ML20136A533
| ML20136A533 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/28/1983 |
| From: | BROWN & ROOT, INC. (SUBS. OF HALLIBURTON CO.) |
| To: | |
| Shared Package | |
| ML20136A539 | List:
|
| References | |
| FOIA-85-59 35-1195, 35-1195-EEI-13, NUDOCS 8601020052 | |
| Download: ML20136A533 (45) | |
Text
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Il vts BROWN & ROOT, INC.
INSTRUCTION EFFECTIVE CPSES NUMBER REVISION DATE PAGE JOB 35-1195 EEI-13 4
3/28/83 1 of 3 TITLE:
ORIGINATOR:
/; s d 3-24-83 REVIEWED BY:
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DATE APPROVED BY:
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<4m CONSTRUCTfDN PROJECT MANAGER
~'OATE 1.0 PURPOSE & SCOPE J
ENSINEERIN3 USE ON.Y 1.1.1 The purpose of this instruction is to establish a process that can be utilized to repair cable, both Class 1E and Non-class 1E, that has either manufacturing defects or physical damage to the jacket and to repair an individual conductor's insulating jacket; and, the cleaning of cable jackets.
1.2.1 This instruction applies to cable jackets on all cables where the damage is limited to the jacket only.
2.0 RESPONSIBILITIES 2.1 The Electrical Superintendent shall be responsible for:
a.
Visually inspecting cables for damage, b.
Reporting damaged cables to the Project' Electrical Engineer.
c.
Effecting repairs in accordance with the requirements of this instruction.
2.2 The Project Electrical Engineer shall b esponsible for:
a.
Evaluating the extent of damage to ubles reported by the Electrical Superintendent.
b.
Providing technical assistance.'a *ha electrical craft to effect repairs.
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8601020052 851113 PDR FOIA PDR GARDE 8 5-59
PROCEDURE EFFECTIVE BR9WN & ROOT, INC.
NUMBER REVISION DATE PAGE CPSES JOB 35-1195 EEI-13 4
3/28/83 2 of 3 3.0 PROCEDURE 3.1 Determination of Extent of Damage When.a cable is found that has either a manufacturing defect or has been damaged, the section in question should be flagged in order for engineering to be able to locate cable in question.
The cable shall-then be reported to Electrical Engineering (for Class IE and a'ssociated cables via NCR, for Non-Class 1E cables, via RFIC). Verbage for reporting of such cables shall be com-plete enough so that the cable can be readily located. Construction will notify DC prior to commencing repairs on Class 1E and associated cabl es.
3.2 Repair Process NOTE: Okonite 35 Jacketing Tape and Raychem WCSF-N Heat Shrink are the only materials authorized for jacket repair.
3.2.1 Damage deemed reparable for cable that will be installed in exposed raceway.
NOTE: Exposed raceway is defined as all cable tray and all conduits that are above grade and not embedded in slabs.
Conduit sleeves less than five feet long shall be treated as exposed raceway. Air drops or cable run inside equip-ment shall be considered exposed raceway.
a.
Mark cable three inches on each side of the dar6 aged area.
NOTE: In some cases for multi-conductor cables it will have been necessary to remove a section of cable jacket ta determine if the inner conductors have been damaged, in this case the mark will be located so that three inches of the original jacket (on each end) will be in the area to be taped.
b.
Clean the section of cable jacket between the marks in (a) above with trichloroethane or an engineer approved solvent.
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PROCEDURE EFFECTIVE BROWN & ROOT, INC.
NUMBER REVISION DATE PAGE CPSES l
J08 35-1195 EEI-13 4
3/28/83 3 of 3 c.
Apply a thin film of Okonite Nuclear Cement to the cleaned section of cable. Allow to dry.
d.
As soon as the cement is no longer tacky, apply three half-lapped layers of Okonite No. 35 jacketing tape over the complete area.
3.2.2 Damage deemed reparable for cable that cdn be installed in any raceway.
NOTE: This is an alternate repair process for 3.2.1.
It is acceptable to use Raychem WCSF-N Heat Shrink in repairing damage. Installation of heat shrink shall be as described in EEI-8, Appendix A.
4.0 Cleaning of Cable Jackets 4.1 Cable jackets can be cleaned with trichloroethane, CRC cable cleaner, or Engineering approved solvents.
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IC3 MAR 2 81983 In Reply Refer To:
f Ocekets: 50-445/83-03
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Texas Utilities Generating Company ATTN:
R. J. Gary, Executive Vice President & General Manager 2001 Bryan Tower Dallas, Texas 75201 Gentlemen:
This refers to the inspection conducted under the Resident Inspection program by our Senior Resident Reactor Inspector, Mr. R. G. Taylor, during the period of October 1982 through February 1983 of activities authorized by NRC Construction Permits CPPR-126 and CPPR-127 for the Comanche Peak facility, Units 1 and 2, and to the discussion of our findings with you and other members of your staff at tne conclusion of,the inspection.
Areas examined during the inspection and our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of selective examination of procedures and representative records, interviews with personnel, and observations by the inspector.
During this inspection, it was found that certain of your activities were in violation of NRC requirements. Consequently, you are required to respond to this violation, in writing, in accordance with the provisions of Section 2.201 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations.
Your response snould be based on the specifics contained in the Notice of Violation enclosed with this letter.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures will be placed in the NRC Public Document Room unless you notify this office, by telephone, within -10 days of the date of this letter, and submit written application to withhold information contained therein within 30 days of the date of thf s letter. Such application must be consistent with tne requirements of 2.790(b)(1).
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RPS1 0/ES 'e M DRRP&ER/RIV TWesterman GMads'en EJohnson JGagl%rdo 3/ /83 3/ /83 3/p/83 3/.'/83 3/.../831
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Texas utilities Generating 2
Company MAR 2 81983 Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely, or:ensi sisned im G. i MADSEN" G. L. Madsen, Chief Reactor Project Branch 1
Enclosures:
1.
Appendix A - Notice of Violation 2.
Appendix B - NRC Inspection Report 50-445/83-03 50-446/83-01 cc w/encis:
Texas Utilities Generating Company ATTN:
H. C. Schmidt, Project Manager 2001 Bryan Tower Dallas, Texas 75201 bec to CMB (IE01) bec distrib. by RIV:
RPB2 Resident Inspector TPB Section Chief MIS SYSTEM E. Johns'en RIV File RIV Reading File Br.. Reading File RA C. Wisner M. Rothschild, ELD TEXAS STATE DEPT. OF HEALTH Juanita Ellis David Preister l
APPENDIX A NOTICE OF VIOLATION Texas Utilities Generating Company Docket:
50-445/83-03 Comanche Peak Steam Electric Station 50-446/83-01 Permits: CPPR-126 CPPR-127 Based on the results of an NRC inspection conducted during the period of October 1982 through February 1983, and.in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C), 47 FR 9987, dated March 9, 1982, the
.following violation was identified:
Failure to Inclement a Quality Assurance Procram for the Fabrication and Installation of Electrical Underwater Flood 11cnt Pole AssemDlies Criterion II of Appendix 8 to 10 CFR 50 requires that the applicant shall identify the structures, systems, and components to be covered by the quality assurance program and that the program shall provide control over activities affecting quality of the identified structures, systems, and components.
FSAR Section 1A(b) commits the applicant to compliance with NRC Regulatory Guide 1.29 which in paragraphs 2 and 4 require the applicant to identify those structures, systems, and components whose continued function is not' required (in a design basis accident) but whose failure could reduce the functioning of any plant feature identified in other paragraphs to an unacceptable level.
Contrary to the above, the Senior Resident Inspector-Construction has determined from investigation of allegations, observation of construction activities and review of design drawings that group of devices collectively identified as " Ele:trical Underwater Floodlighting Poles" (Drawing 2323-EL-0925-02) were not identified as required by Regulatory Guide 1.29' and were not included within the licensee's Quality Assurance-4 Program. Mechanical failure of the devices in a seismic event could damage fuel during reactor core installation activities or in the spent fuel storage pools, although the possibility of such mechanical failure of the pole assembly resulting in damaging fuel is very remote due to the design of upper and lower pole retention devices.
F This is a Severity Level V Violation.
(Supplement II.D.)
Pursuant to the provisions of 10 CFR 2.201, Texas Utilities Generating Company.
is hereby required to submit to this office, within 30 days of the date of this Notice, a written statement or explanation in reply, including:
(1) the corrective steps which*have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.
5 Dated:
2 8 1983 g g
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l APPENDIX B U. S. NUCLEAR REGULATORY COMMISSION REGION IV Report: 50-445/83-03 50-446/83-01 l
Dockets: 50-445; 50-446 Category: A2 Licensee: Texas Utilities Generating Company (TUGCO)
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2001 Bryan Tower Dallas, Texas 75201 Facility Name: Comanche Peak, Units 1 an'd 2 Inspection At: Comanche Peak Steam Electric Station (CPSES), Glen Rose, Texas Inspection Conducted: Octooer 1982 through February 1983 Inspector:
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'R. G. Taylor, Senior' Resident Inspector-Date Construction Approved:
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' T. FV W(ste rman, Chi e f '
Date Reactor Project Section A Insoection Summary Insoection Conducted October 1982 Throuch February 1983 (Recort 50-445/83-03:
50-446/83-01)
Areas Insoected: Routine and special inspection, announced by the Senior 4
i Res1 cent Inspector-Construction (SRIC) including facility tours, investigation of allegations, participation and assistance to the Construction Assessment Team Inspection, and other inspection related activities. The inspection involved 253 inspector-hours by one NRC inspector.
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Results: Within the areas inspected, one violation was identified (failure to implement a QA program for fabrication and installation of underwater lighting poles.)
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Persons Contacted Principal Licensee Personnel l
R. G. Tolson, Site Quality Assurance Supervisor D. M. Chapman, Quality Assurance Manager B. R. Clements, Vice-President, Nuclear J. T. Merritt, Manager of Startup J. S. George, Vice President and Project General Manager
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G. R. Purdy, Project Quality Assurance Manager, Brown & Root (B&R)
D. Frankum, Construction Project Manager, B&R The SRIC also interviewed other licensee and contractor personnel during the inspection period.
i 2.
Licensee Action on Previous Inspection Findinos (Closed) Unresolved Item (50-445/79-24) Quality of Unit 1 Reactor Building Dome Concrete.
This item related to the need for additional assurance that a small amount of concrete placed on the Unit I reactor building done during a rain stom without appropriate controls by quality control was adequate. An earlier evaluation of the in situ concrete by a proprietary testing program had indicated that the material was acceptable.
The testing program was found to be unauditable and therefore, some additional assurance was judged to'be required.
The licensee has now completed the i
structural acceptznce test of the Unit I reactor building with special j
attention directed to the repair area.
The test was successful and no anomolies were identified in the repair area and therefore, it is judged that the concrete is of adequate quality.
(Closed) Unresolved Item (50-445/80-20; 50-446/80-20) Design of the AC Instrument Distribution Panels.
This item involved a finding that the segregation of safety and nonsafety wiring in the panels was not in accordance with Regulatory Guide 1.75 but was in essential compliance with the panel design displayed by FSAR Figure 8.3-15.
After discus-sions between the SRIC, NRR personnel and the 11:ensee's electrical engineering group, a method of correcting the matter was developed.
FSAR F:gure 8.3-15 was revised by Amendment 27 to reflect the method of correction. The SRIC has examined the implementation of the change in two of th? four panels involved and had no further questions.
(Clased) Unresolved Item (50-445/81-14; 50-446/81-14) Control of' Stainless We *.apairs.
This item involved an observation that a previously well i
controlled program for the control of the number and extent of repairs g
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made to weld joints in stainless steel pipe had become less well con-trolled due to personnel changes.
The licensee revised Construction Procedure CP-CPM-6.90 to reflect proper identification controls for craft and QC actions effective in January 1982. The engineering controls were promulgated effective with the issuance of Procedure CP-EP-10.0 in March
'1982.
The SRIC has not observed any instance where the procedures are not being complied with and therefore, has no further questions.
3.
Action on Licensee Identified Desian/ Construction Deficiencies (Closed) Over-Torquaing of Safety Relief Valves. On September 10, 1982, the licensee informed the SRIC that a potentially reportable condition 4
under the purview of 10 CFR 50.55(e) had been identified.
It was reported that the main steam safety relief valves had been over seated by excessive torquaing to stop leaks during the main steam -hydrostatic test.
It was found that the excessive tightening had damaged the valve seats in some instances and that some of the valves appeared to have the valve stems bent out of tolerance.
By letter dated November 10, 1982, the licensee informed the NRC that after review, the matter was not considered formally reportable under the regulation.
The SRIC has reviewed the documentation of the examination cf the valves by the licensee. The examination did not reveal any significant damage had occurred to any of the valves that would have prevented the valves from lifting under pressure which would satisfy the safety function. Some of the valves may have leaked under operating conditions which would be undesireable but not a safety nazard.
The SRIC had no further questions on this matter.
4.
Allecations By Dennis K. Culton On September 16, 1982, Mr. Dennis K. Culton made a limited public appearance before the Atomic Safety and Licensing Board hearing in the matter of TUGCO's application for an operating license for the CPSES.
His statement during the appearance appears in the hearing transcript atQj51,,~
5 5555) In addition, Mr. Culton furnished the Board with a written thra"*
statement which appears in the record at 5556 through 5559) Based upon a review of the record, NRC Region IV determ nec w ar v.ners were two areas of interest that should be evaluated for their validity and effect of
' safety of construction %The first area dealt with the potential misuse of a group of drawings referred to as BRHL while the second dealt with the alleged splicing of safety-related or "Q" electrical cables. The SRIC was assigned to make the evaluation.
5.
Allecation Relative to BRHL's Mr. Culton's concern in this area appears at Tr. 5552 through 5554 and 5557 through 5558.
His concerns can be summarized as follows:
Y I (a) Based upon limited information, he was directed to generate isometric drawings giving support locations.
He states at 5557 that he did'not feel qualified to do this work in the manner directed.
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4 (b) The drawings that he and others in this group generated were released to the field unapproved and were used by the craft labor personnel to locate and install supports.
A BRHL is an isometric drawing made from a modified piping installation isometric drawing to identify the supports on the pipe and to provide locational infomation at an appropriate point in time. The drawing I series has no unique title with the BRML appearing only before the drawing j number to distinguish it from the parent pipe isometric which carries the same number except for its unique prefix, BRP.
j Discussions with various licensee personnel who are familiar with the l history of the development of the BRHL's indicate that the need to gen-erste the drawings became apparent when planning was initiated for the as-build verification program as required by NRC IE Bulletin 79-14.
The very early phase of the work appears to have started at about the same time that Mr. Culton was assigned to the drafting department and it is understood that he and others were hired and/or recruited from the field labor forces specifically for the effort.
As an aid to further understanding this matter, it is also necessary to understand the type of infonention that appears on individual support drawings. These drawings, which carry a prefix BRH and an entirely different number scheme, provide, in addition to the design details of the support, information as to where the support was to have been installed.
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The plan type information is provided by a small square generally with four notations indicating building column lines. Within the square, there is usually a dimensional figure in feet and inches from one or more of
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the column lines. Tha support elevation information is furnished on the main face of the drawing whera the elevation of the pipe and the building structure, as appropriate, are shown.
The use of this system requires either a substantial degree of familiarity with'the various buildings and their column line grids, or ready reference to a set of the architectural layout drawings which clearly show the column line grids.
It can no longer be established just exactly what infomation was given to Mr. Culton for his use in generating the drawings..An interview with the one remaining person still in the original group when Mr. Culton worked there, indicated that the package contained a piping isometric and the individual support drawings along with any of their outstanding change documentation (CMC) that changed the locational information.
The pipe l
isometric was reproduced such that information relative to pipe instal-l 1ation was deleted. This would include deletion of weld joint data and i
the bill of materials.
The remaining information was the isometric line detail, location data (again in the form of column lines and elevation) and reference to connecting isometrics.
The modified isometrics were then annotated with a symbol that was to depict the approximate location of supports and a support number was assigned to e.ach symbol.
The location of a given support appears to have been estimated from the support drawing using the building column lines, elevations, and the piping isometric dimensions that still remained on the drawing after modification.
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5 early BRHL drawings did not give any dimensional information on the i
supports and the first issues were stamped "1ssued for hanger identifica-tion and accountability only" in the drawing approval block.
Subsequent revisions, apparently beginning in early 1981, were updated and began to show dimensions for support locations.
The final versions of the drawings provide verified support locations, at which time the individual support drawings are revised to delete the location information. According to the present supervisor of the central document control center, the BRHL drawings have never been routinely distributed to any of the possible user organizations such as the support installations crews. The drawings were only available on an individual requisition basis which would be stamped "For Information Only" when given to the requisitioner. The BRHL drawings were originally developed and updated periodically to facilitate the final as-built stress analysis.
The only use of the BRHL by other than the stress analysis groups presently occurs when a support has to be modified after the initial as-built verification effort. This arises by reason of the deletion of the support location infonnetion on the individual support drawing which then makes the use of the BRHL vital in order to find the support in the facility.
This situation only arises on a limited basis and is treated on a case basis by the support instal-lation group and the document control center.
N @3, In regard to Mr. CuTton's two major concerns in this area, the SRIC was y
able to locate a few of the early BRHL drawings which carry the initials "DKC" in either the draftsman identification block or in the checker block. A comparison of these drawings to those generated by other drafts-men indicate no significant differences.
The SRIC can only conclude that Mr. Culton was as competent as the other people in the group. Given the non-use of the drawings at the time they were originally developed, this level of competency appears to have been adequate.
Mr. Culton's statement that the drawings were released unapproved for use by the construction forces has been shown to be incorrect in two different ways.
First, the original issues were provided to the document control center for filing with the note " issued for hanger identification and accountability only" on face of each drawing and were approved in the appropriate block on the drawing face.
Secondly, the drawings, while on file in the docisment control center, were never subject to a routine distribution and were not readily available to the construction force who in fact had no need for them.
In addition, numerous observations by the SRIC of the support installation process has indicated that the support location information on the support drawing was used to install and to inspect the supports and that any use of the BRHL for this purpose was so limited in frequency of occurrence that it was never detected.
Mr. Cultcq's allegations regard-ing 8RHL drawings is thus considered to be refuted.
d 6.
Allocation Relative to the Solicina of Electrical Cables W
At Tr. 5551 throJgh 5552 and 5556'through 5557, Mr. Culton stated that he had observed that "Q" electrical cables had been spliced and that these splices were in the Unit 1 spread room.
Following Mr. Culton's appearance j
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before the Atomic Safety and Licensing Board, Mr. Culton was interviewed j
in the NRC Region IV offices on November 8,1982, in an attempt to obtain more information on the matter.
The interview was tape recorded by a 1
1 representative of the intervenor CASE in the proceedings. At Tr. 5552, Mr. Culton stated that he observed the spiteing to have occurred two times _.
and further that there were other instances for which he had some papers.
During the interview, Mr. Culton also indicated that he had other drawings available to him that would pin point the matter and promise to make them available to the NRC, or alternatively he would provide a sketch that would provide more detail.
For the record, Mr. Culton has not yet made available to the NRC any of the documents to which he has alluded.
Based on the information in the hearing record and in a transcript of the interview referred to above, the SRIC initiated an investigation that attempted to determine what cables may have been involved when Mr. Culton made his observation. The following key statements were utilized in j
attempting to isolate the involved cables from the other estimated 6,000 "Q" cables in the Unit 1 spread room:
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At Tr. 5552 and 5556: The cables in question are 800 or more feet long.
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b.
At Tr. 5556: Two cables were observed to have been spliced.
I c.
At Tr. 5557: The cables were going to a relay panel.
d.
Interview Record, Page 3: The relay panel was the third one in from the aisle.
Using the above statements, the SRIC was able to narrow the number of possibilities down to two cables, presumably the same two as observed by Mr. Culton. The basis of the analysis was as follows:
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a.
The applicant has a computerized listing of all cables for the entire facility.
By arrangement with tne computer operators, the SRIC was able to obtain a selected sort of the cables based on the "Q" identification and those in excess of 800 feet.
i b.
The list was reviewed by the SRIC to eliminate those cables that were
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not routed to equipment in either the cable spread room or the control room.
A total of 42 cables were then involved.
j c.
Of the 42 cables, only 5 were shown by the routing records to be j
terminated in a relay panel, more correctly called relay racks.
d.
Of the seven relay racks, only one is the third one from an aisle and also has "Q" cables terminated in it, this being a cabinet identified as the " BOP Aux 11ary Relay Rack 1" with Tag Number CP1-ECPRCR-03. Of the five cables terminated in relay panels, only two are terminated in this panel.
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The cable pulling records indicate that the two cables were orginally identified as E0009231 and E0009240 which were pulled on January 14 and 15, 1980, respectively.
Based on his amployment records, these dates coincide with Mr. Culton's employment in the construction labor force as an electrician.
f.
Engineering changes subsequent to the pulls changed the designation j
of cable E0008231 to A0009231 and E0009240 to SP009240.
The change from "E" to "A" signifies that a previously identified safety function had been downgraded to nonsafety with the cable still routed with safety grade cables. The change from "E" to "SP" indicates that the electrical circuit involved has been deemed to be no longer
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1 Specific findings relative to cables A0009231 and SP009240 are as follows:
i a.
The SRIC, with the assistance of two other NRC inspectors, traced cable A0009231 through the spread room cable tray system from tne point at which the cable entered the room until it left the tray to pass through a conduit into the relay rack.
The only portion of the cable not examined was the approximately 17' of cable in the conduit.
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Of the estimated 50-60' of cable in the tray, there were no anomalies cf identified.
b.
The SRIC found that cable SP009240 had been removed from the tray system on or about November 23, 1982, in response to NCR E-82-01210 which stated that certain tray sections were overfilled.
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engineering solution was to remove several cables that been spared by other design changes. The removal was through the tray system but
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left the cable in the conduit entrance to the relay rack, again approximately 17'.
The SRIC located the removed portion of the cable in a storage yard and visually examined the entire 400' with no anomalies identified.
General findings and considerations:
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Project Specification ES-100 " Electrical Erection" dass not totally
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F p ',,k prohibit the splicing of safety-related cables as indicated by l
p Mr. Culton. The specification allows splicing to be done based upon 5
the engineer's direction and this has been done by the use of
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It should be noted the industry standards l
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(IEEE) do not prohibit field run splices provided they are properly y
qualified.
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Ogl b.
There have been a number of instances where the cable jackets have v
I been repaired when the jackets were damaged either in the process of manufacture or during installation.
These repairs have been accom-p11shed under a standard repair procedure, EEI-13, when directed by the site engineers. One of two repair measures are applicable within l
the procedure. One of the methods utilizes heat shrinkable plastic tubing when the damaged area is not prohibitively far from the end of l
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8 the cable and thus allows the tubing to slip down the cable. The other procedure which was much more generally used early in 1980 involved the use of a fire resistant tape wrapped in half-laps over the damaged area. The fomer procedure produces a very neat slim i
appearance while the latter procedure is relatively bulkly and might well appear to be' a splice.
A number of both types of these repairs were identified during the examination of the specific cabloc discussed above and during an earlier more extensive examination of several tray runs in the spread room.
All of these anomalies were I
judged by the NRC inspector to be jacket repairs.
c.
The SAIC believes that yet another consideration may well be relevant to this matter. The consideration involves a much earlier allegation that cables had been repaired in an unauthorized menner. The allega-tion was received by the SRIC'sometime during February 1980 from an electrician assigned to the electrical cable pulling crew that,had pulled the cable then in question and the two cables identified with Mr. Culton's allegation.
All three cables were pulled during early to mid-January 1980. The SRIC's recollection of the person was that he was a journeyman electrician and assisted the foreman in.the detail supervision of the crew of about 16 men, all of whom were classified p3 as helpers except for the foreman and the journeyman.
Since the ga electrician was sufficiently concerned to report a cable jackat r
repair involving the use of Scotch 33 tape rather than the approved 1
j tape, it seems to follow that he would have also reported an actual cable splice for which there is no approved repair. Given the j
electrician's position with the pulling crtw, it,also seems unlikely that he would not have been aware of an error of a magnitude that would have caused such splices to be made.
(For more infomation j
about the 1980 allegation and the results of the subsequent investigation, see NRC Inspection Report 50-445/80-08; 50-446/80-08.)
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d.
Since 17 feet of each of the identified cables were not inspected by _.
the NRC during the course of this special inspection, it was not possible to conclude positively that the allegation is either j
confirmed or refuted.
Notwithstanding, the inability to positively state that the allegation made by Mr. Culton is substantiated or refuted, the SRIC believes that no further action is warranted based on the following cumulative infomation as follows:
(1) Cable jacket repairs utilizing wrapping with a rubber tape were not and are not unusual.
J (2) There has been no identified reason why the splices should have been necessary.
The rubber-like jackets on the cable are relat.1vely easy to cut with even a dull edge but the wire i
insulation material and the wire itself are relatively hard to 4
cut.
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e (3) A jacket repair made with tape would be very difficult for the inexperienced person to distinguish from an actual splice.
The splice generally would have a somewhat bulkier shape and would probably be somewhat lumpy rather than smooth.
(4) The probability that the SRIC would have learned of such an unusual event as a splice being made to safety-related cable g.
through contacts that had been established in the electrical c,8 crew involved.
(5) Removalofthecablewouidprobablycausedamagetothenearly 30 cables in each of the conduits.
(6) Neither of the two cables now have a safety-related function and there are no requireme,nts that prohibit thegof consafa h *=*rles.
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m V w-a f M,. M W M An article appearing on page 13A of the Fort Worth Star-Telegram dated q
January 7, 1983, stated that Arvil Dillingham, Jr. had made allegations } g which were subsequently investigated first by personnel of B&R and later by personnel of TUGCO. The article stated that Mr. 01111ngham was then charging that these investigations were a " cover-up" to hide safety hazards at the Comanche Peak nuclear power plant.
The article stated that Mr. Dillingham had been employed at the construction site as a foreman and was laid off weeks after he made the allegations. The article also attributes three technical type allegations directly to Mr. Oillingham.
In summary, the technical allegations appearing in the article were:
(a) Mr. Dillingham apparently stated when interviewed by the writer of the article that rejected aggregate was mixed with concrete that was A (,,,. W subsequently poured to form the base for the nuclear reactor.
The article stated that a Larry Witt was the B&R equipment operator who had apparent first hand knowledge of the matter. The article also stated that Mr. Witt could not be reached for comunent.
(b) A second allegation, that the article stated was never previously investigated, involved the construction of underwater lamps for the q
pools surrounding the reactor.
Mr. 01111ngham charged that he was i
prevented from cleaning 'out drill shavings from the lampposts and that these shaving could be washed into-the reactor during refueling j
and could jam the fuel cells and could even fuse to the control rods.
j (c) The third allegation dealt with a contention that holes had been.
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... improperly drill through concrete walls and the interior reinforcing steel. The article attributes the information to another party I
identified as Danny Grisso.
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l 10 The SRIC assigned to the Comanche Peak station obtained both the B&R and TUGC0 files pertaining to the investigations that were stated by the newpaper article to have occurred.
The B&R file was found to contain an undated and unsigned letter addressed to Mr. Thomas Feehan, President of B&R. The letter is indicated in two different places to have been prepared by Arvil..Dillingham, Jr.
The letter is stated in a memorandum addressed to a group vice president of B&R from a vice president of the B&R division to have been hand delivered to Mr. Feehan by Mr. Dillingham on August 6, 1982. The memorandum was dated August 13, 1982.
The undated letter to Mr. Feehan contained eight violations that the writer stated he had observed or had knowledge of that had occurred during his period of employment at the Comanche Peak station.
Review of the letter addressed to Mr. Feehan indicated that only one of the eight violations correlated with the allegations appearing in the newspaper article, this being the item outlined in (c) above pertaining to the drilling of holes in the concrete' walls. The B&R memorandum of August 13, 1982, which is a report of the internal B&R investigation of the eight violations, indicates that seven of the allegations were found to be either without a basis or were not substantiated.
The remaining item was considered in effect to have been substantiated but the corrective measures were already I
taken.
In each case, by what is assumed to be Mr. 01111ngham's signature, j
Mr. 01111ngham acknowledged his satisfaction with the B&R findings.
The i
.above memorandum indicates that a number of other people were interviewed by the B&R investigative group, one of whom was Mr. Witt.
Mr. Witt apparently did not confirm Mr. Dillingham's allegations but made additional allegations related to his experiences during his past employment at CPSES. One of these allegations appears to be substantially the same as that appea?ing in the summarization of the news article as (a).
Mr. Witt also charged that some personnel biased the operation of the concrete batch plant scales by leaning on the wires connecting the scales to the sensors. Additionally, Mr. Witt stated concerns about a 1
possibly missed hold point during the welding of the fuel pool liner'and that some avelding had been done by an uncertified welder.
In an internal B&R memorandum dated August 17, 1982, the B&R investigators susunarized Mr. Witt's concerns and their findings relative to the concerns.
The B&R memorandum indicates that the investigation relative to use of rejected i
aggregate was-apparently partially substantiated but of no concern in that the aggregated pile, rather than actually being unacceptable, simply had not been tested prior to use as required.
The matter was documented on Deficiency and Disposition Report C-446 dated December 9,1976, which appears as attachment A to the memorandum.
In the matter of the missed hold point for the fuel pool liner weld, attachment B to the memorandum documents that no hold point was missed.
Regarding the two remaining Witt allegations, the memorandum states that the allegations were investigated and found to be without basis but provides no other information.
Personnel of TUGC0 performed a separate investigation of Mr. Oillingham's allegations (the Feehan letter) during August of 1982.
The results of that investigation were furnished to TUGC0 management by memorandum dated J
September 2,1982. This investigation found that two of afght items were substantiated with one of these being the same item that was substantiated i
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11 by the B&R investigation.
Both of the substantiated allegations were found by the investigators to have been adequately documented and that corrective measures had been taken or were in progress.
In a separate memorandum dated December 10, 1982, one of the TUGC0 investigators documented a phone call from Mr. Dillingham in which 4
Mr. Dillingham apparently made yet additional allegations. One of these allegations. regarded welding done by an uncertified welder on the turbine-generator pedestal (by implication).
Mr. Dillingham also apparently further mentioned Mr. Witt who was supposed to know about a sensor that had broken off and was buried in the main dam. Also, Mr. Witt was alleged to have personally driven a front loader that returned dry and lumpy cement that had been rejected to the bin, that this cement had been subsequently used in the reactor core, and that this was why the cracks happened. The i
writer of the memorandum stated that he had encourged Mr. D1111nghes to take his concerns to the NRC.
Mr. Dillingham in turn was reported as saying that he had intended on going to the newspapers and Congress instead.
It appears that Mr. 01111ngham carried out his above stated intention in that the above referenced newspaper article has appeared and to the best of SAIC's knowledge, Mr. Dillingham has made no contact with any component of the NRC. NRC Region IV determined that the allegations in the news article should be investigated but that those made in the Feehan letter and in the telephone conversation with TUGC0 should not. This decision was based on the premise that Mr. Dillingham has had his earlier conceens satisfied except for those appearing in the article.
Regarding the above summarized allegation (a), the SRIC established that Mr. Witt was no longer an employee at CPSES and further established that he had relocated from the Glen Rose, Texas, area to another state. NRC Region IV personnel made several attempts to contact Mr. Witt by te,lephone at 5fs new address, to no avail.
A registered letter, receipt requested, was then sent to Mr. Witt requesting that he contact Region IV as soon as
]
possible.
Receipt of the letter was acknowledged but as of this data, i
Mr. Witt has not contacted the region.
It appears that Mr. Witt does not intend to assist the NRC in investigating allegations attributed to him.
j It should be noted that only the B&R investigative group has 'been able to establish contact with Mr. Witt; all others have apparently failed.
)
Regarding sinunarized allegation (c), the SRIC, with assistance of another i
Region IV inspector, was able to establish that the undematar lignting standards were fabricated in such a manner as to leave drilling chips inside and had not been removed.
It was also established that the lighting standards were fabricated completely outside the licensee's QA program which included various welding operations. There are no records of inspection or of the welders involved or of the weld procedures utilized.
Review of the design drawings do not reflect that the A/E considered the lighting standards to be within the QA scope, yet should the standards physically fail during the seismic event, fuel could be damaged. Given the possibility of failure, the standards should have been classified as Seismic Category II (licensee's FSAR definition for l
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components which have no safety function but must not fail in a seismic event since such failure could jeopardize the functioning of a safety-relatad component) and should have been included in the QA program.
This is considered to be a violation of Appendix B to 10 CFR 50.
l Regarding the premise that the drilling chips inside the standards could be swept into the reactor during refueling and cause an accident, the SRIC found six of the standards are nomally located with their bottoms just about the floor level of the refueling pool and that the chips that might have worked their way out of the bottom of the standard could have carried into the reactor at the conclusion.of the refueling process. The size of i
the chips that could work their way out through the 1/2" holes are not of l
a size that could be expected to plug a water channel through the reactor.
core and create a hot spot.
Further, the idea that the chip could fuse to j
the control rods is equally remote in that far higher temperature would be required in the core to achieve such fusion than actually will exist l
there, the differential being 600* to 800*F.
Thus, the safety significance i
of the chips is very small. The uncontrolled (no QA) problem with the l
standards is relatively more important since workmanship on the devices i
has not been established.
Regarding sumanrized allegation (c), the l
allegation has been the subject of another allegation by a person who appears to have substantially more direct knowledge of the matter than indicated by Mr. Dillingham. Under these circtestances, the NRC has determined that it can address the issue in a more satisfactory reanner by i
investigating and evaluating the second party's allegation rather than Mr. 01111ngham's.
l 8.
Postino of NRC Form 3 10 CFR 50 was revised by 47 FR 30452 to add 10 CFR 50.7 " Employee Protec-tion." The change was published July 14, 1982, and had an effective date of October 12, 1982. An important element of the change was that of a requirement to post NRC Fom 3 at locations where the fore een be readily viewed by employees on their way to or from their place of work.
It has.
l been alleged that the licensee did'not post the form. The SRIC learned of the allegation during early January 1983 and found that the fom was posted throughout the main construction administration building and on a bulletin I
i board where most of craft labor for'ce can readily see it, particularily when departing from the construction area.
The SRIC has been informed by
+
licensee employed personnel that they received and posted the foms in the administration building about the first of 1983.
A senior B&R manager indicated that the foms were received, he believed from S&R's Houston office, sometime between Thanks";iving and Christmas and were posted on the craft labor bulletin board near rhe " brass alley" well before the first of the year.
It is thus clear that the forms were not posted on the specified effective date of the change to 10 CFR 50 as alleged.
It is much less clear as to when the forms were actually posted nor is it clear that most people would even have been aware of the posting. The " brass i
alley" bulletin board is a large board, perhaps 4' by 6' in size with many postings. The majority of the postings are required under various federal statutes or regulations. The posting of an additional form procably would not draw much attention from the average worker.
As of the time of 8 P'%T
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13 inspection by the SRIC, the licensee and his principal site contractor were found to have the form posted and to be in compliance with the regulation.
9.
Management Interviews Ihe SRIC held management interviews with one or more of the persons identified in paragraph 1 on a nearly daily basis throughout the inspec-tion period to discuss NRC findings developed during various special inspections and investigations.
The discussions also included the licensee's positions on the NRC findings.
t i
! OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF PAGES:, k-ACCESSION NUMBER (S):
Rfo O / O R O O 5 7 l
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APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492-3939
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TEXAS UTILITIES GENERATING COMPANY TUQ-1790 OFFICE M EMOR ANDUM F
J. T. Merritt Glen Rose, Texas September 2, 1983 To Subject NRC InspectioniReport 83-24/83-15 asAretR1".ig Aw- ;Z L
f The attached form documents an Unresolved Item recently identified in NRC Inspection Report 83-24/83-15.
Please prepare an evaluation and send a written response in order to cloue, or actions that have been or will be taken in this matter, to this office on or before September 27, 1983.
6ALAAJ Y R. G. Tolson
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TUGCO Site QA Supervisor
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TRACKING NO.
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ITEM OF NONCOMPLIANCE
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UNRESOLVED ITEM l
l OPEN ITEM REcurREMENT FINDING SPI. ICING OF ELECTRICAL CABLES IN CABINETS (83$4-01) c The SRIC became aware that the Comanche Peak project electrical engineer had authorized the splicing of safety-related and auxiliary electrical cables within several control _ panels during thd inspection period. Since the licensee had comunitted in FSAR Section 8.l jto comply with IEEE 420,
" Trail-Use Guide for Class lE Control Switchboards for Naclear Power Gener-ating Stations," which forbids splicing of wirfng in such panels, the SRIC judged that the licensee was deviating frcsa these commitments. The licen-see engineer indicated that he interpreted the'.IEEE standard to prohibit l
such splicing only between the cabinet terminal boards and the cabinet devices and did not prohibit such splicing in the field run cables attach-ing to the teminal boards. The engineer stated that action had been 1
initiated with the NRC Office: of Nuclear Reactor Regulation to clarify the issue in the FSAR. The SRIC confirmed that such action had been fnitiated byatelephoneconversationwiththeNRRlitenjingProgramManagerfor Comanche Peak. Pending Action by NRR, this matter will be considered as an unresolved matter.
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bXAS UTILITIES SERVICES IN OFFICE MEMOR ANDUM To RuGtAT61BorrT Glen Rose. Texas October 4.1983 subject 031ANOIE PEAK STEAM ELECTRIC STATION TRACKING ITEM 115 I
WIRE SPLICES IN CLASS 1E PANELS REF: 1) TUQ-1790
- 2) CPP-13,708 In response to the subject tracking it s, we have initiated a change to the FSAR (Section 8.1.5.2).
This change is a new clarification which indicates project compliance with IEEE-420-1973. This change should be included in Amendment No. 44.
Please contact this office if additional infomation or clarification is required.
J
'FreldvG. Burgess Project Engineering Manager e
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/cp cc: ARTS J. T. Merritt L. M. Popplewell D. H. Wade i
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-A-3% indicated then wek several instances in which he felt pressure had been exerted on him not to write NCRs. A-3& stated that within the past month, he 4QE-1 learned of a problem in the Control Room of Unit-I in which electrical enhles were b.eing rgm_oyed witha"* nenpar da-"manration.
A-3b indicated that he wanted to write an NCR on the lack of documentation, but that
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, a QC supervisor, had-instructed him not to write the NCR.
A-38 told of another situation which occurred within the past month in the Safeguards Building in which cable was removed without documentation.
A-3 fb said Y E-he again tried to write an NCR and that it was rejected twice by A-3 6 said that after the third time he submitted the NCR, it was accepted but that he did not know if it was placed in the system.
3-36 described another situation within the last c;uple of weeks 'avolving flex,
conduit in the Fuel Building. Conduit was replaced and not iepaired as described by an.NCR. A-JB, said he had been told by his Lead, U - 2.
. to disposition
._Lh,e NCR, but that he had not tet complied with his lead's orders, r- *
-A-36 recalled another occasion in which his Lead, U-Z., directed him to "close out" an NCR that he was not certified to do. A-3B said that this NCR concerned
\\QL4 conduit and that he told 0-'2. he was not certified to do the job, but that told him to do it anyway. 43D said he closed out the NCR and it was later
" kicked back" and corrected.
-A-y> recalled another, situation, in April 1983 in Unit 1, in which craft needed an NCR closed so they could proceed with the pulling of cable. %-36 said that problems with the Able tray had not been_ corrected. A-3Ps said he remembered 97-5 there was trash in the cable trav[ cuts in parts of the cable, and the cable wat ajso intentoven..A-3b said he refused to close out the NCR.
A-36 said that'his Lead,0-2, was contacted by someone in craft (identification unknown) who told him B7 to.have A f3 close out the NCR. 4-3% said that O-7 told him, "I'm not telling you that you have to do it, I'm telling you that they want it done." 4 -J S,
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to reinspect again, and that he again refused to close out the NCR. *3E said"
$-L that 0-/_"got another' inspector'to 'close out the NCR, and that V-6 (no longer M.
employed by'B&R) was the general foreman who was a witness to this incident.
A-38 concluded that based on these above instances, he. felt he had been harassed as a QC inspector and that his supervisor had made attempts to intimidate him to keep him from performing his duties. A-yb said he had earned the nickname " Shut'em Down A W," and that this title was'used to belittle him and create pressure from his co-workers. 4-3g stated that when he came to work at CPSES, 0-4 the super.isor,-told him, "This company does not care about people, it just cares about getting the job done. You'll do your job as you're told and nothing more."
- 36 said it was his opinion that quality control was not their first concern, but rather production was the important thing.
- 36 was asked for the. NCR identification numbers, but stated he did not recall the NCR numbers. 4-313 said he would obtain the identification numbers of the NCRs and give them to the Nuclear Regulatory Consnission.
INVESTIGATOR'S NOTE: Subsequently, A-3c was contacted on four different occasions and explained he had not been able to identify the NCRs in question.
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MANCIE PEAK STEAM ELECTRIC STATION I
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INSPECTION REPCRT g
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l Verify flex conduit installed (Refer to QI-OP-11.3-28.1)@)l l
l (V) 2.
l Verify proper cable being tenninated (Refer to QI-QP-l l l l
l l 11.3-28.2) l l l l
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Verify cable and cable connect card agreement lgl l
l l b.
Verify jumper cable installed (if required) lWl l
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Vedfy cable continuity check performed (Refer to
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l Verify jacket / insulation removal (Refer to QI-QP-11.3-l l l Sl _/
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VeHfy inner conductors insulation not cut l tM lM / 9f I
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Verify Jackets / insulation souarely cut n
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VeMfy crecer length of exposed conductors E
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Verify crecer tools (Refer to 01-09-11.3-28.5):
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NOTE: Acolicable only when this insDection is N
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VeMfy concression tool calibration C:-
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VeM fy accropMate dies are utilized g
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(V) 6. l Verify cable shielding (Refer to QI-QP-11.3-28.6F l,tA/Fl l
i (V) 7. l Verify proper lug or connector / connections type, size. l l l l wC l
J l and final cMmps (Refer to QI-QP-11.3-28.7) l(l l ;$ C l
(V) 8.
I VeHfy orecaration of surfaces and bolted connections i l i I *C y i
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VeH fy proper surfaces preparation l AA/71 l
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VeMfy proper hartbeare AA/)l
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Verify torque requirements AA4l d
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l VeHfy terminations (Refer to QI-QP-11.3-28.9) fvim/.FA.dB. 4 !
(V)10.
Verify minimum bend radius, inner cabinet, routino and l
l and cable secure (Refer to QI-QP-11.3-28.10) l Vl, l
l (V)11.
Verify cable identific1 tion (Refer to QI.0P-11.3-28.12) V i
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l Verify splicing (Refer to QI-QP-il.3-28.13) gpfvpfyd gjjp W
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CCMANCHE PEAK STEAM ELECTRIC STATICN INSPECTION REPORT QI-QP-ll.3.-28 Rev.
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Ir Verify proper documentation (Refer to O!-0P-11.3-28.14)Vidssiv>h N V) 13.1 (v) 14.1 veri fy component installation (Refer to 01-0P-kAMI I
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Verify heat shrinkahle nuclear cable sleevan fliefer to I I I OI-0P-11.3-28.16) idAfl (W) 16.
Verify Din / plug orientation & continuity check performedl I i I (Refer to 01-0P-11.3-29.17)
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Verify connector free from damaae (Refer to OT-0P-i l I i
11.3-28.17) lAAdl I
(V) 18. ' Verify internal separation (Refer to QI-QP-il.3-28.ll) l#1 1
(W) 19.1 Soare conduit connection instrument nort oluaaaa 1 enr. I I I I
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VeMfy oin/olue eMentation and continuity check cer-I !
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(V) 12.
Veaify eennecter #ree fe'sn damace (Redea to Of-09-11.3 I i'I i
l
~
be.17) lM//l
}
l I
(V) 13.
VeM fv inte'"1al sacaration (Refer to Of-CP-11.3-28.11) IM I I
(b) } } Y lf f /*!" 4! $lkUV {Y b ~h Ol-0/ )/l '.S /.5}
lb l l
l
- "********'W L~/-) /s 7 Z / Y
)(/y' A L /, W U./ 4 i
J~/- 77o0 & '" J p1 mj
'//f-&3//7 p LW/W
~
i 1
N d ' 8 NM i "f/m i " #c gh REVIEWED BY: INMdb LEVEL. [ CATE: /d-
~83 N*
PERM. PLT. RECORD a - r 83
<x di L
17.1.09. b
~
syk.; wc.
suu
- o o.
l v
L 1
-1
s y
COM AN CHE FEAK STEAM ELECTRIC S TATION l
2 e,
INSPECTION REPORT larca QESCRIPT:cm 4
po.
,f_ g g g; C EN T17aCA 7. "N No.
SYSTE68 / 574WC TLAE OES.GMAT:CN CLASS lE CABLE TERMINATION CABLE # E6.g73P J SYSTEM # 99 g56 M /L P//J.C SPE O.NC.
AEV2, REF Q.;. Ccc. & REV. a c.waNhNo.
ES-100 MEASwAE TE3T E;wp. CENT, NO.
QI-QP-ll.3-28, Rev..
3 TOOL # w f KIT # %
U$5!!5'o's CP"iMENS"** CTstE8Ec$
"u'dgench O Ps3 g es v
t ms9. Resus.rs O iNsecenou couei.rTEo, au. 4,*ucaste irEMs sansactce
,I
@fNsPECDCN 4##/_
a-6 -E '3 I
CoM8U[ TID, UNs4DSPECTCM ITIMS v3TIO SE CW IrEM No.
tc INSPECTICN ATTRIBUTES 3
gjC carg t
gg e
E (V) 1.
31 l Verify flex conduit installed (Refer to QI-QP-ll.3-28.1)lM#1 l
I (V) 2.
l Verify proper cable being terminated (Refer to QI-QP-r l l l l
l l11.3-28.2) l l l l
l l a.
Verify cable and cable connect card agreement Ml i$
i I
l b.
Verify jumper cable installed (if required) x/14 l 2 >$
j (V) 3.
l Verify cable continuity check performed (Refer to lQI-QP-11.3-28.3) l l
- 7. O i
vf l
T (V) 4.
l Verify jacket / insulation removal (Refer to QI-QP-il.3-
_ i l
yj
=
l28.4):
Il l W
i d I l a.
Verify inner conductors insulation not cut ldl W
l (if apolicable) l l I Ir i
I b.
Veri fy iackets/ insulation squarely cut V l E
I c.
Verify proper length of exposed conductors
/l H
Ierify (V) 5.
V crecer tools (Refer to 01-0P-11.3-28.5):
I I k
i NOTE:
Acolicable only when this inspection is l
M I
actually observed.
l !
RS I
l a.
Verify compression tool calibration lvt M
/ b l b.
Verify appropriate dies are utilized l# l I Verify cable shielding (Refer to QI-QP-11.3-28.6)
_ /
/j (V) 6.
IW
/s//
/l (V) 7.
l Verify proper lug or connector / connections type, size, jl 1,C / g/
l and final crimps (Refer to QI-QP-11.3-28.7) l#
$/ $/ M (V) 8.
I Verify preparation of surfaces and bolted connections l l
- h d/ f/
)
(Refer to QI-QP-11.3-28.8) l
$@/ g/]
Verify proper surfaces preparation a.
4W 4 (I /g W/ l l b.
Verify proper hardware 8/ 7// l A/A l c.
Verify torque requirements 4M[e.J////
l
+
I (V) 9.
4 Verify terminations (Refer to QI-QP-il.3-28.9)
- F ( /l #/
i (V)10.
Verifv minimum bend radius, inner cabinet. routing and i
i and cable secure (Refer to QI-QP il.3-28.10) 1 l {
(V)ll.
Verify cable identification (Refer to QI-QP-11.3-28.12) ! #
-M i (W)12.
t I
l Verify splicing (Refer to QI-QP-il.3-28.13)
{
p Q.g g )f p (Continued)
\\
v,
\\
/.'
]
/
i 2:.
s' l
CCMANCHE f EA ' STEAM ELECTRIC STATICN INS $EC; TION REPORT Q I-QP-ll. 3-28, Rev.
/
(SUPCLEMENTaL)
)___
N0.
ET-lj j
~:
cA E its.w No.
INSFECTION ATTRISUTES e
- EN-R i2 % si i
1 1
n
'I ft (V) 13.1 Verify orocer documentation (Refe r to 01-0P-11.3-28.14)Vt 4/o-M alp :
(V) 14.1 Verify comoonent installation (Refer to OI-OP-I I I I
i i 11.3-28,15) lad //l I
(W) 15.1 Verify-heat shrinkable' nuclear cable 9iileeves (Refer to l I I i O T-OP-11. 3-28.16)h-+---~~~samic - -
IdMi *
(W) 16.l Verify oin/olug orientation & continuity check performedl i i I (Refer to 01-0P-11.3-28.17) idl (V) 17.1 Verify connector free from damage (Refer to CI-OP-i lI i 11.3-28.17)
Fld'l l
I (V) 18.1 Verify intemal separation (Refer to 01-0P-il.3-28.ll) l#1 I
(W)
- 19. t Soare conduit connection instrument oort oluccad t +ne-i i i I
I anad (Refer to 01-OP-11.L?A 1)
Wl/fi 1
! l l l
t i i I
l l l
w i I I
I i 1 i i I
I ! I l
i I I I
l l l l 1
i a e 'nul W l i i
i ec n 1MCDUMAI LM UnH'I l l
n m sw -----
l l
I i l I
~
l i i l 1-1 A (-W/,?d/3 ) RA /724Y & A ag. &e " w w
n me ei
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gfu g E-g187 h " V "pg ym,, ue y gyy _,
Swa #/4#J WG sL. &
G7-/3yf
& M,' /,2 gy
-y+ 4ky779pf q f.; 6 GTArof
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al an.arto sca no.
l.R. CLOSM~
lStGNA M E d Ub '^
h/p J-/O -///
I oc :N37Ec70R
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is v
i REVL:WE0 BY: MNd LEVEL II DATE: 2 -/d / V
l l
OC&dM C)tg POW STE,AM ELi".'"MIC STCCN e.nr-
-e C"
- U
/b h~N I"*ti-/~O0/4')60 l
se.
37 d sEmig wGAT.G85 ant e e EGIWS 739 4 *3TIkas WT9tbGT AE STGs/35 I
iTERS J43CI871".CN f A> r HI l
CLASS 1E 0 8LE T W INATTon ES-100 e
2m Of-OP-11. 3-29. Rev. /9
.,.,O.w. an-p.
- y. u. a n
, CL d-AV (77-NO C !" M an C%%T'" C@3
- Y7ee, C F" g en c=asstun, au. asubcasts Tess saf:grac?cnv w ge/-/f.[/
8T
~I C taarte tem cosm.rMs. uneartsactoser iTess usTun asLair I
8 INSPECT:CM ATTMtSUTES garg m
1 (Vi 1.
VeHfv fTex conduit installed (Refer to OT nP-11.3-19.lil A//Al i
iy5,
- h. 4 <.,
4,...,
,... s., 4..,...,.
4-,
-,..,..,4 I I I I
Io.s.
.. nr..ao.t,
,_9a
,)
I///A i i
t r.i s,
- h. 4,,, - -... -.,5
%. 4,,...
4,.
.,4 r o.<.
.- n r..,o.
rit i
h, 2.9 35 IM I I
i h.
V.ei dy ambio and emble cannse* e n a'4 tersamea*
Id l l
l h
'Is*4#v 4.nnese c=s hi s int *311 a+4 e n l i f esau 4 *sif i I///81 hh 6
('ll 4
ke*i#v cable cantinuity check ':eeder='ted (Re#ee te l l l M_ A '
bi-cp 11.3-29.3\\
Wl i S
?
Ver4*v er-oe- ;ue er eenneceer/cennectiens tvoe. si e in) i I l'
tvt e la4nat
-,4 in.
t o.s.,., n r.no t t 1 ta 7)
IM l F
(V) 6.
VeMfv termination (Refer to Of-OP-11.3-28.9) 15A I /S' (V) 7.
keMfy minimum bend raduis, inner cabinet reuting, and l l l l
l hable secure (Refer to 0I-0P-11.3-29.10) 16'1 I I
l I'r t a Serify cable identification (Refer to Of-OP-11.3-29.12) tWl l
I IV) 9.
Yeaifv erecee doc. mentation (Refer to OI-OP-11. 3-29.141 I M i l
IV) 10.
Veai'v comeoneat installation (Refea to Of-OP-11. 3-29.15t M41 l
I (V) 11.
VeMfv ein/olue oMentation and continuity check eer-I! #
l l
{
'fer ned (Re#.a to of-OP-11.3-29.17) l/V//' l l
I j
(V) 12.
V.edfy eennecter free fesn < tam.ee (9ede* te OI.0P-11. 3 1 I'l I
f l>e 171 lh'/A l l
l (V) 13.
VeM fv inter 9a1 seaaration (Refer to OI-CP-11.3-29.11) iA i
,f I
I I l l
l
- ( ***. '"'x. E l t/l0 J u y e f' f r io r f O Z $r q.
f/- /700 lia, l
Et-0ieq.rai.,D 2 RMdW-g 1rg-/q ag t 2 SWA-/4//3 l
1W- /7194 f I i
"2/f/
.,li.n.c.ss:4//gc!
j *'" g /j. j= =a w 'f'7,,,_..,
,j ROIEWG H: N b
I. del.I CATE: /Y/MV
/
pggd, FLT RECORD pg6E LOC.
FOR INFORMATION ONLY 17 2.ee.2e l
.u m' 1
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,...-.-.--._.-.-,--w.,,w,n---,,
e
. _. __ _ __ __._ ~ __ __. _.- _ _ _ _ _ _
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,<.an n er ar.s= in.
gang ur=w ma assaa.r:-
l c)RE d/g//f 9f/
yf 130 Cd
/.9f CLASS IE CABLT TT WINATTON t
.i
- g. v., sw a say. a u.us n l.s ws a
.u. sa a ssu. aa.
upsr a.
asv.
E5-100 r 2 o 01-09-11.3-29. Rev. /f T0ct d //
cfT. #Af O I" E C%"'ENd"" CM E#D,e,w en O M en
,l man essa.ra E supecmm casuns, a.t. asum cam.: man samac aser kM J.Af-N E ** * **
O nese= mon casuTun. uneartene one nths i sms se.zw 1sesit:: CN ATTMISUTE3
- 1 grg IV) 1.
Vee 4*v # Tex eseduit installed (Re#ea to of no-11.3-28.1113A41 ivi,
V. 4,v e.,-
..sy4.
.....,.4.,
.,.....s Iwt.
l l
!ro.<...
ar.so.,,
S.,o
,s I I.'
I tvi,-
Iv. 4 sy..~.....wi. 6.4..
4...
ro.<..
.. nr.co.
iW I 1
I i
k, S 9. Si l i I I
i k.
v.c4,v -,et e r ) e,8 se --nne-es er..-e-.
le 1 l
I L
v.w ey 4.e. m ie 4-,stta u. (4<
u4 o l #41 I
I e
tvi 4 Vesev easte e nt % ev e*eetc e e, ed Ise.. es in i I
l i
e r
bf-co-11.3-2s 31 I I I i
i i
tvi e Ve.4*v - -ee. Iue e. e~nne-+erecenne-tions *vae. size an4 i i I
4..,.w
.*to.<.,.
nr-.ao 5,
3 to_vi Id i I
(V) 6.
keMfv ter wination (Refer to Of-CP-11.3-29.9)
Wl I
(V) 7.
VeMfv sinimun bend raduis, inneta cabinet reutine, and 16 l l _D N hable secure (Refoe to Of-OP-11.3-28.10) i l l MN[
kerify cable identification (Refer to OI-Op-11. 3-29.121
'*"f' I
FM / l tvi o (v) 9.
ke-ifv erece, dee.me.itation (Ge#ee to 01-09-11. 3-29.141 V i lT /
l IV) 10.
Verifv esmeentat installation (2efer to CI-CP-11. 3-29.157 4W i l
/
l (V) 11.
VeMfy cin/ols 1,oMentation and continuity check cer-I ! t I /8 l
i
!fervied (Redee te of 00 11. 3-2o.171 l#l#l I/C i
T j
(V) 12.
Ve-4fv eenne-+er #* e f*am dammee (te ea te Of-09-11.3 l#ffl i
I s
be st)
I I i I
l (V) 13.
Vee 4fv inter. sat secarstion (Refer to 0I-CP-11.3-29.11) W1 i i
i I i i l
I "emame tsee.se:x Ena pgjfd.f Cs/DseToR /W)'
ff-/49AJ9 El- /fo/Sk 9M gf/ 1-o*9serdB
'[#As /SAW7"N/A//b $P Ny a7ffs.elL8C:3882parO i ** pr i "*" #
- e,, m -,
RUI DED SY:8dh t.EVEL 27 QATE:
/- 3))-['A p, puf. RECORD.
FOR lilFORMATION DN!Y i
J rousm' 'J.T. No. -
E 3-m
N.
COM t.N CH E i:EAX STIAM E. ECTRIC ST17 CN 1
dm
/J 5 -
INSPECTION RE?CRT DN-cc o3[xg7,fgyj; r
,, SYSTEM d Cgan :ssionar:952'A a lsrs:s.v e srauc arm cascur.e3 icz3 w.c27.c3 io.
3 CLASS lE CABLE TERMINATION CABLE #Ed) Cd9307
/
t 7: 3c.
u v.
au. c.:. ::c. a uv. a c.uact so.
w use s ca raar ca.cor ~c ES-100 2,,QI-QP-11.3-28.-Rev..//,,
TOOL # 5ee KIT # re, w m _'
M37' CM V
fl N P3 C C I
EC 10N s.
ON v
COMM.ETC, AU. APouCAaLZ ITIM: 34713FACTCRY d
h 2 /b l
O mmerien ca um, ununimerany iras us= seu:=
- */ '" '"*'*"
,g
- ^ ' ' ' '
ITEM NO.
W 4e j
j INSPECTION ATTRIBUTES 3.aarg saa m a m '
E e l
,2.
(V) 1.
l Verify flex conduit installed (Refer to QI-QP-ll.3-28.1)LA/Al i
(V) 2.
l Verify proper ccble being terminated (Refer to QI-QP-lJ!
)A'W/,4 l
l 11.3-28.2)
Id h I'U8)/
l l a.
Verify caDie and cable connect card agreement lM '@ \\
%d l b.
Verify jumper cable installed (if required) lA)Wl l N (V) 3.
Verify cable continuity check perfonned (Refer to dl h
s QI-QP-11.3-28.3) l E yL Q
[
(V) 4. 'l Verify jacket / insulation removal (Refer to QI-QP-ll.3-l l 1
)
R (3
[
28.4):
l l l l
74i I
a.
Vertfy inner conductors insulation not cut ld l l
_ hl k (if applicable) l l l l
'-4 99 1.-
I b.
VeHfy.f ackets/ insulation squarely cut
'd l l
7 5'
5 c.
VeHfy proper length of exposed conductors Ml 9
!O N
i (V) 5.
Verify oroner tools (Refer to 01-OP-ll.3-28.5):
ll 5
N NOTE-Aeolienkle only when this insoection is l l l
actually observed.
!I i
a.
Verify compression tool calibration
! d l
t b.
Verify appropriate dies are utilized ld l l
i (V) 6.
Verify cable shielding (Refer to QI-QP-ll.3-28.6) lAll4l, l l
(V) 7. l Verify proper lug or connector / connections type, size, l g,/ Ql l
l and. final crimps (Refer to QI-QP-11.3-28.7) l l
F j
(V) 8.
l Verify creoaration of surfaces and bolted connections i
i M
i (Refer to QI-QP-11.3-28.8)
I l
- W t
c.
Verify proper surfaces preparation IM4l M
H b.
Verify proper hartbeare AlAl D
c.
Verify torque requirements IA/lA l lM (V) 9.
l Verify tenninations (Refer to QI-QP-11.3-28.9)
Id I (V)l0. l Verify minimum bend radius, inner cabinet, routino and dI N.
and cable secure (Refer to QI-QP-ll.3-28.10) l
!l i
s
~'
(V)11.
I Verify cable identification (Refer to QI-QP-11.3-28.12) ! # !
i
(.W)12e' Verify splicing (Refer to. QI-QP-il.3-28.13) vf l (Continued).
I
_ ~
+
___....-,,,---__,-,,,y,w,,-y_.__,.,%.~.-e.,.,.,-,-.-.,.,
/
./
c:.
CCMANCHE PEAK STEAM ELECTRIC STATICN
((~jY //#
INSPECTION REPORT QI-QP-11.3.-28, Rev.,.-
E
! l a!
in.v C A *' F uo.
INSFECTICN ATTalauTES l
-' m.m
@ al Ei (V) 13.1 Verify orocer documentation (Refer to OI-QP-11.3 ' 28.14); d i I
(V) 14.1 VeM fy comoonent installation (Refer to Of-OP-lA/l A l I
i 11.3-28.15)
I I I I
i
_(W) 15.1 Verify heat shrinkable nuclear cable sleeves (Refer to lhlAl i
I OI-0P-11.3-28.16) i I I JW) 16.1 Verify pin / plug orientation & continuity check perfonnedlA)lAl l (Refer to Of-0P-11.3-29.17)
I I I L
(V) 17.i Verify connector free from damage (Refer to 01-0P-LAM I I
i 11.3-28.17)
I l.I I
(V) 18.1 Verify intemal secaration (Refer to 01-0P-11.3-28.11)
I t4 1
(W) 19.1 Soare conduit connection instrument oort clucced 1, ene. WIAI I
~
l m,M (Refer to of-co-11 1 9A ti i I i i
I
! l 1 i
i e i I
I i l i
1 I i l
1 i
ll Iil l
l I i i i
I I ! l l
7l.
.c
- i ;
i I I i I
i i I I i
8 i i i i
I I I i
1 1
i l l
4 l ' -
,\\ l t I
f I
1 I l 1
I 1 I I d
REMARK 3: (cws3.,Mc3,ETc.)
i SOM
/fo V6 l
8 23 2S-5/- OtsY 2 2o
[fg yy I
.DGA / 7'llo 2 2 - 2.-
dT~~/Y67,caj. &
7 gep g hD 0T~~ I l W, / 2 d al 23 cal. dne.
Ykb is no b -/de hM /k.
i i
no anc sca M cAn NedE-gs-Osgif 4./,,
l.R. CLOSED g y
l StGNATURE m
RE M y_E B1]
-y LEVEL II' OATE: 4I--50-.f5 l
OO&d AN CHE PEAM STEAM EiJCMIC STATICN y
9 INSPECTICN REPCRT gg g /-
jaEET-3 7 M M m. m rrnuc w as WX
--r.on p/AN/8 a.
mm _w r.ca 62A8 90 7 Ad CARM 4/IS eem /33#
CLASS 1E CABLE TERMINATION 2
mm a v.
mr. ac. occ. a nav. a cmmen me.
asumma cm.m m. :ceir-ac.
ES-100 s 1e OI-OP-11.3-28. Rev. / 4 T00'. O A/ f KIT-A/>4 A
e
?
C I" E CNN OM d""*-
OP"yt, mayassut.T E meernou consuTun, au. mucasu iTum sarePacTour
[
rir44&O 7-/ 5 f(3 ou m aTa 0 merectum comm.stus, unearisecront rTem ustus am.aw 3
se N
usSPECTION ATTRIBUTES gag l
m a e
l l
(V) 1.
keHfy flex conduit installed (Refer to Of-OP-11.3-29.1) /
(v) 9 keriev inetv.nnene enan. anna it anna.e+4nn m1. inn.d l/dfl l
l(e.f.,+n nr.no.11 1.pn ti I.j.. i l
dl l
(v) 1 k e4ev nenn.,nnht. s.4nn +.-4n.+.a (o.s.,en nr.no.
hi 2.9n 73
'I
~
n.
Verifv enhie and cah4e eennect card a6..-- nt V
l l
h verifv finnner enhle installation (if reeutred)
A/ M I
(V) 4.
kerify cable continuity check eerfomed (Refer to h
lT br-Op-ti.3-2s.3) i I2 keMfy oroner lua or connector / connections tvoe. size and Y l
(v) c
.==
hinaln,4.nne to.<., +n ni no.11 1.9e 7) l 9 (V) 6.
keMfy temination (Refer to 01-0P-11.3-28.9)
'V l %
(V) 7.
keMfy minimum bend raduis, inner cabinet routing, and V
I table secure (Refer to OI-OP-11.3-28.10)
M
'kerify cable identification- (Refer to OI-OP-11.3-29.12) IV tvi e (V) 9.
keMfy oroner decisnentation (Refer to OI-OP-11.3-28,14) V.
C (V) 10.\\ keMfy component installation (Refer to OI-OP-11.3-28.151A/ld i
3 (V) 11.
Verify pin /pluc oMentation and continuity check per.
lA/lAi O
Ifamed (Refer to OI-OP-11.3-29.17) l l l (V) 12.
Verify mmmer free fram daninco (Refer to OI-OP-11.3-lNI/91 l
Pn 17) l l/l l
(V) 13.
VeM fy internal secaration (Refer to OI-0P-11.3-28.11) l #1 l i
i l
I l l
E
$p.02.~R e O /&
W
- I 5#
D6 A - Ibb 95 A-l fRN E /2 4 9 S w e-10 c isdo bis l3 Rh ;d' To F/e x l
r
a== =
i=T i..T.-
sv #9 u* ~.mA C A/ /9-A/ A-rs
/v i
oc a n cTsa i
,e h(5 M g 4 T. R @ @
REVIEWED BY:
A LEVEL II 8,l'E0 ~ ~ * 'l
"" $.99.2s o
i
%]"'*I.T.NO.-
1 E
i
i 00MANCHE PEAK STEAM Ei Z0utC STATICN 1
1 n.er-
-r inmem eeny,sf l*ET-T/ A / 7 cant t *Mr/ot/3 2W Nm.
/ srnucw= !ax Kum 13.5
.ar.ce,
er.c=
m w_
OJA6 407 ^
class 1E CABLE TERMINATION d
m a v.
mr. e,c occ. a nuv. a enames so.
ms.aama cm.m caw. caur.ac.
OI-OP-11.3-28. Rev. /la TOOL e M M KIT-A/A2 a
ES-100 s 2 e
C I" E on U%N"" CIM DepecTrom ma"res?:om men asma.ra
[aspernou castzrso, as t. Appusaas.z noe sawacTone
/
ffffahaa) 'J-/ *f-43 a
-an=.
==nr=, -=r as-u== mo-N g,",
INSPECTION ATTM18UTES
- Isarg e
(V) 1.
VeMfy flex conduit installed (Refer to 01-OP-11.3-28.1) Vi l l
(v) 7 Weriev inet nn ne enar enndnie enanar+4nn ntnaned All4l I
l(Qa#se +n nf no.11 7 7m 11 I
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