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| {{Adams | | {{Adams |
| | number = ML20212P737 | | | number = ML20210S473 |
| | issue date = 08/21/1986 | | | issue date = 02/10/1987 |
| | title = Insp Repts 50-445/86-06 & 50-446/86-04 on 860201-0331. Violations Noted:Failure to Address Spec Criteria for Cable Installation in Procedures,Improper Cable Placement & Failure to Install Cable Support Grips | | | title = Ack Receipt of 861009,31 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-445/86-06 & 50-446/86-04 |
| | author name = Barnes I, Michaud P, Phillips H, Wagner P | | | author name = Johnson E |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Counsil W |
| | addressee affiliation = | | | addressee affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| | docket = 05000445, 05000446 | | | docket = 05000445, 05000446 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-445-86-06, 50-445-86-6, 50-446-86-04, 50-446-86-4, NUDOCS 8609030256 | | | document report number = NUDOCS 8702170638 |
| | package number = ML20212P724 | | | title reference date = 01-22-1987 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 13 | | | page count = 2 |
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| APPENDIX B, CONSTRUCTION INSPECTION REPORT U.S. NUCLEAR REGULATORY COMMISSION
| | In Reply Refer To:' FEB I O INT Dockets: 50-445/86-06 50-446/86-04 Texas Utilities Generating Company ATTN: Mr. W. G. Counsil Executive Vice President 400 North Olive L.B. 81 Dallas, Texas 75201 Gentlemen: |
| | Thank you for your letters of October 9,1986, October 31, 1986, and January 22, 1987, in response to our letters and Notice of Violation dated August 26, 1986, ar.d December 30, 1986. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintained. |
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| ==REGION IV==
| | Sincerely, |
| NRC Inspection Report: 50-445/86-06 Permits: CPPR-126 50-446/86-04 CPPR-127 Dockets: 50-445 Category: A2 50-446 Applicant: Texas Utilities Electric Company (TVEC)
| | < |
| Skyway Tower 400 North Olive Street Lock Box 81 Dallas, Texas 75201 Facility Name: Comanche Peak Steam Electric Station (CPSES), Units 1 & 2 Inspection At: Glen Rose, Texas Inspection Conducted: February 1 through March 31, 1986 Inspectors: zg [.#/ | | svaal signed By |
| H. S. Phillips, SenioTr Resident Reactor 7 Mf4 Date Inspector (SRRI), Construction, Region IV CPSES Group (paragraphs 1, 2, 3, 4, 5, 6a, and 9)
| | /Tl HHf E. H. Johnson, Director Division of Reactor Safety and Projects cc: |
| @ C. 03 % h B/ie/66 Date P. C. Wagner, Reactor g pector, Region IV CPSES (paragraphGroup 7 )
| | Texas Utilities Electric Company ATTN: G. S. Keeley, Manager Licensing Skyway Tower 400 North Olive Street Lock Box 81 Dallas, Texas 75201 RIV:CPRTh CPRT .5F ' |
| 8w Tb/f94 F P. Michaud, Reactor Inspector, Region IV Date (paragraph 8)
| | PCWagner:gb IBarnes 2. /1 /87 |
| ' | | /"DRP EHJohnson 2./$ /87 1/y/87 l$P!888! 8?88;go / {' D PDR \ |
| Consultants: EG&G-J.11. McCleskey (paragraphs 2, 4, and 6b)
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| 8609030256 e60826 DR ADOCK0500g5
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| | = Texas Utilities Generating 2 Company Juanita Ellis President - CASE 1426 South Polk Street Dallas, Texas 75224 Renea Hicks Assistant Attorney General Environmental Protection Division P. O. Box 12548 Austin, Texas 78711-2548 Administrative Judge Peter Bloch U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Elizabeth B. Jahrson Administrative Judge Oak Ridge National Laboratory P. O. Box X, Building 3500 Oak Ridge, Tennessee 37830 Dr. Kenneth A. McCollom 1107 West Knapp , |
| | Stillwater, Oklahoma 74075 Dr. Walter H. Jordan 881 Outer Drive Oak Ridge Tennessee 37830 Anthony Roisman, Esq. |
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| Parameter-J.' C. Gibson (paragraph 7)
| | Executive Director Trial Lawyers for Public Justice 2000 P. Street, N.W. Suite 611 Washington, D.C. 20036 Texas Radiation Control Program Director bec to DMB (IE01) |
| Approved: bw P/2-1/F6 1. Barnes, Chief, Region I Date CPSES Group Inspection Summary Inspection Conducted: February 1 through March 31, 1986 (Report 50-445/86-06)
| | bec distrib. by RIV: |
| Areas Inspected: Routine, unannounced inspections of Unit I which included a plant tour of the reactor, safeguards, electrical control and auxiliary buildings; applicant actions on previous inspection findings; structural steel and steel support safety-related components; and safety-related pipe supports and restraint Results: Within the four areas inspected, no violation or deviations were identifie Inspection Conducted: February 1 through March 31, 1986 (Report 50-446/86-C4J Areas Inspected:
| | *RPB * MIS System |
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| | *RRI-0PS *RSTS Operator |
| Routine, announced and unannounced inspections of Unit 2 which included plant tours of the reactor, safeguards, diesel generator, electrical control, and auxiliary buildings; applicant actions on previous inspection findings; structural steel and steel supports; reactor coolant loop pipe welding; safety-related components, and electrical cable installatio Results: Within the seven areas inspected, two violations (failure to address specification criteria for cable installation in procedures and improper placement of cables, paragraph 7; failure to install cable support grips as required, paragraph 7) were identifie l l
| | *RRI-CONST *R&SPB |
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| | *T. F. Westerman, RSB DRSP V. Noonan, NRR R. Martin, RA L. Chandler, OGC *RSB |
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| | *RIV File J. Taylor, IE |
| | *D. Weiss, RM/ALF J. Conklin, IE |
| | *I. Barnes, CPTG * Project Inspector |
| | *R. Hall P. Wagner |
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| | ! Leg # TXX-6213 File # 10130 IR 86-06 |
| | * TEXAS UTILITIES GENERATING COMPANY IR 86-04 SKYWAY TOWER . 489 NORTH OLIVE STREET. LB. 88 . DALLAS, TEXAS 7M01 January 22, 1987 ~~~- ' |
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| | %?&^*.L #.U E ; # ? 6198'l Mr. Eric H. Johnson, Director I. , _ |
| | Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission L-611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 SUBJECT: COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) |
| | DOCKET NOS. 50-445 AND 50-446 INSPECTION REPORT NOS.: 50-445/86-06 AND 50-445/86-04 SUPPLEMENTAL RESPONSE FOR INFORMATION TO NRC NOTICE OF VIOLATION (N0V) ITEM A(2) |
| | REF: 1. TUGC0 Letter TXX-5037 from W. G. Counsil to E. dated October 9, 1986. |
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| DETAILS Persons Contacted Applicant Personnel
| | 2. TUGC0 Letter TXX-6071 from W. G. Counsil to E. dated October 31, 1986. |
| ***J. Barker, Executive Assistant to Executive Vice President, Texas Utilities Generating Co. (TUGCo)
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| ***J. Beck, Vice President, TUGCo
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| ***T. Brandt, Quality Engineering (QE) Supervisor, EBASCO ,
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| ***R. Camp, Assistant Project General Manager, Unit 1, Impell~ .
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| ***W. Counsil, Executive Vice President, TUGCo .
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| J. Crim, Civil Structural Engineer, TUGCo B. Dacko, Licensing Engineer, TUGCo
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| *P. Halstead, Manager, Quality Control (QC)
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| C. McClaskey, QE, EBASCO - - .
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| * Merritt, Director of Construction, TUGCo -
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| * Streeter, Director of Quality Assurance (QA), TUGCo -
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| ** Redding, Executive Assistant, TUGCo
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| ** Tyler, CPRT Program Director, TUGCo J. Walker, Quality Engineer, TUGCo Contractor Personnel B. Baker, Welding Engineer, Brown & Root Inc. (B&R)
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| 8. Bhujang, Principal Engineer Civil / Structural, Gibbs & Hill Inc. (G&H)
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| H. Porter, Welding Engineer, B&R G. Purdy, QA Manager, B&R D. Wheland, QA Records Review, B&R C. Woodard, Paper Flow Group Review, B&R B. Wright, Welding Engineer, B&R The NRC inspectors also interviewed other applicant and contractor personnel during this inspection perio * Denotes personnel present at the February exi ** Denotes personnel present at the March exi *** Denotes personnel present at both exit . Applicant Actions on Previous Inspection Findings (Closed) Unresolved Item (445/8514-U-02; 446/8511-U-01): SDAR files do not contain sufficient information. The NRC inspector reviewed the following reportable /nonreportable construction deficiency file Nos. CP-82-12, CP-84-17, CP-83-20 and CP-84-16, CP-82-13, CP-84-14, CP-84-19, and CP-84-20, respectively, and found that the files now contain complete auditable documentation, l
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| 4 (0 pen) Unresolved Items (445/8516-U-01; 446/8513-U-01): TUGCo Task Force (TTF) to review SDAR system. The NRC inspector reviewed the status of the TTF effort and found it to be incomplete. The TTF review covers only construction deficiencies which have not been inspected and documented in NRC inspection reports. The following files were reviewed and were complete: (1) reportable items CP-82-12, CP-84-17,andCP-83-20,and(2)nonreportableitemsCP-82-13, CP-84-14 and CP-83-16, CP-84-19, and CP-84-20. From a preliminary list of completed items, only two hardware issues were ready for inspection; 1.e., the " George Washington Bridge" weld failures and a Chiller System room flooding evaluation;- The Chiller System was selected and the NRC field inspection verified corrective actio At the end of March 1986 the status of the review was 87 still in review process, and 36 completed and ready for NRC inspection., ,
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| - (0 pen) Unresolved Item (445/8516-U-02;~446/8513-U-02): TTF to review IE Bulletins. NRC inspectors have previously' inspected TUGCo's system for receiving, distributing, and reporting on IE' Bulletin These inspections were documented in NRC Inspection .
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| Reports 445/84-07, 446/84-06; 445/84-22, 446/84-07; 445/84-29,
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| 446/84-10; and_445/85-16, 446/85-1 These previous NRC inspections consisted of a review of'IE Bulletin files for the period 1975-1984 for Units 1 and 2 and concentrated on evaluating the TUGCo system for handling IE Bulletins. During this
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| inspection, the NRC inspector determined that IE Bulletins 75-05, 75-06, 76-06, 77-04, 77-05, 77-06, 77-08, 79-01, 79-28, 80-18, 81-02, 81-03, 83-05 and 84-03 required either repair, rework, replacement, or engineering evaluation. These IE Bulletins are considered open pending an NRC field inspection of selected hardware or engineering evaluations required by the IE Bulletin.
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| ; In addition to the previously referenced IE Bulletins, IE Bulletins 85-01, 85-02, and 85-03 will be inspected after the TTF completes their review of their present system for handling IE Bulletin Neither the IE Bulletin files nor the actions taken were ready for inspection. The records were still not in the QA vaul No violations or deviations were identifie . General Plant Inspections, Units 1 and 2 At various times during the inspection period, the NRC inspector conducted inspections of the Unit 1 and 2 reactor, safeguards, electrical / control, auxiliary buildings, and the Unit 2 diesel generator building. Almost all of the rooms in these buildings were inspected to observe current work
| | ==Dear Mr. Johnson:== |
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| | We have reviewed your letter dated December 30, 1986, requesting additional information to our responses referenced above regarding NOV 445/8604-V-02 (Item A(2)). We hereby respond to the request for supplemental information in the attachment to this letter. |
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| -. , | | Very truly yours, h th b W. G. ouns 1 By: [, . / |
| | G. S. Keeley W/y Manager, Nuclear ticensing RSB/amb:lw Attachment c - NRC Region IV (0 + 1 copy) |
| | Director, Inspection and Enforcement (15 copies) |
| | U. S. Nuclear Regulatory Commission Washington, D. C. 20555 |
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| activities or major safety-related equipment which was stored in plac The storage inside these buildings and the area for steel supports located just outside Unit 2 were also inspecte A special inspection was performed in Unit 1 during TUGCo's self imposed stop work which resulted from the expiration of the Unit 1 construction permit CPPR-126. The NRC inspector observed no unauthorized work activit NRC licensing letter dated February 10, 1986, extended the subject permit to August 1, 198 During this inspection period, two backshift inspections were performed on the second shift (4-12pm). Work activities in the Unit 2 reactor, safeguards, and diesel generator buildings were observed. The NRC inspector also observed the cleaning of the Unit 2 condensate storage tank. Two minor unsatisfactory in place storage conditions were identified; i.e., in Rooms 73 and 74 in the Unit 2 safeguards building, the splined shafts of the feedwater pumps h61 been decoupled from the motors without the machined surfaces being covered and protected. Workers in this area immediately covered these surfaces and the NRC inspector !
| | Mr. V. S. Noonan Mr. D. L. Kelley |
| considered this matter close The NRC inspector observed the following Unit 2 work activities:
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| ACTIVITY BUILDING DESCRIPTION ROOM RESULTS Welding of SGB Per drawing E2 1703 electrical Room 83 and 1703-0 ground cabinet T22-KEB-J-1 In place storage SGB Access to these breaker control Room 83 components was controlled cabinets for: safety and in place storage was injection pump #21, satisfactory. Components RHR pump #23, were protected from auxiljary feedwater overhead weldin pump #21, component cooling water pump
| | a vunsuov er nus cruurua mcmc corunn b ' |
| #21, and incoming breaker BOS 2A In place storage, SGB Room 80 This material was two cable reels, properly identified and orange color code, store W-706-6 and W-706- Ir place storage SGB In place storage letdown heat Room 80 satisfactor exchange .
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| . Welding of station SGB Drawing BRP-SW-2-SB-03 service water lin Room 53 Welds 1A and 7A, cleanliness and fitup, were acceptabl Welding of diesel SGB Room 85 In process weld per generator ski Drawing MSB-2605-D 601 by welder BJI using WPS10046, Weld Data Card 84-7146-2-3003, and
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| Procedure CCP-22. Weld current being used was as required. Thirteen portable weld ovens in this area were checked
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| and were acceptabl Welding of structural SGB Observed 3 piece parts steel suppor Room 77 (C23G-2-8835-1-01) that were fillet welde These welds were measured to be greater than the required 1/4 inch. The weld was made by welder (symbol COT). Electrical SGB Witnessed part of terminatio Room 103 termination operation of conductor NK028373, points 1-12, in junction box JB 2S-922 and appeared to be acceptabl Completed welding on RCB The 1-inch plate main steam line none (6041-2-5) shown on restrain , drawing MS2-003-414C72K had a rounded indication which initially appeared unacceptabl A review of the visual acceptance i' criteria in ASME Section III, Division 1, subsection NF, showed it to be acceptabl No violations or deviations were identifie I l
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| | . Attachment to TXX-6213' |
| | January 22,--1986 Page 1 of 2 |
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| | NOTICE OF VIOLATION ITEM A(2) 446/8604-V-02 SUPPLEMENTAL REQUEST FOR INFORMATION In your response to Item A(2), you mention that problems related to the overflowing of electrical cable from the cable trays that were identified by the NRC inspector had been previously identified by applicant personnel and were in the process of being reworked. Accordingly, you did not agree that the NRC identified condition was a violation and, therefore, did not provide the information required by the NOV. |
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| 4. Structural Steel and Steel Supports, Units 1 and 2 The NRC inspector inspected structural steel and supports inside and outside containment. Since the work had been completed in most instances, the completed work and records were inspected and reviewed instead of observing in process work activitie Reactor Building Containment Liner Welding, Unit 2: The NRC inspector reviewed the Final Safety Analysis Report (FSAR),
| | Based on our review of the information provided in your response and additional information provided by members of your staff, we cannot agree that the cited condition had been, or necessarily would have been, identified as a result of the rework that had been undertaken. While we agree that many of the same cables were involved in both the NRC identified condition of overflowing cable tray siderails and the rework being conducted, we disagree ; |
| paragraphs 3.1.5 and 3.8, to identify the design and structural requirements. G&H Specification 2323-SS-14 implements FSAR commitments and describes how the containment liner steel is designed to meet -the pressures and temperatures from a spectrum of loss of coolant accidents and secondary system ruptures. A review of this specification indicated to the NRC inspector that it meets the proposed American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division 2, Subgroup on Concrete Components, and American Concrete Institute (ACI) 359. Chicago Bridge & Iron (CB&I) Contract 74-2428 and associated file folders (Nos. 3.0, 4.1.2, 4.1.5, 5.1, 5.2, 5.5, 6.1, 7.2.1, 7.3, 7.4, 7.6.3, 7.1.1, 7.7.2, 7.7.3, 7.9, 7.10, 8.1, 8.4, 8.5, 8.6.1, 8.6.2, 8.7, 8.9, 8.10, 8.11, 8.12, 8.16.2, 8.19 and radiographic film) were reviewed to determine whether the steel liner was assembled and installed as required. Four specific welds in the containment liner were chosen for detailed review. For each of the welds, the file folders identified the following: weld unique identification, location, weld procedure used, weld procedure qualification, weld material, weld material certification (chemical and physical), welder identification, welder qualifications, nondestructive examination (NDE) records, NDE procedures, NDE procedure qualifications, NDE inspection records, NDE performed at specified hold points by qualified inspectors using appropriate test equipment which was
| | that the NRC identified problem would necessarily have been resolved by pulling the cables back to remove interlacing and then reinstalling these cables in the same size cable tray. In addition, the NRC inspector did not identify any QC hold tags (indicating an identified problem) during the NRC inspection. |
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| | SUPPLEMENTAL RESPG : TO ITEM A(2) |
| Nonconformance reports (NCRs) were included in folders 3.0 and These reports showed a description of the problem, review and recommended corrective action, review and signoff for the completed NCR. File folder 8.6.P. was an NCR control list which showed the various steps for each NCR, with a signoff and date for acceptanc Onsite receiving reports showed inspection of the required document The containment steel liner welding records were found to be in order and are stored onsite in the permanent plant records vault (PPRV), Unit 1 and Unit Safety Injection Vertical Restraint Welding, Unit 2: The NRC inspector reviewed paragraphs 3.2 and 6.3 in the FSAR to identify the design and structural requirements. G&H Specification 2323-SS-16B
| | As a result of discussions with the NRC Resident Inspector and our review of this violation, we have determined that a revision to our response is required. The revised response below will provide the supplemental information requested. |
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| | 1. Reason for Violation f We admit the violation, and the requested information follows. |
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| implements the FSAR commitments and describes how the Safety Injection System (SIS) is designed to meet the reactor coolant cooling requirements of a design bases acciden The SIS pipe whip vertical restraint work was divided into eight packages, an upper and lower package for each of the four reactor coolant loops in the reactor containment building. The assemblies are located in each of the reactor coolant pump rooms in the reactor containment building. The supports were constructed using ASME SA540, B23 and B24, class 2 steel. Westinghouse Inc. contract CP-0001 and two of the eight associated B&R document packages (travelers CD84-318-02-8902 and CD84-316-02-8902) were reviewed by the NRC inspector to determine that the installation of this portion of the SIS was accomplished as required. Other documents included in the review were Westinghouse Drawing 22415, Sheet 5, and Quality Release 53333; Teledyne P0 No. 217359; and material certification for Heat No. D744 During the onsite assembly and partial fabrication of the SIS pipe whip vertical restraint, field travelers were used to control the work. Esch traveler identified steps in the work to be performed, hold points for QC inspection, and review and approval of the completed traveler package. The package contained weld history records fer each weld which included or identified the weld location,
| | The deficiences noted in this violation involving unacceptable cable installation'were the result of corrective actions in progress per NCR E-85-101983 and inadequacies in the cited TUGC0 Inspection Instruction QI-QP-11.3-26 and B&R Construction Procedure EEI-7. Specifically, criteria governing the installation and inspection of electrical cable were found insufficient to prevent the improper cable installation identified in the NOV. |
| ! fit up inspection, weld procedures, welder ID, and the weld filler material log. This log identified the issued weld material, the welder withdrawing the material, amount withdrawn, amount returned, and dates. Also included or identified in the package were NDE records, NDE procedures, weld repair records, weld procedures, visual inspection reports, magnetic particle inspection reports, engineering as-built drawings, design change authorizations (DCAs), and a structural assembly verification card (SAVC). The SAVC is a written checklist which verifies that the materials used in the assembly are traceable to material certification documents. One NCR was written against package CD84-316. This NCR described the problem which was reviewed and identified and the corrective action which was reviewed and approved. .0nsite documentation providing support to the packages were NDE proceduro qualification, NDE inspector qualification, weld procedure qualification, and welder qualification records. Other supporting packages from Westinghouse contained the chemical,
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| physical, and Charpy V-notch test result c. Diesel Generator Skid Support Steel, Unit 2: The NRC inspector reviewed FSAR paragraphs 3.2, 3.8, 8.3, 9.5.5, and 9.5.8 to identify the design and structural requirements. G8H Specification 2323-MS-034
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| implements FSAR commitments and descrihes how the diesel generators are designed to meet the requirements of a design basis acciden Delaval Turbine Inc., Engine and Compressor Division Order No. 76001/04, receiving inspection reports (RIRs), and Drawings MSB-2606-DG36-WZ, MSB-2605-DG37-WY, and MSB-2605-DG37-XA were reviewed by the NRC inspector to determine whether installation of
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| - | | 2. Corrective Steos Taken A request for engineering clarification (RFIC E-11180) was initiated on March 4,1986 requesting engineering to evaluate cable tray nodes T240SF001, 02, 03, 04, and 05 for siderails and to document installation l |
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| selected skid steel and piping components of the Train B diesel generator were accomplished as require DCAs were issued against the skid support steel and associated cooling water lines. The required DCA work was performed onsite. The skid offsite and onsite construction records were found by the NRC inspector to be in order and stored in the PPRV and the Interim Records Vault (IRV).
| | i A design change (DCA #24,289) was issued on April 4, 1986, to replace the |
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| The diesel generator skid and parts were receipt inspected, stored, installed, and inspected by qualified inspectors using appropriate test equipment. The specifications of the materials and componer.ts used in the assembly of the skid were verified. The required manufacturing and construction records included chemical and physical test certifications, drawings, and installation records which were apprcpriately verified by QC personne The NRC inspector determined that the PPRV and IRV documents were legible, retrievable, and showed that required inspection activities were complete Documentation for QC and NDE personnel used both offsite and onsite for this project show that they were qualified at the time inspections and tests were performed. The weld and NDE procedures that were used had documented qualification records. The welders used for the modification were documented as being qualified to the procedures used for the welding. The QC and NDE personnel used appropriate testing equipment which was calibrated at the time of the testing and was scheduled for calibration at regular interval During the modification of the diesel generator steel skid supports and coolant lines, weld history records were maintained for each of the 20 welds reviewed. These records included or referenced NDE records, NDE procedures, weld procedures, weld material records, welder identification, and weld repair record The weld material documented the date, size, class of the weld, welder identification, heat number of material and amount issued / amount returned, and the weld procedure. The modification records contained NCRs which described the problem, corrective action, and contained signoffs for review and approva d. Reactor Makeup Water Storage Tank, Unit 2: The NRC inspector reviewed FSAR paragraphs 3.2, 3.8.4, and 9.2.3 to identify the design and structural requirements. G&H Specifications 2323-55-17 and 2323-MS-67B implement FSAR commitments and describe how the reactor make-up water storage tank (RMWST) is designed to meet the initial containment cooling requirements of a design bases accident. The RMWST is constructed from reinforced concrete with a stainless steel liner, which is partitioned by a rubber membrane barrier to separate the water from the air inside the tank. The welded liner is constructed of 3/16 inch ASTM A240, 304L steel. A review of this specification, with respect to the RMWST, indicates that the tank meets the requirements of ASTM A24 CB&I Contract 83426 and associated file folders (Nos. 3.0, 4.1.3, 4.1.4, 4.1.5, 5.1, 5.2,
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| 8.6.1, 8.6.2,=8.9, 8.10, 8.11, 8.12, 8.16.1, 8.16.2, 8.17, and 8.19)
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| were reviewed to determine that the steel liner installation for the RMWST was accomplished as require A review of site records showed that the tank steel liner was dimensionally inspected during onsite. receiving, nondestructively tested, stored, and inspected for fitup prior to welding. The i specifications of.the materials and components used in the assembl of the RMWST were. verified and included chemical and-physical test ,
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| certifications. . Documents also showed that the construction of the RMWST met the G8H specification and that the installed vessel measurements and location were-within design tolerances, and that the
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| ;. The PPRV documents were legible, retrievable and showed that required
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| inspection activities were completed. Documentation for QC and NDE personnel used both offsite and onsite for this project show that
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| they were qualified at the time inspections and tests were performe The inspection personnel used appropriate testing equipment which was calibrated at the tine of the testing, and was scheduled for
| | 12" tray nodes with 18" width trays to correct the stated cable overfill and irregular routing problems. Construction Deficiency Report CDR-87-801 was issued on January 19, 1987 to identify the need for reinspection of existing cable installations for cable overfill conditions. If the disposition of the CDR indicates that corrective action is required, a CAR |
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| calibration at regular interval ,
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| During the construction of the steel tank liner, weld history records were maintained for each weld which included: NDE records, NDE procedures, NDE procedure qualification, NDE inspector. qualification l records, weld repair records, weld procedures, weld procedure j qualification, welder identification, and welder qualification i records. The control list for the nonconformances describes the problem, resolution, action, inspection and acceptance signoff.
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| 5 Structural Steel Design Changes, Unit 1: The NRC inspector selected two design changes for review. DCAs 18728 and 19894 are part of a modification package to change a steel structure in the reactor
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| j containment from nonseismic to Category II. These changes were properly controlled.
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| No violations or deviations were identifie . Unit 2 Reactor Coolant (Rx) Loop Pipe Welding The NRC inspector reviewed the TUGCo FSAR and Quality Assurance Plan to
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| . determine the requirements for controlling special processes such as Rx
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| ! loop welding. These documents stated that special processes are controlled
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| ; by approved or qualified procedures, which include design criteria, codes, standards, specifications, and other special requirements; personnel qualifications; and examinations, tests, and inspections.
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| FSAR Section 17.1.9, " Control of Special Processes," states that audits are to verify the adequacy of selected site and vendor shop activities and the effectiveness of the special process control procedures being-implemente The NRC inspector found that Unit 2 Rx loop welding was accomplished between July 1980 and September 1981. The 1980 and 1981 audit files were reviewed to determine if audits had verified the adequacy of welding to determine.if this special process was effectively controlled. The files in the QA vault did not contain the checklists for all audits performed in 1980 and 1981. This matter was discussed with TUGCo and B&R management, who stated that this information may be in the files at the B&R office in Houston, Texa This item is unresolved pending the receipt and review of all 1980-1986 audit files (445/8606-U-01; 446/8604-U-01).
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| No violations or deviations were identifie . Safety-Related Components, Units 1 and 2 During the general inspections documented in paragraph 3 above, the NRC inspector ~ observed safety-related equipment in both units to determine whether the subject equipment was protected while stored in place (except where access was blocked by construction in Unit 2 and some locked areas in Unit 1). Two specific safety-related components were examined more closely as follows: Component Cooling Water (CCW) Pumps, Units 1 and 2: The NRC inspector reviewed Table 17A-1 of FSAR Volume XIV, Section 17.0 and determined that the CCW pumps are ASME Section III, Class 3 and Seismic Category I. The CCW system provides an intermediate barrier
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| between radioactive heat sources and the Service Water System (SWS).
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| It removes heat from various plant components and must operate during all phases of plant operatio Each system has two 100 percent capacity CCW pumps to provide redundanc The NRC inspector performed an inspection of two Unit 2 Bingham-Willamette pumps after learning from craftsmen that these pumps were in the process of tear down. Startup personnel were contacted to review this work and it was determined that linear indications were found on the cast impellers made from ASTM A216, Grade WCB. According to the documents reviewed, these cracks appeared to be casting shrinkage cracks. B&R had issued NCR M-20,613 and 20,614 dated January 24, 1986. Bingham-Willamette Company letter dated January 9, 1985, documented some discrepancies in the original design concerning running clearances for stationary and rotating wear ring diametrical clearances. This item was also under evaluation per 10 CFR 50.55(e). Resolution of this matter will be tracked as an open item (446/8604-0-04).
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| | . Attachment to TXX-6213 January 22, 1986 Page 2 of 2 |
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| | 3. Action to Prevent Recurrence Inspection Instruction QI-QP-11.3-26 and Construction Procedure EEI-7 have been revised to address the specific requirements of the electrical erection specification in the areas identified in the NOV. An additional inspection attribute has been incorporated into the inspection instruction prohibiting cables from extending above the top of cable tray siderails except where entering and exiting the cable tray. |
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| | 4. Date of Como11ance Implementation of design change DCA-24,289 and associated cable rework is scheduled to be completed by July 1,1987. A change notice (DCN #5) was issued against the Installation Procedure EEI-7 on October 31, 1986. |
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| 12 Containment Spray Pump and Motor Stands, Unit 2: The NRC inspector reviewed FSAR paragraphs 3.2, 3.8, and 6.5.2 to identify the design and structural requirements. G&H Specification 2323-MS-012 implements FSAR requirements and describes how the stands (Serial-Nos. 15210090 and 15210092) are designed to. meet the requirements of a design bases accident. Bingham-Willamette Company, No.'76002/04 and associated files (RIR's 11780/ 12534/13507 and G&H letters 25324, 27896, 29064, 30557, and 30700) were reviewed to determine that the base of the containment _ spray pump and motor-support steel installation (for component numbers CP2-CTAPCS-02 and CP2-CTAPCS-04) was accomplished as required. The skid construction
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| . records were found by the NRC inspector to be in order. .These records are stored onsite in the PPRV and DC The containment spray pump and motor stands'were' receipt inspected,
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| ' stored, installed, and inspected by qualified inspectors. -The specifications of the materials and components used in the assembly of the skid were verified.' The required manufacturing and construction records included chemical and physical test certifications, drawings and construction records which were appropriately verified by quality control personnel. Also-included were checklists used during the-construction which documented the weld metal verification, weld inspections, and procedures, weld
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| procedure approval, and weld procedure qualificatio No violations or deviations were identifie . Electrical Cable Installation During March 1986, the NRC inspector performed an inspection of completed electrical cable installations in the Unit 2 Safeguards Building, elevations 810 feet 6 inches and 832 feet. The inspection consisted of observation of installed cables in cable trays and review of applicable specification, drawing, procedure, and instruction requirement This inspection identified that cables were spilling over the siderails of cable trays T240SF005, 006, 007, 008, and T240SDA91 above area 82 at elevation 810 feet 6 inches, and out of trays T240SF003 and 004 near area 94 at elevation 832 feet. Also at elevation 832 feet. it was identified that cables installed in tray sections 1240SF003 and T240SF004 were not supported (trained to conform to the tray configuration) at the transition from the horizontal to the 45 degree riser sections, and for various distances either side thereo Paragraph 4.2.2.3.a of G&H Electrical Erection Specification 2323-ES-100 requires that all cables be installed in a workman-like manner and that they shall be neatly trained without interlacing. Paragraph 4.2. requires that cables be laid in the trays whenever possible, and to a uniform depth. B&R Procedure EEI-7, Revision 6, dated March 26, 1986,
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| " Cable Pulling," addresses the installation of cables in an orderly manner and stipulates that they are to be laid in the trays whenever possible;
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| -however, this procedure did'not address the installation of cables to a uniform depth. TUGCo' Instruction'QI-QP-11.3-26, Revision 24, dated October 11, 1985, " Electrical ^ Cable Installation Inspection," did not address any of the above specification requirements. . The failure to (a)fullyaddressspecification-requirementsinimplementingdocumentsand (b) to comply with-installation instruction is an apparent violation o Criterion V of Appendix B to 10 CFR-Part 50 (446/8604-V-02).
| | Revision 31 of Inspection Instruction QI-QP-11.3-26 is scheduled to be issued by January 31, 1987, upon completion of requisite training. If required, appropriate corrective action to disposition CDR-87-801 will be completed by July 1,1987. |
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| At elevation 832 feet, it was identified that cable support grips were not
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| , installed at the top of the vertical . risers' containing tray sections T23GECX91 and T24GEDG98. The risers were observed.to be greater than 25 feet high and the installed cables were multi-conductor, No.18 AWG through 12 AWG. Paragraph 4.2.1.5.b(2) of G&H specification 2323-ES-100 states, "One. cable support shall be provided at the top of the vertical raceway or as close to the top as is practical." The specification further
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| . defines, however, that for the aforementioned cable sizes, no support grips would be required if the total height of the vertical riser was less than 25 feet. The NRC inspector reviewed B&R procedure EEI-23, Revision 1, dated July 21, 1983, " Cable Support Grip Installation," and TUGCo Instruction QI-QP-11.3-26, Revision 24, dated October 11, 1985, " Electrical Cable Installation Inspection." Both of these documents reflected the !_
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| specification requirements. The failure to install cable support grips on cables at the top of cable tray risers containing tray sections T23GECX91 and T24GEDG98 is an apparent violation of Criterion V of Appendix.B t CFR Part 50-(446/8604-V-03). , Safety-Related Pipe Supports and Restraints, Unit 1: The NRC' inspector verified the dimensions and locations of eight large bore pipe anchors located on two main steam, three safety injection, and three component ,
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| cooling water lines. The physical ~ dimensions and locations were compared with the as-built drawings to determine their accurac ~
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| Three of the as-built drawings were in agreement with the actual .
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| configuration of the following lines: SI-1-037-005-532A, SI-1-339-001-C41A, and CC-1-198-002-C53A. Two anchors were in agreement with the'as-built drawings for lines MS-1-027-051-553A and MS-1-028-049-C553 Three additional anchors (CC-1-008-029-533A, CC-1-155-013-543A, and !
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| SI-1-300-003-522A) were examined which had QC Hold tags that had been recently applied. The NRC inspector selected and observed'other dimensions that were not affected by the Hold tag and verified that these dimensions were acceptabl No violations or deviations were identifie . Exit Interview Exit interviews were conducted March 4 and April 4, 1986, with the applicant's representatives identified in paragraph 1 of this repor During these' interviews, the NRC inspectors summarized the scope and findings of the inspection. The applicant acknowledged the findings.
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Category:CORRESPONDENCE-LETTERS
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999
Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span
ML20217M5711999-10-20020 October 1999
Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999
Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred
ML20217E7951999-10-12012 October 1999
Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5
ML20212L2891999-10-0101 October 1999
Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases
TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999
Forwards Revised COLR, for Cycle 5 for Unit 2
ML20216J5571999-10-0101 October 1999
Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps
ML20212G0721999-09-24024 September 1999
Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site
ML20212H0461999-09-24024 September 1999
Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820
ML20212F7481999-09-24024 September 1999
Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4
ML20212F1041999-09-23023 September 1999
Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2
ML20212E6661999-09-21021 September 1999
Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure
ML20212D9111999-09-16016 September 1999
Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl
ML20212A7601999-09-14014 September 1999
Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls
TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999
Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC
ML20211P3761999-09-0707 September 1999
Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required
ML20211L9871999-09-0303 September 1999
Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs
TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999
Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl
ML20211K2231999-08-31031 August 1999
Forwards Txu Electric Comments of Rvid,Version 2
ML20211J3801999-08-27027 August 1999
Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted
ML20211G7301999-08-26026 August 1999
Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively
ML20211G1081999-08-26026 August 1999
Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure
ML20211G3441999-08-25025 August 1999
Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2
ML20211B2861999-08-18018 August 1999
Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise
ML20211C4661999-08-18018 August 1999
Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790
ML20210U3981999-08-17017 August 1999
Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred
ML20211C0991999-08-17017 August 1999
Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety
ML20211C4571999-08-16016 August 1999
Forwards Omitted Subj Page of Contractor TER
TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999
Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802
ML20210R6561999-08-13013 August 1999
Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20210S6411999-08-12012 August 1999
Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested
ML20210R2221999-08-12012 August 1999
Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy
ML20210N1101999-08-0404 August 1999
Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
ML20210J2301999-08-0202 August 1999
Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2
ML20210J6071999-08-0202 August 1999
Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2
TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999
Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727
TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999
Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630
ML20210K2321999-07-29029 July 1999
Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted
ML20210G5861999-07-29029 July 1999
Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999
ML20210J0121999-07-27027 July 1999
Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria
TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999
Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES
ML20210F3121999-07-26026 July 1999
Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal,
ML20210D8231999-07-23023 July 1999
Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp
ML20210D3211999-07-21021 July 1999
Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603
ML20210C2931999-07-21021 July 1999
Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld
ML20209H0111999-07-16016 July 1999
Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval
ML20210C3331999-07-16016 July 1999
Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses
ML20209H2551999-07-16016 July 1999
Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230
1999-09-07
[Table view]
Category:NRC TO UTILITY
MONTHYEARML20062G5471990-11-26026 November 1990
Forwards Summary of NRC Understanding of Current Status of Unimplemented GSIs at Facility
ML20058H5501990-11-14014 November 1990
Forwards Insp Repts 50-445/90-40 & 50-446/90-40 on 900918- 1030.Violations Noted But Not Cited
IR 05000445/19900371990-11-0808 November 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-445/90-37 & 50-446/90-37
ML20058G1521990-11-0505 November 1990
Discusses Util 900529 Response to 900402 Notice of Violation.Violations 445/8923-V-01 & 446/8923-V-01 Closed, Per Insp Repts 50-445/89-23 & 50-446/89-23
ML20058G4791990-10-31031 October 1990
Forwards Summary of 901022 Meeting W/Util in Arlington,Tx Re Secondary Plant Reliability Problems at Unit 1
ML20058E6931990-10-29029 October 1990
Forwards Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered on 901010
ML20058D0261990-10-26026 October 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-445/90-36 & 50-446/90-36
ML20058A7121990-10-19019 October 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-445/90-16 & 50-446/90-16 on 900806
ML20058A0971990-10-10010 October 1990
Forwards Insp Repts 50-445/90-31 & 50-446/90-31 on 900807- 0918 & Notice of Violation
ML20062B2211990-10-0909 October 1990
Requests Response to Question Re Facility Cold Overpressure Mitigation Sys Actuation During Accident Events.Response Requested by 901214
ML20059N4711990-10-0303 October 1990
Ack Receipt of Forwarding Rev 8 to Physical Security Plan.Changes Consistent w/10CFR50.54(p)
ML20059K3361990-09-17017 September 1990
Forwards Insp Repts 50-445/90-36 & 50-446/90-36 on 900820- 24 & Notice of Violation
ML20059J9861990-09-13013 September 1990
Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Exam to Be Administered on 901010.Results of Exam Should Be Available within 3 Wks of Completion
ML20059K3581990-09-13013 September 1990
Ack Receipt of 900820 Revised Response to Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57
ML20059K3561990-09-13013 September 1990
Ack Receipt of 900904 Response to Violations Noted in Insp Repts 50-445/90-22 & 50-446/90-22
ML20059J6171990-09-11011 September 1990
Forwards Insp Repts 50-445/90-30 & 50-446/90-30 on 900723- 0802.No Violations or Deviations Noted
ML20059J2451990-09-10010 September 1990
Forwards Insp Repts 50-445/90-29 & 50-446/90-29 on 900723-27.No Violations Noted
ML20059E2301990-08-31031 August 1990
Forwards Insp Repts 50-445/90-26 & 50-446/90-26 on 900705-0807.No Violations or Deviations Noted
ML20059F3021990-08-30030 August 1990
Forwards Insp Repts 50-445/90-28 & 50-446/90-28 on 900716-20.No Violations or Deviations Noted
ML20059D6511990-08-29029 August 1990
Forwards Insp Repts 50-445/90-34 & 50-446/90-34 on 900731- 0807 & Notice of Violation.Action Already Taken to Correct Hot Standby Operating Procedure Inadequacies & No Response to Violation Required
ML20059D7791990-08-28028 August 1990
Forwards Investigation Synopsis Re Alleged Attempt to Inhibit Employee from Bringing Safety Concerns to Nrc. Investigation Completed in Apr 1990
ML20056B2681990-08-22022 August 1990
Advises That 881130,890313,0526 & 0920 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss Acceptable
ML20059A5891990-08-15015 August 1990
Ack Receipt of 900730 Response to Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19
ML20058M2271990-08-0606 August 1990
Forwards Insp Repts 50-445/90-16 & 50-446/90-16 on 900423-27.Unresolved Item Identified.Inspector Determined That Key Emergency Response Personnel Not Always Proficient in Some Duties
ML20058M2441990-08-0303 August 1990
Forwards Insp Repts 50-445/90-22 & 50-446/90-22 on 900606-0703 & Notice of Violation.Written Response Requested Based on Specifics Contained in Notice
ML20056A1741990-07-30030 July 1990
Advises That Written & Operating Licensing Exams Scheduled for Wk of 901126.Licensee Should Furnish Ref Matl Listed in Encl 1 by 900904
ML20056A1161990-07-27027 July 1990
Forwards Summary of 900717 Meeting in Region IV Ofc Re Const Restart for Unit 2.List of Attendees & Viewgraphs Also Encl
ML20055J1481990-07-27027 July 1990
Forwards Performance Assessment Repts 50-445/90-20 & 50-446/90-02 on 900529-0615.Startup Test Program Conducted in Safe & Prof Manner & Facility Operation Could Proceed Above 50% Power
ML20055J4311990-07-26026 July 1990
Advises That 900601 Rev 7 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Portions of Plan Administrative in Nature & Do Not Reduce Plan Effectiveness
ML20056A0441990-07-25025 July 1990
Grants Temporary Waiver of Compliance from Tech Specs 3.3.2 & 3.6.2.1 Re Containment Spray Sys in Order to Repair & Test Containment Pressure Transmitter 1-PT-0934 W/Unit in Hot Standby
ML20055G7671990-07-20020 July 1990
Ack Receipt of in Response to 900705 Telcon Re Acceptability of THERMO-LAG Fire Barrier Matl.Correspondence Reviewed & Matter Closed
ML20055G8701990-07-20020 July 1990
Forwards Insp Repts 50-445/90-23 & 50-446/90-23 on 900618-22.No Violations or Deviations Noted
ML20055G0541990-07-13013 July 1990
Forwards Insp Repts 50-445/90-24 & 50-446/90-24 on 900618-22 & 25-28.No Violations or Deviations Identified
ML20056A0051990-07-11011 July 1990
Advises That NRC Draft Document Re Concerns Associated W/ Util 891229 Response to Insp Repts 50-445/89-60 & 50-446/89-60 Being Placed in Pdr.Opinions in Draft Do Not Constitute Final Agency Position
ML20055E8231990-07-0909 July 1990
Advises of Maint Team Insp Scheduled for Wks of 901015,29 & 1105 at Plant & Confirms Telcon Between to Mckernon & T Hope Re Insp.Team Plans to Hold Meeting W/Util at Plant Site on 901002-04 to Define Scope of Insp.List of Matls Needed Encl
ML20055E4871990-07-0303 July 1990
Expresses Appreciation for Volunteering to Participate in Emergency Response Data Sys (Erds).Implementation of ERDS Will Prove to Be Beneficial to Both NRC & Util.Survey Designed to Provide Hardware & Communications Info Encl
ML20055D4201990-06-29029 June 1990
Forwards Insp Repts 50-445/90-19 & 50-446/90-19 on 900503-0605 & Notice of Violation.Util Should Review Strike Contingency Plans or Procedures to Assure That Appropriate Plans in Place Before Next Strike Negotiation Deadline
ML20055C7611990-06-15015 June 1990
Concludes That Plant Equipment,Program & Personnel Performance Adequate & That Testing Program Can Continue Above 50% Power Plateau to full-power,per Insp Repts 50-445/90-20 & 50-446/90-20 to Be Issued at Later Date
ML20059M8611990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20248H1751989-10-0303 October 1989
Discusses Submittal of Proprietary & Copyrighted Matl W/O Proper Indication.Guidelines & Procedures to Be Followed Re Proprietary & Copyrighted Matl Provided
ML20248D2341989-09-29029 September 1989
Forwards Emergency Response Guidelines (Ergs) Insp Repts 50-445/89-59 & 50-446/89-59 on 890814-25.Weaknesses & Unresolved Item Noted.Engineering Task Group Developed to Resolve Number of Engineering Items Re ERGs
ML20248A6481989-09-26026 September 1989
Forwards Insp Repts 50-445/89-64 & 50-446/89-64 on 890802- 0905 & Notices of Violation & Deviation
ML20248A5031989-09-26026 September 1989
Forwards Insp Repts 50-445/89-66 & 50-446/89-66 on 890802- 0905 & Notice of Violation
ML20247R5801989-09-26026 September 1989
Forwards Insp Repts 50-445/89-63 & 50-446/89-63 on 890802-0905.No Violations or Deviations Noted
ML20248E2671989-09-22022 September 1989
Advises That 880517 Response to Generic Ltr 88-03, Steam Binding of Auxiliary Feedwater Pumps Satisfactory
ML20248B9591989-09-22022 September 1989
Forwards Insp Repts 50-445/89-65 & 50-446/89-65 on 890802- 0905 & Notice of Violation
1990-09-17
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M5711999-10-20020 October 1999
Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
ML20212L2891999-10-0101 October 1999
Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases
ML20212F7481999-09-24024 September 1999
Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4
ML20212F1041999-09-23023 September 1999
Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2
ML20212E6661999-09-21021 September 1999
Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure
ML20212D9111999-09-16016 September 1999
Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl
ML20212A7601999-09-14014 September 1999
Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls
ML20211P3761999-09-0707 September 1999
Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required
ML20211J3801999-08-27027 August 1999
Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted
ML20211B2861999-08-18018 August 1999
Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise
ML20211C4661999-08-18018 August 1999
Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790
ML20211C4571999-08-16016 August 1999
Forwards Omitted Subj Page of Contractor TER
ML20210R2221999-08-12012 August 1999
Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
ML20210K2321999-07-29029 July 1999
Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted
ML20210D8231999-07-23023 July 1999
Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp
ML20210C3331999-07-16016 July 1999
Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses
ML20209H7501999-07-15015 July 1999
Forwards Safety Evaluation on GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2
ML20209G7421999-07-0808 July 1999
Forwards SER Concluding That Licensee Individual Plant Exam of External Events Process Capable of Identifying Most Likely Severe Accidents & Severe Accident Vulnerabilities & IPEEE Met Intent of Supp 4 to GL 88-20
ML20196L0121999-07-0808 July 1999
Forwards Safety Evaluation Granting First 10-Year Interval Inservice Insp Requests for Relief B-6 (Rev 2),B-7 (Rev 2), B-12,B-13,B-14 & C-9,pursuant to Tile 10CFR50.55a(g)(6)(i)
ML20196K6771999-07-0202 July 1999
Ack Receipt of & Encl Scenario for Comanche Peak Steam Electric Station Emergency Plan Exercise Scheduled for 990721-22.Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives
ML20196J4881999-06-29029 June 1999
Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid as Version 2
ML20196J0401999-06-29029 June 1999
Forwards Safety Evaluation Re Plant,Units 1 & 2 Proposed Changes to Emergency Plan
ML20196E6641999-06-22022 June 1999
Forwards Insp Repts 50-445/99-11 & 50-446/99-11 on 990418- 0529.No Violations Noted.Licensee Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance & Acceptable Radiological Control
ML20207H3801999-06-0909 June 1999
Forwards Insp Repts 50-445/99-08 & 50-446/99-08 on 990503-11.Violations Identified & Being Treated as Noncited Violations
ML20195G3771999-06-0909 June 1999
Ack Receipt of Ltr & Encl Objectives for Comanche Peak Steam Electric Station Emergency Plan Exercise Scheduled for 990721.Based on Review,Nrc Determined That Exercise Objectives,Appropriate to Meet Plan Requirements
ML20207G3291999-06-0707 June 1999
Ack Receipt of Which Transmitted Rev 27 to Comanche Peak Steam Electric Station EP Under Provisions of 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of EP No NRC Approval Required
ML20207E9291999-06-0202 June 1999
Discusses 990526 Request That USNRC Exercise Discretion Not to Enforce Compliance with TS 4.8.2.1e Re Performance of Battery Performance Discharge Test,In Lieu of Battery Svc Test.Concludes Action Satisfactory & Discretion Exercised
ML20207D7111999-05-28028 May 1999
Advises That Info Contained in Licensee 990514 Submittal Re License Amend Request 98-01-0 Will Be Withheld from Public Disclosure,Per 10CFR2.790. 10CFR2.790
ML20207D7011999-05-27027 May 1999
Advises That Info Contained in TU Electric 990514 Submittal (TXX-99115) Re License Amend Request 98-010 Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 990511 Application & Affidavit
ML20207B7241999-05-25025 May 1999
Advises That Info Contained in Application & Affidavit 990507 (CAW-99-1333),submitting WCAP-15004,dtd Dec 1997,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20206Q0031999-05-14014 May 1999
Forwards Safety Evaluation Accepting Licensee Response to GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Steam Electric Station,Unit 1
ML20206P5961999-05-12012 May 1999
Forwards Insp Repts 50-445/99-09 & 50-446/99-09 on 990419- 23.No Violations Noted.Nrc Determined That Releases of Radioactive Waste Effluents Controlled,Monitored & Quantified Well
ML20206N7061999-05-12012 May 1999
Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl
ML20206S5841999-05-11011 May 1999
Forwards Insp Repts 50-445/99-07 & 50-446/99-07 on 990307-0417.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint & Acceptable Radiological Controls
ML20206K0311999-05-0707 May 1999
Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key Encl for Info,Without Encl
ML20206H1701999-05-0606 May 1999
Forwards Copy of Exemption & Safety Evaluation Supporting Requirement in App K to 10CFR50.Proposal Will Use New Feedwater Flow Measurement Sys to Allow More Accurate Measurement to Thermal Power
ML20206K3931999-05-0505 May 1999
Ltr Contract,Task Order 41, Comanche Peak Safety System Engineering Insp, Under Contract NRC-03-98-021
ML20206G1221999-05-0303 May 1999
Discusses 981215 Request That Document, Responses & Further Clarifications to NRC Questions from 980929 Meeting, Be Withheld from Public Disclosure.Determined Information to Be Proprietary & Will Be Withheld from Public Disclosure
ML20206F5711999-04-30030 April 1999
Forwards Insp Repts 50-445/99-06 & 50-446/99-06 on 990329-0402.No Violations Noted.Insp Re Focus on Radiation Protection Program Activities During Unit 2 Refueling Outage
ML20206E5211999-04-27027 April 1999
Discusses GL 96-01 Issued on 960110 & TU Responses, ,970102 & 980502 for Cpses,Units 1 & 2.Determined That Submittals Provided Both Info Requested & Responses Required by GL 96-01
ML20206B3831999-04-23023 April 1999
Forwards FEMA Final Rept for 990311,Comanche Peak Steam Electric Station Medical Drill.No Deficiencies or Areas Requiring Corrective Actions Identified
ML20206B5321999-04-22022 April 1999
Ack Receipt of Ltrs Dtd 970407,09 & 0204,which Transmitted Revs 6 & 7 to Safeguards Continency Plan,Rev 10 to Security Training & Qualification Plan & Rev 29 to Physical Security Plan Submitted Under Provisions of 10CFR50.54(p)
ML20206A2301999-04-14014 April 1999
Refers to Public Meeting Conducted on 990329 in Glen Rose, Tx Re Results of Plant Performance Review Completed on 990211 & Transmitted to Licensee on 990319.List of Attendees Encl
ML20205L8711999-04-0707 April 1999
Forwards Insp Repts 50-445/99-03 & 50-446/99-03 on 990124-0306.No Violations Were Identified.Review of Operability Evaluation Re MOVs Disclosed That Licensee Failed to Include Info About Degraded ECCS Performance
ML20205L1051999-04-0606 April 1999
Informs of Completion of Review of Tuec 980312 Submittal Re GL 97-05, SG Tube Insp Techniques. No Concerns Identified with SG Insp Techniques Employed at Cpses,Units 1 & 2,that Would Indicate Noncompliance with Current Licensing Basis
ML20205F9141999-04-0101 April 1999
Informs That as of 990329 Dh Jaffe Has Been Assigned as Senior Project Manager for Plant
IR 05000446/19920491999-03-24024 March 1999
Discusses Concern That Postulated Fire in CR Could Create Single Hot Short in Control Circuitry of MOVs Resulting in Spurious Operation.Required Hardware Mods Implemented to Control Circuits of Affected Mov,Per Insp Rept 50-446/92-49
ML20204F3311999-03-23023 March 1999
Forwards Discussion Items for 990323 Telcon
1999-09-07
[Table view] |
Text
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In Reply Refer To:' FEB I O INT Dockets: 50-445/86-06 50-446/86-04 Texas Utilities Generating Company ATTN: Mr. W. G. Counsil Executive Vice President 400 North Olive L.B. 81 Dallas, Texas 75201 Gentlemen:
Thank you for your letters of October 9,1986, October 31, 1986, and January 22, 1987, in response to our letters and Notice of Violation dated August 26, 1986, ar.d December 30, 1986. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintained.
Sincerely,
<
svaal signed By
/Tl HHf E. H. Johnson, Director Division of Reactor Safety and Projects cc:
Texas Utilities Electric Company ATTN: G. S. Keeley, Manager Licensing Skyway Tower 400 North Olive Street Lock Box 81 Dallas, Texas 75201 RIV:CPRTh CPRT .5F '
PCWagner:gb IBarnes 2. /1 /87
/"DRP EHJohnson 2./$ /87 1/y/87 l$P!888! 8?88;go / {' D PDR \
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= Texas Utilities Generating 2 Company Juanita Ellis President - CASE 1426 South Polk Street Dallas, Texas 75224 Renea Hicks Assistant Attorney General Environmental Protection Division P. O. Box 12548 Austin, Texas 78711-2548 Administrative Judge Peter Bloch U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Elizabeth B. Jahrson Administrative Judge Oak Ridge National Laboratory P. O. Box X, Building 3500 Oak Ridge, Tennessee 37830 Dr. Kenneth A. McCollom 1107 West Knapp ,
Stillwater, Oklahoma 74075 Dr. Walter H. Jordan 881 Outer Drive Oak Ridge Tennessee 37830 Anthony Roisman, Esq.
Executive Director Trial Lawyers for Public Justice 2000 P. Street, N.W. Suite 611 Washington, D.C. 20036 Texas Radiation Control Program Director bec to DMB (IE01)
bec distrib. by RIV:
- T. F. Westerman, RSB DRSP V. Noonan, NRR R. Martin, RA L. Chandler, OGC *RSB
- D. Weiss, RM/ALF J. Conklin, IE
- I. Barnes, CPTG * Project Inspector
-
,
! Leg # TXX-6213 File # 10130 IR 86-06
- TEXAS UTILITIES GENERATING COMPANY IR 86-04 SKYWAY TOWER . 489 NORTH OLIVE STREET. LB. 88 . DALLAS, TEXAS 7M01 January 22, 1987 ~~~- '
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%?&^*.L #.U E ; # ? 6198'l Mr. Eric H. Johnson, Director I. , _
Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission L-611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 SUBJECT: COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 INSPECTION REPORT NOS.: 50-445/86-06 AND 50-445/86-04 SUPPLEMENTAL RESPONSE FOR INFORMATION TO NRC NOTICE OF VIOLATION (N0V) ITEM A(2)
REF: 1. TUGC0 Letter TXX-5037 from W. G. Counsil to E. dated October 9, 1986.
2. TUGC0 Letter TXX-6071 from W. G. Counsil to E. dated October 31, 1986.
Dear Mr. Johnson:
We have reviewed your letter dated December 30, 1986, requesting additional information to our responses referenced above regarding NOV 445/8604-V-02 (Item A(2)). We hereby respond to the request for supplemental information in the attachment to this letter.
Very truly yours, h th b W. G. ouns 1 By: [, . /
G. S. Keeley W/y Manager, Nuclear ticensing RSB/amb:lw Attachment c - NRC Region IV (0 + 1 copy)
Director, Inspection and Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Mr. V. S. Noonan Mr. D. L. Kelley
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. Attachment to TXX-6213'
January 22,--1986 Page 1 of 2
NOTICE OF VIOLATION ITEM A(2) 446/8604-V-02 SUPPLEMENTAL REQUEST FOR INFORMATION In your response to Item A(2), you mention that problems related to the overflowing of electrical cable from the cable trays that were identified by the NRC inspector had been previously identified by applicant personnel and were in the process of being reworked. Accordingly, you did not agree that the NRC identified condition was a violation and, therefore, did not provide the information required by the NOV.
Based on our review of the information provided in your response and additional information provided by members of your staff, we cannot agree that the cited condition had been, or necessarily would have been, identified as a result of the rework that had been undertaken. While we agree that many of the same cables were involved in both the NRC identified condition of overflowing cable tray siderails and the rework being conducted, we disagree ;
that the NRC identified problem would necessarily have been resolved by pulling the cables back to remove interlacing and then reinstalling these cables in the same size cable tray. In addition, the NRC inspector did not identify any QC hold tags (indicating an identified problem) during the NRC inspection.
SUPPLEMENTAL RESPG : TO ITEM A(2)
As a result of discussions with the NRC Resident Inspector and our review of this violation, we have determined that a revision to our response is required. The revised response below will provide the supplemental information requested.
1. Reason for Violation f We admit the violation, and the requested information follows.
The deficiences noted in this violation involving unacceptable cable installation'were the result of corrective actions in progress per NCR E-85-101983 and inadequacies in the cited TUGC0 Inspection Instruction QI-QP-11.3-26 and B&R Construction Procedure EEI-7. Specifically, criteria governing the installation and inspection of electrical cable were found insufficient to prevent the improper cable installation identified in the NOV.
2. Corrective Steos Taken A request for engineering clarification (RFIC E-11180) was initiated on March 4,1986 requesting engineering to evaluate cable tray nodes T240SF001, 02, 03, 04, and 05 for siderails and to document installation l
problems encountered during cable rework associated with NCR E-85-101983.
i A design change (DCA #24,289) was issued on April 4, 1986, to replace the
'
12" tray nodes with 18" width trays to correct the stated cable overfill and irregular routing problems. Construction Deficiency Report CDR-87-801 was issued on January 19, 1987 to identify the need for reinspection of existing cable installations for cable overfill conditions. If the disposition of the CDR indicates that corrective action is required, a CAR
- will be generated, k _ - .
- 4
. Attachment to TXX-6213 January 22, 1986 Page 2 of 2
'
3. Action to Prevent Recurrence Inspection Instruction QI-QP-11.3-26 and Construction Procedure EEI-7 have been revised to address the specific requirements of the electrical erection specification in the areas identified in the NOV. An additional inspection attribute has been incorporated into the inspection instruction prohibiting cables from extending above the top of cable tray siderails except where entering and exiting the cable tray.
4. Date of Como11ance Implementation of design change DCA-24,289 and associated cable rework is scheduled to be completed by July 1,1987. A change notice (DCN #5) was issued against the Installation Procedure EEI-7 on October 31, 1986.
Revision 31 of Inspection Instruction QI-QP-11.3-26 is scheduled to be issued by January 31, 1987, upon completion of requisite training. If required, appropriate corrective action to disposition CDR-87-801 will be completed by July 1,1987.
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