of construction and the practices involved. Four of the tours were accomplished during portions of the second shift with primary emphasis on electrical cable installation efforts.

No items of noncompliance or deviations were identified.

3. Electrical Installation Activities The RRI made a number of observations of electrical cable installations during the inspection period. The primary inspection effort was directed toward verification that the cable installation crews are knowledgeable of the site procedures for such work and are following them. The RRI also observed the activities of the QA/QC personnel assigned to monitor the cable installation in order to ascertain their apparent level of capability and their diligence in monitoring the craft labor activities. The RRI noted, during observations of three different labor crews and four different QA/QC inspectors, that each crew and each inspector was following the respec-tive procedures. The RRI inspected a random selection of cable trays for proper installation and for freedom from burrs and other sharp edges. The inspector also initiated an inspection of the structural steel support system for the cable trays in the Unit No. 2 spread room. This latter effort is not complete due to the size and complexity of the installation.

The RRI observed, on two different occasions, the activities of electrical cable terminators working in the Unit No. I cable spread room termination cabinets. The RRI observed that the stripped ends of the individual wires were free of nicked strands and subsequently observed that each wire was 2

i l

terminated with the correct size lug and connected to the terminal desig-nated on the engineer's termination schedule. The lug compression tools in use by the terminators were noted to be within their calibration period and were in good mechanical condition and correctly used during the observa-tion time.

No itemsiof noncompliance or deviations were identified.

4. Safety-Related Piping System Installation The RRI made limited observations of piping component handling practices during the inrpection period and determined such activities to be consistent with project procedures and good practice. During the period, the RRI observed welder APL working on pass number six of weld FW-6 as identified on Isometric SI-1-090 for line number 10-SI-1-105-2501R2. The welder was observed to be following Welding Procedure No. 88025 on this pass and using weld rod identified by Heat No. 762550. The RRI has verified, during several previous inspection periods, that the weld procedure and the welder have been certified in accordance with ASME Section IX. The RRI obtained and reviewed the Certified Material Test Report for Heat No. 762550 and verified that the material met the requirements of ASME Section II and that the weld material was appropriate for the base metal involved.

The RRI also examined the following radiographs for completed safety Class I and 2 welds as denoted by the last number in the line designation. The radiographs indicated that the welds conformed to the requirements of ASME Section III for the applicable class. The radiographs themselves met the quality requirements of ASME Section V.

Weld Isometric Line W-11, 12 & 13 CS-1-RB-031B 1.5-CS-1-249-2501R1 W-36, 43 & 45 SI-1-RB-015 2-SI-1-086-2501R1 W-42 SI-1-RB-015 2-SI-1-086-2501R1 W-14, 20 & 21 SI-1-RB-015 2-SI-1-059-2501R1 W-13 & 22 SI-1-RB-015 2-SI-1-059-2501R1 FW-2 & FW-3 RC-1-RB-018 4-RC-1-087-2501R1 FW-1 & FW-21 RC-1-RB-08 3-RC-1-052-2501R1 W-27 CS-1-RB-027 2-CS-1-112-2501R1 FW-2 RC-1-RB-020 4-RC-1-075-2501R1 W-4 CS-1-SB-050 1-CS-1-667-2501R1 3

Weld Isometric Line W-13 CS-1-RB-29 2-CS-1-112-2501R1 FW-19 SI-1-RB-016 6-SI-1-029-2501R1 FW SI-1-RB-059 10-SI-1-037-2501R1 W-8 CS-2-RB-042 3-CS-2-235-2501R1 W-6 CS-2-RB-013 2-CS-2-107-2501R1 FW-2 SI-1-RB-054 6-SI-1-327-2501R1 FW-6 CS-2-SB-02 8-CS-2-063-151R2 FW-10 FW-1-SB-20 18-FW-1-37-2003-2 No items of noncompliance or deviations were identified.

5. Protection of Major Installed Equipment The RRI observed, during the general plant tours, that the Reactor Pressure Vessels in both Units No. I and 2 are covered and protected as provided for by the supplier or as recommended by him. The Unit No. 1 Reactor Pressure Vessel internals remain in their enclosures within the Reactor Containment Building while the Unit No. 2 internals are provided with outdoor pro-tection from the atmosphere. The RRI observed that pump motors and valve motors were connected to power for space heating purposes while the various switchgear, motor control centers and control panels were space heated by light bulbs in accordance with standard. industry practices.

No items of noncompliance or deviations were identified.

6. Pipe Hangers and Supports The RRI inspected the licensee's program for design, fabrication, installa-tion and quality control of pipe hangers, supports and restraints (component supports) of safety-related piping systems and for nonsafety systems which have been classified as requiring seismically capable supports due to the secondary consequences of pipe failure in a seismic event.

The RRI randomly selected a total of seventeen installed devices represent-ing a cross section of hangers, supports and movement restraints with five being in Class 2 piping systems, six in Class 3 and six in the Class 5 area (the site designation for nonsafety piping subject to seismic support as -

required by NRC Regulatory Guide 1.20 and the FSAR). The RRI determined' /^ 2 that there was no quality assurance effort being made by the licensee in A regard to the Class 5 hangers / supports except that an on going surveillance pp-7#

f of concrete insert bolts (Hilti) was as applicable to the Class 5 hangers as to any other application of such bolts. Research of the FSAR indicated /

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that many of the plant piping systems had been categorized as Class 5 and that the licensee had commited to applicable portions of Appendix B as required by RG 1.29 and the FSAR. Additional research, particularily of P yro*e t Raari fication MS-46A for saf,ety-re. lated . hanger /s'upports and MS-46B for nonsafety han~ers/ g supports, indicated that the Class 5 devices hii W en olaced into the nonsafety_ specification aid W at no quaIIt'y ^

~

assuranco requirements had been imposed on either the vendors or the field ypIk. The RRI's research indicated that a substantially complete progism 3 for design, material selection, fabrication and installation is_ require _d g '

through the governing code, B31.1_ Power Piping Qode, and the various , fl i

references including the specifications of the American Institute For l Steel Construction (AISC).

The RRI considered this to be an item of noncompliance which was provided h to the licensee by a Region IV letter dated June 23, 1980. I The RRI also inspected the Class 2 and 3 hangers / supports for conformance to the design drawings, reviewed available documentation, and further evaluated the designs versus the governing ASME Code requirement, Section 1 III, Subsection NF. Seven of eleven drawings contained the following notes:

(1) All tolerances in accordance with QCP #2A001 U.N.O.

(2) Fab. Procedure is FH-101 (3) All products designed in N-4 accordance with EPL File No. 1, Rev. 12.

Since all of drawings carry the Brown & Root log and were issued "for construction," it appeared that the above notes were applicable to the field fabrication and installation efforts. The RRI was unaware of these procedures and attempted to obtain them from the site document control center and the QA library of site procedures only to find that such pro-cedures were apparently not on site. Discussions with cognizant licensee personnel indicated that the drawings involved were actually ITT-Grinnell drawings converted to Brown & Root procedures. The licensee stated that the Brown & Root General Piping Procedure CPM 6.9 contained both tolerance and fabrication information that was applicable to the Brown & Root work effort.

The RRI indicated that an apparent item of noncompliance with Criterion V of Appendix B had occurred since it was evident that the field work had not been accomplished in accordance with procedures referenced in applicable -

drawings. The procedures could not have been followed since they were not on site. For the record, the RRI would note that his inspections of hangers.

and supports have not shown any apparent technical problem with the hangers on supports as a result of this noncompliance. sf 3r1 The RRI noted, during the inspection of installed components and the subse-quent drawing review, that a few of the observed attachment welds of various members to their base plates did not appear to conform to the 5

i.

__ . _ _ .-___ _ _ -_ _ . _ _ - - _ . _. - - .~ .

detail requirements of Subsection NF of ASME Section III. The most notable situation was where "I" beams had been tee welded to the base plate and there was generally no weld on the inside edge of the flange. The Code has one of two applicable requirements, depending on whether the joint is considered by the designer as a " plate and shell" or as a " linear type" joint.

In the case of the plate and shell type, the Code requires a full fillet joint. As observed, the flange faces were welded to the base plate and in order to have a full fillet configuration, the inside of the flange as well must also be welded to the plate.

In the case of the linear type support, the NF referenced paragraph XVII-2452.1 requires that side and end welds be returned around the corner at the end or side. In the case of the "I" beam design, the weld on the flange faces would have to turn the end of the flange and go down the inside of the flange two times the specified weld size, or typically about one-half inch.

The RRI also noted other installations and drawings utilizing square structural tubing wherein the weld in several instances was only along two sides,of the tube. The Code appears to require an all around weld if the support is in the plate and shell category and the weld go around the corner of the box on to the currently unwelded faces at least twice in length of the specified weld size, again typically a half-inch.

The RRI noted during a records review of several of the component supports, that while in some instances the QA/QC inspection of the welds had been documented, none of the supports involved in the inspection were finally inspected. Most of the items selected did not indicate that any weld inspection had yet taken place. Since the QA/QC status of the selected supports was relatively incomplete, the RRI does not know what the final acceptance decision by QA/QC is and therefore this will be considered to be an unresolved item.

7. Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of non-compliance, or deviations. One such item disclosed during the inspection is discussed in paragraph 6 and will hereafter be refered to as " Weld Configuration of Component Supports."
8. Management Interviews The RRI met with one or more of the persons identified in paragraph I on June 4, 10, 17, 18 and 25, 1980, to discuss inspection findings and the licensee actions and positions.

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[g a 70 75

  • U QATE HCS ENFCRCEMENT LET*ER. NOTICE. CROER ISSUED: NCTE: SLOCKS K TO N MUST SE l { l l l l l VERIFIED SY 16: MCS

- MM 0 Y Y WHENEVER ENTRIES ARE 76 9 UAGE IN 8 LOCKS T. U V CIVIL PENALTY ISSUED: 1 AND v 77 to w

l l ! l l eATE ree ENTEato NTo C:MPUTER ritt <MonRi. u u y y l 743,,gc,

. _ , . n . - . . _ - _ ---

l l

, , uneTez statss =uctsAz asaubarcev eomanssion l Soms NIC 7se INSPECTION Si ENPORCEMENT - STATISTICAL DATA l

, FESRUARY 1978 iMC 05356 s&C!LITY NAME LGQdDCDC FedK. VDiE 4 1NSPECTOR(51 nuaavi0r PRiNCiP AL INSPEC*CNO I d Y 8 h ttCENSEENENDom Iexas Utilities Generatina C; ;,arv REviEwE, WACrossman x TRANS. OCCKET NuMSER (As AEPORT NC. QATES 4NCaNv ESTONSP AEGION l ACrion I 8 84CM CONQUCTING Typg 'O '

ACTIVITY i l01510 0 0 64 i 416l icil 0 6l Ol 218101 ,E, AE 18 18 M W G 3 y V

  1. "c'=#*

e 31 Co OR LICENSE NO. ($Y DRCDU@

2 14 lo I Is bl 25 TO 30 N

I. ."~' I i i i l I i l I Iiit ! < oil 0 61310l810 l M M O O V V isspfCT:0N agascavg; qv,

1 O REGIONAL OFFICE STAFF 2 R ESIDENT INSPEC*CR e

3 "l PERFORMANCE APPRAISAL TEAM l**** C8 ACmvi*v CONCUC*ES sCwfM CNE BCX CNLv1 1 R34 INSPECTION OTHER G s/ 05 C MANAGEMENT AUOtt 00 C MATL ACCT. 13 C IMPORT 14 C INCulRY CLC SAFE *v 06 C MANAGEMENT VI51T 10 C PLANT SEC. I 15 C INVESTIGATICN 03 CINC:OENT C7 C SPECI AL 11 C INV ENT. VE Rif. l n e invest. aLso cwecx 04 ENFCRCEMENT 08 C VENOCR ,

12 C SHIPMENT / EXPORT l aLocE 33

, 'NSPE 90% on 'NvfS'ic ATiCN waam No 17ANNCUNCEO 20 UNANNOUNCED 25 i ED 5'# 2 O CFF. SHIFT 3 0 WEEKENQtMO LIDAY

,  % QAY SHIFT iNSsE0?iCN iNv E57:GaiiCN NC?iseCA* ION <CwEC< GNE 80x ONL'i 2 Ji

' C 59' 7 *ECICN AL 088'et L E-E n 7C mEFEmmED TO wCS FCs AC9CN A C mECION LET*ER & MCS FOR ACTION l

  • NSP E OT:CN"NVeS'G ATION 8tNC'NGS <CMECE CNE 50x CNLYi K 2 1 C CLEAR 2 CNCOM81.tANCE 3 O CEVIATION 4 C NCNCOMPLl ANCE & CEVIATION L IENFCRCEMENT CONFERENCE MELO: 1039 4 'O

NUMSER CF NCNCOMPLIANCE ITEMS IN LEnER To LICENSEE:

l02 =cTt: cwa,n.c.a.uu.sT

a. .. .v e.a s on c:TED ITEM of NonconspLiasect svo.ns:Tviou s.o Lv 4

N NUMSER C8 CEviATICN ITEMS IN LET*ER 'O LICENSEE: 's casociaLLY oats to anons two recomo.

4A 45 0lI NUM8ER OF LICENSEE EVENTS g g )

, [46 INSPE TION FEE I 1 O NON. ROUTINE /VENCOR fNo Fece 2 C ROUTINE INe Feet 3 C ROUTINE (Fees &C ROUTINE (Fee Resuceal C l47 CONTENTS 2.7900 INFCRMATION C 7 YES I

afgioNAL casiCE LE"ER CR REPORTTR ANSMr*?AL DATE FOR INSPECTION CR INVESTIGATICN

, 591 CR LETTER ISSUED TO LICENSEE REPCRT SENT TO HCS FOR ACTION iMMEDIATE ACTICN LETTER as 13 54 sg =0 SATE E5 l )l#/ l /.,l .* l,d d l l l I I l l l l l l l l l l w M 3 0 v v M M 3 0 y y uu O O y v SUSJE 7 0F tNvESTIGATiON (CNECK ONE SOX QNLy) 6667

  • Y'E A to CFR 20.403 *vpf B 10 C74 20.405 MISC.

I

' C1 C INTERNAL CV EREXPOSURE 06 C I1 C INT. 0VEREXPOSURE 15 C CRITICAL 4Tv 21C ECUIP 8AILURE

, 02 C EXTERNAL OVEREXPCSURE 07 C 12 C EXT. OVEREXPOSURE 16 C LOSS / THEFT 220 ALLEGATION /

S 03C RELEASE TO UNREST. AREA OS C 13 C EXCESS R AO. LEVELS 17 C MUF COMPLAINT 04 O LOSS OF 8 ACILITY 09 C 14 C EXCESS CONC. LEVELS 18 C TRANSPORTAT1CN 23C PVsLIC INTEREST 05 C PRCPERTY OAMAGE 10 C 13 C CONTAM/ LEAKING 24C SAOCTAGE SOURCE 25C ASNORMAL OCCUR, 20 C ENV1RCNMENTAL EVENT 26C CTHER MEAQQUARTERS ENTRIES T HCS ACTION ON INSPnNVEST REFERRED SY REGICN:

s meNeese La w comm l l l f fp

~ 70 75 V DATE HQS ENPQRCEMENT LETTER. NOTICE. CRCER ISSUED: NOTE: 8 LOCKS K TO N MUST SE l l l l l l l VERf FIED SY IE: MQS

- "M 0 0 Y Y WHENEVER ENTRIES ARE 76 l  :

MADE IN SLQCKS T, U j V CIVIL PENALTY ISSUED: ANO V n so l 1 i i i ~

A8TS

  1. CATE 764 ENTEREO INTO COMPUTER PsLE tMC/YR1: y y y y aErgmENCE i

. FORM N*.C 764-3 OCTOBER 1977 (MC 05351 unite s states NucLt:a to:utarony --

. INSPECTION 8: ENFORCEMENT-STATISTICAL DATA SUPPLEMENT GENER AL INSTRUCrlONS: stock A Must et CHECKED TO SHOW TYPE OF INFORMATION CONTAINED oN THE FORM. ONE FORM 15 To BE COMPLETED FOR EACH.

(Al ITEM OF NONCOMPLIANCE CITED.

(5) ITEM OF NONCOMPLIANCE NOT CITED. ANO.

(C) DEVIATION CITED IN ENFORCEMENT CORRESPONDENCE coCKETNuMesR 50-445 oR uCENsf NuMeER REPORT suMeER 80-15 A *YPE OF 81NotNGS 8-SPECIFIC N/C CODE puNcTiomAL (CMECK oNE SOX ONLY) On DEVIATION Caust Paoctount savam Tv antA 11 12 hG 3 7 g 10 A NONCOMPLIANCE lE IB IA l l l l2 l l l l I 1 2 8 LICENSEE 10ENTIFIED ITEMS C-MODULE NUMBER 13 ig C D EVI ATION l2i51010l910 C D -HOW ITEM IDENTIFIED E-CONSEQUE NCES JCHECK ONE Sox CNLYi ICHECK ONE 80X ONLY)

L LICENSEE A CAUSE OR CONSTITUTED ACTUAL OCCURRENCE 20 I h INSPECTOR 21 P H AD POTENTIAL TO WESULT IN ACTUAL OCCURRENCE

  • J .i o GTHER N DIO NOT HAVE POTENTIAL TO RESULT IN ACTUAL OCCURRENCE F -EXEM87 INFORMATION G-AODITIONAL UNITS (ENTER "M'*

IN FIRST Box FCLLOWED 8Y OTHER 23 26 UNIT NUMBERS) lq g l l l 22 S -C CHECK BOX IF EXEMPTINFORMATION tS IPCLUDED IN TEXT SELow. PER 10 CFR 2.790 H-NONCoMPLI ANCE RE*ETITivE OCCURRENCE 7 IlF FIRST OCCURRENCE ENTER ~1"I q Failure to Establish Ouality Assurance program for Class 3 Pioe Suceor:

Svstems Appendix 3, Criterion II states in part, "The applican; shall establish at the earliest practicable time, consistent with the schedule for accomplishing the ac:ivi:1es, a quality assurance program which complies vi:h the requirements of this appendix. This program shall be documented 4

by wri::en policies, procedures, or instrue:1ons and shall be carried out l throughout plant life in accordance with those policies, procedures, or I

instrue: ions. Ihe applicant shall identify the strue:ures, systems, and components to be covered by the quality assurance program . . . ."

FSAR, paragraph 3.2.2.3 defines Class 5 piping systems as those in the 2

non-nuclear saf ety category whose failure in a seismic event could result i

in a loss of capability of a safety-related function. FSAR, Table 17A-1 (page 24) identifies the Chilled Water System as having supports in the Class 5 category and by reference :o Note 27, appearing on page 40 of the same table, indicates that certain portions of Appendix 3 apply.

Contrary to the above:

On or about June 9, 1980, the RRI identified several pipe supports for

Chilled Water piping in the Auxiliary Building (c0= mon to both Uni
s 1 and 2) that appeared to be essentially complete. Reference :o applicable drawings established that these supports had been classified as Class 5 suppor:s. Various inquiries by the RRI, coupled with a search of site i quali:y assurance procedures and the applicable specification 2323-MS-403, l "Non-Nuclear Pipe Hangers and Supports," es:ablished : hat a quality

{ assurance program has noc been established for these hangers as required j by Appendix 3 and commitments of the FSAR. The licenses stated to che RRI that approximately 2500 other Class 3 hangers already installed are involved.

s l

. INSPECTION PLAN I l

IE Inspection Report No. 50-445/80-15; 50-446/80-15 Licensee: Texas Utilities Generating Company Location: Glen Rose, Texas Facility: Comanche Peak, Units 1 & 2 i Type of Licensee: W, PWR, 1150 MWe Type of Inspection: Resident, routine,. announced Dates of Inspection: June 1980 Dates of Previous Inspection: April & May 1980 Inspectors: RGTaylor SCOPE OF INSPECTION Resident Inspection Program for Construction 4

- _ - -_ - 0!17 80 Reactor Inspector Date Approved Date

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

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